National Library of Energy BETA

Sample records for action program radiological

  1. Radiological Assistance Program

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

    1992-04-10

    To establish Department of Energy (DOE) policy, procedures, authorities, and responsibilities for its Radiological Assistance Program. Canceled by DOE O 153.1.

  2. ORISE: Radiological program assessment services

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

    DOECAP-qualified auditors coordinate and conduct radiological control audits of treatment, storage and disposal facilities and other sites as requested. Radiological facility...

  3. ORISE: Radiological program assessment services

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSEHow ORISE is Making aDoseRadiological program assessment

  4. Corrective Action Program Guide

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

    2006-03-02

    This Guide was developed to assist the Department of Energy (DOE) organizations and contractors in the development, implementation, and followup of corrective action programs utilizing the feedback and improvement core safety function within DOE's Integrated Safety Management System. This Guide outlines some of the basic principles, concepts, and lessons learned that DOE managers and contractors might consider when implementing corrective action programs based on their specific needs. Canceled by DOE G 414.1-2B. Does not cancel other directives.

  5. Monitoring activities review of the Radiological Environmental Surveillance Program

    SciTech Connect (OSTI)

    Ritter, P.D.

    1992-03-01

    The 1992 Monitoring Activities Review (MAR) is directed at the Radiological Environment Surveillance Program (RESP) activities at the Radioactive Waste Management Complex (RWMC) of Idaho Engineering Laboratory (INEL). MAR panelists studied RESP documents and discussed their concerns with Environmental Monitoring Unit (EMU) staff and other panel members. These concerns were subsequently consolidated into a collection of recommendations with supporting discussions. Recommendations focus on specific monitoring activities, as well as the overall program. The MAR report also contains pertinent comments that should not require further action.

  6. Nuclear and Radiological Engineering and Medical Physics Programs

    E-Print Network [OSTI]

    Weber, Rodney

    Nuclear and Radiological Engineering and Medical Physics Programs The George W. Woodruff School #12 Year Enrollment - Fall Semester Undergraduate Graduate #12; Nuclear Power Industry Radiological Engineering Industry Graduate School DOE National Labs Nuclear Navy #12; 104 Operating Nuclear Power plants

  7. Environmental Management Los Alamos Field Corrective Action Plan- Radiological Release Phase II

    Broader source: Energy.gov [DOE]

    On March 22, 2015, the Department of Energy established an Environmental Management Los Alamos Field Office (EM-LA) responsible for management of the environmental restoration and the legacy waste management programs at LANL. The NA-LA continues with the responsibility for the management of LANL's national security mission and the enduring waste management program (newly generated waste). As a result of this delineation in responsibilities, this corrective action plan was prepared collaboratively between NA-LA and EM-LA Field Offices, with joint responsibility for addressing the Judgement of Needs (JONs) identified in the Accident Investigation Board Accident Investigation Report, Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014, dated April 2015.

  8. Description of the Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    Not Available

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

  9. EM International Program Action Table

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based|DepartmentStatement |toDepartmentContributesAdvisoryProgram Action

  10. RSAC -6 Radiological Safety Analysis Computer Program

    SciTech Connect (OSTI)

    Schrader, Bradley J; Wenzel, Douglas Rudolph

    2001-06-01

    RSAC-6 is the latest version of the RSAC program. It calculates the consequences of a release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory; decay and in-grow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Internal dose from the inhalation and ingestion pathways is calculated. External dose from ground surface and plume gamma pathways is calculated. New and exciting updates to the program include the ability to evaluate a release to an enclosed room, resuspension of deposited activity and evaluation of a release up to 1 meter from the release point. Enhanced tools are included for dry deposition, building wake, occupancy factors, respirable fraction, AMAD adjustment, updated and enhanced radionuclide inventory and inclusion of the dose-conversion factors from FGR 11 and 12.

  11. Conversational Programming in Action Alexander Repenning

    E-Print Network [OSTI]

    Repenning, Alexander

    Conversational Programming in Action Alexander Repenning AgentSheets Inc. Boulder 80301, Colorado.0 culture, end-user programming, which is programming by end users with limited, if any, formal programming programming languages such as Logo have made programming substantially more accessible to end users. More

  12. RCRA corrective action program guide (Interim)

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

  13. Risk assessment in the DOE Assurance Program for Remedial Action

    SciTech Connect (OSTI)

    Marks, S.; Cross, F.T.; Denham, D.H.; Kennedy, W.E.; Stenner, R.D.

    1985-08-01

    This document provides information obtained during the performance of risk assessment tasks in support of the Assurance Program for Remedial Action (APRA) sponsored by the Office of Operational Safety of the Department of Energy. We have presented a method for the estimation of projected health effects at properties in the vicinity of uranium mill tailing piles due to transported tailings or emissions from the piles. Because radon and radon daughter exposure is identified as the principal factor contributing to health effects at such properties, the basis for estimating lung cancer risk as a result of such exposure is discussed in detail. Modeling of health risk due to a secondary pathway, ingestion of contaminated, home-grown food products, is also discussed since it is a potentially important additional source of exposure in certain geographic locations. Risk assessment methods used in various mill tailings reports are reviewed. The protocols for radiological surveys conducted in DOE-sponsored remedial action programs are critically reviewed with respect to their relevance to the needs of health risk estimation. The relevance of risk assessment to the APRA program is discussed briefly.

  14. SymposiumandIndustrialAffiliatesProgramLightinAction Industrial Affiliates Program

    E-Print Network [OSTI]

    Van Stryland, Eric

    SymposiumandIndustrialAffiliatesProgramLightinAction #12;Industrial Affiliates Program Friday, 8 Session I Abstract: Recently Additive Manufacturing (AM) has been hailed as the "third industrial revolution" by Economist magazine [April -2012]. Precision of the product manufactured by AM largely depends

  15. Audit of Selected Hazardous Waste Remedial Actions Program Costs...

    Office of Environmental Management (EM)

    of Selected Hazardous Waste Remedial Actions Program Costs, ER-B-97-04 Audit of Selected Hazardous Waste Remedial Actions Program Costs, ER-B-97-04 Audit of Selected Hazardous...

  16. New Jersey state information handbook: Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    1980-10-31

    Under the implied authority of the Atomic Energy Act of 1954, as amended, radiological surveys and research work has been conducted to determine radiological conditions at former MED/AEC sites. As of this time, 31 sites in 13 states have been identified that require or may require remedial action. This volume is one of a series produced under contract with DOE, Office of Nuclear Waste Management, by POLITECH CORPORATION to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of New Jersey. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations. The loose-leaf format used in these volumes will allow the material to be updated periodically as the Remedial Action Program progresses.

  17. Annual Radiological Environmental Monitoring Program Report for the Fort St. Vrain Independent Spent Fuel Storage Installation

    SciTech Connect (OSTI)

    Hall, Gregory Graham; Newkirk, Jay Ronald; Borst, Frederick Jon

    2002-02-01

    This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Fort St. Vrain Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the predominant radiation exposure pathway, direct and scattered radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

  18. Radiation Protection Considerations at USACE Formerly Utilized Sites Remedial Action Program (FUSRAP) Projects

    SciTech Connect (OSTI)

    Brown, S.H. [CHP, SHB INC., Centennial, Colorado (United States)

    2008-07-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) was initially authorized by Congress in 1974. FUSRAP was enacted to address residual radioactive contamination associated with numerous sites across the U.S. at which radioactive material (primarily Uranium ores and related milling products) had been processed in support of the nation's nuclear weapons program dating back to the Manhattan Project and the period immediately following World War II. In October 1997, Congress transferred the management of this program from the Department of Energy to the United States Corp of Engineers. Through this program, the Corps addresses the environmental remediation of certain sites once used by DOE's predecessor agencies, the Manhattan Engineer District and the Atomic Energy Commission. The waste at FUSRAP sites consists mainly of low levels of uranium, thorium and radium, along with some mixed wastes. Upon completion of remedial activities, these sites are transferred to DOE for long-term stewardship activities. This paper presents and contrasts the radiological conditions and recent monitoring results associated with five large ongoing FUSRAP projects including Maywood, N.J.; the Linde site near Buffalo, N.Y.; Colonie in Albany N.Y. and the St Louis, Mo. airport and downtown sites. The radiological characteristics of soil and debris at each site and respective regulatory clean up criteria is presented and contrasted. Some differences are discussed in the radiological characteristics of material at some sites that result in variations in radiation protection monitoring programs. Additionally, summary data for typical personnel radiation exposure monitoring results are presented. In summary: 1. The FUSRAP projects for which data and observations are reported in this paper are considered typical of the radiological nature of FUSRAP sites in general. 2. These sites are characterized by naturally occurring uranium and thorium series radionuclides in soil and debris, at concentrations typically < E4 pCi/ gram total activity. 3. Although external exposure rates are generally low resulting in few exposures above background, occasional 'hot spots' are observed in the 1- 10 mR / hr range or higher. However personnel and general area external exposure monitoring programs consistently demonstrate very low potential for external exposure at theses sites. 4. Potential for airborne exposure is controlled by wetting and misting techniques during excavation and movement of materials. Air sampling and bioassay programs confirm low potential for airborne exposure of workers at these sites. 5. Radiation protection and health physics monitoring programs as implemented at these sites ensure that exposures to personal are maintained ALARA. (authors)

  19. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    SciTech Connect (OSTI)

    Dr. Bradley J Schrader

    2010-10-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  20. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado. Attachment 5, Supplemental radiological data: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-10-01

    Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data.

  1. Overview of the U.S. Department of Energy Formerly Utilized Sites Remedial Action Program - 12189

    SciTech Connect (OSTI)

    Clayton, Christopher; Kothari, Vijendra; Starr, Ken; Gillespie, Joey; Widdop, Michael; none,

    2012-02-26

    The U.S. Department of Energy (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP) was established in 1974 to address residual radiological contamination at sites where work was performed for the Manhattan Engineer District and U.S. Atomic Energy Commission. Initially, FUSRAP activities began with a records search for sites that had the potential to contain residual radiological contamination; 46 sites were identified that were eligible for and required remediation. Remedial action began in 1979. In 1997, Congress assigned responsibility for the remediation of FUSRAP sites to the U.S. Army Corps of Engineers (USACE). DOE retains responsibility for determining if sites are eligible for FUSRAP remediation and for providing long-term surveillance and maintenance (LTS&M) of remediated FUSRAP sites. DOE LTS&M activities are designed to ensure that FUSRAP sites remain protective of human health and the environment and to preserve knowledge regarding FUSRAP sites. Additional elements include eligibility determinations, transition of remediated sites from USACE to DOE, LTS&M operations such as inspections and institutional controls management, stakeholder support, preservation of records, and real property and reuse. DOE maintains close coordination with USACE and regulators to ensure there is no loss of protectiveness when sites transition to DOE for LTS&M.

  2. Radiological Threat Reduction (RTR) program : implementing physical security to protect large radioactive sources worldwide.

    SciTech Connect (OSTI)

    Lowe, Daniel L.

    2004-11-01

    The U.S. Department of Energy's Radiological Threat Reduction (RTR) Program strives to reduce the threat of a Radiological Dispersion Device (RDD) incident that could affect U.S. interests worldwide. Sandia National Laboratories supports the RTR program on many different levels. Sandia works directly with DOE to develop strategies, including the selection of countries to receive support and the identification of radioactive materials to be protected. Sandia also works with DOE in the development of guidelines and in training DOE project managers in physical protection principles. Other support to DOE includes performing rapid assessments and providing guidance for establishing foreign regulatory and knowledge infrastructure. Sandia works directly with foreign governments to establish cooperative agreements necessary to implement the RTR Program efforts to protect radioactive sources. Once necessary agreements are in place, Sandia works with in-country organizations to implement various security related initiatives, such as installing security systems and searching for (and securing) orphaned radioactive sources. The radioactive materials of interest to the RTR program include Cobalt 60, Cesium 137, Strontium 90, Iridium 192, Radium 226, Plutonium 238, Americium 241, Californium 252, and Others. Security systems are implemented using a standardized approach that provides consistency through out the RTR program efforts at Sandia. The approach incorporates a series of major tasks that overlap in order to provide continuity. The major task sequence is to: Establish in-country contacts - integrators, Obtain material characterizations, Perform site assessments and vulnerability assessments, Develop upgrade plans, Procure and install equipment, Conduct acceptance testing and performance testing, Develop procedures, and Conduct training. Other tasks are incorporated as appropriate and commonly include such as support of reconfiguring infrastructure, and developing security plans, etc. This standardized approach is applied to specific country and regional needs. Recent examples (FY 2003-2004) include foreign missions to Lithuania, Russian Federation Navy, Russia - PNPI, Greece (joint mission with IAEA), Tanzania, Iraq, Chile, Ecuador, and Egypt. Some of the ambitions and results of the RTR program may be characterized by the successes in Lithuania, Greece, and Russia.

  3. Alternatives for management of wastes generated by the formerly utilized sites remedial action program and supplement

    SciTech Connect (OSTI)

    Gilbert, T.L.; Peterson, J.M.; Vocke, R.W.; Alexander, J.K.

    1983-03-01

    Alternatives for disposal or stabilization of the wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP) are identified and compared, with emphasis on the long-term aspects. These wastes consist of soil material and rubble containing trace amounts of radionuclides. A detailed pathway analysis for the dose to the maximally exposed individual is carried out using an adaptation of the natural analogue method. Comparisons of the different alternatives, based on the results of the pathway analysis and qualitative cost considerations, indicate that, if the hazard is such that the wastes must be removed and disposed of rather than stabilized in place, disposal by immediate dispersal is preferable to containment, and containment followed by slow planned dispersal is preferable to containment without dispersal. The Supplement presents refinements of work that was reported at the 1982 International Decommissioning Symposium. The new material consists of revisions of the estimates of the predicted potential dose to the maximally exposed individual and a more detailed comparative assessment of the radiological impacts of alternatives for management of wastes generated by the US Department of Energy's Formerly Utilized Sites Remedial Action Program (FUSRAP).

  4. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT

    Office of Legacy Management (LM)

    .- - -- CONTENTS INTRODUCTION BACKGROUND Site Function Site Description Radiological History and Status ELIMINATION ANALYSIS REFERENCES ii - ,. -- Page 1 4 4 ..I - --...

  5. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992. Operations Services/Technical Programs

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment.

  6. Pennsylvania state information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    none,

    1980-12-31

    This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and State levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Pennsylvania. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

  7. Florida state information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    1981-02-27

    This volume is one of a series produced under contract with DOE, Office of Nuclear Waste Management, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the federal and state levels, the pertinent programs they administer, each affected state legislature, and current federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Florida. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

  8. Iowa state information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    1981-02-09

    This volume is one of a series produced under contract with the DOE, By Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the state of Iowa. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; the full test of relevant statutes and regulations.

  9. Status of activities on the inactive uranium mill tailings sites remedial action program. Office of the Assistant Secretary for Environment

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

    This report on the status of the Office of Environment's program for inactive uranium mill tailings sites is an analysis of the current status and a forecast of future activities of the Office of Environment. The termination date for receipt of information was September 30, 1980. Aerial radiological surveys and detailed ground radiological assessments of properties within the communities in the vicinity of the designated processing sites in Canonsburg, Pennsylvania, Salt Lake City, Utah, and Boise, Idaho led to the designation of an initial group of vicinity properties for remedial action. The potential health effects of the residual radioactive materials on or near these properties were estimated, and the Assistant Secretary for Environment recommended priorities for performing remedial action to the Department's Assistant Secretary for Nuclear Energy. In designating these properties and establishing recommended priorities for performing remedial action, the Office of Environment consulted with the Environmental Protection Agency, the Nuclear Regulatory Commission, representatives from the affected State and local governments, and individual property owners. After notifying the Governors of each of the affected States and the Navajo Nation of the Secretary of Energy's designation of processing sites within their areas of jurisdiction and establishment of remedial action priorities, a Sample Cooperative Agreement was developed by the Department in consultation with the Nuclear Regulatory Commission and provided to the affected States and the Navajo Nation for comments. During September 1980, a Cooperative Agreement with the Commonwealth of Pennsylvania for the designated Canonsburg processing site was executed by the Department. It is anticipated that a Cooperative Agreement between the State of Utah and the Department to perform remedial actions at the designated Salt Lake City site will be executed in the near future.

  10. Missouri State information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    1980-12-31

    This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of Missouri. It contains: a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature chairmen, and a summary of recent relevant legislative action; a description of the organization and structure of local governments affected by remedial action at the St. Louis area sites; a summary of relevant local ordinances and regulations; an identification of relevant public interest groups; a list of radio stations, television stations, and newspapers that provide public information to the St. Louis area or to Jefferson City; and the full text of relevant statutes and regulations.

  11. Federal government information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    Not Available

    1980-12-31

    This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This Information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the Federal Government. It contains a summary of the organization and responsibilities of agencies within the executive branch of the Federal government which may be relevant to FUSRAP activities; a brief summary of relevant Federal statutes and regulations; a description of the structure of the US Congress, identification of the officers, relevant committees and committee chairmen; a description of the Federal legislative process; a summary of legislation enacted and considered in the recently-adjourned 96th Congress; a description of the Federal budgetary process; a summary of the Carter Administration's comprehensive radioactive waste management program; and excerpts from the text of relevant federal statutes and regulations.

  12. Transcript of See Action and Technical Assistance Program Webinar: Strategic Energy Management

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) See Action Network and Weatherization and Intergovernmental Program Technical Assistance Program sponsored this webinar about strategic management in the public sector on November 7, 2012.

  13. Uranium Mill Tailings Remedial Action Program. Annual status report

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

    The purpose, scope, history, requirements, and management organization of the UMTRA Program are summarized in the Introduction. The remainder of the report describes progress made during the past year (F 1980) and discusses future plants and activities. Early emphasis has been on the four highest-priority sites because of their proximity to population centers. These sites are: (1) Canonsburg, Pennsylvania; (2) Salt Lake City, Utah; (3) Durango, Colorado; and (4) Shiprock, New Mexico (Navajo Reservation). To date, twenty-five vicinity properties near the Canonsburg site and two such properties near the Salt Lake City site have been designated for remedial action. A research effort was undertaken at a major vicinity property, the Mountain States Supply Company in Salt Lake City, to study the effects of heating-and-ventilating-system modification on indoor radon-daughter concentrations. A cooperative agreement was executed between DOE and the Commonwealth of Pennsylvania. A similar agreement with the State of Utah is expected to be executed in early FY 1981. Further, it is expected that additional cooperative agreements will be negotiated during FY 1981 with the States of Colorado and Wyoming and the Navajo Nation. It is expected that the processing site at Canonsburg, PA (the Canonsburg Industrial Park) will be acquired during FY 1981. Draft Environmental Impact Statements for the four highest-priority sites will be completed during FY 1981.

  14. Environmental Management Los Alamos Field Office Corrective Action...

    Energy Savers [EERE]

    Field Office Corrective Action Plan - Radiological Release Phase II Environmental Management Los Alamos Field Office Corrective Action Plan - Radiological Release Phase II On...

  15. Environmental Management Los Alamos Field Corrective Action Plan...

    Energy Savers [EERE]

    Los Alamos Field Corrective Action Plan - Radiological Release Phase II Environmental Management Los Alamos Field Corrective Action Plan - Radiological Release Phase II On March...

  16. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM ELIMINATION REPORT

    Office of Legacy Management (LM)

    SYLVANIA-CORNING NUCLEAR CORPORATION BAYSIDE, NEW YORK VW. Department of Energy Office of Nuclear Energy Office of Remedial Action and Waste Technology Division of Facility and...

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  18. Local action for the global environment : municipal government participation in a voluntary climate protection program

    E-Print Network [OSTI]

    Ravin, Amelia L., 1977-

    2004-01-01

    The Cities for Climate ProtectionTM (CCP) campaign is a voluntary environmental program for municipalities, which is increasingly being applied around the world by local governments taking action on climate change. This ...

  19. The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

    SciTech Connect (OSTI)

    Kehl, S.R.; Mount, M.E.; Robison, W.L.

    1995-09-01

    From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of {sup 90}Sr, {sup 137}Cs, {sup 241}Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA`s radiochemistry department were accepted.

  20. Radiological/Health physics program assessement at Rocky Flats, the process

    SciTech Connect (OSTI)

    Psomas, P.O.

    1996-06-01

    The Department of Energy, Rocky Flats Office, Safety and Health Group, Health Physics Team (HPT) is responsible for oversight of the Radiation Protection and Health Physics Program (RPHP) of the Integrating Management Contractor (IMC), Kaiser-Hill (K-H) operations at the Rocky Flats Environmental Technology Site (RFETS). As of 1 January 1996 the Rocky Flats Plant employed 300 DOE and 4,300 contractor personnel (K-H and their subcontractors). WSI is a subcontractor and provides plant security. To accomplish the RPHP program oversight HPT personnel developed a systematic methodology for performing a functional RPHP Assessment. The initial process included development of a flow diagram identifying all programmatic elements and assessment criteria documents. Formulation of plans for conducting interviews and performance of assessments constituted the second major effort. The generation of assessment reports was the final step, based on the results of this process. This assessment will be a 6 person-year effort, over the next three years. This process is the most comprehensive assessment of any Radiation Protection and Health Physics (RPHP) Program ever performed at Rocky Flats. The results of these efforts will establish a baseline for future RPHP Program assessments at RFETS. This methodology has been well-received by contractor personnel and creates no Privacy Act violations or other misunderstandings.

  1. Digital Preservation in Action: Toward a Campus-Wide Program

    E-Print Network [OSTI]

    Fyffe, Richard; Ludwig, Deborah; Warner, Beth Forrest

    2005-09-13

    This bulletin explores a proposed model for establishing a digital preservation program in colleges and universities - requirements for educating the institutional community, developing roles and policies, and establishing an integrated technical...

  2. SCHOOL OF SOCIAL WORK Program Review Action Plan

    E-Print Network [OSTI]

    Frantz, Kyle J.

    in the BSW program which is an increase of 29% from 2004 (n=158). In the introductory course (SW 2000 a new model of instruction in the Introduction to Social Work course (SW 2000). The course included

  3. FORMERLY UTILIZED SITES LMEDIAL ACTION PROGRAM ELIMINATION REPORT

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and Myers CoMadison -T:..) "..LMEDIAL ACTION

  4. Technology needs for environmental restoration remedial action. Environmental Restoration Program

    SciTech Connect (OSTI)

    Watson, J.S.

    1992-11-01

    This report summarizes the current view of the most important technology needs for the US Department of Energy (DOE) facilities operated by Martin Marietta Energy Systems, Inc. These facilities are the Oak Ridge National Laboratory, the Oak Ridge K-25 Site, the Oak Ridge Y-12 Plant, the Paducah Gaseous Diffusion Plant, and the Portsmouth Gaseous Diffusion Plant. The sources of information used in this assessment were a survey of selected representatives of the Environmental Restoration (ER) programs at each facility, results from a questionnaire distributed by Geotech CWM, Inc., for DOE, and associated discussions with individuals from each facility. This is not a final assessment, but a brief look at an ongoing assessment; the needs will change as the plans for restoration change and, it is hoped, as some technical problems are solved through successful development programs.

  5. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act Amendments (PAAA). While this Standard does not establish requirements, it does restate, paraphrase, or cite many (but not all) of the requirements of 10 CFR 835 and related documents (e.g., occupational safety and health, hazardous materials transportation, and environmental protection standards). Because of the wide range of activities undertaken by DOE and the varying requirements affecting these activities, DOE does not believe that it would be practical or useful to identify and reproduce the entire range of health and safety requirements in this Standard and therefore has not done so. In all cases, DOE cautions the user to review any underlying regulatory and contractual requirements and the primary guidance documents in their original context to ensure that the site program is adequate to ensure continuing compliance with the applicable requirements. To assist its operating entities in achieving and maintaining compliance with the requirements of 10 CFR 835, DOE has established its primary regulatory guidance in the DOE G 441.1 series of Guides. This Standard supplements the DOE G 441.1 series of Guides and serves as a secondary source of guidance for achieving compliance with 10 CFR 835.

  6. Radiological Protection for DOE Activities

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

    1995-09-29

    Establishes radiological protection program requirements that, combined with 10 CFR 835 and its associated implementation guidance, form the basis for a comprehensive program for protection of individuals from the hazards of ionizing radiation in controlled areas. Extended by DOE N 441.3. Cancels DOE 5480.11, DOE 5480.15, DOE N 5400.13, DOE N 5480.11; please note: the DOE radiological control manual (DOE/EH-0256T)

  7. Nuclear Waste Partnership (NWP) Corrective Action Plan Addendum...

    Office of Environmental Management (EM)

    Addendum Radiological Release Event Phase II Nuclear Waste Partnership (NWP) Corrective Action Plan Addendum Radiological Release Event Phase II On Friday, February 14, 2014 there...

  8. Nuclear Waste Partnership (NWP) Corrective Action Plan - Truck...

    Office of Environmental Management (EM)

    - Truck Fire and Radiological Release Phase I Nuclear Waste Partnership (NWP) Corrective Action Plan - Truck Fire and Radiological Release Phase I Submittal of the Underground Salt...

  9. Environmental Management Headquarters Corrective Action Plan...

    Office of Environmental Management (EM)

    I Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase I The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of...

  10. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    For 8 years, from 1972 until 1980, the United States planned and carried out the radiological cleanup, rehabilitation, and resettlement of Enewetak Atoll in the Marshall Islands. This documentary records, from the perspective of DOD, the background, decisions, actions, and results of this major national and international effort. The documentary is designed: First, to provide a historical document which records with accuracy this major event in the history of Enewetak Atoll, the Marshall Islands, the Trust Territory of the Pacific Islands, Micronesia, the Pacific Basin, and the United States. Second, to provide a definitive record of the radiological contamination of the Atoll. Third, to provide a detailed record of the radiological exposure of the cleanup forces themselves. Fourth, to provide a useful guide for subsequent radiological cleanup efforts elsewhere.

  11. New Mexico state information handbook: formerly utilized sites remedial action program

    SciTech Connect (OSTI)

    2014-12-31

    This volume is one of a series produced under contract with the DOE, by Politech Corporation to develop a legislative and regulatory data base to assist the FUSRAP management in addressing the institutional and socioeconomic issues involved in carrying out the Formerly Utilized Sites Remedial Action Program. This information Handbook series contains information about all relevant government agencies at the Federal and state levels, the pertinent programs they administer, each affected state legislature, and current Federal and state legislative and regulatory initiatives. This volume is a compilation of information about the State of New Mexico. It contains a description of the state executive branch structure; a summary of relevant state statutes and regulations; a description of the structure of the state legislature, identification of the officers and committee chairmen, and a summary of recent relevant legislative action; and the full text of relevant statutes and regulations.

  12. Minnesota Voluntary Investigation and Clean-Up Program voids Superfund and provides assurance of no action

    SciTech Connect (OSTI)

    Tepley, W.B.; DeGroot, R.L.

    1994-12-31

    The Minnesota Land Recycling Act of 1992 provides statutory authority to quickly approve clean-up of contaminated properties and provides land owners and lenders assurances which minimize potential liability. The Minnesota Pollution Control Agency`s (MPCA) Voluntary Investigation and Clean-Up (VIC) Program avoids the time and expense of the ``Superfund`` process. This paper outlines the VIC Program and describes it`s application through a site history. The site was impacted with volatile organic compounds, diesel fuels, lead, and cadmium at hazardous waste concentrations. The investigation, clean-up and documentation was performed through the VIC Program. A ``Limited No Action`` letter was received within the time frame of the purchase agreement for the property transaction. The history shows the steps taken through the VIC Program, describes investigation and clean-up methods and associated costs. The result was a successful transfer of the property for a new medical complex.

  13. Annual status report on the Uranium Mill Tailings Remedial Action Program

    SciTech Connect (OSTI)

    Not Available

    1989-12-01

    This eleventh annual status report summarizes activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project undertaken during Fiscal Year (FY) 1989 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1990 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95--604. The DOE will continue to submit an annual report through project completion in order to inform the public of yearly project status. Title I of the UMTRCA authorizes the DOE, in cooperation with affected states and Indian tribes within whose boundaries designated uranium processing sites are located, to provide a program of assessment and remedial action at such sites. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive materials located on the inactive uranium processing sites in a safe and environmentally sound manner and to minimize or eliminate potential radiation health hazards. Commercial and residential properties in the vicinity of designated processing sites that are contaminated with material from the sites, herein referred to as vicinity properties,'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated vicinity properties located in 10 states, and the vicinity properties associated with Edgemont, South Dakota, an inactive uranium mill currently owned by the Tennessee Valley Authority (TVA).

  14. Environmental compliance assessment findings for Weldon Spring Site Remedial Action Program

    SciTech Connect (OSTI)

    Sigmon, C.F.; Levine, M.B.

    1990-03-02

    This report presents the results of an environmental assessment conducted at Weldon Spring Site Remedial Action Project (WSSRAP) in St. Charles County, Missouri, in accordance with the Formerly Utilized Sites Remedial Action Program (FUSRAP) Environmental Compliance Assessment Checklists. The purpose of this assessment was to evaluate the compliance of the site with applicable federal and Missouri environment regulations. Assessments activities included the following: review of site records, reports ,and files; inspection of the WSSRAP storage building, other selected buildings, and the adjacent grounds; and interviews with project personnel. This assessment was conducted on August 28-30, 1989. The assessment covered five management areas as set forth in the Checklist: Hazardous Waste Management, Polychlorinated Biphenyls (PCBs) Management; Air Emissions; Wastewater Discharges and Petroleum Management. No samples were collected. 1 ref., 2 figs., 1 tab.

  15. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

    This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  16. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council Nevada Test Site

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  17. Yakima Tributary Access and Habitat Program : Action Plan Final Report 2002.

