WorldWideScience

Sample records for facility descriptions environmental

  1. Description of work for routine groundwater sampling at the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Ford, B.H.

    1996-09-01

    This document provides a description of work and field implementation guidance for routine (post-baseline) groundwater monitoring sampling program at the Environmental Restoration Disposal Facility. The purpose of this program is to (1) meet the intent of the applicable or relevant and appropriate requirements; (2) document baseline groundwater conditions; (3) monitor those conditions for change; and (4) allow for modifications to groundwater sampling if required by the leachate management program

  2. Hanford Site existing irradiated fuel storage facilities description

    Energy Technology Data Exchange (ETDEWEB)

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  3. Analytical methodology and facility description spent fuel policy

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    Three generic environmental impact statements (GEISs) on domestic fuels, foreign fuels, and storage charges are being prepared to provide environmental input into decisions on whether, and if so how the 1977 Presidential policy on spent fuel storage should be implmented. This report provides background information for two of these environmental impact statements: Storage of U.S. Spent Power Reactor Fuel and Storage of Foreign Spent Power Reactor Fuel. It includes the analytical methodology used in GEISs to assess the environmental effects and a description of the facilities used in the two GEISs.

  4. Analytical methodology and facility description spent fuel policy

    International Nuclear Information System (INIS)

    1978-08-01

    Three generic environmental impact statements (GEISs) on domestic fuels, foreign fuels, and storage charges are being prepared to provide environmental input into decisions on whether, and if so how the 1977 Presidential policy on spent fuel storage should be implmented. This report provides background information for two of these environmental impact statements: Storage of U.S. Spent Power Reactor Fuel and Storage of Foreign Spent Power Reactor Fuel. It includes the analytical methodology used in GEISs to assess the environmental effects and a description of the facilities used in the two GEISs

  5. Earth and environmental science in the 1980's: Part 1: Environmental data systems, supercomputer facilities and networks

    Science.gov (United States)

    1986-01-01

    Overview descriptions of on-line environmental data systems, supercomputer facilities, and networks are presented. Each description addresses the concepts of content, capability, and user access relevant to the point of view of potential utilization by the Earth and environmental science community. The information on similar systems or facilities is presented in parallel fashion to encourage and facilitate intercomparison. In addition, summary sheets are given for each description, and a summary table precedes each section.

  6. Fuel Handling Facility Description Document

    International Nuclear Information System (INIS)

    M.A. LaFountain

    2005-01-01

    The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

  7. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J.F. Beesley

    2005-04-21

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  8. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Beesley. J.F.

    2005-01-01

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process

  9. UO3 plant turnover - facility description document

    International Nuclear Information System (INIS)

    Clapp, D.A.

    1995-01-01

    This document was developed to provide a facility description for those portions of the UO 3 Facility being transferred to Bechtel Hanford Company, Inc. (BHI) following completion of facility deactivation. The facility and deactivated state condition description is intended only to serve as an overview of the plant as it is being transferred to BHI

  10. Brief description of the Wackersdorf Reprocessing Facility

    International Nuclear Information System (INIS)

    1986-01-01

    The DWK is now planning the construction and operation of a facility for the reprocessing of spent fuel elements and the fabrication of mixed-oxide fuel elements which will initially have an average daily throughput of 2 tons (t) of nuclear fuel. The application required by the Atomic Law was submitted to the Bavarian State Ministry for State Development and Environmental Matters on October 28, 1982. According to Par. 3, Section 1, No. 1 of the Atomic Law Procedural Ordinance such an application for permission in accordance with par. 7 AtL must explicitly be accompanied by a safety report which shall make it possible for third parties to make a judgment whether the impacts associated with the facility and its operation could damage their rights. The safety report is intended to present and explain the concept of the facility, the safety-technological design bases, and the operation of the plant, including its operation and safety systems and the impacts and proposed preventive measures. In addition to the detailed presentations in the safety report, Par. 3 of the Atomic Law Procedural Ordinance also requires a brief description of the plant designed for general public understanding, suitable for the design, which will also explain the expected impacts on the general environment and the surrounding area. Hence the brief description presents and explains the following matters: the site; the technology and state of the art for reprocessing of spent nuclear fuel; the structure and function of the proposed facility; safety provisions of the proposed facility and the management of perturbations in operation; the impacts of the facility and its operation on the environment; measures to be taken for dealing with the radioactive wastes; and provisions for ultimate shut-down of the facility

  11. Environmental Monitoring Report - United States Department of Energy, Oak Ridge Facilities, Calendar Year 1984

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, R.G.

    1999-01-01

    Each year since 1972, a report has been prepared on the environmental monitoring activities for the DOE facilities in oak Ridge, Tennessee, for the previous calendar year. previously, the individual facilities published quarterly and annual progress reports that contained some environmental monitoring data. The environmental monitoring program for 1984 includes sampling and analysis of air, water from surface streams, groundwater, creek sediment, biota, and soil for both radioactive and nonradioactive (including hazardous) materials. Special environmental studies that have been conducted in the Oak Ridge area are included in this report, primarily as abstracts or brief summaries. The annual report for 1984 on environmental monitoring and surveillance of the Oak Ridge community by Oak Ridge Associated Universities (ORAU) is included as an appendix. A brief description of the topography and climate of the Oak Ridge area and a short description of the three DOE facilities are provided below to enhance the reader's understanding of the direction and contents of the environmental monitoring program for Oak Ridge.

  12. Supervision of Waste Management and Environmental Protection at the Swedish Nuclear Facilities 2001

    CERN Document Server

    Persson, M

    2003-01-01

    The report summarizes the supervision of waste management and environmental protection at the nuclear facilities that was carried out by the Swedish Radiation Protection Authority in 2001. A summary of the inspections and a description of important issues connected with the supervision of the nuclear facilities are given.The inspections during 2001 have focused on theme inspections of waste management, environmental inspections considering the environmental monitoring at the Swedish nuclear facilities and review safety analysis and research programs from the Swedish Nuclear Fuel and Waste Management Co.The Swedish Radiation Protection Authority finds that the operations are mainly performed according to current regulations

  13. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  14. Environmental Toxicology Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Fully-equipped facilities for environmental toxicology researchThe Environmental Toxicology Research Facility (ETRF) located in Vicksburg, MS provides over 8,200 ft...

  15. Supervision of waste management and environmental protection at the Swedish nuclear facilities 1999

    International Nuclear Information System (INIS)

    2000-03-01

    The report summarizes the supervision of waste management and environmental protection at the nuclear facilities that was carried out by the Swedish Radiation Protection Institute in 1999. A summary of the inspections during 1999 and a description of important issues connected with the supervision of the nuclear facilities are given. The inspections during 1999 have focused on the management of liquid discharges and components containing induced activity at some of the nuclear facilities. Also, routines for filing environmental samples, discharge water samples and documents were inspected at all the different nuclear facilities. The Swedish Radiation Protection Institute finds that the operations are mainly performed according to current regulations

  16. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

  17. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    International Nuclear Information System (INIS)

    1997-01-01

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns

  18. Defense Waste Processing Facility staged operations: environmental information document

    International Nuclear Information System (INIS)

    1981-11-01

    Environmental information is presented relating to a staged version of the proposed Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The information is intended to provide the basis for an Environmental Impact Statement. In either the integral or the staged design, the DWPF will convert the high-level waste currently stored in tanks into: a leach-resistant form containing about 99.9% of all the radioactivity, and a residual, slightly contaminated salt, which is disposed of as saltcrete. In the first stage of the staged version, the insoluble sludge portion of the waste and the long lived radionuclides contained therein will be vitrified. The waste glass will be sealed in canisters and stored onsite until shipped to a Federal repository. In the second stage, the supernate portion of the waste will be decontaminated by ion exchange. The recovered radionuclides will be transferred to the Stage 1 facility, and mixed with the sludge feed before vitrification. The residual, slightly contaminated salt solution will be mixed with Portland cement to form a concrete product (saltcrete) which will be buried onsite in an engineered landfill. This document describes the conceptual facilities and processes for producing glass waste and decontaminated salt. The environmental effects of facility construction, normal operations, and accidents are then presented. Descriptions of site and environs, alternative sites and waste disposal options, and environmental consultations and permits are given in the base Environmental Information Document

  19. Descriptions of representative contaminated sites and facilities within the DOE complex

    International Nuclear Information System (INIS)

    Short, S.M.; Buck, J.W.; Clark, L.L.; Fletcher, J.F.; Glantz, C.S.; Holdren, G.R.; Huesties, L.R.; Williams, M.D.; Oates, L.

    1994-10-01

    The U.S. Department of Energy (DOE) has initiated efforts to prepare a Programmatic Environmental Impact Statement (PEIS) that will analyze the existing environmental restoration and waste management program and evaluate alternatives for an integrated program. The alternatives being evaluated include (1) a open-quotes No Actionclose quotes alternative as required by the National Environmental Policy Act (NEPA), (2) an Applicable, Relevant, and Appropriate Requirements (ARAR)-driven alternative, (3) a land-use-driven alternative, (4) a health-risk-driven alternative, and (5) a combination land-use and health-risk-driven alternative. The analytical approach being taken to evaluate each of these alternatives is to perform a remedial engineering analysis and human health and ecosystem effects analyses on every contaminated site and facility in the DOE complex. One of Pacific Northwest Laboratory's (PNL) roles in this approach has been to compile the source term and environmental setting data needed to drive each of these analyses. To date, over 10,000 individual contaminated sites and facilities located throughout the DOE complex of installations have been identified and at least some minimal data compiled on each. The PEIS analyses have been appreciably simplified by categorizing all of these contaminated sites and facilities into six broad categories: (1) contaminated buildings, (2) contaminated soils, (3) solid waste sites (e.g., burial grounds), (4) liquid containment structures (e.g., tanks), (5) surface water sites, and (6) contaminated groundwater sites. A report containing a complete description of each of these thousands of contaminated sites and facilities would be tremendously large and unwildy, as would separate reports describing the application of the analytical methodologies to each

  20. Health and environmental aspects of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1996-11-01

    The purpose of the present publication is to give a generic description of health and environmental aspects of nuclear fuel cycle facilities. Primarily the report is meant to stand alone; however, because of the content of the publication and in the context of the DECADES project, it may serve as a means of introducing specialists in other fuel cycles to the nuclear fuel cycle. Refs, figs, tabs

  1. Detailed description of an SSAC at the facility level for research laboratory facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-08-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  2. Environmentally Regulated Facilities in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — A unique record for each facility site with an environmental interest by DNR (such as permits). This brings together core environmental information in one place for...

  3. Near-facility environmental monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, J.W.; Johnson, A.R.; Markes, B.M.; McKinney, S.M.; Perkins, C.J.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the routine near-facility environmental monitoring programs which are presently being conducted at the Hanford Site. Several types of environmental media are sampled near nuclear facilities to monitor the effectiveness of waste management and restoration activities, and effluent treatment and control practices. These media include air, surface water and springs, surface contamination, soil and vegetation, investigative sampling (which can include wildlife), and external radiation. Sampling and analysis information and analytical results for 1994 for each of these media are summarized in this section. Additional data and more detailed information may be found in Westinghouse Hanford Company Operational Environmental Monitoring Annual Report, Calendar Year 1994.

  4. Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

    International Nuclear Information System (INIS)

    Palomaeki, J.; Ristimaeki, L.