    SciTech Connect (OSTI)

    Myra, David (South Central Washington Resource Conservation and Development Council, Ellensburg, WA); Ready, Carol A. (Kittitas County Water Purveyors, Ellensburg, WA)

    2003-04-01

    This report covers activities conducted by the Yakima Tributary Access and Habitat Program under Bonneville Power Administration (BPA) grant project No. 2002-025-00 for fiscal year 2002. The Yakima Tributary Access and Habitat Program (YTAHP, Program) was organized to restore salmonid passage to Yakima tributaries that historically supported salmonids and improve habitat in areas where access is restored. Specifically, this program is designed to (a) screen unscreened diversion structures to prevent fish entrainment into artificial waterways; (b) provide for fish passage at man-made barriers, such as diversion dams, culverts, siphons and bridges; and (c) provide information and assistance to landowners interested in to contributing to the improvement of water quality, water reliability and stream habitat. The YTAHP developed from a number of groups actively engaged in watershed management, and/or habitat restoration within the Yakima River Basin. These groups include the Washington State Fish and Wildlife (WDFW), Kittitas County Conservation District (KCCD), North Yakima Conservation District (NYCD), Kittitas County Water Purveyors (KCWP), and Ahtanum Irrigation District (AID). The US Bureau of Reclamation (Reclamation) and Yakama Nation (YN) both participated in the development of the objectives of YTAHP. Other entities that will be involved during permitting or project review may include the YN, the federal Natural Resources Conservation Service (NRCS), the US Fish and Wildlife Service (USFWS), the National Marine Fisheries Service (NMFS), and US Army Corps of Engineers (COE). Achievements of YTAHP with BPA Action Plan funding during FY 2002 were to: (1) Establish contracts with RC&D and YTAHP participants. (2) Determine contract mechanism for MWH engineering services. (3) Provide engineering designs and services for 11 early action projects, including inverted siphons, pump and gravity diversion screening, diversion metering, rock weirs for improved fish passage, headgates and fishways. These designs were used to submit for project implementation funding through the WA Salmon Recovery Funding Board. (4) Complete 6 early action projects on Ahtanum Creek--One gravity diversion was replaced with a pump and pump end screen and 5 pump end screens were installed. (5) Conduct two topographic surveys--For the City of Yakima on the Fruitvale diversion for the North Yakima Conservation District to support the installation of a pumping plant which would eliminate the need to divert directly from the Naches River and build the gravel berm each year during low flows. For the Taylor Ditch system for the North Yakima Conservation District to support as feasibility of opening the ditch for habitat and at the same time maintaining irrigation deliveries. (6) Procure materials for use in future YTAHP projects, including siphon pipe, delivery pipe, rock, screens, and water meters. These materials will act as match and support the completion of these subsequent YTAHP projects. Overall, with broad agency support and Action Plan funding through BPA, the YTAHP has achieved substantial enhancements that support aquatic species and which will leverage subsequent work through engineering designs and materials. The program was also able to establish the personnel and equipment support for beginning the stream assessment process on tributaries in Yakima and Kittitas Counties. Completion of this year's effort has provided significant inroads to working on the private lands in two counties which will be vital to future efforts by YTAHP and others to protect and enhance Yakima River Basin habitat.

  18. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  19. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    1998-02-01

    This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

  20. Review of well-logging techniques. [For use in remedial action programs

    SciTech Connect (OSTI)

    Olsen, K.B.; Young, J.A.; Thomas, V.W.

    1983-04-01

    A literature review has been conducted to determine whether suitable borehole-logging techniques exist for the measurement of gamma-ray-emitting elements using downhole detectors. Most of the methods that have been used for the last 30 years by the uranium-exploration industry involve passive gamma-ray measurement techniques utilizing NaI(Tl) and, occasionally, intrinsic germanium detectors. Parameters the industry has had to consider in calibrating these detectors are variations in (1) casing material and thickness, (2) water in the borehole, (3) hole diameter, (4) disequilibrium between uranium and its daughters in the ore zone, (5) spatial distribution of the radioactive material, and (6) dead time of the analyzer. The methods they have used to address these variable parameters appear to be applicable to remedial action programs. The techniques that have been used for the measurement of subsurface radium concentration by DOE during the engineering assessment of UMTRAP/FUSRAP sites and by NRC at one remedial action site will be described in this report.

  1. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  2. Summary of FIRE Actions in Response to Next Step Options Program Advisory Committee Report #4, January 2002

    E-Print Network [OSTI]

    Summary of FIRE Actions in Response to Next Step Options Program Advisory Committee Report #4, January 2002 Previous Findings and Recommendations The FIRE Project has made good progress on responding where we deem they are of very high priority. 1. NBI for FIRE Finding 1: At our previous meeting we

  3. Determination of ecologically vital groundwaters at selected sites in the Formerly Utilized Sites Remedial Action Program

    SciTech Connect (OSTI)

    Vinikour, W.S.; Yin, S.C.L.

    1989-08-01

    The US Department of Energy is classifying groundwaters at sites in its Formerly Utilized Sites Remedial Action Program (FUSRAP). Of particular concern is the potential presence of groundwaters that are highly vulnerable to contamination and that are either (1) irreplaceable sources of drinking water or (2) ecologically vital. Conditions at nine FUSRAP sites were evaluated to determine if ecologically vital groundwaters are present. The sites evaluated were Wayne Interim Storage Site, Maywood Interim Storage Site, and Middlesex Sampling Plant in New Jersey; Ashland 2 Site, Seaway Industrial Park, Colonie Interim storage Site, and Niagara Falls Storage Site in New York; and the St. Louis Airport Site and Hazelwood Interim Storage Site in Missouri. The analyses indicated that groundwaters are vulnerable to contamination at all but two of the sites -- the Ashland 2 and Seaway Industrial Park sites in New York. Groundwater discharge points were identified within a 2-mile radius (i.e., the classification review area) of all of the sites. No ecologically vital groundwater areas exist in the vicinities of any of the nine FUSRAP sites evaluated. 35 refs., 17 figs.

  4. HANFORD TANK FARM RESOURCE CONVERVATION & RECOVERY ACT (RCRA) CORRECTIVE ACTION PROGRAM

    SciTech Connect (OSTI)

    KRISTOFZSKI, J.G.

    2007-01-15

    As a consequence of producing special nuclear material for the nation's defense, large amounts of extremely hazardous radioactive waste was created at the US Department of Energy's (DOE) Hanford Site in south central Washington State. A little over 50 million gallons of this waste is now stored in 177 large, underground tanks on Hanford's Central Plateau in tank farms regulated under the Atomic Energy Act and the Resource, Conservation, and Recovery Act (RCRA). Over 60 tanks and associated infrastructure have released or are presumed to have released waste in the vadose zone. In 1998, DOE's Office of River Protection established the Hanford Tank Farm RCRA Corrective Action Program (RCAP) to: (1) characterize the distribution and extent of the existing vadose zone contamination; (2) determine how the contamination will move in the future; (3) estimate the impacts of this contamination on groundwater and other media; (4) develop and implement mitigative measures; and (5) develop corrective measures to be implemented as part of the final closure of the tank farm facilities. Since its creation, RCAP has made major advances in each of these areas, which will be discussed in this paper.

  5. Weldon Spring Site Remedial Action Project: Report from the DOE voluntary protection program onsite review, November 17--21, 1997

    SciTech Connect (OSTI)

    1998-01-28

    This report summarizes the Department of Energy Voluntary Protection Program (DOE-VPP) Review Team`s findings from the five-day onsite evaluation of the Weldon Spring Site Remedial Action Project (WSSRAP), conducted November 17--21, 1997. The site was evaluated against the program requirements contained in ``US Department of Energy Voluntary Protection Program, Part 1: Program Elements`` to determine its success in implementing the five tenets of DOE-VPP. DOE-VPP consists of three programs, with names and functions similar to those in OSHA`s VPP. These programs are STAR, MERIT, and DEMONSTRATION. The STAR program is the core of DOE-VPP. The program is aimed at truly outstanding protectors of employee safety and health. The MERIT program is a steppingstone for contractors and subcontractors that have good safety and health programs but need time and DOE guidance to achieve STAR status. The DEMONSTRATION program is rarely used; it allows DOE to recognize achievements in unusual situations about which DOE needs to learn more before determining approval requirements for the STAR status.

  6. Environmental Management Headquarters Corrective Action Plan - Radiological

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLfor InnovativeProcessing FacilityJanuary 20,membership

  7. Environmental Management Headquarters Corrective Action Plan - Radiological

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLfor InnovativeProcessing FacilityJanuary 20,membershipRelease Phase II |

  8. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Safety 3 C #12;Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2013-2014 Page 1

  9. Roadmap: Radiologic Imaging Sciences -Nuclear Medicine (with AAS Radiologic Technology) -

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor Imaging Sciences - Nuclear Medicine (with AAS Radiologic Technology) - Bachelor of Radiologic and Imaging of Radiologic and Imaging Sciences Technology [RE-BRIT-RIS-NMRT] Regional College Catalog Year: 2012-2013 Page 1

  10. UCSF Emergency Action Plan Template Campus Emergency Preparedness Program www.police.ucsf.edu

    E-Print Network [OSTI]

    Derisi, Joseph

    specific to their individual locations. Your Emergency Action Plan should address preparedness measures for a variety of emergency situations, e.g., medical emergencies, citywide disasters; power outages, hazardous

  11. Formerly Utilized Sites Remedial Action Program (FUSRAP) Hazelwood Interim Storage Site annual site environmental report. Calendar year 1985. [FUSRAP

    SciTech Connect (OSTI)

    Not Available

    1986-04-01

    The Hazelwood Interim Storage Site (HISS) is presently used for the storage of low-level radioactively contaminated soils. Monitoring results show that the HISS is in compliance with DOE concentration guides and radiation protection standards. Derived Concentration Guides (DCGs) represent the concentrations of radionuclides in air or water that would limit the radiation dose to 100 mrem/y. The applicable limits have been revised since the 1984 environmental monitoring report was published. The limits applied in 1984 were based on a radiation protection standard of 500 mrem/y; the limits applied for 1985 are based on a standard of 100 mrem/y. The HISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where low-level radioactive contamination remains from the early years of the nation's atomic energy program. To determine whether the site is in compliance with DOE standards, environmental measurements are expressed as percentages of the applicable DCG, while the calculated doses to the public are expressed as percentages of the applicable radiation protection standard. The monitoring program at the HISS measures uranium, radium, and thorium concentrations in surface water, groundwater, and sediment; radon gas concentrations in air; and external gamma radiation exposure rates. Potential radiation doses to the public are also calculated. The HISS was designated for remedial action under FUSRAP because radioactivity above applicable limits was found to exist at the site and its vicinity. Elevated levels of radiation still exist in areas where remedial action has not yet been completed.

  12. Environmental audit of the Maywood Site: Formerly Utilized Sites Remedial Action Program, Maywood Interim Storage Site vicinity properties

    SciTech Connect (OSTI)

    Not Available

    1990-12-01

    This report presents the results of the Environmental Audit of the Maywood Site managed by the Formerly Utilized Sites Remedial Action Program (FUSRAP). The Audit was carried out from November 7 through 16, 1990. The Audit Team found overall technical competence and knowledge of management and staff to be excellent. This applies to DOE as well as to Bechtel National, Incorporated (BNI). In particular, there was excellent knowledge of federal, state, and local environmental regulations, as well as analysis for applicability of these regulations to FUSRAP. Project management of the Maywood Site is also excellent. BNI and DOE project staff have made frequent contact with members of the community, and all removal actions and remedial investigation activities have been planned, scheduled, and accomplished with competence and attention to total quality principles. To date, all actions taken for the Maywood Site cleanup have been completed ahead of schedule and on or under budget. Weakness noted include self-assessment efforts by DOE, failure to fully implement DOE Order requirements throughout the program, and some discrepancies in formally documenting and reviewing procedures. 7 figs., 10 tabs.

  13. Vicinity Property Assessments at Formerly Utilized Sites Remedial Action Program Project Sites in the New York District - 13420

    SciTech Connect (OSTI)

    Ewy, Ann; Hays, David

    2013-07-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) has addressed sites across the nation for almost 4 decades. Multiple stake holder pressures, multiple regulations, and process changes occur over such long time periods. These result in many challenges to the FUSRAP project teams. Initial FUSRAP work was not performed under Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Records of Decision (ROD). The ROD identifies the remedy decision and ultimately the criteria to be used to release a site. Early FUSRAP projects used DOE Orders or the Uranium Mill Tailings Radiation Control Act (UMTRCA) standards. Under current RODs, regulations may differ, resulting in different cleanup criteria than that used in prior Vicinity Property (VP) remediation. The USACE, in preparation for closeout of Sites, conducts reviews to evaluate whether prior actions were sufficient to meet the cleanup criteria specified in the current ROD. On the basis of these reviews, USACE has conducted additional sampling, determined that prior actions were sufficient, or conducted additional remediation consistent with the selected remedy in the ROD. As the public pressures, regulations, and processes that the FUSRAP encounters continue to change, the program itself continues to evolve. Assessment of VPs at FUSRAP sites is a necessary step in the life cycle of our site management. (authors)

  14. Annual status report on the Uranium Mill Tailings Remedial Action Program

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    This fourteenth annual status report for the Uranium Mill Tailings Remedial Action (UMTRA) Project Office summarizes activities of the Uranium Mill Tailings Remedial Action Surface (UMTRA-Surface) and Uranium Mill Tailings Remedial Action Groundwater (UMTRA-Groundwater) Projects undertaken during fiscal year (FY) 1992 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1993 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604. The DOE will continue to submit annual reports to DOE-Headquarters, the states, tribes, and local representatives through Project completion in order to inform the public of the yearly Project status. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive material (RRM) located on the inactive uranium processing sites in a safe and environmentally sound manner, and to minimize or eliminate potential health hazards. Commercial and residential properties near designated processing sites that are contaminated with material from the sites, herein referred to as ``vicinity properties (VP),`` are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated VPs located in 10 states, and the VPs associated with the Edgemont, South Dakota, uranium mill currently owned by the Tennessee Valley Authority (TVA) (Figure A.1, Appendix A).

  15. Transcript of See Action and Technical Assistance Program Webcast: Energy Audit and Retro-Commissioning Policies for Public and Commercial Buildings

    Broader source: Energy.gov [DOE]

    U.S. Department of Energy Office (DOE) of Energy Efficiency and Renewable Energy (EERE) transcript of See Action and Technical Assistance Program Webcast: Energy Audit and Retro-Commissioning Policies for Public and Commercial Buildings.

  16. Radiation Shielding and Radiological Protection

    E-Print Network [OSTI]

    Shultis, J. Kenneth

    Radiation Shielding and Radiological Protection J. Kenneth Shultis Richard E. Faw Department Shielding and Radiological Protection .. Example Calculations for Distributed Sources

  17. CLOSEOUT REPORT REMEDIAL ACTION

    E-Print Network [OSTI]

    FINAL CLOSEOUT REPORT REMEDIAL ACTION AREA OF CONCERN 6 BUILDING 650 RECLAMATION FACILITY SUMP York 11973 REGISTERED TO ISO 14001 #12;AOC 6 BUILDING 650 RECLAMATION FACILITY SUMP AND SUMP OUTFALL .................................................................................9 2.6.1 Final Radiological Status Survey Design

  18. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect (OSTI)

    Bechtel Nevada

    1999-12-31

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

  19. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological...

  20. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological...

  1. INEEL Radiological Control Performance Indicator Report - Quarterly

    SciTech Connect (OSTI)

    Hinckley, Frank Leroy

    1999-02-01

    This document provides a report of an analysis of the Radiological Control Program through the fourth quarter of Calendar Year (CY-98) and is the annual report for the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth quarter, all areas experienced deletions of work resulting from the Maintenance Stand Down. This reduction in work is a primary factor in the difference in the year end dose and the ALARA goal. The work will be completed during CY-99. Beginning in CY-98, a numeric Radiological Performance Index (RPI) is being used to compare radiological performance. The RPI takes into consideration frequency and severity of events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI measures the cost of these events in cents per hour of radiological work performed. To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used. The data are compared on a quarterly basis to the prior year to show measurable performance.

  2. Compilation of Bioassay Issues Reported During the 120-Day Suspension of PAAA Enforcement Actions Related to Internal Dose Evaluation Programs by Contractors in the Department of Energy Complex

    Broader source: Energy.gov [DOE]

    The DOE Office of Enforcement and Investigation (EH Enforcement) invoked a 120-day suspension of PAAA enforcement actions for issues associated with contractor Internal Dose Evaluation Programs (IDEP). Prior to initiation of the suspension, EH Enforcement had identified deficiencies in DOEcontractor implemented bioassay programs at numerous sites within the DOE complex. The commonality of the IDEP deficiencies at the various sites, as well as the possibility of the existence of similar deficiencies at other DOE sites, led EH Enforcement to the conclusion that a suspension of enforcement actions would be appropriate to provide DOE-contractors an opportunity to review their own IDEPs to determine whether similar or other program deficiencies existed, and, if so, to take appropriate corrective action.

  3. Gamma radiological surveys of the Oak Ridge Reservation, Paducah Gaseous Diffusion Plant, and Portsmouth Gaseous Diffusion Plant, 1990-1993, and overview of data processing and analysis by the Environmental Restoration Remote Sensing Program, Fiscal Year 1995

    SciTech Connect (OSTI)

    Smyre, J.L.; Moll, B.W.; King, A.L.

    1996-06-01

    Three gamma radiological surveys have been conducted under auspices of the ER Remote Sensing Program: (1) Oak Ridge Reservation (ORR) (1992), (2) Clinch River (1992), and (3) Portsmouth Gaseous Diffusion Plant (PORTS) (1993). In addition, the Remote Sensing Program has acquired the results of earlier surveys at Paducah Gaseous Diffusion Plant (PGDP) (1990) and PORTS (1990). These radiological surveys provide data for characterization and long-term monitoring of U.S. Department of Energy (DOE) contamination areas since many of the radioactive materials processed or handled on the ORR, PGDP, and PORTS are direct gamma radiation emitters or have gamma emitting daughter radionuclides. High resolution airborne gamma radiation surveys require a helicopter outfitted with one or two detector pods, a computer-based data acquisition system, and an accurate navigational positioning system for relating collected data to ground location. Sensors measure the ground-level gamma energy spectrum in the 38 to 3,026 KeV range. Analysis can provide gamma emission strength in counts per second for either gross or total man-made gamma emissions. Gross count gamma radiation includes natural background radiation from terrestrial sources (radionuclides present in small amounts in the earth`s soil and bedrock), from radon gas, and from cosmic rays from outer space as well as radiation from man-made radionuclides. Man-made count gamma data include only the portion of the gross count that can be directly attributed to gamma rays from man-made radionuclides. Interpretation of the gamma energy spectra can make possible the determination of which specific radioisotopes contribute to the observed man-made gamma radiation, either as direct or as indirect (i.e., daughter) gamma energy from specific radionuclides (e.g., cesium-137, cobalt-60, uranium-238).

  4. Geothermal Program Review XII: proceedings. Geothermal Energy and the President's Climate Change Action Plan

    SciTech Connect (OSTI)

    Not Available

    1994-12-31

    Geothermal Program Review XII, sponsored by the Geothermal Division of US Department of Energy, was held April 25--28, 1994, in San Francisco, California. This annual conference is designed to promote effective technology transfer by bringing together DOE-sponsored researchers; utility representatives; geothermal energy developers; suppliers of geothermal goods and services; representatives from federal, state, and local agencies; and others with an interest in geothermal energy. In-depth reviews of the latest technological advancements and research results are presented during the conference with emphasis on those topics considered to have the greatest potential to impact the near-term commercial development of geothermal energy.

  5. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 1 The Radiological Research Accelerator Facility for Radiological Research (CRR). Using the mi- crobeam facility, 10% of the cells were irradiated through particle beam as well as the first fo- cused microbeam in the new microbeam facility. · Another significant

  6. Radiological worker training

    SciTech Connect (OSTI)

    1998-10-01

    This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

  7. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  8. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

    2004-11-01

    This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

  9. EA-1919: Recycle of Scrap Metals Originating from Radiological Areas

    Broader source: Energy.gov [DOE]

    This Programmatic EA evaluates alternatives for the management of scrap metal originating from DOE radiological control areas, including the proposed action to allow for the recycle of uncontaminated scrap metal that meets the requirements of DOE Order 458.1. (Metals with volumetric radioactive contamination are not included in the scope of this Programmatic EA.)

  10. Hanford Radiological Protection Support Services Annual Report for 2000

    SciTech Connect (OSTI)

    Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

    2001-05-07

    During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

  11. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control

  12. Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement

    SciTech Connect (OSTI)

    Seguin, Nicole R. [Los Alamos National Laboratory

    2012-07-18

    Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

  13. Roadmap: Radiologic Imaging Sciences Nuclear Medicine (with certification and ATS Radiologic Technology)

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Imaging Sciences ­ Nuclear Medicine (with certification and ATS Radiologic Technology) ­ Bachelor of Radiologic Imaging Sciences Technology [RE-BRIT-RIS-NMHO] Regional College Catalog technology; successfully completed the certification exam for the American Registry of Radiologic Technology

  14. Radiological Monitoring Continues at WIPP

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

    investigate this event. WIPP is developing a plan to safely re-enter the WIPP underground facility. Radiological professionals from other DOE locations and National Laboratories...

  15. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

    A radiation dosimeter providing an indication of the dose of radiation to which the radiation sensor has been exposed. The dosimeter contains features enabling the monitoring and evaluating of radiological risks so that a user can concentrate on the task at hand. The dosimeter provides an audible alarm indication that a predetermined time period has elapsed, an audible alarm indication reminding the user to check the dosimeter indication periodically, an audible alarm indicating that a predetermined accumulated dose has been prematurely reached, and an audible alarm indication prior or to reaching the 3/4 scale point.

  16. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of 9

  17. Radiological Control Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of 99

  18. Radiological Technician Training

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 ofDOE

  19. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

  20. The Radiological Research Accelerator THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    The Radiological Research Accelerator Facility #12;84 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY Director: David J. Brenner, Ph.D., D.Sc., Manager: Stephen A. Marino, M.S. An NIH SupportedV/µm 4 He ions using the microbeam facility (Exp. 73) also continued. The transformation frequency

  1. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 71 The Radiological Research Accelerator Facility the irradiated cells. Both the microbeam and the track segment facilities continue to be utilized in various investigations of this phenomenon. The single- particle microbeam facility provides precise control of the number

  2. Radiological Research Accelerator Facility Service Request Form

    E-Print Network [OSTI]

    Radiological Research Accelerator Facility Service Request Form National Institute of Biomedical Imaging and Bioengineering Radiological Research Accelerator Facility Service request form Estimate when(s) to control for this experiment (if more than one, please prioritize): Radiological Research Accelerator

  3. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY #12;115 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY An NIH-Supported Resource Center WWW.RARAF.ORG Director: David J. Brenner, Ph.D., D.Sc. Manager delighted that NIH funding for continued development of our single-particle microbeam facility was renewed

  4. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY

    E-Print Network [OSTI]

    175 THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY #12;176 #12;177 THE RADIOLOGICAL RESEARCH the microbeam and the track-segment facilities have been utilized in various investigations. Table 1 lists-segment facility. Samples are treated with graded doses of radical scavengers to observe changes in the cluster

  5. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

    The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

  6. Radiological Threat Reduction | ornl.gov

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

    Removal of radiological materials from unstable regions around the world, safely packaging and transporting those materials to a more stable state; and Protecting radiological...

  7. Handling and Packaging a Potentially Radiologically Contaminated...

    Office of Environmental Management (EM)

    Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is...

  8. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    SciTech Connect (OSTI)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  9. Pacific Northwest National Laboratory Potential Impact Categories for Radiological Air Emission Monitoring

    SciTech Connect (OSTI)

    Ballinger, Marcel Y.; Gervais, Todd L.; Barnett, J. M.

    2012-06-05

    In 2002, the EPA amended 40 CFR 61 Subpart H and 40 CFR 61 Appendix B Method 114 to include requirements from ANSI/HPS N13.1-1999 Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities for major emission points. Additionally, the WDOH amended the Washington Administrative Code (WAC) 246-247 Radiation protection-air emissions to include ANSI/HPS N13.1-1999 requirements for major and minor emission points when new permitting actions are approved. A result of the amended regulations is the requirement to prepare a written technical basis for the radiological air emission sampling and monitoring program. A key component of the technical basis is the Potential Impact Category (PIC) assigned to an emission point. This paper discusses the PIC assignments for the Pacific Northwest National Laboratory (PNNL) Integrated Laboratory emission units; this revision includes five PIC categories.

  10. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

    Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and frequency, similar to the approach of DOE-STD-3011-94. Because this binning does not require high precision, a standardized approach for radiological dose evaluations is taken for all the facilities at the site. This is done through a standard calculation ``template`` for use by all safety analysts preparing the new documents. This report describes this template and its use.

  11. Corrective Action

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

    Community, Environment Environmental Protection Obeying Environmental Laws Individual Permit Corrective Action Individual Permit: Corrective Action Certifications If...

  12. Results of the radiological survey at 142 West Central Avenue, Maywood, New Jersey (MJ041)

    SciTech Connect (OSTI)

    Foley, R.D.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 142 West Central Avenue, Maywood, New Jersey (MJ041), was conducted during 1988. Results of the survey indicated scattered radiation or ''shine'' from a storage pile, located off the property, containing residual radioactive material. Lead-shielded measurements showed radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 4 refs., 8 figs., 3 tabs.

  13. Results of the radiological survey at 205 Main Street, Lodi, New Jersey (LJ075)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 205 Main Street, Lodi, New Jersey (LJ075), was conducted during 1987 and 1988. Results of the survey indicated radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 21 figs., 3 tabs.

  14. Results of the radiological survey at 72 Sidney Stret, Lodi, New Jersey (LJ067)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. (Oak Ridge National Lab., TN (USA))

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residues used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 72 Sidney Street, Lodi, New Jersey (LJ067), was conducted during 1987. Results indicated concentrations of {sup 232}Th slightly in excess of the DOE remedial action criterion for subsurface soil. This finding, coupled with the fact that adjacent properties have been designated by DOE for remedial action, and that the old Lodi Brook streambed is apparently beneath the property, suggests that it be considered for inclusion in the DOE remedial action program. 4 refs., 5 figs., 3 tabs.

  15. Radiological safety training for accelerator facilities: DOE handbook

    SciTech Connect (OSTI)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  16. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  17. The Radiological Research Accelerator Facility

    SciTech Connect (OSTI)

    Hall, E.J.; Marino, S.A.

    1993-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. This report provides a listing and brief description of experiments performed at RARAF during the May 1, 1992 through April 30, 1993.

  18. Results of the radiological survey at 4 Branca Court, Lodi, New Jersey (LJ037)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.R.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 4 Branca Court, Lodi, New Jersey (LJ037), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. However, this property is apparently located directly over the old Lodi Brook streambed. This factor in combination with the elevated gamma logs of several auger holes is sufficient to recommend this site for inclusion in the DOE remedial action program. 5 refs., 5 figs., 4 tabs.

  19. Computational Science and Engineering Certification for Nuclear, Plasma, and Radiological Engineering

    E-Print Network [OSTI]

    Gilbert, Matthew

    Computational Science and Engineering Certification for Nuclear, Plasma, and Radiological Engineering The Computational Science and Engineering certificate program is designed to provide NPRE a certificate in "Computational Science and Engineering", students must complete the required courses listed

  20. Radiological characterization of main cooling reservoir bottom sediments at The South Texas Project Electrical Generating Station 

    E-Print Network [OSTI]

    Blankinship, David Randle

    1993-01-01

    The South Texas Project Electrical Generating Station (STPEGS operating license directs that an effective radiological environmental monitoring program be established. Site- specific data should then augment the generation of an accurate dose model...

  1. Analytical methods for removing radiological constituents prior to organic analysis

    SciTech Connect (OSTI)

    Hakonson, K.; Monagle, M.; Cournoyer, M.

    1997-12-31

    Within the Department of Energy (DOE), there is a need to analyze mixed waste materials (i.e. materials that are contaminated with both radiological and hazardous components). As part of the technical support the Organic Analysis Group provides for programs within Los Alamos National Laboratory, methods are under development for radiologically contaminated oil samples being tested for polychlorinated biphenyls and other semivolatile constituents. Radionuclides are removed from oil samples by filtering the samples through a commercials available solid phase extraction cartridge. An aliquot of the eluent is then analyzed to quantitate the residual radioactivity.

  2. Radiological Assistance Program | National Nuclear Security Administra...

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

    practical, including initial interface with these entities for joint participation in drills, exercises, and support for domestic preparedness. RAP's unique qualifications make it...

  3. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest forToolsDOE-HDBK-1106-97

  4. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest forToolsDOE-HDBK-1106-97DOE.F

  5. Radiological Assistance Program | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-RichProton DeliveryRadioactive Materials at SSRL

  6. Southwest Michigan Community Action Agency Â… Weatherization Assistance Program Funds Provided by the American Recovery and Reinvestment Act of 2009

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool FitsProjectDataSecretaryDepartment7 Annual ReportSouthwest Michigan Community Action

  7. Post remedial action survey report for Building 003, Santa Susana Field Laboratories, Rockwell International, Ventura County, California, October 1981; April 1982. Surplus Facilities Management Program

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-10-01

    Rockwell International's Santa Susana Laboratories in Ventura County, California, have been the site of numerous Federally-funded projects involving the use of radioactive materials. One such project was the System for Nuclear Auxiliary Power (SNAP) Program. Building 003 on the Santa Susana site was used in conjunction with the SNAP Program and contained a highly shielded area designed for remote manipulation of radioactive materials. Such facilities are commonly referred to as hot caves. During the SNAP Program, fuel burnup samples were analyzed and irradiation experiments were evaluated in the Building 003 hot cave. Use of the hot cave facility ended when the SNAP Program was terminated in 1973. Subsequently, the Building 003 facilities were declared excess and were decontaminaed and decommissioned during the first half of calendar year 1975. At that time, the building was given a preliminary release. In 1981, a post-remedial-action (certification) survey of Building 003 was conducted at the request of the Department of Energy. Significant levels of residual contamination were found in various parts of the building. Consequently, additional decontamination was conducted by Rockwell International. A final post-remedial-action survey was conducted during April 1982, and those areas in Building 003 that had been found contaminated in 1981 were now found to be free of detectable radioactive contamination. Sludge samples taken from the sewer sump showed elevated levels of enriched uranium contaminant. Hence, all sewer lines within Building 003 were removed. This permitted unconditional release of the building for unrestricted use. However, the sewer lines exterior to the building, which remain in place, must be considered potentially contaminated and, therefore, subject to restricted use.

  8. Roadmap: Radiologic Technology Radiology Department Management Technology Associate of Technical Study

    E-Print Network [OSTI]

    Sheridan, Scott

    Roadmap: Radiologic Technology ­ Radiology Department Management Technology ­ Associate-Nov-13/LNHD This roadmap is a recommended semester-by-semester plan of study for this major. However

  9. Needed improvements in the development of systemic corrective actions.

    SciTech Connect (OSTI)

    Campisi, John A.