    2013-10-01

    The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

  5. Detailed description of an SSAC at the facility level for mixed oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-09-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a mixed oxide fuel fabrication facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  6. Fuels and Materials Examination Facility: Environmental assessment, Hanford site, Richland, Washington: Environmental assessment

    International Nuclear Information System (INIS)

    1980-07-01

    The Fuels and Materials Examination Facility (FMEF) and the High Performance Fuel Laboratory (HPFL) were originally proposed to be constructed as separate facilities in the 400 Area of the Hanford Site near Richland, Washington. The environmental effects of these two facilities were described and evaluated in the FMEF Environmental Assessment and the HPFL Final Environmental Impact Statement, ERDA-1550. For economic reasons, the two facilities will no longer be built as separate facilities. The FMEF facility plans have been modified to incorporate some of the features of the proposed HPFL facility while retaining essentially all of the capabilities of the original FMEF proposal. The purpose of this document is to update the FMEF Environmental Assessment to appropriately reflect addition of certain HPFL features into the FMEF facility and to assess the environmental affects of the facility which resulted from inclusion of HPFL features into the FMEF facility

  7. Environmental Compliance and Protection Program Description Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Jacobs

    2009-02-26

    The objective of the Environmental Compliance and Protection (EC and P) Program Description (PD) is to establish minimum environmental compliance requirements and natural resources protection goals for the Bechtel Jacobs Company LLC (BJC) Oak Ridge Environmental Management Cleanup Contract (EMCC) Contract Number DE-AC05-98OR22700-M198. This PD establishes the work practices necessary to ensure protection of the environment during the performance of EMCC work activities on the US Department of Energy's (DOE's) Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee, by BJC employees and subcontractor personnel. Both BJC and subcontractor personnel are required to implement this PD. A majority of the decontamination and demolition (D and D) activities and media (e.g., soil and groundwater) remediation response actions at DOE sites on the ORR are conducted under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). CERCLA activities are governed by individual CERCLA decision documents (e.g., Record of Decision [ROD] or Action Memorandum) and according to requirements stated in the Federal Facility Agreement for the Oak Ridge Reservation (DOE 1992). Applicable or relevant and appropriate requirements (ARARs) for the selected remedy are the requirements for environmental remediation responses (e.g., removal actions and remedial actions) conducted under CERCLA.

  8. Program of radiological monitoring environmental a nuclear facility in latency

    International Nuclear Information System (INIS)

    Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

    2013-01-01

    This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

  9. Descriptions of reference LWR facilities for analysis of nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Kabele, T.J.

    1979-09-01

    To contribute to the Department of Energy's identification of needs for improved environmental controls in nuclear fuel cycles, a study was made of a light water reactor system. A reference LWR fuel cycle was defined, and each step in this cycle was characterized by facility description and mainline and effluent treatment process performance. The reference fuel cycle uses fresh uranium in light water reactors. Final treatment and ultimate disposition of waste from the fuel cycle steps were not included, and the waste is assumed to be disposed of by approved but currently undefined means. The characterization of the reference fuel cycle system is intended as basic information for further evaluation of alternative effluent control systems.

  10. Descriptions of reference LWR facilities for analysis of nuclear fuel cycles

    International Nuclear Information System (INIS)

    Schneider, K.J.; Kabele, T.J.

    1979-09-01

    To contribute to the Department of Energy's identification of needs for improved environmental controls in nuclear fuel cycles, a study was made of a light water reactor system. A reference LWR fuel cycle was defined, and each step in this cycle was characterized by facility description and mainline and effluent treatment process performance. The reference fuel cycle uses fresh uranium in light water reactors. Final treatment and ultimate disposition of waste from the fuel cycle steps were not included, and the waste is assumed to be disposed of by approved but currently undefined means. The characterization of the reference fuel cycle system is intended as basic information for further evaluation of alternative effluent control systems

  11. Retrievable surface storage facility conceptual system design description

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-01

    The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts.

  12. Retrievable surface storage facility conceptual system design description

    International Nuclear Information System (INIS)

    1977-03-01

    The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts

  13. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    International Nuclear Information System (INIS)

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE's proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP

  14. Environmental assessment of the Carlsbad Environmental Monitoring and Research Center Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This Environmental Assessment has been prepared to determine if the Carlsbad Environmental Monitoring and Research Center (the Center), or its alternatives would have significant environmental impacts that must be analyzed in an Environmental Impact Statement. DOE`s proposed action is to continue funding the Center. While DOE is not funding construction of the planned Center facility, operation of that facility is dependent upon continued funding. To implement the proposed action, the Center would initially construct a facility of approximately 2,300 square meters (25,000 square feet). The Phase 1 laboratory facilities and parking lot will occupy approximately 1.2 hectares (3 acres) of approximately 8.9 hectares (22 acres) of land which were donated to New Mexico State University (NMSU) for this purpose. The facility would contain laboratories to analyze chemical and radioactive materials typical of potential contaminants that could occur in the environment in the vicinity of the DOE Waste Isolation Pilot Plant (WIPP) site or other locations. The facility also would have bioassay facilities to measure radionuclide levels in the general population and in employees of the WIPP. Operation of the Center would meet the DOE requirement for independent monitoring and assessment of environmental impacts associated with the planned disposal of transuranic waste at the WIPP.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  16. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    International Nuclear Information System (INIS)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year

  17. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    Energy Technology Data Exchange (ETDEWEB)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

  18. Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-11-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  19. Facility Environmental Management System

    Data.gov (United States)

    Federal Laboratory Consortium — This is the Web site of the Federal Highway Administration's (FHWA's) Turner-Fairbank Highway Research Center (TFHRC) facility Environmental Management System (EMS)....

  20. Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

    International Nuclear Information System (INIS)

    1987-09-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs

  1. Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

    Energy Technology Data Exchange (ETDEWEB)

    1987-09-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs.

  2. Description of an engineering-scale facility for uranium fluorination studies

    International Nuclear Information System (INIS)

    Yagi, Eiji; Saito, Shinichi; Horiuchi, Masato

    1976-03-01

    In the research program of power reactor fuel reprocessing by fluoride volatility process, the engineering facility was constructed to establish the techniques of handling kilogram quantities of fluorine and uranium hexafluoride and to obtain engineering data on the uranium fluidized-bed oxidation and fluorination. This facility is designed for a capacity of 5 kg per batch. Descriptions on the facility and equipment are given, including design philosophy, safety and its analysis. (auth.)

  3. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Koelzer, W.

    1988-01-01

    Environmental monitoring of nuclear facilities is part of general monitoring for environmental radioactivity all over the territory of the Federal Republic of Germany. General principles of environmental monitoring were formulated by the ICRP in 1965. In 1974 guidelines for measures of monitoring the environment of NPP incorporating LWR were drafted, which helped to standardize environmental monitoring programs. Since 1958, data on environmental radioactivity from measurements by authorized laboratories have been published in reports. (DG)

  4. Environmental assessment: South microwave communication facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-06-01

    Western Area Power Administration (Western) is proposing to construct, operate, and maintain eight microwave repeater stations in southwestern Colorado, southeastern Utah, and northern Arizona, in order to meet the minimum fade criteria established by the Western Systems Coordinating Council (WSCC) for the operation and protection of electric power systems. The proposed microwave facilities would increase the reliability of communication. This environmental assessment (EA) describes the existing environmental conditions and the impacts from construction of the eight microwave communication facilities. The EA was prepared in compliance with the National Environmental Policy Act of 1969, the Council on Environmental Quality Regulations (40 CFR 1500-1508), and the Department of Energy Guidelines (52 FR 47662, December 15, 1987). The proposed project would consist of constructing eight microwave facilities, each of which would include a self-supported lattice tower, an equipment building, a propane tank, distribution lines to provide electric power to the sites, and access roads to the sites. The facilities would be constructed in San Miguel and Montezuma Counties in Colorado, San Juan County, Utah, and Navajo, Apache, Coconino, and Yavapai Counties in Arizona. 20 refs., 2 figs., 2 tabs.

  5. Description of pelletizing facility

    Energy Technology Data Exchange (ETDEWEB)

    Vojin Cokorilo; Dinko Knezevic; Vladimir Milisavljevic [University of Belgrade, Belgrade (Serbia). Faculty of Mining and Geology

    2006-07-01

    A lot of electrical energy in Serbia was used for heating, mainly for domestics. As it is the most expensive source for heating the government announced a National Program of Energy Efficiency with only one aim, to reduce the consumption of electric energy for the heating. One of the contributions to mentioned reduction is production of coal pellets from the fine coal and its use for domestic heating but also for heating of schools, hospitals, military barracks etc. Annual production of fine coal in Serbia is 300,000 tons. The stacks of fine coal present difficulties at each deep mine because of environmental pollution, spontaneous combustion, low price, smaller market etc. To overcome the difficulties and to give the contribution to National Program of Energy Efficiency researchers from the Department of Mining Engineering, the University of Belgrade designed and realized the project of fine coal pelletizing. This paper describes technical aspect of this project. Using a CPM machine Model 7900, a laboratory facility, then a semi-industrial pelletizing facility followed by an industrial facility was set up and produced good quality pellets. The plant comprised a coal fines hopper, conveyor belt, hopper for screw conveyor, screw conveyor, continuous mixer conditioner, binder reservoir, pump and pipelines, pellet mill, product conveyor belt and product hopper. 4 refs., 3 figs., 1 tab.

  6. State Environmental Policy Act (SEPA) environmental checklist forms for 304 Concretion Facility Closure Plan

    International Nuclear Information System (INIS)

    1993-11-01

    The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 304 Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 304 Facility, the history of materials and waste managed, and the procedures that will be followed to close the 304 Facility. The 304 Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

  7. 47 CFR 2.948 - Description of measurement facilities.

    Science.gov (United States)

    2010-10-01

    ... description of the measurement facilities employed. (1) If the measured equipment is subject to the... number; (v) FCC Registration Number (FRN); (vi) A statement as to whether or not the laboratory performs... supporting structures, and all structures within 5 times the distance between the measuring antenna and the...

  8. Environmental Test Facility (ETF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Environmental Test Facility (ETF) provides non-isolated shock testing for stand-alone equipment and full size cabinets under MIL-S-901D specifications. The ETF...

  9. Cold Vacuum Drying facility civil - structural system design description (SYS 06)

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document

  10. The methodology of environmental impacts assessment of environmentally hazardous facilities

    OpenAIRE

    Adamenko, Yaroslav

    2017-01-01

    The article deals with the methodology of environmental impacts assessment of environmentally hazardous facilities and activities. The stages of evaluation of environmental impacts are proved. The algorithm and technology of decision-making in the system of environmental impact assessments based on a multi-criteria utility theory are proposed.

  11. Models for environmental impact assessments of releases of radioactive substances from CERN facilities

    CERN Document Server

    Vojtyla, P

    2005-01-01

    The document describes generic models for environmental impact assessments of releases of radioactive substances from CERN facilities. Except for few models developed in the Safety Commission, the models are based on the 1997 Swiss directive HSK-R-41 and on the 2001 IAEA Safety Report No. 19. The writing style is descriptive, facilitating the practical implementation of the models at CERN. There are four scenarios assumed for airborne releases: (1) short-term releases for release limit calculations, (2) actual short-term releases, (3) short-term releases during incidents/accidents, and (4) chronic long-term releases during the normal operation of a facility. For water releases, two scenarios are considered: (1) a release into a river, and (2) a release into a water treatment plant. The document shall be understood as a reference for specific environmental studies involving radioactive releases and as a recommendation of the Safety Commission.

  12. Near-Facility Environmental Monitoring Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    MCKINNEY, S.M.

    2000-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards

  13. Detailed description of an SSAC at the facility level for research reactors

    International Nuclear Information System (INIS)

    Jones, R.J.

    1984-09-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  14. Standarized input for Hanford environmental impact statements. Part II: site description

    International Nuclear Information System (INIS)

    Jamison, J.D.

    1982-07-01

    Information is presented under the following section headings: summary description; location and physiography; geology; seismology; hydrology; meteorology; ecology; demography and land use; and radiological condition. Five appendixes are included on the 100N, 200 east, 200 west, 300, and 400 areas. This report is intended to provide a description of the Hanford Site against which the environmental impacts of new projects at Hanford can be assessed. It is expected that the summary description amplified with material from the appropriate appendix, will serve as the basic site description section of environmental impact statements prepared to address the requirements of the National Environmental Policy Act

  15. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.

    1982-09-01

    The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

  16. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

    International Nuclear Information System (INIS)

    Schneider, K.J.

    1982-09-01

    The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation

  17. Environmental Survey Report for the ETTP: Environmental Management Waste Management Facility (EMWMF) Haul Road Corridor, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, M.J.