    2009-07-01

    There are indications that corrective actions, as implemented at Sandia National Laboratories are not fully adequate. Review of independent audits spanning multiple years provides evidence of recurring issues within the same or similar operations and programs. Several external audits have directly called into question the ability Sandia's assessment and evaluation processes to prevent recurrence. Examples of repeated findings include lockout/tagout programs, local exhaust ventilation controls and radiological controls. Recurrence clearly shows that there are underlying systemic factors that are not being adequately addressed by corrective actions stemming from causal analyses. Information suggests that improvements in the conduct of causal analyses and, more importantly, in the development of subsequent corrective actions are warranted. Current methodolgies include Management Oversight Risk Tree, developed in the early 1970s and Systemic Factors Analysis. Recommendations for improvements include review of other causal analysis systems, training, improved formality of operations, improved documentation, and a corporate method that uses truly systemic solutions. This report was written some years ago and is being published now to form the foundation for current, follow-on reports being developed. Some outdated material is recognized but is retained for report completeness.

  10. Development and operativity of a real-time radiological monitoring network centered on the nuclear power plant of Almaraz (Spain)

    SciTech Connect (OSTI)

    Baeza, A.; Miro, C.; Puerto, J.A. del; Rio, M. del; Ortiz, F.; Paniagua, J.M.

    1993-12-01

    This work presents the hardware and software characteristics of the environmental surveillance radiological network that has been installed around the nuclear power station of Almaraz (Spain). A description is given of the program RADLINE which allows radiological data to be logged in real time, and a study is made of the operativity of the network and the methodology followed in establishing the radiological pre-alert and alert levels.

  11. Radiological Work Planning and Procedure

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-01-01

    Each facility is tasked with maintaining personnel radiation exposure as low as reasonably achievable (ALARA). A continued effort is required to meet this goal by developing and implementing improvements to technical work documents (TWDs) and work performance. A review of selected TWDs from most facilities shows there is a need to incorporate more radiological control requirements into the TWD. The Radioactive Work Permit (RWP) provides a mechanism to place some of the requirements but does not provide all the information needed by the worker as he/she is accomplishing the steps of the TWD. Requiring the engineers, planners and procedure writers to put the radiological control requirements in the work steps would be very easy if all personnel had a strong background in radiological work planning and radiological controls. Unfortunately, many of these personnel do not have the background necessary to include these requirements without assistance by the Radiological Control organization at each facility. In addition, there seems to be confusion as to what should be and what should not be included in the TWD.

  12. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  13. Los Alamos National Security Corrective Action Plan - Radiological Release

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy A plug-inPPLforLDRDEnergyTurbineProcesses toDepartmentSpurred by aPhase II |

  14. Implementation of the National Incident Management System (NIMS)/Incident Command System (ICS) in the Federal Radiological Monitoring and Assessment Center(FRMAC) - Emergency Phase

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-04-01

    Homeland Security Presidential Directive HSPD-5 requires all federal departments and agencies to adopt a National Incident Management System (NIMS)/Incident Command System (ICS) and use it in their individual domestic incident management and emergency prevention, preparedness, response, recovery, and mitigation programs and activities, as well as in support of those actions taken to assist state and local entities. This system provides a consistent nationwide template to enable federal, state, local, and tribal governments, private-sector, and nongovernmental organizations to work together effectively and efficiently to prepare for, prevent, respond to, and recover from domestic incidents, regardless of cause, size, or complexity, including acts of catastrophic terrorism. This document identifies the operational concepts of the Federal Radiological Monitoring and Assessment Center's (FRMAC) implementation of the NIMS/ICS response structure under the National Response Plan (NRP). The construct identified here defines the basic response template to be tailored to the incident-specific response requirements. FRMAC's mission to facilitate interagency environmental data management, monitoring, sampling, analysis, and assessment and link this information to the planning and decision staff clearly places the FRMAC in the Planning Section. FRMAC is not a mitigating resource for radiological contamination but is present to conduct radiological impact assessment for public dose avoidance. Field monitoring is a fact-finding mission to support this effort directly. Decisions based on the assessed data will drive public protection and operational requirements. This organizational structure under NIMS is focused by the mission responsibilities and interface requirements following the premise to provide emergency responders with a flexible yet standardized structure for incident response activities. The coordination responsibilities outlined in the NRP are based on the NIMS/ICS construct and Unified Command (UC) for management of a domestic incident. The NRP Nuclear/Radiological Incident Annex (NUC) further provides requirements and protocols for coordinating federal government capabilities to respond to nuclear/radiological Incidents of National Significance (INS) and other radiological incidents. When a FRMAC is established, it operates under the parameters of NIMS as defined in the NRP. FRMAC and its operations have been modified to reflect NIMS/ICS concepts and principles and to facilitate working in a Unified Command structure. FRMAC is established at or near the scene of the incident to coordinate radiological monitoring and assessment and is established in coordination with the U.S. Department of Homeland Security (DHS); the coordinating agency; other federal agencies; and state, local, and tribal authorities. However, regardless of the coordinating agency designation, U.S. Department of Energy (DOE) coordinates radiological monitoring and assessment activities for the initial phases of the offsite federal incident response through the Radiological Assistance Program (RAP) and FRMAC assets. Monitoring and assessment data are managed by FRMAC in an accountable, secure, and retrievable format. Monitoring data interpretations, including exposure rate contours, dose projections, and any requested radiological assessments are to be provided to the DHS; to the coordinating agency; and to state, local, and tribal government agencies.

  15. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  16. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Radiological Advisory Team | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

  17. Nuclear Radiological Threat Task Force Established | National...

    National Nuclear Security Administration (NNSA)

    Radiological Threat Task Force Established | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  18. Results of the radiological survey at 4 Hancock Street, Lodi, New Jersey (LJ060)

    SciTech Connect (OSTI)

    Foley, R.D.; Carier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 4 Hancock Street, Lodi, New Jersey (LJ060), was conducted during 1985 and 1986. Gamma logging results found during this survey and during a previous survey conducted by Bechtel National, Incorporated, strongly indicated radionuclide concentrations in subsurface soil in excess of DOE remedial action criteria. This finding, coupled with the fact that adjacent properties have been found to be contaminated and that Lodi Brook apparently flows under the property, suggests that it be considered for inclusion in the DOE remedial action program. 5 refs., 4 figs., 4 tabs.

  19. Fall Protection Procedures for Sealing Bulk Waste Shipments by Rail Cars at Formerly Utilized Sites Remedial Action Program (FUSRAP) Sites - 13509

    SciTech Connect (OSTI)

    Boyle, J.D.; Fort, E. Joseph; Lorenz, William; Mills, Andy

    2013-07-01

    Rail-cars loaded with radioactive materials must be closed and fastened to comply with United States Department of Transportation (DOT) requirements before they shipped. Securing waste shipments in a manner that meets these regulations typically results in the use of a sealable rail-car liner. Workers accessing the tops of the 2.74 m high rail-cars to seal and inspect liners for compliance prior to shipment may be exposed to a fall hazard. Relatively recent revisions to the Fall Protection requirements in the Safety and Health Requirements Manual (EM385-1-1, U.S. Army Corps of Engineers) have necessitated modifications to the fall protection systems previously employed for rail-car loading at Formerly Utilized Sites Remedial Action Program (FUSRAP) sites. In response these projects have developed site-specific procedures to protect workers and maintain compliance with the improved fall protection regulations. (authors)

  20. Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-07-01

    Corrective Action Unit 106 comprises the four corrective action sites (CASs) listed below: • 05-20-02, Evaporation Pond • 05-23-05, Atmospheric Test Site - Able • 05-45-04, 306 GZ Rad Contaminated Area • 05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from groundwater pumping during the Radionuclide Migration study program (CAS 05-20-02), a weapons-related airdrop test (CAS 05-23-05), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). The presence and nature of contamination from surface-deposited radiological contamination from CAS 05-23-05, Atmospheric Test Site - Able, and other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) from the remaining three CASs will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: • Conduct radiological surveys. • Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. • If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where the total effective dose at the site exceeds final action levels (i.e., corrective action boundary). • Collect samples of investigation-derived waste, as needed, for waste management purposes.

  1. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01

    ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

  2. Departmental Radiological Emergency Response Assets

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

    2007-06-27

    The order establishes requirements and responsibilities for the DOE/NNSA national radiological emergency response assets and capabilities and Nuclear Emergency Support Team assets. Supersedes DOE O 5530.1A, DOE O 5530.2, DOE O 5530.3, DOE O 5530.4, and DOE O 5530.5.

  3. Radiological science involves technologists use

    E-Print Network [OSTI]

    Sibille, Etienne

    English Composition II Mathematics MATH 0110 Fundamentals of Mathematics THE HUMAN EXPERIENCE Students new Clinical Experience Radiographic Procedures II Radiation Protection II Radiographic Film ProcessingRadiological science involves technologists use X-rays to see the inside of the human body. Health

  4. Hanford radiological protection support services annual report for 1994

    SciTech Connect (OSTI)

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Olsen, P.C.

    1995-06-01

    Various Hanford Site radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy Richland Operations Office and Hanford contractors are described in this annual report for the calendar year 1994. These activities include external dosimetry measurements and evaluations, internal dosimetry measurements and evaluations, in vivo measurements, radiological record keeping, radiation source calibration, and instrument calibration and evaluation. For each of these activities, the routine program and any program changes or enhancements are described, as well as associated tasks, investigations, and studies. Program- related publications, presentations, and other staff professional activities are also described.

  5. Education and the energy crisis: policies and actions for the Department of Energy. [Options and alternatives, DOE Education Programs Div

    SciTech Connect (OSTI)

    1980-01-22

    This report is the result of a study carried out to determine options and alternatives for the Education Programs Division (EPD) of the Department of Energy. In the conduct of this study, numerous individuals from various concerned institutions were interviewed. While the project scope clearly precluded contact with every involved or potentially involved party, a concerted effort was made to obtain a representative sampling of the opinions and views of relevant government, academic and private sector agencies and organizations. A listing of those contacted, excluding the Department of Energy, is provided. In addition to interviews, an extensive range of literature was drawn upon including memoranda, brochures, program statements, school-enrollment data, speeches and the like. It was determined during this study that a wide range of public and private institutions are actively involved in the energy-education field. Oil companies, utilities, public interest groups, schools, agencies at every level of government, and others are formulating and delivering education which is enormously varied. It was concluded, however, that the public is not being reached, partially because current efforts are unfocused and partially because the public has become inured to problems and resistant to many of the traditional means of education. The study found that within this crowded and varied energy education field the Department of Energy is well placed to begin to provide direction and focus to the widespread activity now occurring.

  6. A national program for energy-efficient mortgages and home energy rating systems: A blueprint for action

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    This Review Draft reports findings and recommendations of the National Collaborative on Home Energy Rating Systems and Mortgage Incentives for Energy Efficiency. The US Department of Energy, in cooperation with the US Department of Housing and Urban Development, formed this National Collaborative as a National Energy Strategy initiative. Participating in the Collaborative were representatives of the primary and secondary mortgage markets, builder and remodeler organizations, real estate and appraiser associations, the home energy rating system industry, utility associations, consumer and public interest groups, state and local government interest groups, and environmental organizations. The Collaborative's purpose was to develop a voluntary national program encouraging energy efficiency in homes through mortgage incentives linked to home energy ratings.

  7. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    SciTech Connect (OSTI)

    NONE

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV`s) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG and G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin).

  8. Radiological Training for Tritium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8

  9. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

    Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

  10. Corrective Action Tracking System User's Guide | Department of...

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

    September 07, 2004 Corrective Action Tracking System (CATS) User's Guide for Direct Web Access The Department of Energy (DOE) Corrective Action Management Program (CAMP) prescribes...

  11. Hanford radiological protection support services annual report for 1991

    SciTech Connect (OSTI)

    Lyon, M.; Bihl, D.E.; Fix, J.J.; Piper, R.K.; Froelich, T.J.; Leonwich, J.A.; Lynch, T.P.

    1992-07-01

    Various Hanford sitewide radiation protection services provided by the Pacific Northwest Laboratory for the US Department of Energy, Richland Field Office and Hanford contractors are described In this annual report for calendar year 1991. These activities include internal dosimetry measurements and evaluations, in vivo measurements, external dosimetry measurements and evaluations, instrument calibration and evaluation, radiation source calibration, and radiological records keeping. For each of these activities, the routine program, program changes and enhancements, associated tasks, investigations and studies, and related publications, presentations, and other staff professional activities are discussed as applicable.

  12. Uranium Mill Tailings Remedial Action Project Annual Environmental Monitoring Report calendar year 1992: Volume 2

    SciTech Connect (OSTI)

    none,

    1993-12-31

    This report contains environmental monitoring information for the following UMTRA sites for the 1992 Calendar Year: Lakeview, OR; Lowman, ID; Mexican Hat, UT; Monument Valley, AZ; Rifle, CO; Riverton, WY; Shiprock, NM; Spook, WY; Tuba City, AZ. Each site report contains a site description, compliance summary, environmental program information, environmental radiological and non-radiological program information, water resources protection, and quality assurance information.

  13. ORISE: Radiological Assessment and Monitoring System (RAMS)

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

    place. Radiological data is then normalized so it can be readily incorporated into geographic information systems tools, which are used by local, state and federal decision...

  14. Operating Experience Level 3: Radiologically Contaminated Respirators...

    Energy Savers [EERE]

    Experience Level 3 provides information on a safety concern related to radiological contamination of launderedreconditioned respirators and parts that have been certified as...

  15. Cardiovascular and Interventional Radiological Society of Europe...

    Office of Scientific and Technical Information (OSTI)

    Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease Citation Details In-Document Search Title:...

  16. Radiological Training for Tritium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8DOE

  17. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 75 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2005 76 The Radiological Research Accelerator Facility AN NIH .................................................................................................................................................72 Development of Facilities

  18. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 65 RARAF - Table of Contents RARAF Professional FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2006 66 The Radiological Research Accelerator Facility AN NIH..................................................................................................................................................66 Development of facilities

  19. Federal Radiological Monitoring and Assessment Center

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

    1992-12-02

    To establish Department of Energy (DOE) policy, procedures, authorities, and requirements for the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC), as set forth in the Federal Radiological Emergency Response Plan (FRERP). This directive does not cancel another directive. Canceled by DOE O 153.1.

  20. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2013-05-28

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  1. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Broader source: Energy.gov [DOE]

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

  2. NV/YMP radiological control manual, Revision 2

    SciTech Connect (OSTI)

    Gile, A.L.

    1996-11-01

    The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

  3. Results of the radiological survey at 24 Long Valley Road, Lodi, New Jersey (LJ048)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monozite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 24 Long Valley Road, Lodi, New Jersey (LJ048), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 8 figs., 3 tabs.

  4. Results of the radiological survey at 6 Hancock Street, Lodi, New Jersey (LJ033)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth, earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 6 Hancock Street, Lodi, New Jersey (LJ033), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site.

  5. Results of the radiological survey at 99 Garibaldi Avenue, Lodi, New Jersey (LJ064)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Crutcher, J.W.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 99 Garibaldi Avenue, Lodi, New Jersey (LJ064), was conducted during 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 8 figs., 3 tabs.

  6. Results of the radiological survey at 106 Columbia Lane, Lodi, New Jersey (LJ063)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Crutcher, J.W.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 106 Columbia Lane, Lodi, New Jersey (LJ063), was conducted during 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 7 figs., 3 tabs.

  7. Results of the radiological survey at 30 Long Valley Road, Lodi, New Jersey (LJ045)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 30 Long Valley Road, Lodi, New Jersey (LJ045), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 10 figs., 3 tabs.

  8. Results of the radiological survey at 12 Long Valley Road, Lodi, New Jersey (LJ054)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extracting process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 12 Long Valley Road, Lodi, New Jersey (LJ054), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  9. Results of the radiological survey at 10 Long Valley Road, Lodi, New Jersey (LJ055)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 10 Long Valley Road, Lodi, New Jersey (LJ055), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 5 figs., 3 tabs.

  10. Results of the radiological survey at 32 Long Valley Road, Lodi, New Jersey (LJ046)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 32 Long Valley Road, Lodi, New Jersey (LJ046), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  11. Results of the radiological survey at 7 Hancock Street, Lodi, New Jersey (LJ027)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. AT the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 7 Hancock Street, Lodi, New Jersey (LJ027), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  12. Results of the radiological survey at 5 Hancock Street, Lodi, New Jersey (LJ029)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 5 Hancock Street, Lodi, New Jersey (LJ029), was conducted during 1985 and 1986. Results of the survey demonstrated concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of the material originating from the MCW site. 5 refs., 6 figs., 3 tabs.

  13. Results of the radiological survey at 19 Redstone Lane, Lodi, New Jersey (LJ056)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 19 Redstone Lane, Lodi, New Jersey (LJ056), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 4 figs., 3 tabs.

  14. Results of the radiological survey at 2 Branca Court, Lodi, New Jersey (LJ036)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1961 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 2 Branca Court, Lodi, New Jersey (LJ036), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site.

  15. Results of the radiological survey at 1 Branca Court, Lodi, New Jersey (LJ034)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 1 Branca Court, Lodi, New Jersey (LJ034), was conducted during 1985 and 1986. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 4 figs., 3 tabs.

  16. Results of the radiological survey at 174 Essex Street, Lodi, New Jersey (LJ073)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 174 Essex Street, Lodi, New Jersey (LJ073), was conducted during 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site.

  17. Results of the radiological survey at 17 Redstone Lane, Lodi, New Jersey (LJ030)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 17 Redstone Lane, Lodi, New Jersey (LJ030), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 7 figs., 3 tabs.

  18. Results of the radiological survey at 62 Trudy Drive, Lodi, New Jersey (LJ080)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 62 Trudy Drive, Lodi, New Jersey (LJ080), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  19. Results of the radiological survey at 9 Hancock Street, Lodi, New Jersey (LJ028)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Hancock Street, Lodi, New Jersey (LJ028), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  20. Results of the radiological survey at 160 Essex Street, Lodi, New Jersey (LJ072)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 160 Essex Street, Lodi, New Jersey (LJ072), was conducted during 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 10 figs., 2 tabs.

  1. Results of the radiological survey at 10 Hancock Street, Lodi, New Jersey (LJ031)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling from radionuclide analyses. The survey of this site, 10 Hancock Street, Lodi, New Jersey (LJ031), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 4 figs., 3 tabs.

  2. Results of the radiological survey at 28 Long Valley Road, Lodi, New Jersey (LJ047)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 28 Long Valley Road, Lodi, New Jersey (LJ047), was conducted during 1985, 1986, 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the Survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 8 figs., 3 tabs.

  3. Results of the radiological survey at 7 Redstone Lane, Lodi, New Jersey (LJ044)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclides analyses. The survey of this site, 7 Redstone Lane, Lodi, New Jersey (LJ044), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 4 figs., 3 tabs.

  4. Radiological survey results at the former Bridgeport Brass Company facility, Seymour, Connecticut

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1993-06-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of the former Bridgeport Brass Company facility, Seymour, Connecticut. The survey was performed in May 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed in the Ruffert building under government contract in the 1960s. The survey included a gamma scanning over a circumscribed area around the building, and gamma and beta-gamma scanning over all indoor surfaces as well as the collection of soil and other samples for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and wall surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in Rooms 1--6 that had been used in the early government work.

  5. Unified Resolve 2014: A Proof of Concept for Radiological Support...

    Office of Environmental Management (EM)

    Concept for Radiological Support to Incident Commanders Unified Resolve 2014: A Proof of Concept for Radiological Support to Incident Commanders Daniel Blumenthal*, U.S....

  6. Radiological Source Term Estimates for the February 14, 2014...

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

    Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event Radiological Source Term Estimates for the February 14, 2014 WIPP Release Event This document was...

  7. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  8. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect (OSTI)

    Asou, M. [CEA/DEN/VALRHO/UMODD, 30207 Bagnols-sur-Ceze Cedex (France); Le Goaller, C. [CEA/DEN/VALRHO/DDCO, 30207 Bagnols-sur-Ceze Cedex (France); Martin, F. [AREVA NC DAP/MOP (France)

    2007-07-01

    Cleanup operations in the Marcoule Vitrification Facility (AVM) will start in 2007. This plant includes 20 highly irradiating storage tanks for high-level liquid waste before vitrification. The objective of the cleanup phase is to significantly decrease the amount of highly radioactive waste resulting from dismantling. A comprehensive radiological survey of the plant was initiated in 2000. Most of the tanks were characterized using advanced technologies: gamma imaging, CdZnTe gamma spectroscopy, dose rate measurements and 3D calculations codes. At the same time, inspections were conducted to develop 3D geometrical models of the tanks. The techniques used and the main results obtained are described as well as lessons learned from these operations. The rinsing program was defined in 2006. Decontamination operations are expected to begin in 2007, and radiological surveys will be followed up to monitor the efficiency of the decontamination process. Specific rinsing of all tanks and equipment will be carried out from 2007 to 2009. Concentrated liquid solutions will be vitrified between 2008 and 2010; the decommissioning of AVM will be delayed until the end of 2010. This strategy aims at producing less than 5% 'B' type (long-lived intermediate-level) waste from the decommissioning operations, as well as reducing the dose rate and risks by simplified remote dismantling. The paper reviews the main options selected for decontamination, as well as the radiological characterization strategy. Some cost-related aspects will also be analyzed. (authors)

  9. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, A.M.; Ward, C.R.; Jones, J.D.; Mallet, W.R.; Harpring, L.J.; Collins, M.X.; Anderson, E.K.

    1999-08-10

    A mobile robotic system is described that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console. 4 figs.

  10. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, Aed M. (Dearborn, MI); Ward, Clyde R. (Aiken, SC); Jones, Joel D. (Aiken, SC); Mallet, William R. (Cowichan Bay, CA); Harpring, Larry J. (North Augusta, SC); Collins, Montenius X. (Blackville, SC); Anderson, Erin K. (Pleasanton, CA)

    1999-01-01

    A mobile robotic system that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console.

  11. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, Aed M. (Augusta, GA); Wagner, David G. (Augusta, GA); Teese, Gregory D. (Aiken, SC)

    1994-01-01

    An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

  12. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, A.M.; Wagner, D.G.; Teese, G.D.

    1994-06-28

    An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

  13. ORIS: the Oak Ridge Imaging System program listings. [Nuclear...

    Office of Scientific and Technical Information (OSTI)

    program listings. Nuclear medicine imaging with rectilinear scanner and gamma camera Bell, P. R.; Dougherty, J. M. 62 RADIOLOGY AND NUCLEAR MEDICINE; 46 INSTRUMENTATION RELATED...

  14. Surplus Facilities Management Program. Post-remedial-action survey report for SNAP-8 Experimental Reactor Facility, Building 010 site, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Mayes, C.B.; Justus, A.L.; Flynn, K.F.

    1984-04-01

    Based on the results of the radiological assessment, the Argonne National Laboratory Radiological Survey Group arrived at the following conclusions: (1) soil contaminated with the radionuclides /sup 60/Co and /sup 152/Eu of undetermined origin was detected in the southwest quadrant of the Building 010 site. /sup 60/Co was also detected in one environmental sample taken from an area northwest of the site and in a borehole sample taken from the area that previously held the radioactive gas hold-up tanks. Uranium was detected in soil from a hole in the center of the building site and in a second hole southwest of the building site. In all cases, the radionuclide levels encountered in the soil were well below the criteria set by DOE for this site; and (2) the direct instrument readings at the surface of the site were probably the result of natural radiation (terrestrial and celestial), as well as shine from the material being stored at the nearby RMDF facility. There was no evidence that the contaminated soil under the asphalt pad contributed detectable levels to the total background readings.

  15. ES H action plan

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This document contains planned actions to correct the deficiencies identified in the Pre-Tiger Team Self-Assessment (PTTSA), January 1991, of Sandia National Laboratories (SNL -- Albuquerque, New Mexico; Tonopah, Nevada; and Kauai, Hawaii). The Self-Assessment was conducted by a Self-Assessment Working Group consisting of 19 department managers, with support from Environment, Safety, and Health (ES H) professionals, from October through December 1990. Findings from other past audits, dating back to 1985, were reviewed and compared with the PTTSA findings to determine if additional findings, key findings, or root causes were warranted. The resulting ES H Action Plan and individual planned actions were prepared by the ES H Action Plan Project Group with assistance from the Program owners/authors during February and March 1991. The plan was reviewed by SNL Management in April 1991. This document serves as a planning instrument for the Laboratories to aid in the scoping and sizing of activities related to ES H compliance for the coming five years. It will be modified as required to ensure a workload/funding balance and to address the findings resulting from the Tiger Team assessment at SNL, Albuquerque. The process of producing this document has served well to prepare SNL, Albuquerque, for the coming task of producing the required post-Tiger Team action plan document. 8 tabs.

  16. Apparatus for safeguarding a radiological source

    DOE Patents [OSTI]

    Bzorgi, Fariborz M

    2014-10-07

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  17. eFRMAC Overview: Data Management and Enabling Technologies for Characterization of a Radiological Release A Case Study: The Fukushima Nuclear Power Plant Incident

    SciTech Connect (OSTI)

    Blumenthal, Daniel J. [NNSA; Clark, Harvey W. [NSTec; Essex, James J. [NSTec; Wagner, Eric C. [NSTec

    2013-07-01

    The eFRMAC enterprise is a suite of technologies and software developed by the United States Department of Energy, National Nuclear Security Administration’s Office of Emergency Response to coordinate the rapid data collection, management, and analysis required during a radiological emergency. This enables the Federal Radiological Monitoring and Assessment Center assets to evaluate a radiological or nuclear incident efficiently to facilitate protective actions to protect public health and the environment. This document identifies and describes eFRMAC methods including (1) data acquisition, (2) data management, (3) data analysis, (4) product creation, (5) quality control, and (6) dissemination.

  18. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1989-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  19. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M. (Scotia, NY)

    1990-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  20. Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry

    SciTech Connect (OSTI)

    Foltman, A.; Newsom, D.; Lerner, K.

    1988-01-01

    The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility.

  1. Programming

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-Rich Matricesstudents working inProgramming Programming

  2. Programming

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-Rich Matricesstudents working inProgrammingProgramming

  3. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2004 RARAF -Table of Contents

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2004 RARAF - Table of Contents RARAF Staff ...................................................................................................................................................67 Development of Facilities

  4. Idaho National Engineering and Environmental Laboratory Radiological Control Performance Indicator Report -- Fourth Quarter, Calendar Year 1998

    SciTech Connect (OSTI)

    Hinckley, F.L.

    1999-02-01

    This document provides a report of an analysis of the Radiological Control Program through the fourth quarter of Calendar Year (CY-98) and is the annual report for the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth quarter, all areas experienced deletions of work resulting from the Maintenance Stand Down. This reduction in work is a primary factor in the difference in the year end dose and the ALARA goal. The work will be completed during CY-99. Beginning in CY-98, a numeric Radiological Performance Index (RPI) is being used to compare radiological performance. The RPI takes into consideration frequency and severity of events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI measures the cost of these events in cents per hour of radiological work performed. To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used. The data are compared on a quarterly basis to the prior year to show measurable performance.

  5. Formerly Utilized MED/AEC Sites Remedial Action Program. Project management plan for the decontamination of Jones Laboratory, Ryerson Physical Laboratory, and Eckhart Hall, the University of Chicago, Chicago, Illinois

    SciTech Connect (OSTI)

    Flynn, K.F.; Smith, W.H.; Wynveen, R.A.

    1984-01-01

    The Department of Energy (DOE) has in place a plan for the decontamination and decommissioning of contaminated sites that had been formerly utilized by the Manhattan Engineering District (MED) and/or the Atomic Energy Commission. This plan is referred to as the Formerly Utilized Sites Remedial Action Program (FUSRAP). Among these sites are Jones Laboratory, Ryerson Physical Laboratory and Eckhart Hall of The University of Chicago at Chicago, Illinois. This document represents the Project Management Plan for the decontamination of these facilities. 13 references, 3 figures, 1 table.

  6. ACTION PLAN

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach HomeA Better Anode Design to Improve4AJ01) (See Energy Level79AJ01) (NotAdvanced ABSTRACTSFor-1 ACTION

  7. Corrective Action

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News PublicationsAuditsClusterInformationContractCorporate Culture | NationalCorrective Action

  8. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    Iaccarino, Vittorio Venetucci, Pietro

    2012-12-15

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  9. Executive summary: Weldon Spring Site Environmental Report for calendar year 1992. Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    This report has been prepared to provide information about the public safety and environmental protection programs conducted by the Weldon Spring Site Remedial Action Project. The Weldon Spring site is located in southern St. Charles County, Missouri, approximately 48 km (30 mi) west of St. Louis. The site consists of two main areas, the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. The objectives of the Site Environmental Report are to present a summary of data from the environmental monitoring program, to characterize trends and environmental conditions at the site, and to confirm compliance with environmental and health protection standards and requirements. The report also presents the status of remedial activities and the results of monitoring these activities to assess their impacts on the public and environment. The scope of the environmental monitoring program at the Weldon Spring site has changed since it was initiated. Previously, the program focused on investigations of the extent and level of contaminants in the groundwater, surface waters, buildings, and air at the site. In 1992, the level of remedial activities required monitoring for potential impacts of those activities, particularly on surface water runoff and airborne effluents. This report includes monitoring data from routine radiological and nonradiological sampling activities. These data include estimates of dose to the public from the Weldon Spring site; estimates of effluent releases; and trends in groundwater contaminant levels. Also, applicable compliance requirements, quality assurance programs, and special studies conducted in 1992 to support environmental protection programs are reviewed.

  10. Programming

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-Rich Matricesstudents working inProgramming

  11. A comparison of the RCRA Corrective Action and CERCLA Remedial Action Processes

    SciTech Connect (OSTI)

    Traceski, Thomas T.

    1994-02-01

    This document provides a comprehensive side-by-side comparison of the RCRA corrective action and the CERCLA remedial action processes. On the even-numbered pages a discussion of the RCRA corrective action process is presented and on the odd-numbered pages a comparative discussion of the CERCLA remedial action process can be found. Because the two programs have a difference structure, there is not always a direct correlation between the two throughout the document. This document serves as an informative reference for Departmental and contractor personnel responsible for oversight or implementation of RCRA corrective action and CERCLA remedial action activities at DOE environmental restoration sites.