    2005-12-20

    This report summarizes the results of environmental surveys conducted within the corridor of a temporary haul road (''Haul Road'') to be constructed from East Tennessee Technology Park (ETTP) to the Environmental Management Waste Management Facility (EMWMF) located just west of the Y-12 National Security Complex (Y-12). Environmental surveys were conducted by natural resource experts at Oak Ridge National Laboratory who routinely assess the significance of various project activities on the Oak Ridge Reservation (ORR). ORNL assistance to the Haul Road Project included environmental assessments necessary to determine the best route for minimizing impacts to sensitive resources such as wetlands or rare plants. Once the final route was chosen, environmental surveys were conducted within the corridor to evaluate the impacts to sensitive resources that could not be avoided. The final Haul Road route follows established roads and a power-line corridor to the extent possible (Fig. 1). Detailed explanation regarding the purpose of the Haul Road and the regulatory context associated with its construction is provided in at least two major documents and consequently is not presented here: (1) Explanation of Significant Differences for the Record of Decision for the Disposal of Oak Ridge Reservation Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Waste, Oak Ridge, Tennessee (January 2005, DOE/OR/01-2194&D2), and (2) Environmental Monitoring Plan for The ETTP to EMWMF Haul Road for the Disposal of Oak Ridge Reservation Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Waste, Oak Ridge, Tennessee (April 2005, BJC/OR-2152). The focus of this report is a description of the sensitive resources to be impacted by Haul Road construction. Following a short description of the methods used for the environmental surveys, results and observations are presented in the following subsections: (1) General description

  18. Course Descriptions in Environmental Studies Part One: Historical Courses.

    Science.gov (United States)

    Hughes, Donald; And Others

    1984-01-01

    Presents descriptions (syllabi, outlines, goals) of selected environmental studies courses which approach the discipline from an historical and humanistic perspective. Areas explored in the courses include human ecology, American environmental history, environmental politics, and others. (JN)

  19. Sandia National Laboratories/New Mexico existing environmental analyses bounding environmental test facilities.

    Energy Technology Data Exchange (ETDEWEB)

    May, Rodney A.; Bailey-White, Brenda E. (Sandia Staffing Alliance, LLC, Albuquerque, NM); Cantwell, Amber (Sandia Staffing Alliance, LLC, Albuquerque, NM)

    2009-06-01

    This report identifies current environmental operating parameters for the various test and support facilities at SNL/NM. The intent of this report is solely to provide the limits which bound the facilities' operations. Understanding environmental limits is important to maximizing the capabilities and working within the existing constraints of each facility, and supports the decision-making process in meeting customer requests, cost and schedule planning, modifications to processes, future commitments, and use of resources. Working within environmental limits ensures that mission objectives will be met in a manner that protects human health and the environment. It should be noted that, in addition to adhering to the established limits, other approvals and permits may be required for specific projects.

  20. Standarized input for Hanford environmental impact statements. Part II: site description

    Energy Technology Data Exchange (ETDEWEB)

    Jamison, J.D.

    1982-07-01

    Information is presented under the following section headings: summary description; location and physiography; geology; seismology; hydrology; meteorology; ecology; demography and land use; and radiological condition. Five appendixes are included on the 100N, 200 east, 200 west, 300, and 400 areas. This report is intended to provide a description of the Hanford Site against which the environmental impacts of new projects at Hanford can be assessed. It is expected that the summary description amplified with material from the appropriate appendix, will serve as the basic site description section of environmental impact statements prepared to address the requirements of the National Environmental Policy Act (NEPA).

  1. State Environmental Policy Act (SEPA) environmental checklist forms for 304 Concretion Facility Closure Plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 304 Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 304 Facility, the history of materials and waste managed, and the procedures that will be followed to close the 304 Facility. The 304 Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  2. Course Descriptions in Environmental Studies Part Two: Interdisciplinary Courses.

    Science.gov (United States)

    Dunlap, Riley; And Others

    1984-01-01

    Presents descriptions (syllabi, outlines, goals) of interdisciplinary environmental studies courses. Topic areas of these courses include: environmental sociology; human ecology (politics, institutions, and the environment); humans and the environment in historical perspective; environmental management; humans, hazards, and disasters; and other…

  3. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  4. Analysis of general specifications for nuclear facilities environmental monitoring vehicles

    International Nuclear Information System (INIS)

    Xu Xiaowei

    2014-01-01

    At present, with the nuclear energy more increasingly extensive application, the continuous stable radiation monitoring has become the focus of the public attention. The main purpose of the environmental monitoring vehicle for the continuous monitoring of the environmental radiation dose rate and the radionuclides concentration in the medium around nuclear facilities is that the environmental radiation level and the radioactive nuclides activity in the environment medium are measured. The radioactive pollution levels, the scope contaminated and the trends of the pollution accumulation are found out. The change trends for the pollution are observed and the monitoring results are explained. The domestic demand of the environmental monitoring for the nuclear facilities is shown in this report. The changes and demands of the routine environmental monitoring and the nuclear emergency monitoring are researched. The revision opinions for EJ/T 981-1995 General specifications for nuclear facilities environmental monitoring vehicles are put forward. The purpose is to regulate domestic environmental monitoring vehicle technical criterion. The criterion makes it better able to adapt and serve the environmental monitoring for nuclear facilities. The technical guarantee is provided for the environmental monitoring of the nuclear facilities. (authors)

  5. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry.

  6. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry. (author)

  7. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho

    2000-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows: The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost some level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water sample were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author)

  8. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo; Choi, Young Ho; Lee, M.H. [and others

    1999-02-01

    Environmental radiation monitoring was carried out with measurement of environment radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul research reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul research reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross {alpha}, {beta} radioactivity in environmental samples showed a environmental level. {gamma}-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul research reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by {gamma}-spectrometry. (author). 3 refs., 50 tabs., 12 figs.

  9. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Chang Woo; Choi, Geun Sik and others

    2001-02-01

    Environmental Radiation Monitoring was carried out with measurement of environment. Radiation and environmental radioactivity analysis around KAERI nuclear facilities and Seoul Research Reactor. The results of environmental radiation monitoring around KAERI nuclear facilities and Seoul Research Reactor are the follows : The average level of environmental radiation dose measured by NaI scintillation counter and accumulated radiation dose by TLD was almost same level compared with the past years. Gross α, β radioactivity in environmental samples showed a environmental level. γ-radionuclides in water samples were not detected. But only radionuclide K-40, which is natural radionuclide, was detected in the all samples and Cs-137 was detected in the surface soil and discharge sediment. The average level of environmental radiation dose around Seoul Research Reactor was almost same level compared with the past years, and Be-7 and Cs-137 were detected in some surface soil and discharge sediment by γ-spectrometry

  10. Environmental Factors Associated with Norovirus Transmission in Long-Term Care Facilities in South Carolina.

    Science.gov (United States)

    Jayasekara, Lalani; Leone, Cortney M; Sharp, Julia; Getty, Morgan

    2016-09-01

    In the U.S., 60% of norovirus outbreaks are attributed to long-term care facilities (LTCFs). A descriptive study of 26 LTCFs in South Carolina was conducted to determine the presence of environmental factors associated with transmission of human noroviruses. Sanitary conditions in one common area, one staff/visitor bathroom, and the main kitchen were assessed using two audit forms. While surfaces in all kitchens were in good sanitary condition, 23 LTCFs used quaternary ammonium-based sanitizers and three LTCFs used chlorine bleach for kitchen sanitization. All common areas were also clean and in good condition; however, 20 LTCFs had upholstered chairs, and five LTCFs had carpeted floors. Seven facilities used quaternary ammonium-based disinfectants exclusively, whereas six LTCFs used chlorine bleach exclusively, and eight LTCFs used both to disinfect common areas. Seven staff/visitor bathrooms were accessible to residents, and hand washing signage was missing from 10. These results reveal the presence of environmental factors that might facilitate norovirus transmission within LTCFs.

  11. Decommissioning and environmental restoration of nuclear facilities in China

    International Nuclear Information System (INIS)

    Pan Ziqiang

    2000-01-01

    In the beginning of the 1980s, the Scientific and Technological Commission (STC) began the study on the environmental impact of the nuclear industry in China. At the end of the 1980s, the STC initiated the study on the decommissioning of nuclear facilities and environmental restoration. In 1989 the STC completed the project entitled ''Radiological and Environmental Quality Assessment of the Nuclear Industry in China Over the Past Thirty Years''. The status of the environmental pollution of various nuclear facility sites was subsequently analysed. In 1994, the decommissioning and environmental restoration of the first research and manufacture complex for nuclear weapons was completed. The complex is now accessible to the public without restriction and the site has become a town. Some nuclear related facilities, such as uranium mines, are currently being decommissioned. Although uranium mining and milling has a more serious impact on the environment, the technology for decommissioning and environmental restoration in mining and milling installations is not much more complicated than that used for reactor and reprocessing facilities: much has been achieved in the area of mining and milling. (author)

  12. IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

    Energy Technology Data Exchange (ETDEWEB)

    Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

    2000-08-01

    In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

  13. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Winter, M.

    1983-01-01

    The objectives of one environmental monitoring program for nuclear facilities, are presented. The program in Federal Republic of Germany, its goals, its basic conditions, its regulations, and its dose limits are emphasized. (E.G.) [pt

  14. Classified facilities for environmental protection

    International Nuclear Information System (INIS)

    Anon.

    1993-02-01

    The legislation of the classified facilities governs most of the dangerous or polluting industries or fixed activities. It rests on the law of 9 July 1976 concerning facilities classified for environmental protection and its application decree of 21 September 1977. This legislation, the general texts of which appear in this volume 1, aims to prevent all the risks and the harmful effects coming from an installation (air, water or soil pollutions, wastes, even aesthetic breaches). The polluting or dangerous activities are defined in a list called nomenclature which subjects the facilities to a declaration or an authorization procedure. The authorization is delivered by the prefect at the end of an open and contradictory procedure after a public survey. In addition, the facilities can be subjected to technical regulations fixed by the Environment Minister (volume 2) or by the prefect for facilities subjected to declaration (volume 3). (A.B.)

  15. Environmental Management Guide for Educational Facilities

    Science.gov (United States)

    APPA: Association of Higher Education Facilities Officers, 2017

    2017-01-01

    Since 1996, APPA and CSHEMA, the Campus Safety Health and Environmental Management Association, have collaborated to produce guidance documents to help educational facilities get ahead of the moving target that is environmental compliance. This new 2017 edition will help you identify which regulations pertain to your institution, and assist in…

  16. Compliance determination procedures for environmental radiation protection standards for uranium recovery facilities 40 CFR part 190

    International Nuclear Information System (INIS)

    1982-03-01

    Uranium Milling operations are licensed by the Nuclear Regulatory Commission and by some States in agreement with the Commission. The radiation dose to any individual from the operation of facilities within the uranium fuel cycle is limited to levels set by the Environmental Protection Agency. These levels are contained in the EPA Environmental Radiation Protection Standards for Nuclear Power Operations, in Part 190 of Title 40 of the Code of Federal Regulations (40 CFR Part 190). This report describes the procedures used within NRC's Uranium Recovery Licensing Branch for evaluating compliance with these regulations for uranium milling operations. The report contains descriptions of these procedures, dose factors for evaluating environmental measurement data, and guidance to the NRC staff reviewer

  17. Near-facility environmental monitoring quality assurance project plan

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1997-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near facility environmental monitoring performed by Waste Management Federal Services, Inc., Northwest Operations and supersedes WHC-EP-0538-2. This plan applies to all sampling and monitoring activities performed by waste management Federal Services, Inc., Northwest Operations in implementing facility environmental monitoring at the Hanford Site

  18. Environmental monitoring around the Swedish Nuclear Facilities

    International Nuclear Information System (INIS)

    Bondesson, A.; Luening, M.; Wallberg, L.; Wijk, H.