  12. Northern Marshall Islands radiological survey: sampling and analysis summary

    SciTech Connect (OSTI)

    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-07-23

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

  13. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 118 RARAF Table of Contents RARAF Professional ANNUAL REPORT 2008 119 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................119 Development of Facilities

  14. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 113 RARAF - Table of Contents RARAF Professional · ANNUAL REPORT 2007 114 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE CENTER................................................................................................................................................114 Development of Facilities

  15. Radiological Scoping Survey of the Scotia Depot, Scotia, NY

    SciTech Connect (OSTI)

    Bailey, E. N.

    2008-02-25

    The objectives of the radiological scoping survey were to collect adequate field data for use in evaluating the radiological condition of Scotia Depot land areas, warehouses, and support buildings.

  16. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF -Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 117 RARAF - Table of Contents RARAF Professional RESEARCH · ANNUAL REPORT 2010 118 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................117 Development of Facilities

  17. THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents

    E-Print Network [OSTI]

    THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY RARAF Table of Contents RARAF Professional Staff RESEARCH ANNUAL REPORT 2009 The Radiological Research Accelerator Facility AN NIH-SUPPORTED RESOURCE................................................................................................................................................101 Development of Facilities

  18. Results of the radiological survey at Interstate 80, North Right of Way at Lodi Brook, Lodi, New Jersey (LJ077)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and oil sampling for radionuclide analyses. The survey of this site, on the North Right of Way of Interstate 80 at Lodi Brook, Lodi, New Jersey (LJ077), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

  19. Results of the radiological survey at the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Napp Chemical Company, 199 Main Street, Lodi, New Jersey (LJ076), was conducted during 1987. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area. 4 refs., 8 figs., 3 tabs.

  20. Results of the radiological survey at Kennedy Park, Money and Sidney Streets, Lodi, New Jersey (LJ062)

    SciTech Connect (OSTI)

    Foley, R.D.; Cottrell, W.D.; Floyd, L.M.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, Kennedy Park, Money and Sidney Streets, Lodi, New Jersey (LJ062), was conducted during 1986 and 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 4 figs., 3 tabs.

  1. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Broader source: Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  2. ASPECT Emergency Response Chemical and Radiological Mapping

    ScienceCinema (OSTI)

    LANL

    2009-09-01

    A unique airborne emergency response tool, ASPECT is a Los Alamos/U.S. Environmental Protection Agency project that can put chemical and radiological mapping tools in the air over an accident scene. The name ASPECT is an acronym for Airborne Spectral Photometric Environmental Collection Technology. Update, Sept. 19, 2008: Flying over storm-damaged refineries and chemical factories, a twin-engine plane carrying the ASPECT (Airborne Spectral Photometric Environmental Collection Technology) system has been on duty throughout the recent hurricanes that have swept the Florida and Gulf Coast areas. ASPECT is a project of the U.S. U.S. Environmental Protection Agencys National Decontamination Team. Los Alamos National Laboratory leads a science and technology program supporting the EPA and the ASPECT aircraft. Casting about with a combination of airborne photography and infrared spectroscopy, the highly instrumented plane provides emergency responders on the ground with a clear concept of where danger lies, and the nature of the sometimes-invisible plumes that could otherwise kill them. ASPECT is the nations only 24/7 emergency response aircraft with chemical plume mapping capability. Bob Kroutil of Bioscience Division is the project leader, and while he said the team has put in long hours, both on the ground and in the air, its a worthwhile effort. The plane flew over 320 targeted sites in four days, he noted. Prior to the deployment to the Gulf Coast, the plane had been monitoring the Democratic National Convention in Denver, Colorado. Los Alamos National Laboratory Divisions that are supporting ASPECT include, in addition to B-Division, CTN-5: Networking Engineering and IRM-CAS: Communication, Arts, and Services. Leslie Mansell, CTN-5, and Marilyn Pruitt, IRM-CAS, were recognized the the U.S. EPA for their outstanding support to the hurricane response of Gustav in Louisiana and Ike in Texas. The information from the data collected in the most recent event, Hurricane Ike, was sent to the EPA Region 6 Rapid Needs Assessment and the State of Texas Joint Field Office in Austin, Texas. It appears that though there is considerable damage in Galveston and Texas City, there are fewer chemical leaks than during either hurricanes Katrina or Rita. Specific information gathered from the data was reported out to the U.S. Environmental Protection Agency Headquarters, the Federal Emergency Management Agency, the Department of Homeland Security, and the State of Texas Emergency Management Agency.

  3. Request for Curriculum Action Curriculum Deadlines

    E-Print Network [OSTI]

    Barrash, Warren

    Request for Curriculum Action Curriculum Deadlines: November 1 Deadline for submitting changes ONLY) Undergraduate Curriculum Graduate Curriculum Department or Program Chair or Program Coordinator Signature Date Curriculum Change(s) Create new* major/program/minor/emphasis/option/certificate Create new

  4. Radiological Control Manual Environment, Safety, Health, and Quality Division

    E-Print Network [OSTI]

    Wechsler, Risa H.

    ............................................................................................................................................8 128 Facility Modifications and Radiological Design ConsiderationsRadiological Control Manual Environment, Safety, Health, and Quality Division SLAC-I-720-0A05Z-001 and published by ESHQ Publishing Document Title: Radiological Control Manual Original Publication Date: 1

  5. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2001 RARAF Staff Photo

    E-Print Network [OSTI]

    RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 77 The Radiological Research Accelerator Facility AN NIHCENTER FOR RADIOLOGICAL RESEARCH ·ANNUAL REPORT 2001 76 RARAF Staff Photo RARAF staff (l-r): Dr and the track segment facilities continue to be utilized in various investigations of this phenomenon

  6. Applicable or relevant and appropriate requirements (ARARs) for remedial actions at the Paducah Gaseous Diffusion Plant: A compendium of environmental laws and guidance. Environmental Restoration Program

    SciTech Connect (OSTI)

    Etnier, E.L.; Eaton, L.A. [Oak Ridge National Lab., TN (United States)

    1992-03-01

    Section 121 of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 specifies that remedial actions for cleanup of hazardous substances found at sites placed on the National Priorities List (NPL) by the US Environmental Protection Agency (EPA) must comply with applicable or relevant and appropriate requirements (ARARs) or standards under federal and state environmental laws. To date, the US Department of Energy (DOE) Paducah Gaseous Diffusion Plant (PGDP) has not been on the NPL. Although DOE and EPA have entered into an Administrative Consent Order (ACO), the prime regulatory authority for cleanup at PGDP will be the Resource Conservation and Recovery Act (RCRA). This report supplies a preliminary list of available federal and state ARARs that might be considered for remedial response at PGDP in the event that the plant becomes included on the NPL or the ACO is modified to include CERCLA cleanup. A description of the terms ``applicable`` and ``relevant and appropriate`` is provided, as well as definitions of chemical-, location-, and action-specific ARARS. ARARs promulgated by the federal government and by the state of Kentucky are listed in tables. In addition, the major provisions of RCRA, the Safe Drinking Water Act, the Clean Water Act, the Clean Air Act, and other acts, as they apply to hazardous and radioactive waste cleanup, are discussed.

  7. Corrective Action Tracking System (CATS) | Department of Energy

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

    The CATS web-based database is used to enter, track, and report the status of corrective actions developed and implemented in the DOE Corrective Action Management Program (CAMP) to...

  8. Completion Report for Well ER-12-4, Corrective Action Unit 99: Rainier Mesa - Shoshone Mountain (includes Errata Sheet)

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Bechtel Nevada

    2006-05-01

    Well ER-12-4 was drilled for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, in support of the Nevada Environmental Restoration Project at the Nevada Test Site, Nye County, Nevada. This well was drilled in May 2005, as part of a hydrogeologic investigation program for the Rainier Mesa-Shoshone Mountain Corrective Action Unit in the north-central portion of the Nevada Test Site. The well is located on Rainier/Aqueduct Mesa, northwest of Yucca Flat, within Area 12 of the Nevada Test Site. The well provided information regarding the radiological and physical environment near underground nuclear tests conducted in U12t Tunnel, information on the pre-Tertiary rocks in the area, and depth to the regional water table.

  9. Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    G. N. Doyle

    2002-02-01

    Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

  10. Radiological risk assessment of environmental radon

    SciTech Connect (OSTI)

    Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi

    2013-11-27

    Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 ± 76.8 Bq m{sup ?3} to 571.1 ± 251.4 Bq m{sup ?3}, 101.0 ± 41.0 Bq m{sup ?3} to 245.3 ± 100.2 Bq m{sup ?3}, 53.1 ± 7.5 Bq m{sup ?3} to 181.8 ± 9.7 Bq m{sup ?3}, 256.1 ± 59.3 Bq m{sup ?3} to 652.2 ± 222.2 Bq m{sup ?3} and 164.5 ± 75.9 Bq m{sup ?3} to 653.3 ± 240.0 Bq m{sup ?3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 ± 194.3 Bq m{sup ?3}, 192.1 ± 75.4 Bq m{sup ?3}, 176.1 ± 85.9 Bq m{sup ?3} and 28.4 ± 5.7 Bq m{sup ?3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the action level for radon gas of 148 Bq m{sup ?3} proposed by EPA except monazite 0.15 kg, struverite 0.15 kg and 0.25 kg. Whereas, all building material samples have exceeded the radon concentration in concrete and building materials of 3 to 7 Bq m{sup ?3} estimated by ICRP. The annual effective dose, effective dose equivalent, and radon exhalation rates in tin tailings were calculated to be in the range of 2.47 to 11.46 mSv, 5.94 to 1090.56 mSv y{sup ?1}, and 0.23 to 1.18 mBq kg{sup ?1} h{sup ?1}. For building materials, the calculated risk assessment of the annual effective dose, effective dose equivalent, radon exhalation rates and fatal cancer risk were 0.72 to 10.00 mSv, 1.73 to 24.00 mSv y{sup ?1}, 0.010 to 0.06 mBq kg{sup ?1} h{sup ?1} and 40 to 550 chances of persons will suffer the cancer per million (1 × 10{sup 6}), respectively.

  11. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, Sumner Daniel (Danville, CA)

    2010-08-24

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  12. The Formerly Utilized Sites Remedial Action Program (FUSRAP) was initiated in 1974 to identify, investigate, and clean up or control sites throughout the United States that were part of the Nation's early atomic weapons and energy programs during the 1940

    E-Print Network [OSTI]

    US Army Corps of Engineers

    performed by the Manhattan Engineer District or under the Atomic Energy Commission. Both were predecessors atomic weapons and energy programs during the 1940s, 1950s, and 1960s. Activities at the sites were of the Department of Energy. Management of the program was transferred to the US Army Corps of Engineers from the U

  13. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect (OSTI)

    Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

    2010-05-25

    This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

  14. Chemical and Biological Engineering Summary of Actions

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    Chemical and Biological Engineering Summary of Actions 2014-2015 Concern Recommendation Action Follow-up 1. The department name is Chemical and Biological Engineering. An analysis of student Biological Engineering programs. 4. The second semester of the senior capstone sequence in Chemical

  15. Request for Salary Action Requesting action

    E-Print Network [OSTI]

    Arnold, Jonathan

    Request for Salary Action Requesting action: Above "annual entry maximum" Mid-year increase Promotional salary increase exception Counter offer Salary supplement Other Jan. 28 2015 Tracking number Date

  16. EA-1900: Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York

    Broader source: Energy.gov [DOE]

    The Naval Nuclear Propulsion Program (NNPP) intent to prepare an Environmental Assessment for a radiological work and storage building at the Knolls Atomic Power Laboratory (Kesselring Site in West Milton, New York. A new facility is needed to streamline radioactive material handling and storage operations, permit demolition of aging facilities, and accommodate efficient maintenance of existing nuclear reactors.

  17. Nuclear facility decommissioning and site remedial actions

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  18. SEE Action Series: Local Strategies for Whole-Building Energy...

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

    TAP Webinar eere.energy.gov The Parker Ranch installation in Hawaii DOE Technical Assistance Program SEE Action Series: Local Strategies for Whole-Building Energy Savings Molly...

  19. Insights from Smart Meters: Identifying Specific Actions, Behaviors...

    Energy Savers [EERE]

    and Characteristics That Drive Savings in Behavior-Based Programs Insights from Smart Meters: Identifying Specific Actions, Behaviors, and Characteristics That Drive...

  20. Take Action Now: Empower a Secure Energy Future

    Broader source: Energy.gov [DOE]

    Document features a Federal Energy Management Program (FEMP) template for creating a Take Action Now: Empower a Secure Energy Future campaign handout.

  1. Take Action Now: Empower a Secure Energy Future 2

    Broader source: Energy.gov [DOE]

    Document features a Federal Energy Management Program (FEMP) template for creating a Take Action Now: Empower a Secure Energy Future 2 handout.

  2. Texas Solar Collaboration Action Plan

    SciTech Connect (OSTI)

    Winland, Chris

    2013-02-14

    Texas Solar Collaboration Permitting and Interconenction Process Improvement Action Plan. San Antonio-specific; Investigate feasibility of using electronic signatures; Investigate feasibility of enabling other online permitting processes (e.g., commercial); Assess need for future document management and workflow/notification IT improvements; Update Information Bulletin 153 regarding City requirements and processes for PV; Educate contractors and public on CPS Energy’s new 2013 solar program processes; Continue to discuss “downtown grid” interconnection issues and identify potential solutions; Consider renaming Distributed Energy Resources (DER); and Continue to participate in collaborative actions.

  3. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdom’s National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

  4. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.

  5. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  6. Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2010-12-01

    Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. This site is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for the CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The site will be investigated based on the data quality objectives (DQOs) developed on July 6, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for the Baneberry site. The primary release associated with Corrective Action Unit 365 was radiological contamination from the Baneberry nuclear test. Baneberry was an underground weapons-related test that vented significant quantities of radioactive gases from a fissure located in close proximity to ground zero. A crater formed shortly after detonation, which stemmed part of the flow from the fissure. The scope of this investigation includes surface and shallow subsurface (less than 15 feet below ground surface) soils. Radionuclides from the Baneberry test with the potential to impact groundwater are included within the Underground Test Area Subproject. Investigations and corrective actions associated with the Underground Test Area Subproject include the radiological inventory resulting from the Baneberry test.

  7. Guam Energy Action Plan

    SciTech Connect (OSTI)

    Conrad, M. D.; Ness, J. E.

    2013-07-01

    Describes the four near-term strategies selected by the Guam Energy Task Force during action planning workshops conducted in March 2013, and outlines the steps being taken to implement those strategies. Each strategy addresses one of the energy sectors identified in the earlier Guam strategic energy plan as being an essential component of diversifying Guam's fuel sources and reducing fossil energy consumption 20% by 2020. The four energy strategies selected are: (1) expanding public outreach on energy efficiency and conservation, (2) establishing a demand-side management revolving loan program, (3) exploring waste-to-energy options, and (4) influencing the transportation sector via anti-idling legislation, vehicle registration fees, and electric vehicles.

  8. Radiation protection program for early detection of breast cancer in a mammography facility

    SciTech Connect (OSTI)

    Mariana, Villagomez Casimiro E-mail: cesar@fisica.unam.mx; Cesar, Ruiz Trejo E-mail: cesar@fisica.unam.mx; Ruby, Espejo Fonseca

    2014-11-07

    Mammography is the best tool for early detection of Breast Cancer. In this diagnostic radiology modality it is necessary to establish the criteria to ensure the proper use and operation of the equipment used to obtain mammographic images in order to contribute to the safe use of ionizing radiation. The aim of the work was to implement at FUCAM-AC the radiation protection program which must be established for patients and radiation workers according to Mexican standards [1–4]. To achieve this goal, radiation protection and quality control manuals were elaborated [5]. Furthermore, a quality control program (QCP) in the mammography systems (analog/digital), darkroom included, has been implemented. Daily sensitometry, non-variability of the image quality, visualizing artifacts, revision of the equipment mechanical stability, compression force and analysis of repetition studies are some of the QCP routine tests that must be performed by radiological technicians of this institution as a set of actions to ensure the protection of patients. Image quality and patients dose assessment were performed on 4 analog equipment installed in 2 mobile units. In relation to dose assessment, all equipment passed the acceptance criteria (<3 mGy per projection). The image quality test showed that most images (70%)– presented artifacts. A brief summary of the results of quality control tests applied to the equipment and film processor are presented. To maintain an adequate level of quality and safety at FUCAM-AC is necessary that the proposed radiation protection program in this work is applied.

  9. Radiological and Nuclear Security in A Global Context

    E-Print Network [OSTI]

    Jones, Nick

    2010-01-01

    This paper considers the state of nuclear and radiological security in the UK and abroad and reports on the methods that could be employed by terrorists with radiological or nuclear material to cause destruction. It is shown that despite current safeguards that problems arise due to materials that are unaccounted for and poor implementation of detection regimes in some geographical regions. The prospect of a future terrorist event that involves nuclear or radiological materials seems likely despite best efforts of prevention.

  10. Hazelwood Interim Storage Site, Hazelwood, Missouri: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP). [FUSRAP

    SciTech Connect (OSTI)

    Not Available

    1988-04-01

    The monitoring program at the HISS measures radon concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 1 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. The results of 1987 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 12 refs., 6 figs., 11 tabs.

  11. Niagara Falls Storage Site, Lewiston, New York: Annual site environmental report, Calendar year 1987: Formerly Utilized Sites Remedial Action Program (FUSRAP)

    SciTech Connect (OSTI)

    Not Available

    1988-04-01

    The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1987 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 13 refs., 10 figs., 20 tabs.

  12. Climate change action plan

    E-Print Network [OSTI]

    Delivery Climate change action plan 2009-2011 #12;2 | Climate change action plan ©istockphoto.com #12;Climate Change Action Plan Climate change action plan | 3 Contents Overview 4 Preface and Introduction 5 Climate change predictions for Scotland 6 The role of forestry 7 Protecting and managing

  13. FIRE Project Action Plan in Response to

    E-Print Network [OSTI]

    1 FIRE Project Action Plan in Response to Next Step Options Program Advisory Committee Report (PAC1) FIRE Mission: Finding F1-1: PAC-1 felt that the FIRE mission statement, "Attain, explore, understand states the scientific direction and objectives of the FIRE program, but that the mission statement does

  14. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentations

    Office of Energy Efficiency and Renewable Energy (EERE)

    November 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site May 2013 THE MARSAME METHODOLOGY Fundamentals, Benefits, and Applications March 2013 Working to Keep our Shipments Safe, Secure and Economical ANL Facility Decommissioning Training Program January 2013 DOE Corporate Operating Experience Program Radiological Reporting Annual Site Environmental Reports (ASERs) & HSS Environmental and Radiation Protection Performance Dashboards November 2012 Environmental Measurements in an Emergency: This is not a Drill! BGRR D&D Presentation for the DOE ERAD Working Group September 2012 Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Development of Authorized Limits for Portsmouth Oil Inventory Disposition Clearance of Real and Personal Property Under DOE Radiation Protection Directive DOE Order 458.1 June 2012 RESRAD Codes for ERAD June 27, 2012 Florida International University (FIU) D&D Knowledge Management Information Tool, June 27, 2012 May 2012 Integrated Cloud Based Environmental Data Management System DOE Order 458.1, Radiation Protection of the Public and the Environment

  15. FIRE Action Plan to Respond to Next Step Options

    E-Print Network [OSTI]

    1 FIRE Action Plan to Respond to Next Step Options Program Advisory Committee Report #2 July 3, 2001 The FIRE Action s are listed among the NSO-PAC2 recommendations. 1. Response to NSO PAC-1 Report Representatives of the FIRE project presented an action plan for how to respond to issues that had been raised

  16. Accident Investigations of the February 14, 2014, Radiological...

    Office of Environmental Management (EM)

    Room 7 of the underground. Inspections of the mine on April 30, 2014, established that fire behaviors might have been associated with the radiological release event. Because of...

  17. Silver-Mordenite for Radiologic Gas Capture from Complex Streams...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Silver-Mordenite for Radiologic Gas Capture from Complex Streams: Dual Catalytic CH3I Decomposition and I Confinement Citation Details In-Document Search Title:...

  18. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Broader source: Energy.gov [DOE]

    The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients.

  19. Review of the Hanford Tank Farms Radiological Controls Activity...

    Energy Savers [EERE]

    Independent Oversight Review of the Hanford Tank Farms Radiological Controls Activity-Level Implementation May 2011 December 2012 Office of Safety and Emergency Management...

  20. Radiological Release Event at the Waste Isolation Pilot Plant...

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

    radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following...

  1. Nuclear and Radiological Field Training Center | Y-12 National...

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

    Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological...

  2. Bachelor of Science, Radiologic Sciences, Diagnostic Radiology Emphasis, 2014-2015 Name ID# Date

    E-Print Network [OSTI]

    Barrash, Warren

    Information Technology In Radiologic Sciences RADSCI 350 Imaging Pathophysiology RADSCI 370 Junior Recitation 200 Civic and Ethical Foundations 3 DLN BIOL 227 Human Anatomy and Physiology 4 DLN CHEM 101, 101L-4 BIOL 228 Human Anatomy and Physiology 4 BUSCOM 201 Business Communication 3 HLTHST 101 Medical

  3. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About Us ShirleyU.S. DRIVE Vehicle Technologies Office:Vote Phase 2 Radiological

  4. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann Jackson About Us ShirleyU.S. DRIVE Vehicle Technologies Office:Vote Phase 2 Radiological

  5. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

    Michael L. Abbott; Lee C. Cadwallader; David A. Petti

    2003-04-01

    This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

  6. Radiological Safety Training for Accelerator Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 of

  7. Radiological Safety Training for Uranium Facilities

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||Department ofRequest7of 9 Radiological Control8 ofDOE

  8. Nuclear / Radiological Advisory Team | National Nuclear Security

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJessework usesofPublications64NewsroomNontoxicAdministration / Radiological

  9. Uranium Mill Tailings Remedial Action Project 1993 Environmental Report

    SciTech Connect (OSTI)

    Not Available

    1994-10-01

    This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

  10. Infrastructure to support ultra high throughput biodosimetry screening after a radiological event

    E-Print Network [OSTI]

    Brenner, David Jonathan

    GUY GARTY1 , ANDREW KARAM2 , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, Radiological Research Accelerator Facility, Nevis Laboratories, Columbia UniverInfrastructure to support ultra high throughput biodosimetry screening after a radiological event

  11. Remedial Action Plan for the codisposal and stabilization of the Monument Valley and Mexican Hat uranium mill tailings at Mexican Hat, Utah: Appendices C--E. Final report

    SciTech Connect (OSTI)

    NONE

    1993-02-01

    This document provides appendices C, D, and E this Remedial Action Plan (RAP) which is a revision of the original Mexican Hat Remedial Action Plan and RAP Modification submitted in July 1988 and January 1989, respectively, along with updated design documents. Appendix C provide the Radiological Support Plan, Appendix D provides the Site Characterization, and Appendix E provides the Water Resources Protection Strategy.

  12. SBMS Home Page | Program Descriptions | Instructions | Definitions | Revision Record | Toggle Highlighting

    E-Print Network [OSTI]

    and Reports 7. ALARA Program Glossary Introduction This Radiological Protection program description supports of the activities performed and includes formal plans and measures for applying the ALARA process to occupational

  13. Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 98: Frenchman Flat, Nevada National Security Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    Irene Farnham and Sam Marutzky

    2011-07-01

    This CADD/CAP follows the Corrective Action Investigation (CAI) stage, which results in development of a set of contaminant boundary forecasts produced from groundwater flow and contaminant transport modeling of the Frenchman Flat CAU. The Frenchman Flat CAU is located in the southeastern portion of the NNSS and comprises 10 underground nuclear tests. The tests were conducted between 1965 and 1971 and resulted in the release of radionuclides in the subsurface in the vicinity of the test cavities. Two important aspects of the corrective action process are presented within this CADD/CAP. The CADD portion describes the results of the Frenchman Flat CAU data-collection and modeling activities completed during the CAI stage. The corrective action objectives and the actions recommended to meet the objectives are also described. The CAP portion describes the corrective action implementation plan. The CAP begins with the presentation of CAU regulatory boundary objectives and initial use restriction boundaries that are identified and negotiated by NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The CAP also presents the model evaluation process designed to build confidence that the flow and contaminant transport modeling results can be used for the regulatory decisions required for CAU closure. The first two stages of the strategy have been completed for the Frenchman Flat CAU. A value of information analysis and a CAIP were developed during the CAIP stage. During the CAI stage, a CAIP addendum was developed, and the activities proposed in the CAIP and addendum were completed. These activities included hydrogeologic investigation of the underground testing areas, aquifer testing, isotopic and geochemistry-based investigations, and integrated geophysical investigations. After these investigations, a groundwater flow and contaminant transport model was developed to forecast contaminant boundaries that enclose areas potentially exceeding the Safe Drinking Water Act radiological standards at any time within 1,000 years. An external peer review of the groundwater flow and contaminant transport model was completed, and the model was accepted by NDEP to allow advancement to the CADD/CAP stage. The CADD/CAP stage focuses on model evaluation to ensure that existing models provide adequate guidance for the regulatory decisions regarding monitoring and institutional controls. Data-collection activities are identified and implemented to address key uncertainties in the flow and contaminant transport models. During the CR stage, final use restriction boundaries and CAU regulatory boundaries are negotiated and established; a long-term closure monitoring program is developed and implemented; and the approaches and policies for institutional controls are initiated. The model evaluation process described in this plan consists of an iterative series of five steps designed to build confidence in the site conceptual model and model forecasts. These steps are designed to identify data-collection activities (Step 1), document the data-collection activities in the 0CADD/CAP (Step 2), and perform the activities (Step 3). The new data are then assessed; the model is refined, if necessary; the modeling results are evaluated; and a model evaluation report is prepared (Step 4). The assessments are made by the modeling team and presented to the pre-emptive review committee. The decision is made by the modeling team with the assistance of the pre-emptive review committee and concurrence of NNSA/NSO to continue data and model assessment/refinement, recommend additional data collection, or recommend advancing to the CR stage. A recommendation to advance to the CR stage is based on whether the model is considered to be sufficiently reliable for designing a monitoring system and developing effective institutional controls. The decision to advance to the CR stage or to return to step 1 of the process is then made by NDEP (Step 5).

  14. Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01

    This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

  15. Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

    SciTech Connect (OSTI)

    Greg Ruskauff

    2010-04-01

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevada’s groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations are used to compute radionuclide concentrations in time and space within the CAU for the 1,000-year contaminant boundary. These three-dimensional (3-D) concentration simulations are integrated into probabilistic forecasts of the likelihood of groundwater exceeding or remaining below the radiological standards of the Safe Drinking Water Act (CFR, 2009) defined as the contaminant boundary. Contaminant boundaries are not discrete predictions of the location or concentration of contaminants, but instead are spatial representations of the probability of exceeding Safe Drinking Water Act radiological standards. The forecasts provide planning tools to facilitate regulatory decisions designed to protect the health and safety of the public.

  16. APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1

    E-Print Network [OSTI]

    APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES 1998 SITE ENVIRONMENTAL REPORTB-1 APPENDIX B Radiological Data Methodologies 1. DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY Dispersion of airborne and distance. Facility-specific radionuclide release rates (in Ci per year) were also used. All annual site

  17. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2012 Research Using RARAF

    E-Print Network [OSTI]

    at RARAF January 1 - December 31, 2012 #12;THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY Page97CENTER FOR RADIOLOGICAL RESEARCH · ANNUAL REPORT 2012 Page96 Research Using RARAF For almost two Facilities continue to be utilized in various investigations of this phenomenon. Research into bystander

  18. C-1 2003 SITE ENVIRONMENTAL REPORT Radiological Data Methodologies

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2003 SITE ENVIRONMENTAL REPORT APPENDIX C Radiological Data Methodologies DOSE CALCULATION to calculate annual disper- sions for the midpoint of a given sector and distance. Facility Protection Agency Exposure Factors Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur

  19. A Data Warehouse for Integrating Radiologic and Pathologic Data

    E-Print Network [OSTI]

    Rubin, Daniel L.

    A Data Warehouse for Integrating Radiologic and Pathologic Data Daniel L. Rubin, MD, MSa,b , Terry the medical enterprise. Our objective is to describe the design, methodology, and implementation of a data warehouse to integrate and make accessible the types of medical data pertinent to radiology research

  20. Current Trends in Gamma Ray Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

    Mukhopadhyay, S., Guss, P., Maurer, R.

    2011-08-18

    Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

  1. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27

    During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

  2. Results of the radiological survey at the Firemen's Memorial Park and Fire Hall No. 2, Garibaldi Avenue and Kennedy Drive, Lodi, New Jersey (LJ066)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Crutcher, J.W. (Oak Ridge National Lab., TN (USA))

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of the gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the Firemen's Memorial Park and Fire Hall 2, Garibaldi Avenue and Kennedy Drive, Lodi, New Jersey (LJ066) was conducted during 1987. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 4 refs., 10 figs., 3 tabs.

  3. A Web-Based Annotation System for Lung Cancer Radiology Reports

    E-Print Network [OSTI]

    Chen, Xiang

    2012-01-01

    Results in Radiology Reports. Journal of Digital Imagingfrom pathology reports into a Disease Knowledgefor Lung Cancer Radiology Reports A thesis submitted in

  4. Fourth report on the Oak Ridge National Laboratory Biological Monitoring and Abatement Program for White Oak Creek Watershed and the Clinch River

    SciTech Connect (OSTI)

    Loar, J.M. [ed.] [ed.

    1994-04-01

    In response to a condition of the National Pollutant Discharge Elimination System (NPDES) permit issued to Oak Ridge National Laboratory (ORNL) on April 1, 1986, a Biological Monitoring and Abatement Program (BMAP) was developed for White Oak Creek (WOC) and selected tributaries. BMAP currently consists of six major tasks that address both radiological and nonradiological contaminants in the aquatic and terrestrial environs on-site and the aquatic environs off-site. These tasks are (1) toxicity monitoring, (2) bioaccumulation monitoring of nonradiological contaminants in aquatic biota, (3) biological indicator studies, (4) instream ecological monitoring, (5) assessment of contaminants in the terrestrial environment, and (6) radioecology of WOC and White Oak Lake. The ecological characterization of the WOC watershed will provide baseline data that can be used to document the ecological effects of the water pollution control program and the remedial action program. The long-term nature of BMAP ensures that the effectiveness of remedial measures will be properly evaluated.

  5. 2014 Joint Action Workshop

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Joint Action Workshop is an annual event for joint action agencies and their members to meet informally and discuss emerging policy, regulatory, and power supply issues, and other topics...

  6. The Gauged Unparticle Action

    E-Print Network [OSTI]

    A. Lewis Licht

    2008-06-24

    We show that the unparticle action that is made gauge invariant by the inclusion of an open Wilson line factor can be transformed into the integral-differential operator action that avoids the use of the Wilson line factor. The two forms of the action should therefore give the same Feynman diagrams. We also show that it is relatively easy to construct Feynman diagrams using the operator action.

  7. Radioanalytical Data Quality Objectives and Measurement Quality Objectives during a Federal Radiological Monitoring and Assessment Center Response

    SciTech Connect (OSTI)

    E. C. Nielsen

    2006-01-01

    During the early and intermediate phases of a nuclear or radiological incident, the Federal Radiological Monitoring and Assessment Center (FRMAC) collects environmental samples that are analyzed by organizations with radioanalytical capability. Resources dedicated to quality assurance (QA) activities must be sufficient to assure that appropriate radioanalytical measurement quality objectives (MQOs) and assessment data quality objectives (DQOs) are met. As the emergency stabilizes, QA activities will evolve commensurate with the need to reach appropriate DQOs. The MQOs represent a compromise between precise analytical determinations and the timeliness necessary for emergency response activities. Minimum detectable concentration (MDC), lower limit of detection, and critical level tests can all serve as measurements reflecting the MQOs. The relationship among protective action guides (PAGs), derived response levels (DRLs), and laboratory detection limits is described. The rationale used to determine the appropriate laboratory detection limit is described.

  8. Recovery from chemical, biological, and radiological incidents :

    SciTech Connect (OSTI)

    Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

    2012-06-01

    To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

  9. Highly Effective Actions

    E-Print Network [OSTI]

    John H. Schwarz

    2013-11-22

    It is conjectured that the world-volume action of a probe D3-brane in an $AdS_5 \\times S^5$ background of type IIB superstring theory, with one unit of flux, can be reinterpreted as the exact effective action (or highly effective action) for U(2), ${\\cal N} = 4$ super Yang-Mills theory on the Coulomb branch. An analogous conjecture for $U(2)_k \\times U(2)_{-k} $ ABJM theory is also presented. The main evidence supporting these conjectures is that the brane actions have all of the expected symmetries and dualities. Highly effective actions have general coordinate invariance, even though they describe nongravitational theories.

  10. COMMUNITY ACTION PROGRAM OF EAST CENTRAL OREGON

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D B LReports from the Cloud ModelingPracticesWESTERN

  11. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and Myers CoMadison -T:..) "..LMEDIAL"

  12. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and Myers CoMadison -T:..) "..LMEDIAL".

  13. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700, 1.Reports1E~ S·D3 WeldonY.B.FINDING

  14. FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouth DakotaRobbins and700, 1.Reports1E~ S·D3 WeldonY.B.FINDING

  15. Savannah River Site ALARA Program appraisals

    SciTech Connect (OSTI)

    Johnson, J.R.

    1992-01-01

    ALARA Program audits are recommended in PNL-6566, Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are As Low As Reasonably Achievable (ALARA).'' The Department of Energy (DOE) Order 5480.11, Radiation Protection For Occupational Workers,'' requires contractors to conduct internal audits of all functional elements of the radiological protection program, which includes the ALARA program, as often as necessary, but at a minimum every three years. At the Savannah River Site (SRS), these required audits are performed as part of the Health Protection Internal Appraisal Program. This program was established to review the Site radiological protection program, which includes the ALARA program, on an ongoing basis and to provide recommendations for improvement directly to senior Health Protection management. This paper provides an overview of the SRS Health Protection Internal Appraisal program. In addition, examples of specific performance criteria and detailed appraisal guidelines used ALARA appraisals are provided.

  16. Savannah River Site ALARA Program appraisals

    SciTech Connect (OSTI)

    Johnson, J.R.

    1992-06-01

    ALARA Program audits are recommended in PNL-6566, ``Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are As Low As Reasonably Achievable (ALARA).`` The Department of Energy (DOE) Order 5480.11, ``Radiation Protection For Occupational Workers,`` requires contractors to conduct internal audits of all functional elements of the radiological protection program, which includes the ALARA program, as often as necessary, but at a minimum every three years. At the Savannah River Site (SRS), these required audits are performed as part of the Health Protection Internal Appraisal Program. This program was established to review the Site radiological protection program, which includes the ALARA program, on an ongoing basis and to provide recommendations for improvement directly to senior Health Protection management. This paper provides an overview of the SRS Health Protection Internal Appraisal program. In addition, examples of specific performance criteria and detailed appraisal guidelines used ALARA appraisals are provided.

  17. Action Item Review and Status

    Office of Environmental Management (EM)

    Waste Corporate Board Action Items Action Item Resolution Action Item Strategic Planning Initiative Optimization Study Resolution Presentation by S. Schneider (HLW System...

  18. Action Sheet 36 Final Report

    SciTech Connect (OSTI)

    Kips, R E; Kristo, M J; Hutcheon, I D

    2012-02-24

    Pursuant to the Arrangement between the European Commission DG Joint Research Centre (EC-JRC) and the Department of Energy (DOE) to continue cooperation on research, development, testing, and evaluation of technology, equipment, and procedures in order to improve nuclear material control, accountancy, verification, physical protection, and advanced containment and surveillance technologies for international safeguards, dated 1 September 2008, the IRMM and LLNL established cooperation in a program on the Study of Chemical Changes in Uranium Oxyfluoride Particles under IRMM-LLNL Action Sheet 36. The work under this action sheet had 2 objectives: (1) Achieve a better understanding of the loss of fluorine in UO{sub 2}F{sub 2} particles after exposure to certain environmental conditions; and (2) Provide feedback to the EC-JRC on sample reproducibility and characteristics.

  19. INTERIOR WETLANDS PROGRAM STRATEGIC PLAN

    E-Print Network [OSTI]

    #12;INTERIOR WETLANDS PROGRAM STRATEGIC PLAN 1993 -1997 July 1993 FRASER RIVER ACTION PLAN CANADA'S GREEN PLAN ENVIRONMENT CANADA DUCKS UNLIMITED CANADA GOVERNMENT OF BRITISH COLUMBIA #12;Table

  20. General statement of policy and procedures for NRC enforcement actions: Enforcement policy. Revision 1

    SciTech Connect (OSTI)

    1998-05-01

    This document includes the US Nuclear Regulatory Commission`s (NRC`s or Commission`s) revised General Statement of Policy and Procedure for Enforcement Actions (Enforcement Policy) as it was published in the Federal Register on May 13, 1998 (63 ER 26630). The Enforcement Policy is a general statement of policy explaining the NRC`s policies and procedures in initiating enforcement actions, and of the presiding officers and the Commission in reviewing these actions. This policy statement is applicable to enforcement matters involving the radiological health and safety of the public, including employees` health and safety, the common defense and security, and the environment.

  1. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  2. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Mexican Hat, Utah: Appendix D. Final report

    SciTech Connect (OSTI)

    NONE

    1988-07-01

    This appendix is an assessment of the present conditions of the inactive uranium mill site near Mexican Hat, Utah. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan. Plan is to characterize the conditions at the mill and tailings site so that the Remedial Action Contractor may complete final designs of the remedial action.

  3. Posting and Labeling for Radiological Control Guide for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection

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

    1999-05-24

    This Guide provides an acceptable methodology for establishing and operating a radiological hazard posting and labeling program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection Canceled by DOE G 441.1-1B.

  4. Selected Programs College Program

    E-Print Network [OSTI]

    Rosen, Jay

    Technology Radiologic Technology Community Health Nuclear Medicine Technology Nursing - RN Nursing - LPN / Rehabilitation / School Counseling Community Health Speech-Language Pathology Medical Laboratory Technology Medical Laboratory Technology Nursing Mental Health Counselling Social Work Bronx CC Medical Laboratory

  5. Radiological Release Accident Investigation Report (Phase II...

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

    Investigation Report (Phase II Report) More Documents & Publications Central Characterization Program (CCP) Los Alamos National Laboratory (LANL) Interface Document Oak Ridge...

  6. Bayesian Network Analysis of Radiological Dispersal Device Acquisitions 

    E-Print Network [OSTI]

    Hundley, Grant Richard

    2012-02-14

    It remains unlikely that a terrorist organization could produce or procure an actual nuclear weapon. However, the construction of a radiological dispersal device (RDD) from commercially produced radioactive sources and conventional explosives could...

  7. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 113: Reactor Maintenance, Assembly, and Disassembly Building Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    J. L. Smith

    2001-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the action necessary for the closure in place of Corrective Action Unit (CAU) 113 Area 25 Reactor Maintenance, Assembly, and Disassembly Facility (R-MAD). CAU 113 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (NDEP, 1996). The CAU is located in Area 25 of the Nevada Test Site (NTS) and consists of Corrective Action Site (CAS) 25-04-01, R-MAD Facility (Figures 1-2). This plan provides the methodology for closure in place of CAU 113. The site contains radiologically impacted and hazardous material. Based on preassessment field work, there is sufficient process knowledge to close in place CAU 113 using the SAFER process. At a future date when funding becomes available, the R-MAD Building (25-3110) will be demolished and inaccessible radiologic waste will be properly disposed in the Area 3 Radiological Waste Management Site (RWMS).

  8. Protective Actions and Reentry

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

    1997-08-21

    This volume defines appropriate protective actions and reentry of a site following an emergency. Canceled by DOE G 151.1-4.

  9. In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268

    SciTech Connect (OSTI)

    Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike; Matthews, Brian

    2012-07-01

    Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

  10. Office of radiation and indoor air: Program description

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    The goal of the Environmental Protection Agency`s (EPA) Office of Radiation and Indoor Air is to protect the public and the environment from exposures to radiation and indoor air pollutants. The Office develops protection criteria, standards, and policies and works with other programs within EPA and other agencies to control radiation and indoor air pollution exposures; provides technical assistance to states through EPA`s regional offices and other agencies having radiation and indoor air protection programs; directs an environmental radiation monitoring program; responds to radiological emergencies; and evaluates and assesses the overall risk and impact of radiation and indoor air pollution. The Office is EPA`s lead office for intra- and interagency activities coordinated through the Committee for Indoor Air Quality. It coordinates with and assists the Office of Enforcement in enforcement activities where EPA has jurisdiction. The Office disseminates information and works with state and local governments, industry and professional groups, and citizens to promote actions to reduce exposures to harmful levels of radiation and indoor air pollutants.

  11. Antiplatelet and Anticoagulant Drugs in Interventional Radiology

    SciTech Connect (OSTI)

    Altenburg, Alexander; Haage, Patrick, E-mail: patrick.haage@helios-kliniken.de [University Hospital Witten/Herdecke, Department of Diagnostic and Interventional Radiology, HELIOS Klinikum Wuppertal (Germany)

    2012-02-15

    In treating peripheral arterial disease, a profound knowledge of antiplatelet and anticoagulative drug therapy is helpful to assure a positive clinical outcome and to anticipate and avoid complications. Side effects and drug interactions may have fatal consequences for the patient, so interventionalists should be aware of these risks and able to control them. Aspirin remains the first-line agent for antiplatelet monotherapy, with clopidogrel added where dual antiplatelet therapy is required. In case of suspected antiplatelet drug resistance, the dose of clopidogrel may be doubled; prasugrel or ticagrelor may be used alternatively. Glycoprotein IIb/IIIa inhibitors (abciximab or eptifibatide) may help in cases of hypercoagulability or acute embolic complications. Desmopressin, tranexamic acid, or platelet infusions may be used to decrease antiplatelet drug effects in case of bleeding. Intraprocedurally, anticoagulant therapy treatment with unfractionated heparin (UFH) still is the means of choice, although low molecular-weight heparins (LMWH) are suitable, particularly for postinterventional treatment. Adaption of LMWH dose is often required in renal insufficiency, which is frequently found in elderly patients. Protamine sulphate is an effective antagonist for UFH; however, this effect is less for LMWH. Newer antithrombotic drugs, such as direct thrombin inhibitors or factor X inhibitors, have limited importance in periprocedural treatment, with the exception of treating patients with heparin-induced thrombocytopenia (HIT). Nevertheless, knowing pharmacologic properties of the newer drugs facilitate correct bridging of patients treated with such drugs. This article provides a comprehensive overview of antiplatelet and anticoagulant drugs for use before, during, and after interventional radiological procedures.

  12. Corrective Action Investigation Plan for Corrective Action Unit 550: Smoky Contamination Area Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2012-05-01

    Corrective Action Unit (CAU) 550 is located in Areas 7, 8, and 10 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 550, Smoky Contamination Area, comprises 19 corrective action sites (CASs). Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plumes, it was determined that some of the CAS releases are co-located and will be investigated as study groups. This document describes the planned investigation of the following CASs (by study group): (1) Study Group 1, Atmospheric Test - CAS 08-23-04, Atmospheric Test Site T-2C; (2) Study Group 2, Safety Experiments - CAS 08-23-03, Atmospheric Test Site T-8B - CAS 08-23-06, Atmospheric Test Site T-8A - CAS 08-23-07, Atmospheric Test Site T-8C; (3) Study Group 3, Washes - Potential stormwater migration of contaminants from CASs; (4) Study Group 4, Debris - CAS 08-01-01, Storage Tank - CAS 08-22-05, Drum - CAS 08-22-07, Drum - CAS 08-22-08, Drums (3) - CAS 08-22-09, Drum - CAS 08-24-03, Battery - CAS 08-24-04, Battery - CAS 08-24-07, Batteries (3) - CAS 08-24-08, Batteries (3) - CAS 08-26-01, Lead Bricks (200) - CAS 10-22-17, Buckets (3) - CAS 10-22-18, Gas Block/Drum - CAS 10-22-19, Drum; Stains - CAS 10-22-20, Drum - CAS 10-24-10, Battery. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 31, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 550. The potential contamination sources associated with the study groups are from nuclear testing activities conducted at CAU 550. The DQO process resulted in an assumption that the total effective dose (TED) within the default contamination boundary of CAU 550 exceeds the final action level and requires corrective action. The presence and nature of contamination outside the default contamination boundary at CAU 550 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each group of CASs.

  13. Results of the radiological survey at the property at Main Street and Highway 46, Lodi, New Jersey (LJ074)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurements of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site located at the intersection of Main Street and Highway 46, Lodi, New Jersey (LJ074), was conducted during 1987. While some radiological measurements taken at the vacant lot at the intersection of Main Street and Highway 46 were greater than background levels typically encountered in the northern New Jersey area, no radiation levels nor radionuclide concentrations exceeded the applicable DOE criteria. The survey results demonstrate that the radiological condition of this property conforms to DOE guidelines for remedial action. 4 refs., 5 figs., 3 tabs.

  14. Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.:0

    SciTech Connect (OSTI)

    Wickline, Alfred

    2005-12-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 137: Waste Disposal Sites. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. Corrective Action Unit 137 contains sites that are located in Areas 1, 3, 7, 9, and 12 of the Nevada Test Site (NTS), which is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 137 is comprised of the eight corrective action sites (CASs) shown on Figure 1-1 and listed below: (1) CAS 01-08-01, Waste Disposal Site; (2) CAS 03-23-01, Waste Disposal Site; (3) CAS 03-23-07, Radioactive Waste Disposal Site; (4) CAS 03-99-15, Waste Disposal Site; (5) CAS 07-23-02, Radioactive Waste Disposal Site; (6) CAS 09-23-07, Radioactive Waste Disposal Site; (7) CAS 12-08-01, Waste Disposal Site; and (8) CAS 12-23-07, Waste Disposal Site. The Corrective Action Investigation (CAI) will include field inspections, radiological surveys, geophysical surveys, sampling of environmental media, analysis of samples, and assessment of investigation results, where appropriate. Data will be obtained to support corrective action alternative evaluations and waste management decisions. The CASs in CAU 137 are being investigated because hazardous and/or radioactive constituents may be present in concentrations that could potentially pose a threat to human health and the environment. Existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives for the CASs. Additional information will be generated by conducting a CAI before evaluating and selecting corrective action alternatives.

  15. Progress Continues on Mitigation of Radiological Contamination

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass mapSpeedingProgramExemptions | NationalProcurementworkProgramProgramsProgress

  16. ORISE Resources: Radiological and Nuclear Terrorism: Medical...

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

    Health asked the Oak Ridge Institute for Science and Education (ORISE) to develop a Web-based and CD-ROM training program to prepare clinicians-medical doctors and registered...

  17. Uranium Mill Tailings Remedial Action Project 1994 environmental report

    SciTech Connect (OSTI)

    NONE

    1995-08-01

    This annual report documents the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1994, surface remedial action was complete at 14 of the 24 designated UMTRA Project processing sites: Canonsburg, Pennsylvania; Durango, Colorado; Grand Junction, Colorado; Green River Utah, Lakeview, Oregon; Lowman, Idaho; Mexican Hat, Utah; Riverton, Wyoming; Salt Lake City, Utah; Falls City, Texas; Shiprock, New Mexico; Spook, Wyoming, Tuba City, Arizona; and Monument Valley, Arizona. Surface remedial action was ongoing at 5 sites: Ambrosia Lake, New Mexico; Naturita, Colorado; Gunnison, Colorado; and Rifle, Colorado (2 sites). Remedial action has not begun at the 5 remaining UMTRA Project sites that are in the planning stage. Belfield and Bowman, North Dakota; Maybell, Colorado; and Slick Rock, Colorado (2 sites). The ground water compliance phase of the UMTRA Project started in 1991. Because the UMTRA Project sites are.` different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.

  18. Implement an Institutional Change Action Plan for Sustainability

    Broader source: Energy.gov [DOE]

    Writing a good action plan is one thing; implementing it is another. Institutional change principles and methods can be incorporated into action plans (program design), but on-the-ground implementation activities must also be conducted in a manner that is suitable to the organizational context and the people in the roles being targeted.

  19. UNIVERSITY OF CALIFORNIA, IRVINE "GREEN" ACTIONS UNDERWAY OR COMPLETED

    E-Print Network [OSTI]

    Rose, Michael R.

    into 18 categories: 1. Research: Centers and Academic Programs 2. Green Buildings 3. Renewable Energy 4UNIVERSITY OF CALIFORNIA, IRVINE "GREEN" ACTIONS UNDERWAY OR COMPLETED "I recognize the right #12;July 2011 UC IRVINE "GREEN" ACTIONS UNDERWAY OR COMPLETED JULY 2011 This outline summarizes UC

  20. SEE Action Webinar on Community-Based Social Marketing

    Broader source: Energy.gov [DOE]

    Hosted by the State and Local Energy Efficiency Action Network, this webinar will describe community-based social marketing as a behavior-based approach for developing energy efficiency programs.

  1. Program Development

    SciTech Connect (OSTI)

    Atencio, Julian J.

    2014-05-01

    This presentation covers how to go about developing a human reliability program. In particular, it touches on conceptual thinking, raising awareness in an organization, the actions that go into developing a plan. It emphasizes evaluating all positions, eliminating positions from the pool due to mitigating factors, and keeping the process transparent. It lists components of the process and objectives in process development. It also touches on the role of leadership and the necessity for audit.

  2. An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York

    SciTech Connect (OSTI)

    Berry, H.A.

    1991-09-01

    An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs.

  3. Radiological assessment. A textbook on environmental dose analysis

    SciTech Connect (OSTI)

    Till, J.E.; Meyer, H.R.

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

  4. USING RISK-BASED CORRECTIVE ACTION (RBCA) TO ASSESS (THEORETICAL) CANCER DEATHS AVERTED COMPARED TO THE (REAL) COST OF ENVIRONMENTAL REMEDIATION

    SciTech Connect (OSTI)

    Miller, M. L.; Hylko, J. M.

    2002-02-25

    In 1978, on the basis of existing health studies at the time, the Uranium Mill Tailings Remedial Action (UMTRA) Project legislation was proposed that would authorize remedial action at inactive uranium processing sites and vicinity properties. The cost of the program to the Federal Government was expected to be $180 million. With the completion of this project, approximately 1300 theoretical cancer deaths were prevented in the next 100 years at a cost of $1.45 billion, based on the Fiscal Year 1998 Federal UMTRA budget. The individual site costs ranged from $0.2 million up to $18 billion spent per theoretical cancer death averted over the next 100 years. Resources required to sustain remediation activities such as this are subject to reduction over time, and are originally based on conservative assumptions that tend to overestimate risks to the general public. This evaluation used a process incorporating risk-based corrective action (RBCA); a three-tiered, decision-making process tailoring corrective action activities according to site-specific conditions and risks. If RBCA had been applied at the start of the UMTRA Project, and using a criterion of >1 excess cancer death prevented as justification to remediate the site, only 50% of the existing sites would have been remediated, yielding a cost savings of $303.6 million to the Federal Government and affected States, which share 10% of the cost. This cost savings equates to 21% of the overall project budget. In addition, only 22% of the vicinity properties had structural contamination contributing to elevated interior gamma exposure and radon levels. Focusing only on these particular properties could have saved an additional $269.3 million, yielding a total savings of $573 million; 40% of the overall project budget. As operational experience is acquired, including greater understanding of the radiological and nonradiological risks, decisions should be based on the RBCA process, rather than relying on conservative assumptions that tend to overestimate risks to the general public.

  5. Notices ACTION: Notice.

    Office of Environmental Management (EM)

    8867 Federal Register Vol. 80, No. 215 Friday, November 6, 2015 Notices ACTION: Notice. SUMMARY: This notice announces EPA's receipt of an application 91163-EUP-R from Texas...

  6. Notices ACTION: Notice.

    Energy Savers [EERE]

    867 Federal Register Vol. 80, No. 215 Friday, November 6, 2015 Notices ACTION: Notice. SUMMARY: This notice announces EPA's receipt of an application 91163-EUP-R from Texas...

  7. Corrective Action Investigation Plan for Corrective Action Unit 562: Waste Systems Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2009-04-01

    Corrective Action Unit 562 is located in Areas 2, 23, and 25 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 562 is comprised of the 13 corrective action sites (CASs) listed below: • 02-26-11, Lead Shot • 02-44-02, Paint Spills and French Drain • 02-59-01, Septic System • 02-60-01, Concrete Drain • 02-60-02, French Drain • 02-60-03, Steam Cleaning Drain • 02-60-04, French Drain • 02-60-05, French Drain • 02-60-06, French Drain • 02-60-07, French Drain • 23-60-01, Mud Trap Drain and Outfall • 23-99-06, Grease Trap • 25-60-04, Building 3123 Outfalls These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on December 11, 2008, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 562. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 562 includes the following activities: • Move surface debris and/or materials, as needed, to facilitate sampling. • Conduct radiological surveys. • Perform field screening. • Collect and submit environmental samples for laboratory analysis to determine the nature and extent of any contamination released by each CAS. • Collect samples of source material to determine the potential for a release. • Collect samples of potential remediation wastes. • Collect quality control samples. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended February 2008). Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval of the plan.

  8. Assessment of SRS radiological liquid and airborne contaminants and pathways

    SciTech Connect (OSTI)

    Jannik, G.T.

    1997-04-01

    This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people.

  9. Bondholders and Securities Class Actions

    E-Print Network [OSTI]

    Park, James

    2015-01-01

    2006). 89. See Consolidated Class Action Complaint ¶¶ 42–53,Sept. 30, 2005); Consolidated Class Action Complaint ¶ 1, Inlikely to satisfy various class certification hurdles. See

  10. Climate Action Plan 2013 Update

    E-Print Network [OSTI]

    Rose, Michael R.

    UC Irvine Climate Action Plan 2013 Update #12;CLIMATE ACTION PLAN - 2013 UPDATE 1 TABLE OF CONTENTS CLIMATE PROTECTION GOALS...............................................................18 OPPORTUNITIES-2050 CLIMATE NEUTRALITY.........................................................29 MEDICALCENTER IMPLEMENTATION

  11. Savannah River Site Radiological Technology Center's Efforts Supporting Waste Minimization

    SciTech Connect (OSTI)

    Rosenberger, K. H.; Smith, L. S.; Bates, R. L.

    2003-02-25

    This paper describes the efforts of the newly formed Radiological Technology Center (RTC) at the Department of Energy's Savannah River Site (SRS) to support waste minimization. The formation of the RTC was based upon the highly successful ALARA Center at the DOE Hanford Site. The RTC is tasked with evaluation and dissemination of new technologies and techniques for radiological hazard reduction and waste minimization. Initial waste minimization efforts have focused on the promotion of SRS containment fabrication capabilities, new personal protective equipment and use of recyclable versus disposable materials.

  12. Corrective Action Decision Document/Closure Report for Corrective Action Unit 106: Area 5, 11 Frenchman Flat Atmospheric Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews and Dawn Peterson

    2011-09-01

    Corrective Action Unit 106 comprises four corrective action sites (CASs): (1) 05-20-02, Evaporation Pond; (2) 05-23-05, Atmospheric Test Site - Able; (3) 05-45-04, 306 GZ Rad Contaminated Area; (4) 05-45-05, 307 GZ Rad Contaminated Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 106 based on the implementation of corrective actions. The corrective action of clean closure was implemented at CASs 05-45-04 and 05-45-05, while no corrective action was necessary at CASs 05-20-02 and 05-23-05. Corrective action investigation (CAI) activities were performed from October 20, 2010, through June 1, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (mechanical displacement and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 106 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Industrial Area exposure scenario (2,250 hours of annual exposure). The only radiological dose exceeding the FAL was at CAS 05-45-05 and was associated with potential source material (PSM). It is also assumed that additional PSM in the form of depleted uranium (DU) and DU-contaminated debris at CASs 05-45-04 and 05-45-05 exceed the FAL. Therefore, corrective actions were undertaken at these CASs that consisted of removing PSM and collecting verification samples. Results of verification samples show that remaining soil does not contain contamination exceeding the FALs. Therefore, the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) provides the following recommendations: (1) No further corrective actions are necessary for CAU 106. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 106. (3) Corrective Action Unit 106 should be moved from Appendix III to Appendix IV of the FFACO.

  13. Corrective Action Decision Document/Closure Report for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-06-01

    Corrective Action Unit 367 comprises four corrective action sites (CASs): • 10-09-03, Mud Pit • 10-45-01, U-10h Crater (Sedan) • 10-45-02, Ess Crater Site • 10-45-03, Uncle Crater Site The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation of the corrective actions and site closure activities implemented at CAU 367. A corrective action of closure in place with use restrictions was completed at each of the three crater CASs (10-45-01, 10-45-02, and 10-45-03); corrective actions were not required at CAS 10-09-03. In addition, a limited soil removal corrective action was conducted at the location of a potential source material release. Based on completion of these correction actions, no additional corrective action is required at CAU 367, and site closure is considered complete. Corrective action investigation (CAI) activities were performed from February 2010 through March 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 367: Area 10 Sedan, Ess and Uncle Unit Craters, Nevada Test Site, Nevada. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of non-test or other releases (e.g., migration in washes and potential source material). Based on the proximity of the Uncle, Ess, and Sedan craters, the impact of the Sedan test on the fallout deposited from the two earlier tests, and aerial radiological surveys, the CAU 367 investigation was designed to study the releases from the three crater CASs as one combined release (primary release). Corrective Action Site 10-09-03, Mud Pit, consists of two mud pits identified at CAU 367. The mud pits are considered non-test releases or other releases and were investigated independent of the three crater CASs. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 367 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels (FALs) established in this document. For the primary release, radiological doses exceeding the FAL of 25 millirem per year were not found to be present in the surface or shallow subsurface soil outside the default contamination boundary. However, it was assumed that radionuclides are present in subsurface media within each of the three craters (Sedan, Ess, and Uncle) due to prompt injection of radionuclides from the tests. Based on the assumption of radiological dose exceeding the FAL, corrective actions were undertaken that consisted of implementing a use restriction and posting warning signs at each crater CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. With regard to other releases, no contaminants of concern were identified at the mud pits or any of the other release locations, with one exception. Potential source material in the form of lead was found at one location. A corrective action of clean closure was implemented at this location, and verification samples indicated that no further action is necessary. Therefore, NNSA/NSO provides the following recommendations: • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 367. • Corrective Action Unit 367 should be promoted from Appendix III to Appendix IV of the FFACO.

  14. C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2001 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES DOSE CALCULATION sector and distance. Facility-specificradionuclidereleaserates(incuries per year [Ci/yr]) were also used 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

  15. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01

    radiological exposures may also present first to healthcare facilities.facility-based decontamination of victims exposed to chemical, biological, and radiologicalfacility-based decontamination of victims exposed to chemical, biological, and radiological

  16. Surface with two paint strips for detection and warning of chemical warfare and radiological agents

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2013-04-02

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  17. Method for warning of radiological and chemical substances using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2012-03-13

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  18. Paint for detection of corrosion and warning of chemical and radiological attack

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA)

    2010-08-24

    A system for warning of corrosion, chemical, or radiological substances. The system comprises painting a surface with a paint or coating that includes an indicator material and monitoring the surface for indications of the corrosion, chemical, or radiological substances.

  19. Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada: Revision 0

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2004-05-03

    The general purpose of this Corrective Action Investigation Plan is to ensure that adequate data are collected to provide sufficient and reliable information to identify, evaluate, and select technically viable corrective action alternatives (CAAs) for Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. Located in Areas 6 and 15 on the NTS, CAU 543 is comprised of a total of seven corrective action sites (CASs), one in Area 6 and six in Area 15. The CAS in Area 6 consists of a Decontamination Facility and its components which are associated with decontamination of equipment, vehicles, and materials related to nuclear testing. The six CASs in Area 15 are located at the U.S. Environmental Protection Agency Farm and are related to waste disposal activities at the farm. Sources of possible contamination at Area 6 include potentially contaminated process waste effluent discharged through a process waste system, a sanitary waste stream generated within buildings of the Decon Facility, and radiologically contaminated materials stored within a portion of the facility yard. At Area 15, sources of potential contamination are associated with the dairy operations and the animal tests and experiments involving radionuclide uptake. Identified contaminants of potential concern include volatile organic compounds, semivolatile organic compounds, petroleum hydrocarbons, pesticides, herbicides, polychlorinated biphenyls, metals, and radionuclides. Three corrective action closure alternatives - No Further Action, Close in Place, or Clean Closure - will be recommended for CAU 543 based on an evaluation of all the data quality objective-related data. Field work will be conducted following approval of the plan. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document.