    1999-01-01

    The environmental monitoring programme for the nuclear facilities has shown that the radioactive discharges increase the concentrations of some radionuclides in the local marine environment around the Swedish nuclear facilities. Samples from the terrestrial environment rarely show increased radionuclide concentrations. From a radiological point of view the most important nuclide in the environmental samples usually is CS-137. However, the largest part of the present concentrations of Cs-137 in the Swedish environment originate from the Chernobyl accident. The concentrations of radionuclides that can be found in biota around the nuclear facilities are much lower than the concentration levels that are known to give acute damage to organisms. The total radiation doses from the discharges of radionuclides are small. (au)

  19. A model for evaluating the environmental benefits of elementary school facilities.

    Science.gov (United States)

    Ji, Changyoon; Hong, Taehoon; Jeong, Kwangbok; Leigh, Seung-Bok

    2014-01-01

    In this study, a model that is capable of evaluating the environmental benefits of a new elementary school facility was developed. The model is composed of three steps: (i) retrieval of elementary school facilities having similar characteristics as the new elementary school facility using case-based reasoning; (ii) creation of energy consumption and material data for the benchmark elementary school facility using the retrieved similar elementary school facilities; and (iii) evaluation of the environmental benefits of the new elementary school facility by assessing and comparing the environmental impact of the new and created benchmark elementary school facility using life cycle assessment. The developed model can present the environmental benefits of a new elementary school facility in terms of monetary values using Environmental Priority Strategy 2000, a damage-oriented life cycle impact assessment method. The developed model can be used for the following: (i) as criteria for a green-building rating system; (ii) as criteria for setting the support plan and size, such as the government's incentives for promoting green-building projects; and (iii) as criteria for determining the feasibility of green building projects in key business sectors. Copyright © 2013 Elsevier Ltd. All rights reserved.

  20. A proposed descriptive methodology for environmental geologic (envirogeologic) site characterization

    International Nuclear Information System (INIS)

    Schwarz, D.L.; Snyder, W.S.

    1994-01-01

    We propose a descriptive methodology for use in environmental geologic (envirogeologic) site characterization. The method uses traditional sedimentologic descriptions augmented by environmental data needs, and facies analysis. Most other environmental methodologies for soil and sediment characterization use soil engineering and engineering geology techniques that classify by texture and engineering properties. This technique is inadequate for envirogeologic characterization of sediments. In part, this inadequacy is due to differences in the grain-size between the Unified soil Classification and the Udden-Wentworth scales. Use of the soil grain-size classification could easily cause confusion when attempting to relate descriptions based on this classification to our basic understanding of sedimentary depositional systems. The proposed envirogeologic method uses descriptive parameters to characterize a sediment sample, suggests specific tests on samples for adequate characterization, and provides a guidelines for subsurface facies analysis, based on data retrieved from shallow boreholes, that will allow better predictive models to be developed. This methodology should allow for both a more complete site assessment, and provide sufficient data for selection of the appropriate remediation technology, including bioremediation. 50 refs

  1. Cold Vacuum Drying Facility Condensate Collection System Design Description. System 19

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    2000-01-01

    The Cold Vacuum Drying (CVD) Facility of Spent Nuclear Fuel (SNF) provides required process systems, supporting equipment, and facilities to support the SNF Project mission. This system design description (SDD) addresses the Condensate Collection System (CCS). This is a general service system. The CCS begins at the condensate outlet of the general process air-handling unit (AHU) and the condensate outlets for the active process bays AHUs. The system terminates at each condensate collection tank (5 total)

  2. Environmental assessment for the deactivation of the N Reactor facilities

    International Nuclear Information System (INIS)

    1995-05-01

    This environmental assessment (EA) provides information for the US Department of Energy (DOE) to decide whether the Proposed Action for the N Reactor facilities warrants a Finding of No Significant Impact or requires the preparation of an environmental impact statement (EIS). The EA describes current conditions at the N Reactor facilities, the need to take action at the facilities, the elements of the Proposed Action and alternatives, and the potential environmental impacts. As required by the National Environmental Policy Act of 1969 (NEPA), this EA complies with Title 40, Code of Federal Regulations (CFR), parts 1500--1508, ''Regulations for Implementing the Procedural Provisions of NEPA. '' It also implements the ''National Environmental Policy Act; Implementing Procedures and Guidelines'' (10 CFR 1021)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  4. St. James marine terminal facility description

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    The US Department of Energy (DOE) currently owns and operates a marine terminal on the west bank of the Mississippi River at St. James, Louisiana. The St. James facility was constructed by the Department to provide marine services associated with the fill and drawdown of the Strategic Petroleum Reserve (SPR) crude oil storage facilities located at Bayou Choctaw and Weeks Island, Louisiana. Although strategic to the mission of the SPR in the event of a national emergency, the St. James terminal is situated such that it has a high potential to also serve the commercial industry`s needs for crude oil terminalling and storage. The St. James terminal is located approximately 45 miles west of New Orleans and 30 miles southeast of Baton Rouge, and approximately 160 miles upstream from the mouth of the Mississippi River. Construction of the St. James terminal was initiated in 1978 and was completed in 1980. Since then, the terminal has received and transferred over 125 million barrels of crude oil to the SPR sites for storage. For crude oil distribution, the St. James terminal was connected to the neighboring LOCAP terminal by a 0.1 mile 36-inch pipeline in 1981 and to the Capline terminal by a 0.5 mile 30-inch pipeline in 1988. The terminal also has a 30-inch pipeline connection to the Koch oil terminal which was used for initial fill purposes; however, this pipeline has been disconnected and is currently inactive. A complete description of the St. James terminal facilities, operational capabilities, operational certifications, and future Government requirements are presented in Sections 2, 3, 4, and 5 respectively.

  5. Nuclear energy: Environmental issues at DOE's nuclear defense facilities

    International Nuclear Information System (INIS)

    1986-01-01

    GAO's review of nine Department of Energy defense facilities identified a number of significant environmental issues: (1) eight facilities have groundwater contaminated with radioactive and/or hazardous substances to high levels; (2) six facilities have soil contamination in unexpected areas, including offsite locations; (3) four facilities are not in full compliance with the Clean Water Act; and (4) all nine facilities are significantly changing their waste disposal practices to obtain a permit under the Resource Conservation and Recovery Act. GAO is recommending that DOE develop and overall groundwater and soil protection strategy that would provide a better perspective on the environmental risks and impacts associated with operating DOE's nuclear defense facilities. GAO also recommends that DOE allow outside independent inspections of the disposal practices used for any waste DOE self-regulates and revise its order governing the management of hazardous and mixed waste

  6. Environmental information document defense waste processing facility

    International Nuclear Information System (INIS)