  20. Mitigation Action Plan

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    This Mitigation Action Plan (MAP) focuses on mitigation commitments stated in the Supplemental Environmental Impact Statement (SEIS) and the Record of Decision (ROD) for the Naval Petroleum Reserve No. 1 (NPR-1). Specific commitments and mitigation implementation actions are listed in Appendix A-Mitigation Actions, and form the central focus of this MAP. They will be updated as needed to allow for organizational, regulatory, or policy changes. It is the intent of DOE to comply with all applicable federal, state, and local environmental, safety, and health laws and regulations. Eighty-six specific commitments were identified in the SEIS and associated ROD which pertain to continued operation of NPR-1 with petroleum production at the Maximum Efficient Rate (MER). The mitigation measures proposed are expected to reduce impacts as much as feasible, however, as experience is gained in actual implementation of these measures, some changes may be warranted.

  1. Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2010 SITE ENVIRONMENTAL REPORT8-1 DRAFT The radiological dose assessment assures stakeholders that BNL facilities and operations are in compliance with federal, state, and local regulations and the public is protected. The potential radiological dose to members of the public

  2. The RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological developments

    E-Print Network [OSTI]

    Brenner, David Jonathan

    , & DAVID J. BRENNER3 1 Radiological Research Accelerator Facility, 2 Department of Mechanical EngineeringThe RABiT: A Rapid Automated Biodosimetry Tool for radiological triage. II. Technological, and 3 Center for Radiological Research, Columbia University, New York, NY, USA (Received 14 September

  3. Radiological Dose Assessment 8 2011 Site environmental report8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2011 Site environmental report8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and operations are in compliance with federal, state and local regulations, and that the public is protected. The potential radiological dose to members

  4. Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2013 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

  5. Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1

    E-Print Network [OSTI]

    Radiological Dose Assessment 8 2012 SITE ENVIRONMENTAL REPORT8-1 BNL's annual radiological dose assessment assures stakeholders that on-site facilities and BNL operations are in compliance with federal, state, and local regulations, and that the public is protected. The potential radiological dose

  6. Compressed Air Storage Strategies; Industrial Technologies Program...

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

    Industrial Technologies Program Suggested Actions * Review the plant's compressed air demand patterns to determine whether storage would be beneficial. * Examine the compressed...

  7. Continuity Programs - DOE Directives, Delegations, and Requirements

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

    O 150.1, Continuity Programs on Mar 31, 2014 Bonneville Power Administration There are no Technical Standards invoked in this document. Document Actions Print this Gary Richards...

  8. Environmental Compliance Audit & Assessment Program Manual

    E-Print Network [OSTI]

    Thorson, Patrick

    2009-01-01

    Environmental Restoration (ERP) Environmental Services (ESG)Action Program (CAP). The ERP is responsible for carryingResponsibilities of the ERP include the following: ERP

  9. INEEL Radiological Control Performance Indicator Report - Quarterly for CY-99

    SciTech Connect (OSTI)

    Hinckley, Frank Leroy

    2000-02-01

    This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 63.034 person-rem year to date, compared to a goal of 83.1 person-rem. During the fourth quarter, all areas experienced deletions of work resulting from the Maintenance Stand Down. This reduction in work is a primary factor in the difference in the year end dose and the ALARA goal. The work will be completed during CY-99. Beginning in CY-98, a numeric Radiological Performance Index (RPI) is being used to compare radiological performance. The RPI takes into consideration frequency and severity of events such as skin contaminations, clothing contaminations, spills, exposures to radiation exceeding limits, and positive internal dose. The RPI measures the cost of these events in cents per hour of radiological work performed. To make the RPI meaningful, tables have been prepared to show the facility that contributes to the values used. The data are compared on a quarterly basis to the prior year to show measurable performance.

  10. CENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 Research Using RARAF

    E-Print Network [OSTI]

    understanding the cellular response to DNA damage and low dose radiation risk assessment. Yigal Horowitz of BenCENTER FOR RADIOLOGICAL RESEARCH ANNUAL REPORT 2011 1 Research Using RARAF For over a decade, many in various investigations of this phenomenon. Research into bystander effects in 3-D systems continued

  11. BACHELOR OF SCIENCE IN RADIOLOGICAL SCIENCE (Suggested 4 Year Plan)

    E-Print Network [OSTI]

    Benos, Panayiotis "Takis"

    Credits per term 16 Credits per term 18 Credits per academic year 34 FOURTH YEAR, 1ST TERM FOURTH YEAR, 2ND TERM FOURTH YEAR, 3rd TERM (Summer) Radiographic Procedures III Radiation Biology General ReviewBACHELOR OF SCIENCE IN RADIOLOGICAL SCIENCE (Suggested 4 Year Plan) Please note

  12. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

  13. Radiological Modeling for Determination of Derived Concentration Levels of an Area with Uranium Residual Material - 13533

    SciTech Connect (OSTI)

    Perez-Sanchez, Danyl [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)] [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)

    2013-07-01

    As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decay series as Th-230, Ra-226 and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirmed their presence. This paper presents the methodology used to calculate the derived concentration level to ensure that the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modeling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of radon (Rn-222). As result was concluded that, if the concentration of Ra-226 in the first 15 cm of soil is lower than, 0.34 Bq g{sup -1}, the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (authors)

  14. Results of the radiological survey at 9 Redstone Lane, Lodi, New Jersey (LJ069)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process waste and residues associated with the production and refining of thorium and thorium compounds from monozite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Areas residents used the sandlike waste from this thorium extraction process mixed with teas and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigate radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Redstone Lane, Lodi, New Jersey (LJ069), was conducted during 1987. Measurements at the private property located at 9 Redstone Lane indicate slightly elevated gamma exposure rates in association with cinder-like material observed in logging holes. These elevated levels result from naturally occurring radioactivity present in such substances as ashes and cinders. They are not related to the deposit of residues from processing operations at the MCW site. All other radiological findings conform to the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. 4 refs., 3 figs., 3 tabs.

  15. Radiological Security Partnership | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal GasAdministration Medal of HonorPosterNationalPrograms | NationalREPORT NT-15-1

  16. Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01

    Corrective Action Unit (CAU) 190 is located in Areas 11 and 14 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 190 is comprised of the four Corrective Action Sites (CASs) listed below: (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; and (4) 14-23-01, LTU-6 Test Area. These sites are being investigated because existing information is insufficient on the nature and extent of potential contamination to evaluate and recommend corrective action alternatives. Additional information will be obtained before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS by conducting a corrective action investigation (CAI). The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on August 24, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture, and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 190. The scope of the CAU 190 CAI includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling; (2) Conduct radiological and geophysical surveys; (3) Perform field screening; (4) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present; (5) If COCs are present, collect additional step-out samples to define the lateral and vertical extent of the contamination; (6) Collect samples of source material, if present, to determine the potential for a release; (7) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes; and (8) Collect quality control samples. This Corrective Action Investigation Document (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) agreed to by the State of Nevada, U.S. Department of Energy, and U.S. Department of Defense. Under the FFACO, this CAIP will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval.

  17. Closure Report for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2012-07-17

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as Appendix F of this report. The requirements are summarized in Section 5.2 of this report. The proposed post-closure requirements consist of visual inspections to determine the condition of postings and radiological surveys to verify contamination has not migrated. NNSA/NSO requests the following: (1) A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 547; and (2) The transfer of CAU 547 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO.

  18. Financing Energy Improvements on Utility Bills: Market Updates and Key Program Design Considerations for Policymakers and Administrators

    SciTech Connect (OSTI)

    2014-05-22

    Provides an overview of the current state of on-bill programs and provides actionable insights on key program design considerations for on-bill lending programs.

  19. Corrective Action Investigation Plan for Corrective Action Unit 567: Miscellaneous Soil Sites, Nevada National Security Site, Nevada, with ROTC 1 Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick K.

    2013-07-01

    Corrective Action Unit (CAU) 567 is located in Areas 1, 3, 5, 20, and 25 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 567 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 567, which comprises the following corrective action sites (CASs): • 01-23-03, Atmospheric Test Site T-1 • 03-23-25, Seaweed E Contamination Area • 05-23-07, A5b RMA • 20-23-08, Colby Mud Spill • 25-23-23, J-11 Soil RMA These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on May 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 567. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 567 releases are nuclear test operations and other NNSS operations. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary at Atmospheric Test Site T-1 exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default contamination boundary at Atmospheric Test Site T-1 and all other CAU 567 CASs will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based FAL. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  20. Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory

    SciTech Connect (OSTI)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

  1. Conjugate flow action functionals

    E-Print Network [OSTI]

    Daniele Venturi

    2013-10-15

    We present a new general method to construct an action functional for a non-potential field theory. The key idea relies on representing the governing equations of the theory relative to a diffeomorphic flow of curvilinear coordinates which is assumed to be functionally dependent on the solution field. Such flow, which will be called the conjugate flow of the theory, evolves in space and time similarly to a physical fluid flow of classical mechanics and it can be selected in order to symmetrize the Gateaux derivative of the field equations with respect to suitable local bilinear forms. This is equivalent to requiring that the governing equations of the field theory can be derived from a principle of stationary action on a Lie group manifold. By using a general operator framework, we obtain the determining equations of such manifold and the corresponding conjugate flow action functional. In particular, we study scalar and vector field theories governed by second-order nonlinear partial differential equations. The identification of transformation groups leaving the conjugate flow action functional invariant could lead to the discovery of new conservation laws in fluid dynamics and other disciplines.

  2. Extension Program Council's Executive Board. 

    E-Print Network [OSTI]

    Marshall, Mary G.; Richardson, Burl B.

    1986-01-01

    ing committee or task force to plan an action program. The Executive Board, assisted by Ex tension agents and resource people, decides whether this need can be directed to an ex isting program area committee, a new-program area committee, or to a... at the national level are those designed to improve conditions of low-income people. Through con gressional legislation, Extension at state and county levels develops appropriate educational programs to assist low-income families and in dividuals. Programs...

  3. Status of Corrective Actions

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

    Director for Environmental Programs (ADEP), the Principal Associate Director for Operations (PADOPS) and the Principal Associate Director for Science, Technology and...

  4. Corrective Action Investigation Plan for Corrective Action Unit 106: Areas 5, 11 Frenchman Flat Atmospheric Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2010-04-01

    Corrective Action Unit (CAU) 106 is located in Area 5 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 106 comprises the five corrective action sites (CASs) listed below: •05-23-02, GMX Alpha Contaminated Area •05-23-05, Atmospheric Test Site - Able •05-45-01, Atmospheric Test Site - Hamilton •05-45-04, 306 GZ Rad Contaminated Area •05-45-05, 307 GZ Rad Contaminated Area These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 19, 2010, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 106. The presence and nature of contamination at CAU 106 will be evaluated based on information collected from a field investigation. The CAU includes land areas impacted by the release of radionuclides from a weapons-effect tower test (CAS 05-45-01), a weapons-related airdrop test (CAS 05-23-05), “equation of state” experiments (CAS 05-23-02), and unknown support activities at two sites (CAS 05-45-04 and CAS 05-45-05). Surface-deposited radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample plot locations to the dose-based final action level. The TED will be calculated as the total of separate estimates of internal and external doses. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample plot will be used to measure external radiological dose. The presence and nature of contamination from other types of releases (such as migration and excavation as well as any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the corrective action investigation for CAU 106 includes the following activities: •Conduct radiological surveys. •Collect and submit environmental samples for laboratory analysis to determine internal dose rates and the presence of contaminants of concern. •If contaminants of concern are present, collect additional samples to define the extent of the contamination and determine the area where TED at the site exceeds final action levels (i.e., corrective action boundary). •Collect samples of investigation-derived waste, as needed, for waste management purposes.

  5. Method for warning of radiological and chemical agents using detection paints on a vehicle surface

    DOE Patents [OSTI]

    Farmer, Joseph C. (Tracy, CA); Brunk, James L. (Martinez, CA); Day, S. Daniel (Danville, CA)

    2012-03-27

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  6. Aerial vehicle with paint for detection of radiological and chemical warfare agents

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, S. Daniel

    2013-04-02

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  7. Nuclear Waste Partnership (NWP) Corrective Action Plan Addendum

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergy AEnergy Managing853926 News enDepartment ofProgram mission is toRadiological

  8. Corrective Action Decision Document/Closure Report for Corrective Action Unit 365: Baneberry Contamination Area, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-09-01

    Corrective Action Unit 365 comprises one corrective action site (CAS), CAS 08-23-02, U-8d Contamination Area. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 365 based on the implementation of the corrective action of closure in place with a use restriction (UR). Corrective action investigation (CAI) activities were performed from January 18, 2011, through August 2, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 365: Baneberry Contamination Area. The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 365 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is complete and acceptable for use in supporting the DQO decisions. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present to the southwest of the Baneberry crater. It was also assumed that radionuclide levels present within the crater and fissure exceed the FAL. Corrective actions were undertaken that consisted of establishing a UR and posting warning signs for the crater, fissure, and the area located to the southwest of the crater where soil concentrations exceeded the FAL. These URs were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions beyond what are described in this document are necessary for CAU 365. (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 365. (3) Corrective Action Unit 365 should be moved from Appendix III to Appendix IV of the FFACO.

  9. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  10. Corrective Action Plan for Environmenta' Management Headquarters

    Office of Environmental Management (EM)

    for Environmenta' Management Headquarters Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant on February 14 2014 Washington, DC 20585 August 2015 Corrective...

  11. Corrective Action Investigation Plan for Corrective Action Unit 541: Small Boy Nevada National Security Site and Nevada Test and Training Range, Nevada with ROTC 1

    SciTech Connect (OSTI)

    Matthews, Patrick

    2014-09-01

    Corrective Action Unit (CAU) 541 is co-located on the boundary of Area 5 of the Nevada National Security Site and Range 65C of the Nevada Test and Training Range, approximately 65 miles northwest of Las Vegas, Nevada. CAU 541 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 541, which comprises the following corrective action sites (CASs): • 05-23-04, Atmospheric Tests (6) - BFa Site • 05-45-03, Atmospheric Test Site - Small Boy These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on April 1, 2014, by representatives of the Nevada Division of Environmental Protection; U.S. Air Force; and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 541. The site investigation process also will be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CASs 05-23-04 and 05-45-03 are from nuclear testing activities conducted at the Atmospheric Tests (6) - BFa Site and Atmospheric Test Site - Small Boy sites. The presence and nature of contamination at CAU 541 will be evaluated based on information collected from field investigations. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  12. Corrective Action Investigation Plan for Corrective Action Unit 571: Area 9 Yucca Flat Plutonium Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Bailey, Bernadine; Matthews, Patrick

    2013-07-01

    CAU 571 is a grouping of sites where there has been a suspected release of contamination associated with nuclear testing. This document describes the planned investigation of CAU 571, which comprises the following corrective action sites (CASs): • 09-23-03, Atmospheric Test Site S-9F • 09-23-04, Atmospheric Test Site T9-C • 09-23-12, Atmospheric Test Site S-9E • 09-23-13, Atmospheric Test Site T-9D • 09-45-01, Windrows Crater These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the investigation report. The sites will be investigated based on the data quality objectives (DQOs) developed on March 6, 2013, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (now the Nevada Field Office). The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 571. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with CAU 571 CASs are from nuclear testing activities. The DQO process resulted in an assumption that total effective dose (TED) within a default contamination boundary exceeds the final action level (FAL) and requires corrective action. The presence and nature of contamination outside the default contamination boundaries at CAU 571 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the TED at sample locations to the dose-based FAL. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Chemical contamination will be evaluated by comparing soil sample results to the FAL. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  13. Corrective Action Investigation Plan for Corrective Action Unit 570: Area 9 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2012-08-01

    CAU 570 comprises the following six corrective action sites (CASs): • 02-23-07, Atmospheric Test Site - Tesla • 09-23-10, Atmospheric Test Site T-9 • 09-23-11, Atmospheric Test Site S-9G • 09-23-14, Atmospheric Test Site - Rushmore • 09-23-15, Eagle Contamination Area • 09-99-01, Atmospheric Test Site B-9A These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 570. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The presence and nature of contamination at CAU 570 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed near the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  14. Environmental regulatory guide for radiological effluent monitoring and environmental surveillance

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    Under the Atomic Energy Act of 1954, as amended, the US Department of Energy (DOE) is obligated to regulate its own activities so as to provide radiation protection for both workers and the public.'' Presidential Executive Order 12088, Federal Compliance with Pollution Control Standards,'' further requires the heads of executive agencies to ensure that all Federal facilities and activities comply with applicable pollution control standards and to take all actions necessary for the prevention, control, and abatement of environmental pollution. This regulatory guide describes the elements of an acceptable effluent monitoring and environmental surveillance program for DOE sites involving radioactive materials. These elements are applicable to all DOE and contractor activities for which the DOE exercises environmental, safety, and health responsibilities, and are intended to be applicable over the broad range of DOE facilities and sites. In situations where the high-priority elements may not provide sufficient coverage of a specific monitoring or surveillance topic, the document provides additional guidance. The high-priority elements are written as procedures and activities that should'' be performed, and the guidance is written as procedures and activities that should'' be performed. The regulatory guide both incorporates and expands on requirements embodied in DOE 5400.5 and DOE 5400.1. 221 refs., 2 figs., 6 tabs.

  15. Comparison of RCRA SWMU corrective action and CERCLA remedial action. Master's thesis

    SciTech Connect (OSTI)

    Rupe, S.C.

    1991-09-30

    With the passage of the Hazardous and Solid Waste Amendments of 1984 and the addition of expanded authorities to require corrective action for release of hazardous constituents from solid waste management units (SWMUs) at hazardous waste treatment, storage, and disposal facilities, the Solid Waste Disposal Act (hereafter referred to as the Resource Conservation and Recovery Act or RCRA) will dramatically influence the Superfund program under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). Not only will the RCRA corrective action program help prevent current RCRA sites from becoming Superfund sites, but it also offers EPA and the states an important alternative to address superfund sites that already exist. EPA recognized this and, hoping to conserve Superfund resources, developed a policy to defer listing of sites from the National Priority List if those sites can be addressed under RCRA's corrective action authorities. Private industry and federal agencies with problem sites that could qualify under either program need to compare the advantages and disadvantages of each program. EPA's deferral policy continues to evolve and appears to be ripe for expansion.

  16. Status Update on the NCRP Scientific Committee SC 5-1 Report: Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents - 13450

    SciTech Connect (OSTI)

    Chen, S.Y.

    2013-07-01

    In August 2008, the U.S. Department of Homeland Security (DHS) issued its final Protective Action Guide (PAG) for radiological dispersal device (RDD) and improvised nuclear device (IND) incidents. This document specifies protective actions for public health during the early and intermediate phases and cleanup guidance for the late phase of RDD or IND incidents, and it discusses approaches to implementing the necessary actions. However, while the PAG provides specific guidance for the early and intermediate phases, it prescribes no equivalent guidance for the late-phase cleanup actions. Instead, the PAG offers a general description of a complex process using a site-specific optimization approach. This approach does not predetermine cleanup levels but approaches the problem from the factors that would bear on the final agreed-on cleanup levels. Based on this approach, the decision-making process involves multifaceted considerations including public health, the environment, and the economy, as well as socio-political factors. In an effort to fully define the process and approach to be used in optimizing late-phase recovery and site restoration following an RDD or IND incident, DHS has tasked the NCRP with preparing a comprehensive report addressing all aspects of the optimization process. Preparation of the NCRP report is a three-year (2010-2013) project assigned to a scientific committee, the Scientific Committee (SC) 5-1; the report was initially titled, Approach to Optimizing Decision Making for Late- Phase Recovery from Nuclear or Radiological Terrorism Incidents. Members of SC 5-1 represent a broad range of expertise, including homeland security, health physics, risk and decision analysis, economics, environmental remediation and radioactive waste management, and communication. In the wake of the Fukushima nuclear accident of 2011, and guided by a recent process led by the White House through a Principal Level Exercise (PLE), the optimization approach has since been expanded to include off-site contamination from major nuclear power plant accidents as well as other nuclear or radiological incidents. The expanded application under the current guidance has thus led to a broadened scope of the report, which is reflected in its new title, Decision Making for Late-Phase Recovery from Nuclear or Radiological Incidents. The NCRP report, which is due for publication in 2013, will substantiate the current DHS guidance by clarifying and elaborating on the processes required for the development and implementation of procedures for optimizing decision making for late-phase recovery, enabling the establishment of cleanup goals on a site-specific basis. The report will contain a series of topics addressing important issues related to the long-term recovery from nuclear or radiological incidents. Special topics relevant to supporting the optimization of the decision-making process will include cost-benefit analysis, radioactive waste management, risk communication, stakeholder interaction, risk assessment, and decontamination approaches and techniques. The committee also evaluated past nuclear and radiological incidents for their relevance to the report, including the emerging issues associated with the Fukushima nuclear accident. Thus, due to the commonality of the late-phase issues (such as the potential widespread contamination following an event), the majority of the information pertaining to the response in the late-phase decision-making period, including site-specific optimization framework and approach, could be used or adapted for use in case of similar situations that are not due to terrorism, such as those that would be caused by major nuclear facility accidents or radiological incidents. To ensure that the report and the NCRP recommendations are current and relevant to the effective implementation of federal guidance, SC 5-1 has actively coordinated with the agencies of interest and other relevant stakeholders throughout the duration of the project. The resulting report will be an important resource to guide those involved

  17. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    SciTech Connect (OSTI)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  18. Climate Action Plan 2009 Sustainability

    E-Print Network [OSTI]

    Capogna, Luca

    Climate Action Plan September 2009 Sustainability Council This plan outlines methods by which. This document is publicly available at http://sustainability.uark.edu. #12;2 University of Arkansas Climate....................................................................................................................................7 Climate Action Plan Committee

  19. An aerial radiological survey of Naturita, Colorado and surrounding area

    SciTech Connect (OSTI)

    Jaffe, R.J.

    1982-09-01

    An aerial radiological survey of four areas in the vicinity of the inactive uranium mill tailings site at Naturita, Colorado was conducted in September 1981. The average background radiation exposure rate (normalized to 3 feet above the ground) was about 10 to 16 microroentgens per hour ({mu}R/h). Uranium ore or tailings were detected at Naturita, Nucla, East Vancorum, and the general region downriver and downwind from the former mill tailings site.

  20. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99 OctoberRadiological

  1. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99385 Radiological Considerations

  2. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99385 Radiological Considerations6

  3. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99385 Radiological

  4. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99385 RadiologicalInstructor's

  5. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control

  6. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control Unit

  7. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control Unit

  8. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control

  9. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8

  10. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8

  11. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8

  12. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86

  13. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86

  14. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological

  15. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 RadiologicalStudy

  16. Predicting error in detecting mammographic masses among radiology trainees using statistical models based on BI-RADS features

    SciTech Connect (OSTI)

    Grimm, Lars J., E-mail: Lars.grimm@duke.edu; Ghate, Sujata V.; Yoon, Sora C.; Kim, Connie [Department of Radiology, Duke University Medical Center, Box 3808, Durham, North Carolina 27710 (United States)] [Department of Radiology, Duke University Medical Center, Box 3808, Durham, North Carolina 27710 (United States); Kuzmiak, Cherie M. [Department of Radiology, University of North Carolina School of Medicine, 2006 Old Clinic, CB No. 7510, Chapel Hill, North Carolina 27599 (United States)] [Department of Radiology, University of North Carolina School of Medicine, 2006 Old Clinic, CB No. 7510, Chapel Hill, North Carolina 27599 (United States); Mazurowski, Maciej A. [Duke University Medical Center, Box 2731 Medical Center, Durham, North Carolina 27710 (United States)] [Duke University Medical Center, Box 2731 Medical Center, Durham, North Carolina 27710 (United States)

    2014-03-15

    Purpose: The purpose of this study is to explore Breast Imaging-Reporting and Data System (BI-RADS) features as predictors of individual errors made by trainees when detecting masses in mammograms. Methods: Ten radiology trainees and three expert breast imagers reviewed 100 mammograms comprised of bilateral medial lateral oblique and craniocaudal views on a research workstation. The cases consisted of normal and biopsy proven benign and malignant masses. For cases with actionable abnormalities, the experts recorded breast (density and axillary lymph nodes) and mass (shape, margin, and density) features according to the BI-RADS lexicon, as well as the abnormality location (depth and clock face). For each trainee, a user-specific multivariate model was constructed to predict the trainee's likelihood of error based on BI-RADS features. The performance of the models was assessed using area under the receive operating characteristic curves (AUC). Results: Despite the variability in errors between different trainees, the individual models were able to predict the likelihood of error for the trainees with a mean AUC of 0.611 (range: 0.502–0.739, 95% Confidence Interval: 0.543–0.680,p < 0.002). Conclusions: Patterns in detection errors for mammographic masses made by radiology trainees can be modeled using BI-RADS features. These findings may have potential implications for the development of future educational materials that are personalized to individual trainees.

  17. Interactions between Energy Efficiency Programs funded under the Recovery Act and Utility Customer-Funded Energy Efficiency Programs

    E-Print Network [OSTI]

    Goldman, Charles A.

    2011-01-01

    and Timeline: State Energy Program National Evaluation,”program supports states’ efforts to align with national energyNational Action Plan for Energy Efficiency 2008. “Understanding Cost-Effectiveness of Energy Efficiency Programs:

  18. RCRA corrective action and closure

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    This information brief explains how RCRA corrective action and closure processes affect one another. It examines the similarities and differences between corrective action and closure, regulators` interests in RCRA facilities undergoing closure, and how the need to perform corrective action affects the closure of DOE`s permitted facilities and interim status facilities.

  19. Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 547: Miscellaneous Contaminated Waste Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss

    2011-09-01

    The purpose of this CADD/CAP is to present the corrective action alternatives (CAAs) evaluated for CAU 547, provide justification for selection of the recommended alternative, and describe the plan for implementing the selected alternative. Corrective Action Unit 547 consists of the following three corrective action sites (CASs): (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; and(3) CAS 09-99-06, Gas Sampling Assembly. The gas sampling assemblies consist of inactive process piping, equipment, and instrumentation that were left in place after completion of underground safety experiments. The purpose of these safety experiments was to confirm that a nuclear explosion would not occur in the case of an accidental detonation of the high-explosive component of the device. The gas sampling assemblies allowed for the direct sampling of the gases and particulates produced by the safety experiments. Corrective Action Site 02-37-02 is located in Area 2 of the Nevada National Security Site (NNSS) and is associated with the Mullet safety experiment conducted in emplacement borehole U2ag on October 17, 1963. Corrective Action Site 03-99-19 is located in Area 3 of the NNSS and is associated with the Tejon safety experiment conducted in emplacement borehole U3cg on May 17, 1963. Corrective Action Site 09-99-06 is located in Area 9 of the NNSS and is associated with the Player safety experiment conducted in emplacement borehole U9cc on August 27, 1964. The CAU 547 CASs were investigated in accordance with the data quality objectives (DQOs) developed by representatives of the Nevada Division of Environmental Protection (NDEP) and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for CAU 547. Existing radiological survey data and historical knowledge of the CASs were sufficient to meet the DQOs and evaluate CAAs without additional investigation. As a result, further investigation of the CAU 547 CASs was not required. The following CAAs were identified for the gas sampling assemblies: (1) clean closure, (2) closure in place, (3) modified closure in place, (4) no further action (with administrative controls), and (5) no further action. Based on the CAAs evaluation, the recommended corrective action for the three CASs in CAU 547 is closure in place. This corrective action will involve construction of a soil cover on top of the gas sampling assembly components and establishment of use restrictions at each site. The closure in place alternative was selected as the best and most appropriate corrective action for the CASs at CAU 547 based on the following factors: (1) Provides long-term protection of human health and the environment; (2) Minimizes short-term risk to site workers in implementing corrective action; (3) Is easily implemented using existing technology; (4) Complies with regulatory requirements; (5) Fulfills FFACO requirements for site closure; (6) Does not generate transuranic waste requiring offsite disposal; (7) Is consistent with anticipated future land use of the areas (i.e., testing and support activities); and (8) Is consistent with other NNSS site closures where contamination was left in place.

  20. The Gravisphere Method Algorithm Programming

    E-Print Network [OSTI]

    A. E. Rosaev

    2008-01-23

    The action sphere method program is written. The initial conditions set at pericenter of planetocentric orbits. When action sphere radius is reached, the heliocentric orbit is calculated and data redirected to numeric integration program. The method is useful for capture and collision problem investigation. The very preliminary numeric results were obtained and discussed. A manifold in orbital elements space, leads to temporary capture about 50 year (4 Jupiter revolutions), was found.

  1. N Reactor Deactivation Program Plan. Revision 4

    SciTech Connect (OSTI)

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities {center_dot} in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually.

  2. International-Aerial Measuring System (I-AMS) Training Program

    SciTech Connect (OSTI)

    Wasiolek, Piotre T.; Malchor, Russell L.; Maurer, Richard J.; Adams, Henry L.

    2015-10-01

    Since the Fukushima reactor accident in 2011, there has been an increased interest worldwide in developing national capabilities to rapidly map and assess ground contamination resulting from nuclear reactor accidents. The capability to rapidly measure the size of the contaminated area, determine the activity level, and identify the radionuclides can aid emergency managers and decision makers in providing timely protective action recommendations to the public and first responders. The development of an aerial detection capability requires interagency coordination to assemble the radiation experts, detection system operators, and aviation aircrews to conduct the aerial measurements, analyze and interpret the data, and provide technical assessments. The Office of International Emergency Management and Cooperation (IEMC) at the U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) sponsors an International - Aerial Measuring System (I-AMS) training program for partner nations to develop and enhance their response to radiological emergencies. An initial series of courses can be conducted in the host country to assist in developing an aerial detection capability. As the capability develops and expands, additional experience can be gained through advanced courses with the opportunity to conduct aerial missions over a broad range of radiation environments.

  3. Securities Class Actions and Bankrupt Companies

    E-Print Network [OSTI]

    Park, James J.

    2014-01-01

    the utility of securities class actions. Certainly, contextthe merit of securities class actions. UCLA | SCHOOL OF LAWof James J. Park, Securities Class Actions and Bankrupt

  4. Tonopah Test Range Air Monitoring: CY2013 Meteorological, Radiological, and Airborne Particulate Observations

    SciTech Connect (OSTI)

    Mizell, Steve A; Nikolich, George; Shadel, Craig; McCurdy, Greg; Etyemezian, Vicken; Miller, Julianne J

    2014-10-01

    In 1963, the U.S. Department of Energy (DOE) (formerly the Atomic Energy Commission [AEC]), implemented Operation Roller Coaster on the Tonopah Test Range (TTR) and an adjacent area of the Nevada Test and Training Range (NTTR) (formerly the Nellis Air Force Range). This test resulted in radionuclide-contaminated soils at Clean Slate I, II, and III. This report documents observations made during on-going monitoring of radiological, meteorological, and dust conditions at stations installed adjacent to Clean Slate I and Clean Slate III and at the TTR Range Operations Control center. The primary objective of the monitoring effort is to determine if winds blowing across the Clean Slate sites are transporting particles of radionuclide-contaminated soils beyond both the physical and administrative boundaries of the sites. Results for the calendar year (CY) 2013 monitoring include: (1) the gross alpha and gross beta values from the monitoring stations are approximately equivalent to the highest values observed during the CY2012 reporting at the surrounding Community Environmental Monitoring Program (CEMP) stations (this was the latest documented data available at the time of this writing); (2) only naturally occurring radionuclides were identified in the gamma spectral analyses; (3) the ambient gamma radiation measurements indicate that the average annual gamma exposure is similar at all three monitoring stations and periodic intervals of increased gamma values appear to be associated with storm fronts passing through the area; and (4) the concentrations of both resuspended dust and saltated sand particles generally increase with increasing wind speed. However, differences in the observed dust concentrations are likely due to differences in the soil characteristics immediately adjacent to the monitoring stations. Neither the resuspended particulate radiological analyses nor the ambient gamma radiation measurements suggest wind transport of radionuclide-contaminated soils.

  5. Corrective Action Investigation Plan for Corrective Action Unit 104: Area 7 Yucca Flat Atmospheric Test Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-08-01

    CAU 104 comprises the 15 CASs listed below: (1) 07-23-03, Atmospheric Test Site T-7C; (2) 07-23-04, Atmospheric Test Site T7-1; (3) 07-23-05, Atmospheric Test Site; (4) 07-23-06, Atmospheric Test Site T7-5a; (5) 07-23-07, Atmospheric Test Site - Dog (T-S); (6) 07-23-08, Atmospheric Test Site - Baker (T-S); (7) 07-23-09, Atmospheric Test Site - Charlie (T-S); (8) 07-23-10, Atmospheric Test Site - Dixie; (9) 07-23-11, Atmospheric Test Site - Dixie; (10) 07-23-12, Atmospheric Test Site - Charlie (Bus); (11) 07-23-13, Atmospheric Test Site - Baker (Buster); (12) 07-23-14, Atmospheric Test Site - Ruth; (13) 07-23-15, Atmospheric Test Site T7-4; (14) 07-23-16, Atmospheric Test Site B7-b; (15) 07-23-17, Atmospheric Test Site - Climax These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 28, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 104. The releases at CAU 104 consist of surface-deposited radionuclides from 30 atmospheric nuclear tests. The presence and nature of contamination at CAU 104 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) to the dose-based final action level (FAL). The presence of TED exceeding the FAL is considered a radiological contaminant of concern (COC). Anything identified as a COC will require corrective action. The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters will be used to measure external radiological dose. Based on process knowledge of the releases associated with the nuclear tests and radiological survey information about the location and shape of the resulting contamination plume, it was determined that the releases from the nuclear tests are co-located and will be investigated concurrently. A field investigation will be performed to define areas where TED exceeds the FAL and to determine whether other COCs are present at the site. The investigation will also collect information to determine the presence and nature of contamination associated with migration and excavation, as well as any potential releases discovered during the investigation. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  6. Results of the radiological survey at 80 Industrial Road, Lodi, New Jersey (LJ061)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 80 Industrial Road, Lodi, New Jersey (LJ061), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of DOE remedial action criteria, primarily from the /sup 232/Th decay chain, with some contamination from /sup 226/Ra. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 11 figs., 3 tabs.

  7. Rulison Site corrective action report

    SciTech Connect (OSTI)

    NONE

    1996-09-01

    Project Rulison was a joint US Atomic Energy Commission (AEC) and Austral Oil Company (Austral) experiment, conducted under the AEC`s Plowshare Program, to evaluate the feasibility of using a nuclear device to stimulate natural gas production in low-permeability gas-producing geologic formations. The experiment was conducted on September 10, 1969, and consisted of detonating a 40-kiloton nuclear device at a depth of 2,568 m below ground surface (BGS). This Corrective Action Report describes the cleanup of petroleum hydrocarbon- and heavy-metal-contaminated sediments from an old drilling effluent pond and characterization of the mud pits used during drilling of the R-EX well at the Rulison Site. The Rulison Site is located approximately 65 kilometers (40 miles) northeast of Grand Junction, Colorado. The effluent pond was used for the storage of drilling mud during drilling of the emplacement hole for the 1969 gas stimulation test conducted by the AEC. This report also describes the activities performed to determine whether contamination is present in mud pits used during the drilling of well R-EX, the gas production well drilled at the site to evaluate the effectiveness of the detonation in stimulating gas production. The investigation activities described in this report were conducted during the autumn of 1995, concurrent with the cleanup of the drilling effluent pond. This report describes the activities performed during the soil investigation and provides the analytical results for the samples collected during that investigation.

  8. Soils Project Risk-Based Corrective Action Evaluation Process with ROTC 1 and ROTC 2, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick; Sloop, Christina

    2012-04-01

    This document formally defines and clarifies the NDEP-approved process the NNSA/NSO Soils Activity uses to fulfill the requirements of the FFACO and state regulations. This process is used to establish FALs in accordance with the risk-based corrective action (RBCA) process stipulated in Chapter 445 of the Nevada Administrative Code (NAC) as described in the ASTM International (ASTM) Method E1739-95 (NAC, 2008; ASTM, 1995). It is designed to provide a set of consistent standards for chemical and radiological corrective actions.

  9. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    SciTech Connect (OSTI)

    Barnett, J. M.; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

    2012-11-12

    Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1 considerations. This DQO report also updates the discussion of the Environmental Monitoring Plan for the PNNL Site air samples and how existing Hanford Site monitoring program results could be used. This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs.

  10. Java Programming Certificate Program

    E-Print Network [OSTI]

    Loudon, Catherine

    Java Programming Certificate Program COMPUTER PROGRAMMING The Java programming language lies that fuel the Internet economy. In addition, the portability inherent in Java is useful for programming languages are likely to encounter projects in the near future that require knowledge of Java. Who Should

  11. Java Programming Certificate Program

    E-Print Network [OSTI]

    Loudon, Catherine

    Java Programming Certificate Program COMPUTER PROGRAMMING The Java programming language lies that fuel the Internet economy. In addition, the portability inherent in Java is useful for programming are likely to encounter projects in the near future that require knowledge of Java. Who Should Enroll

  12. Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014

    Broader source: Energy.gov [DOE]

    On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following the event, the investigation was broken into two phases. The Phase 1 report focused on how the radiological material was released into the atmosphere and Phase 2, performed once limited access to the underground was re?established, focused on the source of the released radiological material.

  13. Corrective Action Decision Document/Closure Report for Corrective Action Unit 375: Area 30 Buggy Unit Craters, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-08-01

    Corrective Action Unit 375 comprises three corrective action sites (CASs): (1) 25-23-22, Contaminated Soils Site; (2) 25-34-06, Test Cell A Bunker; and (3) 30-45-01, U-30a, b, c, d, e Craters. The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 375 based on the implementation of corrective action of closure in place with administrative controls at CAS 25-23-22, no further action at CAS 25-34-06, and closure in place with administrative controls and removal of potential source material (PSM) at CAS 30-45-01. Corrective action investigation (CAI) activities were performed from July 28, 2010, through April 4, 2011, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 375: Area 30 Buggy Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides, and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 375 dataset of investigation results was evaluated based on the data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL of 25 millirem per year was established based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were assumed to be present within the default contamination boundaries at CASs 25-23-22 and 30-45-01. No contaminants were identified at CAS 25-34-06, and no corrective action is necessary. Potential source material in the form of lead plate, lead-acid batteries, and oil within an abandoned transformer were identified at CAS 30-45-01, and corrective actions were undertaken that consisted of removing the PSM. Use restrictions and warning signs were implemented for the remaining radiological contamination at CASs 25-23-22 and 30-45-01. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: (1) No further corrective actions are necessary for CAU 375; (2) A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 375; and (3) Move CAU 375 from Appendix III to Appendix IV of the FFACO.

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    SciTech Connect (OSTI)

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  15. Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.

    SciTech Connect (OSTI)

    Fournier, Sean Donovan; Beall, Patrick S [Sandia National Laboratories, Livermore, CA; Miller, Mark L.

    2014-08-01

    Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrument on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.

  16. Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 408: Bomblet Target Area Tonopah Test Range (TTR), Nevada, Revision 1

    SciTech Connect (OSTI)

    Mark Krauss

    2010-03-01

    This Streamlined Approach for Environmental Restoration Plan addresses the actions needed to achieve closure of Corrective Action Unit (CAU) 408, Bomblet Target Area (TTR). Corrective Action Unit 408 is located at the Tonopah Test Range and is currently listed in Appendix III of the Federal Facility Agreement and Consent Order. Corrective Action Unit 408 comprises Corrective Action Site TA-55-002-TAB2, Bomblet Target Areas. Clean closure of CAU 408 will be accomplished by removal of munitions and explosives of concern within seven target areas and potential disposal pits. The target areas were used to perform submunitions related tests for the U.S. Department of Energy (DOE). The scope of CAU 408 is limited to submunitions released from DOE activities. However, it is recognized that the presence of other types of unexploded ordnance and munitions may be present within the target areas due to the activities of other government organizations. The CAU 408 closure activities consist of: • Clearing bomblet target areas within the study area. • Identifying and remediating disposal pits. • Collecting verification samples. • Performing radiological screening of soil. • Removing soil containing contaminants at concentrations above the action levels. Based on existing information, contaminants of potential concern at CAU 408 include unexploded submunitions, explosives, Resource Conservation Recovery Act metals, and depleted uranium. Contaminants are not expected to be present in the soil at concentrations above the action levels; however, this will be determined by radiological surveys and verification sample results.

  17. Finding of no significant impact: Changes in the sanitary sludge land application program on the Oak Ridge Reservation, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-10-01

    The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1042) that evaluates potential impacts of proposed changes in the sanitary sludge land application program on the DOE Oak Ridge Reservation (ORR), Oak Ridge, Tennessee. Changes in lifetime sludge land application limits and radionuclide loading are proposed, and two new sources of sewage sludge from DOE facilities would be transported to the City of Oak Ridge Publicly Owned Treatment Works (COR POTW). Lifetime sludge land application limits would increase from 22 tons/acre to 50 tons/acre, which is the limit approved and permitted by the Tennessee Department of Environment and Conservation (TDEC). With the approval of TDEC, the permissible radiological dose from sludge land application would change from the current limit of 2x background radionuclide concentrations in receiving soils to a risk-based dose limit of 4 millirem (mrem) per year for the maximally exposed individual. Sludge land application sites would not change from those that are currently part of the program. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement (EIS) is not necessary, and DOE is issuing this Finding of No Significant Impact (FONSI). 70 refs., 2 figs., 17 tabs.

  18. Training Workers to use Localized Ventilation for Radiological Work

    SciTech Connect (OSTI)

    WAGGONER, L.O.

    2000-09-01

    Work on radiological systems and components needs to be accomplished using techniques that reduce radiation dose to workers, limit contamination spread, and minimize radioactive waste. One of the best methods to control contamination spread is to use localized ventilation to capture radioactive material and keep it from spreading. The Fluor Hanford ALARA Center teaches workers how to use ventilation in partnership with other engineered controls and this has resulted in improved work practices, minimized the impact on adjacent work operations, and decreased the amount of radioactive waste generated. This presentation will emphasize how the workers are trained to use localized ventilation for contamination control.

  19. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, Thomas R. (Pittsburgh, PA)

    1998-01-01

    A compact cyclone filter train for the removal of hazardous and radiologi particles from a gaseous fluid medium which permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired.

  20. Compact cyclone filter train for radiological and hazardous environments

    DOE Patents [OSTI]

    Bench, T.R.

    1998-04-28

    A compact cyclone filter train is disclosed for the removal of hazardous and radiological particles from a gaseous fluid medium. This filter train permits a small cyclone separator to be used in a very small space envelope due to the arrangement of the filter housing adjacent to the separator with the cyclone separator and the filters mounted on a plate. The entire unit will have a hoist connection at the center of gravity so that the entire unit including the separator, the filters, and the base can be lifted and repositioned as desired. 3 figs.

  1. Federal Radiological Monitoring and Assessment Center Health and Safety Manual

    SciTech Connect (OSTI)

    FRMAC Health and Safety Working Group

    2012-03-20

    This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

  2. Understanding Contamination; Twenty Years of Simulating Radiological Contamination

    SciTech Connect (OSTI)

    Emily Snyder; John Drake; Ryan James

    2012-02-01

    A wide variety of simulated contamination methods have been developed by researchers to reproducibly test radiological decontamination methods. Some twenty years ago a method of non-radioactive contamination simulation was proposed at the Idaho National Laboratory (INL) that mimicked the character of radioactive cesium and zirconium contamination on stainless steel. It involved baking the contamination into the surface of the stainless steel in order to 'fix' it into a tenacious, tightly bound oxide layer. This type of contamination was particularly applicable to nuclear processing facilities (and nuclear reactors) where oxide growth and exchange of radioactive materials within the oxide layer became the predominant model for material/contaminant interaction. Additional simulation methods and their empirically derived basis (from a nuclear fuel reprocessing facility) are discussed. In the last ten years the INL, working with the Defense Advanced Research Projects Agency (DARPA) and the National Homeland Security Research Center (NHSRC), has continued to develop contamination simulation methodologies. The most notable of these newer methodologies was developed to compare the efficacy of different decontamination technologies against radiological dispersal device (RDD, 'dirty bomb') type of contamination. There are many different scenarios for how RDD contamination may be spread, but the most commonly used one at the INL involves the dispersal of an aqueous solution containing radioactive Cs-137. This method was chosen during the DARPA projects and has continued through the NHSRC series of decontamination trials and also gives a tenacious 'fixed' contamination. Much has been learned about the interaction of cesium contamination with building materials, particularly concrete, throughout these tests. The effects of porosity, cation-exchange capacity of the material and the amount of dirt and debris on the surface are very important factors. The interaction of the contaminant/substrate with the particular decontamination technology is also very important. Results of decontamination testing from hundreds of contaminated coupons have lead to certain conclusions about the contamination and the type of decontamination methods being deployed. A recent addition to the DARPA initiated methodology simulates the deposition of nuclear fallout. This contamination differs from previous tests in that it has been developed and validated purely to simulate a 'loose' type of contamination. This may represent the first time that a radiologically contaminated 'fallout' stimulant has been developed to reproducibly test decontamination methods. While no contaminant/methodology may serve as a complete example of all aspects that could be seen in the field, the study of this family of simulation methods provides insight into the nature of radiological contamination.

  3. Energy deposition and radiological studies for the LBNF Hadron Absorber

    E-Print Network [OSTI]

    Rakhno, I L; Tropin, I S; Eidelman, Y I

    2015-01-01

    Results of detailed Monte Carlo energy deposition and radiological studies performed for the LBNF hadron absorber with the MARS15 code are described. The model of the entire facility, that includes a pion-production target, focusing horns, target chase, decay channel, hadron absorber system - all with corresponding radiation shielding - was developed using the recently implemented ROOT-based geometry option in the MARS15 code. Both normal operation and accidental conditions were studied. Results of detailed thermal calculations with the ANSYS code helped to select the most viable design options.

  4. Radiological Security Partnership | Y-12 National Security Complex

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMassR&D100 Winners * Impacts on GlobalRachel RuggirelloRadiative98-2008,Radiological

  5. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99 OctoberRadiological Protection

  6. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-99 OctoberRadiologicalExternal

  7. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control Unit4

  8. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control Unit4-

  9. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8 ALARA

  10. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8 ALARA

  11. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control8 ALARA

  12. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  13. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  14. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  15. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  16. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  17. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  18. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  19. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  20. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of 9

  1. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 Radiological Control86 of

  2. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 RadiologicalStudy Guide

  3. DOE-HDBK-1122-99; Radiological Control Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 RadiologicalStudyStudy

  4. DOE-HDBK-1122-99; Radiological Technician Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY TakestoFlex8-993859 RadiologicalStudyStudy5 of

  5. DOE-HDBK-1141-2001; Radiological Assessor Training, Overheads

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY6.1 DOE-HDBK-1141-2001 Overhead 6.1 Radiological

  6. ORISE: REAC/TS Radiological Incident Medical Consultation

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSEHow ORISE is Making a DifferenceRadiological Incident

  7. Corrective Action Investigation Plan for Corrective Action Unit 552: Area 12 Muckpile and Ponds, Nevada Test Site, Nevada, Rev. No.: 1 with ROTC 1 and 2

    SciTech Connect (OSTI)

    David A. Strand

    2005-01-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 552: Area 12 Muckpile and Ponds, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense. The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 552 is comprised of the one Corrective Action Site which is 12-23-05, Ponds. One additional CAS, 12-06-04, Muckpile (G-Tunnel Muckpile), was removed from this CAU when it was determined that the muckpile is an active site. A modification to the FFACO to remove CAS 12-06-04 was approved by the Nevada Division of Environmental Protection (NDEP) on December 16, 2004. The G-Tunnel ponds were first identified in the 1991 Reynolds Electrical & Engineering Co., Inc. document entitled, ''Nevada Test Site Inventory of Inactive and Abandoned Facilities and Waste Sites'' (REECo, 1991). Corrective Action Unit 552 is being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Therefore, additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating and selecting the corrective action alternatives for the site. The CAI will include field inspections, radiological surveys, and sampling of appropriate media. Data will also be obtained to support investigation-derived waste (IDW) disposal and potential future waste management decisions.

  8. Closure Report for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks Nevada National Security Site, Nevada with ROTC-1, Revision 0

    SciTech Connect (OSTI)

    Mark Kauss

    2011-06-01

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 539: Areas 25 and 26 Railroad Tracks, Nevada National Security Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 539 are located within Areas 25 and 26 of the Nevada National Security Site. Corrective Action Unit 539 comprises the following CASs: • 25-99-21, Area 25 Railroad Tracks • 26-99-05, Area 26 Railroad Tracks The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CASs within CAU 539 were met. To achieve this, the following actions were performed: • Reviewed documentation on historical and current site conditions, including the concentration and extent of contamination. • Conducted radiological walkover surveys of railroad tracks in both Areas 25 and 26. • Collected ballast and soil samples and calculated internal dose estimates for radiological releases. • Collected in situ thermoluminescent dosimeter measurements and calculated external dose estimates for radiological releases. • Removed lead bricks as potential source material (PSM) and collected verification samples. • Implemented corrective actions as necessary to protect human health and the environment. • Properly disposed of corrective action and investigation wastes. • Implemented an FFACO use restriction (UR) for radiological contamination at CAS 25-99-21. The approved UR form and map are provided in Appendix F and will be filed in the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Facility Information Management System; the FFACO database; and the NNSA/NSO CAU/CAS files. From November 29, 2010, through May 2, 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 539: Areas 25 and 26 Railroad Tracks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 539. Assessment of the data generated from closure activities revealed the following: • At CAS 26-99-05, the total effective dose for radiological releases did not exceed the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at three locations. A corrective action of clean closure was implemented at these locations, and verification samples indicated that no further action is necessary. • At CAS 25-99-21, the total effective dose for radiological releases exceeds the FAL of 25 millirem per Industrial Area year. Potential source material in the form of lead bricks was found at eight locations. A corrective action was implemented by removing the lead bricks and soil above FALs at these locations, and verification samples indicated that no further action is necessary. Pieces of debris with high radioactivity were identified as PSM and remain within the CAS boundary. A corrective action of closure in place with a UR was implemented at this CAS because closure activities showed evidence of remaining soil contamination and radioactive PSM. Future land use will be restricted from surface and intrusive activities. Closure activities generated waste streams consisting of industrial solid waste, recyclable materials, low-level radioactive waste, and mixed low-level radioactive waste. Wastes were disposed of in the appropriate onsite landfills. The NNSA/NSO prov

  9. Termination of Nondeterministic Quantum Programs

    E-Print Network [OSTI]

    Yangjia Li; Nengkun Yu; Mingsheng Ying

    2012-01-04

    We define a language-independent model of nondeterministic quantum programs in which a quantum program consists of a finite set of quantum processes. These processes are represented by quantum Markov chains over the common state space. An execution of a nondeterministic quantum program is modeled by a sequence of actions of individual processes. These actions are described by super-operators on the state Hilbert space. At each step of an execution, a process is chosen nondeterministically to perform the next action. A characterization of reachable space and a characterization of diverging states of a nondeterministic quantum program are presented. We establish a zero-one law for termination probability of the states in the reachable space of a nondeterministic quantum program. A combination of these results leads to a necessary and sufficient condition for termination of nondeterministic quantum programs. Based on this condition, an algorithm is found for checking termination of nondeterministic quantum programs within a fixed finite-dimensional state space. A striking difference between nondeterministic classical and quantum programs is shown by example: it is possible that each of several quantum programs simulates the same classical program which terminates with probability 1, but the nondeterministic program consisting of them terminates with probability 0 due to the interference carried in the execution of them.

  10. Part Six: How the Program is Implemented I. Program measures

    E-Print Network [OSTI]

    Program. The Council recognizes these actions as measures that the Bonneville Power Administration program consists of a number of different types of "measures." The Northwest Power Act (and thus (Bonneville) and the other federal agencies have committed to fund and implement under Sections 4(h)(10)(A

  11. Oak Ridge National Laboratory Corrective Action Plan in response to Tiger Team assessment

    SciTech Connect (OSTI)

    Kuliasha, Michael A.

    1991-08-23

    This report presents a complete response to the Tiger Team assessment that was conducted to Oak Ridge National Laboratory (ORNL) and at the US Department of Energy (DOE) Oak Ridge Operations Office (ORO) from October 2, 1990, through November 30, 1990. The action plans have undergone both a discipline review and a cross-cutting review with respect to root cause. In addition, the action plans have been integrated with initiatives being pursued across Martin Marietta Energy Systems, Inc., in response to Tiger Team findings at other DOE facilities operated by Energy Systems. The root cause section is complete and describes how ORNL intends to address the root cause of the findings identified during the assessment. This report is concerned with reactors safety and health findings, responses, and planned actions. Specific areas include: organization and administration; quality verification; operations; maintenance; training and certification; auxiliary systems; emergency preparedness; technical support; nuclear criticality safety; security/safety interface; experimental activities; site/facility safety review; radiological protection; personnel protection; fire protection; management findings, responses, and planned actions; self-assessment findings, responses, and planned actions; and summary of planned actions, schedules, and costs.

  12. Critical Legal Consciousness in Action

    E-Print Network [OSTI]

    Cummings, Scott L

    2007-01-01

    www.ufcw.org/take_action/walmart_workers_campaign_info/Editorial, Global Retailing: WalMart’s Waterloo, Guardian (Buffer Zones Would Prevent Walmart, Others, Park La Brea

  13. JAS - a Java action semantics

    E-Print Network [OSTI]

    Brown, D.F.; Watt, D.A.

    Brown,D.F. Watt,D.A. Proceedings of 2nd International Workshop on Action Semantics pp 43-56 Dept of Computer Science, University of Aarhus

  14. QCD Thermodynamics with Improved Actions

    E-Print Network [OSTI]

    Karsch, Frithjof; Engels, J; Joswig, R; Laermann, E; Peikert, A; Petersson, B

    1996-01-01

    The thermodynamics of the SU(3) gauge theory has been analyzed with tree level and tadpole improved Symanzik actions. A comparison with the continuum extrapolated results for the standard Wilson action shows that improved actions lead to a drastic reduction of finite cut-off effects already on lattices with temporal extent $N_\\tau=4$. Results for the pressure, the critical temperature, surface tension and latent heat are presented. First results for the thermodynamics of four-flavour QCD with an improved staggered action are also presented. They indicate similarly large improvement factors for bulk thermodynamics.

  15. Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

    SciTech Connect (OSTI)

    2013-04-30

    This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996 as amended). CAU 366 consists of the following six Corrective Action Sites (CASs) located in Area 11 of the Nevada National Security Site: · CAS 11-08-01, Contaminated Waste Dump #1 · CAS 11-08-02, Contaminated Waste Dump #2 · CAS 11-23-01, Radioactively Contaminated Area A · CAS 11-23-02, Radioactively Contaminated Area B · CAS 11-23-03, Radioactively Contaminated Area C · CAS 11-23-04, Radioactively Contaminated Area D Site characterization activities were performed in 2011 and 2012, and the results are presented in Appendix A of the Corrective Action Decision Document (CADD) for CAU 366 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2012a). The following closure alternatives were recommended in the CADD: · No further action for CAS 11-23-01 · Closure in place for CASs 11-08-01, 11-08-02, 11-23-02, 11-23-03, and 11-23-04 The scope of work required to implement the recommended closure alternatives includes the following: · Non-engineered soil covers approximately 3 feet thick will be constructed at CAS 11-08-01 over contaminated waste dump (CWD) #1 and at CAS 11-08-02 over CWD #2. · FFACO use restrictions (URs) will be implemented for the areas where the total effective dose (TED) exceeds the final action level (FAL) of 25 millirems per Occasional Use Area year (mrem/OU-yr). The FAL is based on an assumption that the future use of the site includes occasional work activities and that workers will not be assigned to the area on a regular basis. A site worker under this scenario is assumed to be on site for a maximum of 80 hours per year for 5 years. The FFACO UR boundaries will encompass the areas where a worker would be exposed to 25 millirems of radioactivity per year if they are present for 80 hours per year. These boundaries will be defined as follows: – It is assumed that radiological contaminants are present at CAS 11-08-01 and CAS 11-08-02 within CWDs #1 and #2 at levels exceeding the FAL. Therefore, UR boundaries will be established around the perimeters of the soil covers that will be constructed at CWD #1 and CWD #2. A geophysical survey revealed buried metallic debris outside the fence and adjacent to CWD #1. Therefore, the UR boundary for CWD #1 will be expanded to include the mound containing buried material. – It is assumed that radiological contaminants are present at CAS 11-23-02, CAS 11-23-03, and CAS 11-23-04, within the three High Contamination Area (HCA) boundaries associated with the 11b, 11c, and 11d test areas at levels exceeding the FAL. Therefore, the UR boundaries will be established around the perimeters of the HCAs. The TED at an area of soil impacted by radiological debris outside the fence and adjacent to the 11c test area HCA exceeds the FAL of 25 mrem/OU-yr. Because the radiological impact from the debris at this location is visible on the aerial flyover radiological survey, all other areas within this isopleth of the flyover survey are conservatively also assumed to exceed the FAL. Therefore, the UR boundaries for the 11b, 11c, and 11d test areas will be expanded to include the areas within this isopleth. · The FFACO URs will all be located within the large Contamination Area (CA) that encompasses Plutonium Valley. Because access to the CA is limited and entry into the CA for post-closure inspections and maintenance would be impractical, UR warning signs will be posted along the existing CA fence. In accordance with the Soils Risk-Based Corrective Action Evaluation Process (NNSA/NSO, 2012b), an administrative UR will be implemented as a best management practice for the areas where the TED exceeds 25 millirems per Industrial Area year. This limit is based on continuous industrial use of the site and addresses exposure to industrial workers who would regularly be assigned to the work area for an entire career (250 days

  16. Corrective Action Decision Document/Corrective Action Plan for Corrective Action Unit 447: Project Shoal Area, Subsurface, Nevada, Rev. No.: 3 with Errata Sheet

    SciTech Connect (OSTI)

    Tim Echelard

    2006-03-01

    This Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) has been prepared for Corrective Action Unit (CAU) 447, Project Shoal Area (PSA)-Subsurface, Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996). Corrective Action Unit 447 is located in the Sand Springs Mountains in Churchill County, Nevada, approximately 48 kilometers (30 miles) southeast of Fallon, Nevada. The CADD/CAP combines the decision document (CADD) with the Corrective Action Plan (CAP) and provides or references the specific information necessary to recommend corrective actions for CAU 447, as provided in the FFACO. Corrective Action Unit 447 consists of two corrective action sites (CASs): CAS 57-49-01, Emplacement Shaft, and CAS 57-57-001, Cavity. The emplacement shaft (CAS-57-49-01) was backfilled and plugged in 1996 and will not be evaluated further. The purpose of the CADD portion of the document (Section 1.0 to Section 4.0) is to identify and provide a rationale for the selection of a recommended corrective action alternative for the subsurface at PSA. To achieve this, the following tasks were required: (1) Develop corrective action objectives. (2) Identify corrective action alternative screening criteria. (3) Develop corrective action alternatives. (4) Perform detailed and comparative evaluations of the corrective action alternatives in relation to the corrective action objectives and screening criteria. (5) Recommend a preferred corrective action alternative for the subsurface at PSA. The original Corrective Action Investigation Plan (CAIP) for the PSA was approved in September 1996 and described a plan to drill and test four characterization wells, followed by flow and transport modeling (DOE/NV, 1996). The resultant drilling is described in a data report (DOE/NV, 1998e) and the data analysis and modeling in an interim modeling report (Pohll et al., 1998). After considering the results of the modeling effort, the U.S. Department of Energy (DOE) determined that the degree of uncertainty in transport predictions for PSA remained unacceptably large. As a result, a second CAIP was developed by DOE and approved by the Nevada Division of Environmental Protection (NDEP) in December 1998 (DOE/NV, 1998a). This plan prescribed a rigorous analysis of uncertainty in the Shoal model and quantification of methods of reducing uncertainty through data collection. This analysis is termed a Data Decision Analysis (Pohll et al., 1999a) and formed the basis for a second major characterization effort at PSA (Pohll et al., 1999b). The details for this second field effort are presented in an Addendum to the CAIP, which was approved by NDEP in April 1999 (DOE/NV, 1999a). Four additional characterization wells were drilled at PSA during summer and fall of 1999; details of the drilling and well installation are in IT Corporation (2000), with testing reported in Mihevc et al. (2000). A key component of the second field program was a tracer test between two of the new wells (Carroll et al., 2000; Reimus et al., 2003). Based on the potential exposure pathways, two corrective action objectives were identified for CAU 447: Prevent or mitigate exposure to groundwater contaminants of concern at concentrations exceeding regulatory maximum contaminant levels or risk-based levels; and Reduce the risk to human health and the environment to the extent practicable. Based on the review of existing data, the results of the modeling, future use, and current operations at PSA, the following alternatives have been developed for consideration at CAU 447: Alternative 1--No Further Action; Alternative 2--Proof-of-Concept and Monitoring with Institutional Controls; and Alternative 3--Contaminant Control. The corrective action alternatives were evaluated based on the approach outlined in the ''Focused Evaluation of Selected Remedial Alternatives for the Underground Test Area'' (DOE/NV, 1998b). Each alternative was assessed against nine evaluation criteria. These criteria include overall protection of human health and the environment;

  17. FIRE Actions in Response to Next Step Options

    E-Print Network [OSTI]

    FIRE Actions in Response to Next Step Options Program Advisory Committee Report NSO-PAC CHARGES #1. The present level of effort in physics analysis is not fully adequate for ongoing high priority FIRE studies a strong focused effort on the FIRE physics and engineering studies. High priority must also be given

  18. Opportunities, Barriers and Actions for Industrial Demand Response in

    E-Print Network [OSTI]

    LBNL-1335E Opportunities, Barriers and Actions for Industrial Demand Response in California A.T. Mc of Global Energy Partners. This work described in this report was coordinated by the Demand Response Demand Response in California. PIER Industrial/Agricultural/Water EndUse Energy Efficiency Program. CEC

  19. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul P. Guss

    2008-04-01

    This paper describes the contingency planning for the launch of the Mars Science Laboratory scheduled for the 21-day window beginning on September 15, 2009. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the U.S. Department of Energy (DOE) in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec’s Remote Sensing Laboratory (RSL) is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. RSL is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools RSL has available to support these efforts will be reported. The data platform RSL will provide shall also be compatible with integration of assets and field data acquired with other DOE, National Space and Aeronautics and Space Administration (NASA), state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

  20. Radiological Contingency Planning for the Mars Science Laboratory Launch

    SciTech Connect (OSTI)

    Paul Guss, Robert Augdahl, Bill Nickels, Cassandra Zellers

    2008-04-16

    This paper describes the contingency planning for the launch of the Mars Science Laboratory scheduled for the 21-day window beginning on September 15, 2009. National Security Technologies, LLC (NSTec), based in Las Vegas, Nevada, will support the U.S. Department of Energy (DOE) in its role for managing the overall radiological contingency planning support effort. This paper will focus on new technologies that NSTec’s Remote Sensing Laboratory (RSL) is developing to enhance the overall response capability that would be required for a highly unlikely anomaly. This paper presents recent advances in collecting and collating data transmitted from deployed teams and sensors. RSL is responsible to prepare the contingency planning for a range of areas from monitoring and assessment, sample collection and control, contaminated material release criteria, data management, reporting, recording, and even communications. The tools RSL has available to support these efforts will be reported. The data platform RSL will provide shall also be compatible with integration of assets and field data acquired with other DOE, National Aeronautics and Space Administration, state, and local resources, personnel, and equipment. This paper also outlines the organizational structure for response elements in radiological contingency planning.

  1. Radiological Characterization of TFA metallic tubes from CERN Accelerator Complex

    E-Print Network [OSTI]

    Saraiva, Joăo Pedro de Carvalho; Carvalho, Joăo

    The scope of this thesis consists in the radiological characterization of chilled water pipes used for air-conditioning and exposed to ionizing radiation in the PS accelerator, one of the CERN accelerators, for more than 40 years. Due to corrosion problems, the 1200 m of steel pipeline were removed from the PS tunnel during the long shutdowns between the years 2000 to 2004. The radiological characterization, that included the use of FLUKA Monte Carlo simulations and the JEREMY code, began in mid-2011 and revealed a radionuclide inventory with the presence of 55Fe as dominant radionuclide and 60Co as dominant gamma emitter. Due to operational reasons, only 5.5% of the pipeline were characterized for validation. In the course of this work it was found that the contribution of both aforementioned radionuclides corresponds to more than 90% of the total computed IRAS factor (Indice Radiologique d’Acceptation en Stokage). Two different methods were used for the characterization of the PS pipes, yielding two diffe...

  2. C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 2002 SITE ENVIRONMENTAL REPORT APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specificradionuclidereleaserates(incu- ries per year [Ci/yr]) were also used.All annual site

  3. B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    B-1 1999 SITE ENVIRONMENTAL REPORT APPENDIX B: RADIOLOGICAL DATA METHODOLOGIES APPENDIX B: DOSE to calculate annual dispersions for the midpoint of a given sector and distance. Facility specific radionuclide Handbook (EPA 1996). RADIOLOGICAL DATA PROCESSING Radiation events occur in a random fashion

  4. 2010 Radiological Monitoring Results Associated with the Advance Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    mike lewis

    2011-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  5. C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES

    E-Print Network [OSTI]

    Homes, Christopher C.

    C-1 SITE ENVIRONMENTAL REPORT 2000 APPENDIX C: RADIOLOGICAL DATA METHODOLOGIES APPENDIX C: Radiological Data Methodologies DOSE CALCULATION - ATMOSPHERIC RELEASE PATHWAY The effective dose equivalent. Facility-specific radionu- clide release rates (in curies per year [Ci/yr]) were also used. All annual site

  6. Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1

    E-Print Network [OSTI]

    Tanner, Herbert G.

    Intelligent Sensor Management in Nuclear Searches and Radiological Surveys A.V. Klimenko1 , W Special nuclear materials (SNMs) are weak emitters of radiation and are difficult to detect, especially developed intelligent sensor management strategies for nuclear search and radiological surveys

  7. College of Engineering: Open Rank Faculty Department of Nuclear, Plasma, and Radiological Engineering

    E-Print Network [OSTI]

    Lee, Tonghun

    College of Engineering: Open Rank Faculty Department of Nuclear, Plasma, and Radiological Engineering University of Illinois at Urbana-Champaign The Department of Nuclear, Plasma, and Radiological. Well-qualified candidates with background in areas related to nuclear applications including nuclear

  8. 2013 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2014-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  9. 2012 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2013-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (#LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  10. 2011 Radiological Monitoring Results Associated with the Advanced Test Reactor Complex Cold Waste Pond

    SciTech Connect (OSTI)

    Mike Lewis

    2012-02-01

    This report summarizes radiological monitoring performed of the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste wastewater prior to discharge into the Cold Waste Pond and of specific groundwater monitoring wells associated with the Industrial Wastewater Reuse Permit (LA-000161-01, Modification B). All radiological monitoring is performed to fulfill Department of Energy requirements under the Atomic Energy Act.

  11. Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    David Strand

    2006-06-01

    Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if contaminants of concern are present. (5) If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. (6) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection, and field work will commence following approval.

  12. BIOMASS ACTION PLAN FOR SCOTLAND

    E-Print Network [OSTI]

    BIOMASS ACTION PLAN FOR SCOTLAND #12; #12;© Crown copyright 2007 ISBN: 978 0 7559 6506 9 Scottish% recyclable. #12;A BIOMASS ACTION PLAN FOR SCOTLAND #12;#12;1 CONTENTS FOREWORD 3 1. EXECUTIVE SUMMARY 5 2. INTRODUCTION 9 3. WIDER CONTEXT 13 4. SCOTLAND'S ROLE IN THE UK BIOMASS STRATEGY 17 5. BIOMASS HEATING 23 6

  13. Corrective Action Investigation Plan for Corrective Action Unit 105: Area 2 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2012-09-01

    Corrective Action Unit (CAU) 105 is located in Area 2 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 105 is a geographical grouping of sites where there has been a suspected release of contamination associated with atmospheric nuclear testing. This document describes the planned investigation of CAU 105, which comprises the following corrective action sites (CASs): • 02-23-04, Atmospheric Test Site - Whitney • 02-23-05, Atmospheric Test Site T-2A • 02-23-06, Atmospheric Test Site T-2B • 02-23-08, Atmospheric Test Site T-2 • 02-23-09, Atmospheric Test Site - Turk These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2012, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 105. The site investigation process will also be conducted in accordance with the Soils Activity Quality Assurance Plan, which establishes requirements, technical planning, and general quality practices to be applied to this activity. The potential contamination sources associated with all CAU 105 CASs are from atmospheric nuclear testing activities. The presence and nature of contamination at CAU 105 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose at sample locations to the dose-based final action level. The total effective dose will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; DOE, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted after the plan is approved.

  14. Radiological Characterization Issues and Success Stories for the Melton Valley Scrap Yard and Homogeneous Reactor Experiment Evaporator Response Actions

    SciTech Connect (OSTI)

    Patterson, J.E.; Goldsmith, W.A.; Mitchell, K.G. [Strata-G, LLC, Knoxville, TN (United States); Gilpin, J.K. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States)

    2007-07-01

    Proper characterization is essential for assuring that wastes meet any treatment or disposal site waste acceptance criteria (WAC). In addition characterization is vital for proper preparation of shipping papers for transporting the waste for treatment or disposal. Process knowledge was inadequate for characterization of legacy waste items from two sites involved in the Melton Valley Decontamination and Decommissioning (MVD and D) project at the Department of Energy's (DOE) Oak Ridge National Laboratory (ORNL): a scrap yard containing miscellaneous contaminated items, and a liquid waste evaporator used by an experimental nuclear reactor. Waste items at both sites were contaminated with Cs-137/Ba-137 m. Through the use of scaling factors, the gamma radiation associated with this radionuclide pair was used to characterize these items for proper disposal. Application of scaling factors permitted successful remediation of these sites on an accelerated schedule and avoided radiation exposure concerns associated with traditional sampling and analysis. (authors)

  15. Agents That Talk Back (Sometimes): Filter Programs for Affective Communication

    E-Print Network [OSTI]

    Bari, UniversitĂ  degli Studi di

    Agents That Talk Back (Sometimes): Filter Programs for Affective Communication Helmut Prendinger- action that supports basic features of affective conver- sation. As essential requirements for animated

  16. Checklist for Managing a General Program Evaluation Study

    Broader source: Energy.gov [DOE]

    This checklist for managing a general program evaluation study provides action items covering the following topics:  initial planning; evaluation design and procurement; implementation of study;...

  17. Environmental Management Headquarters Corrective Action Plan...

    Energy Savers [EERE]

    Report for the Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 24 Conclusions and 40 Judgments of Need...

  18. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01

    This document constitutes an addendum to the August 2001, Corrective Action Decision Document / Closure Report for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the UR for CAS 22-99-05, Fuel Storage Area. This UR was established as part of a Federal Facility Agreement and Consent Order (FFACO) corrective action and is based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove the UR because contamination is not present at the site above the risk-based FALs. Requirements for inspecting and maintaining this UR will be canceled, and the postings and signage at this site will be removed. Fencing and posting may be present at this site that are unrelated to the FFACO UR such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at this site.

  19. Skyshine And Groundshine Phenomena And Related Radiological quantities evaluated For The Environment Of A High Current Spallation Facility

    E-Print Network [OSTI]

    Zazula, J M; Cloth, P

    1987-01-01

    Skyshine And Groundshine Phenomena And Related Radiological quantities evaluated For The Environment Of A High Current Spallation Facility

  20. On-Line Educational Means on Radiological Protection and Accelerator General Safety Policy in Radiotherapy and Industrial Sterilization Facilities

    E-Print Network [OSTI]

    Spyropoulos, B

    1999-01-01

    On-Line Educational Means on Radiological Protection and Accelerator General Safety Policy in Radiotherapy and Industrial Sterilization Facilities

  1. Corrective Action Investigation Plan for Corrective Action Unit 224: Decon Pad and Septic Systems Nevada Test Site, Nevada, Rev. No.: 0, with ROTC 1 and 2

    SciTech Connect (OSTI)

    David A. Strand

    2004-04-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 224: Decon Pad and Septic Systems, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the State of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (DoD). The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Unit 224 is comprised of the nine Corrective Action Sites (CASs) listed below: 02-04-01, Septic Tank (Buried); 03-05-01, Leachfield; 05-04-01, Septic Tanks (4)/Discharge Area; 06-03-01, Sewage Lagoons (3); 06-05-01, Leachfield; 06-17-04, Decon Pad and Wastewater Catch; 06-23-01, Decon Pad Discharge Piping; 11-04-01, Sewage Lagoon; and 23-05-02, Leachfield. Corrective Action Sites 06-05-01, 06-23-01, and 23-05-02 were identified in the 1991 Reynolds Electrical & Engineering Co., Inc. (REECo) inventory (1991). The remaining sites were identified during review of various historical documents. Additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating and selecting a corrective action alternative for each CAS. The CAI will include field inspections, radiological and geological surveys, and sample collection. Data will also be obtained to support investigation-derived waste (IDW) disposal and potential future waste management decisions.

  2. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  3. Enforcement actions: Significant actions resolved individual actions. Semiannual progress report, January 1996--June 1996

    SciTech Connect (OSTI)

    1996-08-01

    This document summarizes significant enforcement actions that have been resolved during the period of January-June 1996. The report includes copies of Orders and Notices of Violations sent by the Nuclear Regulatory Commission to individuals with respect to the enforcement actions.

  4. Science in Action: 9-12 Science Education within the University Infrastructure

    E-Print Network [OSTI]

    Science in Action: 9-12 Science Education within the University Infrastructure Fosters Effective-MORE GEMS award, I was afforded the opportunity to join my co-authors at the 2014 Ocean Sciences Meeting College's inaugural Science in Action 2013 summer program for high school students. Our poster also

  5. FIA-12-0050- In the Matter of Cause of Action

    Broader source: Energy.gov [DOE]

    On October 4, 2012, The Office of Hearings and Appeals (OHA) granted an Appeal filed by Cause of Action (COA) under the FOIA of a final determination issued by the Loan Guarantee Program Office ...

  6. A Picture Is Worth A Thousand Words: Needs Assessment for Multimedia Radiology Reports in a Large Tertiary Care

    E-Print Network [OSTI]

    Rubin, Daniel L.

    A Picture Is Worth A Thousand Words: Needs Assessment for Multimedia Radiology Reports in a Large, Jafi A. Lipson, MD Rationale and Objectives: Radiology reports are the major, and often only, means referring physicians' preferences about radiology reports and to quantify their perceived value

  7. Hanford surplus facilities programs facilities listings and descriptions. Revision 1

    SciTech Connect (OSTI)

    Kiser, S.K.; Witt, T.L.

    1994-01-01

    On the Hanford Site, many surplus facilities exist (including buildings, stacks, tanks, cribs, burial grounds, and septic systems) that are scheduled to be decommissioned. Many of these facilities contain large inventories of radionuclides, which present potential radiological hazards on and off the Hanford Site. Some structures with limited structural deterioration present potential radiological and industrial safety hazards to personnel. Because of the condition of these facilities, a systematic surveillance and maintenance program is performed to identify and correct potential hazards to personnel and the environment until eventual decommissioning operations are completed.

  8. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5

    SciTech Connect (OSTI)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  9. Corrective Action Decision Document/Closure Report for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Matthews, Patrick and Sloop, Christy

    2011-04-01

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 372, Area 20 Cabriolet/Palanquin Unit Craters, located within Areas 18 and 20 at the Nevada National Security Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 372 comprises four corrective action sites (CASs): • 18-45-02, Little Feller I Surface Crater • 18-45-03, Little Feller II Surface Crater • 20-23-01, U-20k Contamination Area • 20-45-01, U-20L Crater (Cabriolet) The purpose of this CADD/CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 372 based on the implementation of the corrective action of closure in place with administrative controls at all CASs. Corrective action investigation (CAI) activities were performed from November 9, 2009, through December 10, 2010, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 372: Area 20 Cabriolet/Palanquin Unit Craters. The approach for the CAI was divided into two facets: investigation of the primary release of radionuclides and investigation of other releases (migration in washes and chemical releases). The purpose of the CAI was to fulfill data needs as defined during the data quality objective (DQO) process. The CAU 372 dataset of investigation results was evaluated based on a data quality assessment. This assessment demonstrated the dataset is acceptable for use in fulfilling the DQO data needs. Investigation results were evaluated against final action levels (FALs) established in this document. A radiological dose FAL was established of 25 millirem per year based on the Remote Work Area exposure scenario (336 hours of annual exposure). Radiological doses exceeding the FAL were found to be present at all four CASs. It is assumed that radionuclide levels present within the Little Feller I and Cabriolet high contamination areas and within the craters at Palanquin and Cabriolet exceed the FAL. It is also assumed that potential source material in the form of lead bricks at Little Feller I and lead-acid batteries at Palanquin and Cabriolet exceed the FAL. Therefore, corrective actions were undertaken that consist of removing potential source material, where present, and implementing a use restriction and posting warning signs at each CAS. These use restrictions were recorded in the FFACO database; the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Facility Information Management System; and the NNSA/NSO CAU/CAS files. Therefore, NNSA/NSO provides the following recommendations: • No further corrective actions are necessary for CAU 372. • A Notice of Completion to NNSA/NSO is requested from the Nevada Division of Environmental Protection for closure of CAU 372. • Corrective Action Unit 372 should be moved from Appendix III to Appendix IV of the FFACO.

  10. Results of the radiological survey at 6 Branca Court, Lodi, New Jersey (LJ041)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.; Carrier, R.F.; Crutcher, J.W.

    1989-06-01

    Maywood Chemical works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rate earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 6 Branca Court, Lodi, New Jersey (LJ041), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Act program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 6 figs., 3 tabs.

  11. Corrective Action Investigation Plan for Corrective Action Unit 569: Area 3 Yucca Flat Atmospheric Test Sites Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews; Christy Sloop

    2012-02-01

    Corrective Action Unit (CAU) 569 is located in Area 3 of the Nevada National Security Site, which is approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 569 comprises the nine numbered corrective action sites (CASs) and one newly identified site listed below: (1) 03-23-09, T-3 Contamination Area (hereafter referred to as Annie, Franklin, George, and Moth); (2) 03-23-10, T-3A Contamination Area (hereafter referred to as Harry and Hornet); (3) 03-23-11, T-3B Contamination Area (hereafter referred to as Fizeau); (4) 03-23-12, T-3S Contamination Area (hereafter referred to as Rio Arriba); (5) 03-23-13, T-3T Contamination Area (hereafter referred to as Catron); (6) 03-23-14, T-3V Contamination Area (hereafter referred to as Humboldt); (7) 03-23-15, S-3G Contamination Area (hereafter referred to as Coulomb-B); (8) 03-23-16, S-3H Contamination Area (hereafter referred to as Coulomb-A); (9) 03-23-21, Pike Contamination Area (hereafter referred to as Pike); and (10) Waste Consolidation Site 3A. Because CAU 569 is a complicated site containing many types of releases, it was agreed during the data quality objectives (DQO) process that these sites will be grouped. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each study group. The results of the field investigation will support a defensible evaluation of viable CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the DQOs developed on September 26, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 569. The presence and nature of contamination at CAU 569 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated as the total of separate estimates of internal and external dose. Results from the analysis of soil samples will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at the center of each sample location will be used to measure external radiological dose. A field investigation will be performed to define any areas where TED exceeds the FAL and to determine whether contaminants of concern are present at the site from other potential releases. The presence and nature of contamination from other types of releases (e.g., excavation, migration, and any potential releases discovered during the investigation) will be evaluated using soil samples collected from biased locations indicating the highest levels of contamination. Appendix A provides a detailed discussion of the DQO methodology and the objectives specific to each study group.

  12. Corrective Action Investigation Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Patrick Matthews

    2011-09-01

    Corrective Action Unit 366 comprises the six corrective action sites (CASs) listed below: (1) 11-08-01, Contaminated Waste Dump No.1; (2) 11-08-02, Contaminated Waste Dump No.2; (3) 11-23-01, Radioactively Contaminated Area A; (4) 11-23-02, Radioactively Contaminated Area B; (5) 11-23-03, Radioactively Contaminated Area C; and (6) 11-23-04, Radioactively Contaminated Area D. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). Additional information will be obtained by conducting a corrective action investigation before evaluating CAAs and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of CAAs that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed July 6, 2011, by representatives of the Nevada Division of Environmental Protection and the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 366. The presence and nature of contamination at CAU 366 will be evaluated based on information collected from a field investigation. Radiological contamination will be evaluated based on a comparison of the total effective dose (TED) at sample locations to the dose-based final action level (FAL). The TED will be calculated by summing the estimates of internal and external dose. Results from the analysis of soil samples collected from sample plots will be used to calculate internal radiological dose. Thermoluminescent dosimeters placed at each sample location will be used to measure external radiological dose. Based on historical documentation of the releases associated with the nuclear tests, it was determined that CASs 11-23-02, 11-23-03, and 11-23-04 will be investigated as one release site. The three test areas associated with these CASs are in close proximity; the devices tested were all composed of plutonium and enriched uranium; and the ground zeroes are all posted high contamination areas (HCAs). Because the device tested at CAS 11-23-01 was composed primarily of enriched uranium and the ground zero is not a posted HCA, the CAS will be investigated as a separate release. The DQO process also resulted in an assumption that TED within the HCAs and contaminated waste dumps exceeds the FAL and requires corrective action. A field investigation will be performed to define where TED exceeds the FAL and to determine whether other contaminants of concern are present at the site associated with other activities that took place at the site or from spills or waste discovered during the investigation. The presence and nature of contamination from other types of releases (such as migration and any potential releases discovered during the investigation) will be evaluated using soil samples collected from the locations most likely containing contamination, if present. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS.

  13. Knowledge-to-Action Guides: Preparing Families to Be Partners in Making Educational Decisions

    E-Print Network [OSTI]

    Turnbull, Ann P.; Zuna, Nina; Hong, Joo Young; Hu, Xiaoyi; Kyzar, Kathleen; Obremski, Shea; Summers, Jean Ann; Turnbull, H. Rutherford; Stowe, Matthew J.

    2010-01-01

    parents become experts in special education, and help make good decisions about their children's education programs? Knowledge to action (KTA) guides are one resource, providing families access to top tier knowledge on evidence- based practice... Coordination Providing Emotional Snppoil to Families Through Parent to Parent Programs Video in English and Spajiish Parent quotes/action steps from Community of Practice 4 family stories 4 stale education department family- friendly guides 3 family stories...

  14. Closure Report for Corrective Action Unit 566: EMAD Compound, Nevada National Security Site, Nevada with ROTC-1, Revision 0

    SciTech Connect (OSTI)

    Mark Krauss

    2011-06-01

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 566: EMAD Compound, Nevada National Security Site, Nevada. Corrective Action Unit 566 comprises Corrective Action Site (CAS) 25-99-20, EMAD Compound, located within Area 25 of the Nevada National Security Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 566 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 566 issued by the Nevada Division of Environmental Protection. From October 2010 through May 2011, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 566: EMAD Compound, Nevada National Security Site, Nevada. The purposes of the activities as defined during the data quality objectives process were as follows: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels (FALs) to determine COCs for CAU 566. Assessment of the data from collected soil samples, and from radiological and visual surveys of the site, indicates the FALs were exceeded for polychlorinated biphenyls (PCBs), semivolatile organic compounds (SVOCs), and radioactivity. Corrective actions were implemented to remove the following: • Radiologically contaminated soil assumed greater than FAL at two locations • Radiologically contaminated soil assumed greater than FAL with lead shot • PCB-contaminated soil • Radiologically contaminated filters and equipment • Fuels, lubricants, engine coolants, and oils • Lead debris • Electrical and lighting components assumed to be potential source materials, including - fluorescent light bulbs - mercury switches (thermostats) - circuit boards - PCB-containing ballasts Closure of CAU 566 was achieved through a combination of removal activities and closure in place. Corrective actions to remove COCs, and known and assumed potential source materials, were implemented as was practical. The PCBs remaining at the site are bounded laterally, but not vertically, within CAS 25-99-20 based upon step-out sampling; the sources (e.g., PCB transformer oils, diesel fuel from locomotive reservoirs) have been removed; the practice of the application of PCB-containing oils for soil stabilization has ceased; and the COCs are not readily mobile in the environment. Closure in place is necessary, and future land use of the site will be restricted from intrusive activities. This will effectively eliminate inadvertent contact by humans with the contaminated media. The DOE, National Nuclear Security Administration Nevada Site Office, provides the following recommendations: • No further corrective action is required at CAS 25-99-20. • Closure in place of CAS 25-99-20. • A use restriction is required at CAU 566. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 566. • Corrective Action Unit 566 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  15. Results of the radiological survey at 146 W. Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and reining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from OaK Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. These surveys typically include direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, a private property at 146 West Central Avenue, Maywood, New Jersey (MJ034), was conducted during 1987 and 1988. While some measurements at this property were greater than background levels typically encountered in the New jersey area, no radiation levels nor radionuclide concentrations exceeded the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. However, because of the proximity of the railroad property, which will be remediated, and the DOE's ALARA (As Low As Reasonably Achievable) policy, concurrent removal of the slightly elevated soil layers at 146 W. Central Avenue may be justified. 6 refs., 6 figs., 3 tabs.

  16. RCRA corrective action: Work plans

    SciTech Connect (OSTI)

    Not Available

    1995-02-01

    This Information Brief describes the work plans that owners/operators may have to prepare in conjunction with the performance of corrective action for compliance with RCRA guidelines. In general, the more complicated the performance of corrective action appears from the remedial investigation and other analyses, the more likely it is that the regulator will impose work plan requirements. In any case, most owner/operators will prepare work plans in conjunction with the performance of corrective action processes as a matter of best engineering management practices.

  17. HAZARDS OF THERMAL EXPANSION FOR RADIOLOGICAL CONTAINER ENGULFED IN FIRE

    SciTech Connect (OSTI)

    Donna Post Guillen

    2013-05-01

    Fire accidents pose a serious threat to nuclear facilities. It is imperative that transport casks or shielded containers designed to transport/contain radiological materials have the ability to withstand a hypothetical fire. A numerical simulation was performed for a shielded container constructed of stainless steel and lead engulfed in a hypothetical fire as outlined by 10 CFR §71.73. The purpose of this analysis was to determine the thermal response of the container during and after the fire. The thermal model shows that after 30 minutes of fire, the stainless steel will maintain its integrity and not melt. However, the lead shielding will melt since its temperature exceeds the melting point. Due to the method of construction of the container under consideration, ample void space must be provided to allow for thermal expansion of the lead upon heating and melting, so as to not overstress the weldment.

  18. Status of ion sources at National Institute of Radiological Sciences

    SciTech Connect (OSTI)

    Kitagawa, A.; Fujita, T.; Goto, A.; Hattori, T.; Hamano, T.; Hojo, S.; Honma, T.; Imaseki, H.; Katagiri, K.; Muramatsu, M.; Sakamoto, Y.; Sekiguchi, M.; Suda, M.; Sugiura, A.; Suya, N.

    2012-02-15

    The National Institute of Radiological Sciences (NIRS) maintains various ion accelerators in order to study the effects of radiation of the human body and medical uses of radiation. Two electrostatic tandem accelerators and three cyclotrons delivered by commercial companies have offered various life science tools; these include proton-induced x-ray emission analysis (PIXE), micro beam irradiation, neutron exposure, and radioisotope tracers and probes. A duoplasmatron, a multicusp ion source, a penning ion source (PIG), and an electron cyclotron resonance ion source (ECRIS) are in operation for these purposes. The Heavy-Ion Medical Accelerator in Chiba (HIMAC) is an accelerator complex for heavy-ion radiotherapy, fully developed by NIRS. HIMAC is utilized not only for daily treatment with the carbon beam but also for fundamental experiments. Several ECRISs and a PIG at HIMAC satisfy various research and clinical requirements.

  19. Final voluntary release assessment/corrective action report

    SciTech Connect (OSTI)

    NONE

    1996-11-12

    The US Department of Energy, Carlsbad Area Office (DOE-CAO) has completed a voluntary release assessment sampling program at selected Solid Waste Management Units (SWMUs) at the Waste Isolation Pilot Plant (WIPP). This Voluntary Release Assessment/Corrective Action (RA/CA) report has been prepared for final submittal to the Environmental protection Agency (EPA) Region 6, Hazardous Waste Management Division and the New Mexico Environment Department (NMED) Hazardous and Radioactive Materials Bureau to describe the results of voluntary release assessment sampling and proposed corrective actions at the SWMU sites. The Voluntary RA/CA Program is intended to be the first phase in implementing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) and corrective action process at the WIPP. Data generated as part of this sampling program are intended to update the RCRA Facility Assessment (RFA) for the WIPP (Assessment of Solid Waste Management Units at the Waste Isolation Pilot Plant), NMED/DOE/AIP 94/1. This Final Voluntary RA/CA Report documents the results of release assessment sampling at 11 SWMUs identified in the RFA. With this submittal, DOE formally requests a No Further Action determination for these SWMUs. Additionally, this report provides information to support DOE`s request for No Further Action at the Brinderson and Construction landfill SWMUs, and to support DOE`s request for approval of proposed corrective actions at three other SWMUs (the Badger Unit Drill Pad, the Cotton Baby Drill Pad, and the DOE-1 Drill Pad). This information is provided to document the results of the Voluntary RA/CA activities submitted to the EPA and NMED in August 1995.

  20. ICDF Complex Remedial Action Report

    SciTech Connect (OSTI)

    W. M. Heileson

    2007-09-26

    This Idaho CERCLA Disposal Facility (ICDF) Remedial Action Report has been prepared in accordance with the requirements of Section 6.2 of the INEEL CERCLA Disposal Facility Remedial Action Work Plan. The agency prefinal inspection of the ICDF Staging, Storage, Sizing, and Treatment Facility (SSSTF) was completed in June of 2005. Accordingly, this report has been developed to describe the construction activities completed at the ICDF along with a description of any modifications to the design originally approved for the facility. In addition, this report provides a summary of the major documents prepared for the design and construction of the ICDF, a discussion of relevant requirements and remedial action objectives, the total costs associated with the development and operation of the facility to date, and identification of necessary changes to the Agency-approved INEEL CERCLA Disposal Facility Remedial Action Work Plan and the ICDF Complex Operations and Maintenance Plan.