    1981-07-01

    This report documents the impact analysis of a proposed Defense Waste Processing Facility (DWPF) for immobilizing high-level waste currently being stored on an interim basis at the Savannah River Plant (SRP). The DWPF will process the waste into a form suitable for shipment to and disposal in a federal repository. The DWPF will convert the high-level waste into: a leach-resistant form containing above 99.9% of all the radioactivity, and a residue of slightly contaminated salt. The document describes the SRP site and environs, including population, land and water uses; surface and subsurface soils and waters; meteorology; and ecology. A conceptual integrated facility for concurrently producing glass waste and saltcrete is described, and the environmental effects of constructing and operating the facility are presented. Alternative sites and waste disposal options are addressed. Also environmental consultations and permits are discussed

  7. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  8. Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Process Water Conditioning (PWC) System. The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), the HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the PWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  9. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  10. Addendum to environmental monitoring plan Nevada Test Site and support facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    This 1992 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/1 0630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1992 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  11. Addendum to Environmental Monitoring Plan, Nevada Test Site and Support Facilities

    International Nuclear Information System (INIS)

    1993-11-01

    This 1993 Addendum to the ''Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,'' Report No. DOE/NV/10630-28 (EMP) applies to the US Department of Energy's (DOE's) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Operations Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1993 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards

  12. PUREX facility preclosure work plan

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D)

  13. Greening Federal Facilities: An Energy, Environmental, and Economic Resource Guide for Federal Facility Managers and Designers; Second Edition

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, A.

    2001-05-16

    Greening Federal Facilities, Second Edition, is a nuts-and-bolts resource guide compiled to increase energy and resource efficiency, cut waste, and improve the performance of Federal buildings and facilities. The guide highlights practical actions that facility managers, design and construction staff, procurement officials, and facility planners can take to save energy and money, improve the comfort and productivity of employees, and benefit the environment. It supports a national effort to promote energy and environmental efficiency in the nation's 500,000 Federal buildings and facilities. Topics covered include current Federal regulations; environmental and energy decision-making; site and landscape issues; building design; energy systems; water and wastewater; materials; waste management, and recycling; indoor environmental quality; and managing buildings.

  14. Environmental compliance audits of electric generating facilities - a practical approach

    International Nuclear Information System (INIS)

    Staker, R.D.

    1992-01-01

    As environmental regulations expand in complexity and number, and as regulatory agencies place more emphasis on enforcing regulations, it is increasingly important that electric utilities perform periodic environmental compliance audits to determine if their facilities are in compliance with federal, state, and local environmental regulations. Explicit commitment by the utility's top management and careful planning and execution of an audit are key elements in the effectiveness of an audit. This paper is directed to electric utility environmental managers and company management. The paper presents a practical approach for planning and performing a multi-media environmental compliance of an electric generating facility

  15. Environmental consequences of hydroelectric development: the role of facility size and type

    International Nuclear Information System (INIS)

    Gleick, P.H.

    1992-01-01

    The development of hydroelectric power throughout the world is receiving renewed attention as the economic, political, and environmental costs of conventional energy production rise. There is currently a perception that hydroelectricity has environmental and economic advantages over electricity produced by conventional energy technologies, but there is a paucity of information about the environmental impacts of hydroelectric facilities as a function of size and type. We characterize the environmental impacts of hydroelectric developments and quantify these impacts as a function of the size and type of project. Several unexpected conclusions arise from our analysis. For most hydroelectric facilities, size, as measured by installed capacity, is not necessarily a good indicator or the severity of environmental costs. For impacts such as land flooded and evaporative water lost, smaller facilities cause greater environmental disruptions per unit of energy produced than do larger facilities. (Author)

  16. Cold Vacuum Drying Facility Crane and Hoist System Design Description. System 14

    International Nuclear Information System (INIS)

    TRAN, Y.S.

    2000-01-01

    This system design description (SDD) is for the Cold Vacuum Drying (CVD) Facility overhead crane and hoist system. The overhead crane and hoist system is a general service system. It is located in the process bays of the CVD Facility, supports the processes required to drain the water and dry the spent nuclear fuel (SNF) contained in the multi-canister overpacks (MCOs) after they have been removed from the K-Basins. The location of the system in the process bay is shown

  17. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1994-06-01

    This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement

  18. Operating manual for the High Flux Isotope Reactor. Description of the facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    1965-06-01

    This report contains a comprehensive description of the High Flux Isotope Reactor facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procedures are presented in another report.

  19. A description of the demonstration Integral Fast Reactor fuel cycle facility

    International Nuclear Information System (INIS)

    Courtney, J.C.; Carnes, M.D.; Dwight, C.C.; Forrester, R.J.

    1991-01-01

    A fuel examination facility at the Idaho National Engineering Laboratory is being converted into a facility that will electrochemically process spent fuel. This is an important step in the demonstration of the Integral Fast Reactor concept being developed by Argonne National Laboratory. Renovations are designed to bring the facility up to current health and safety and environmental standards and to support its new mission. Improvements include the addition of high-reliability earthquake hardened off-gas and electrical power systems, the upgrading of radiological instrumentation, and the incorporation of advances in contamination control. A major task is the construction of a new equipment repair and decontamination facility in the basement of the building to support operations

  20. Environmental and nursing-staff factors contributing to aggressive and violent behaviour of patients in mental health facilities.

    Science.gov (United States)

    van Wijk, Evalina; Traut, Annalene; Julie, Hester

    2014-08-14

    Aggressive and violent behaviour of inpatients in mental health facilities disrupts the therapeutic alliance and hampers treatment. The aim of the study was to describe patients' perceptions of the possible environmental and staff factors that might contribute to their aggressive and violent behaviour after admission to a mental health facility; and to propose strategies to prevent and manage such behaviour. A qualitative, phenomenological study was utilised, in which purposefully sampled inpatients were interviewed over a six-month period. Inpatients were invited to participate if they had been admitted for at least seven days and were in touch with reality. Forty inpatients in two mental health facilities in Cape Town participated in face-to-face, semi-structured interviews over a period of six months. Tesch's descriptive method of open coding formed the framework for the data analysis and presentation of the results. Trustworthiness was ensured in accordance with the principles of credibility, confirmability, transferability and dependability. Analysis of the data indicates two central categories in the factors contributing to patients' aggressive and violent behaviour, namely, environmental factors and the attitude and behaviour of staff. From the perspective of the inpatients included in this study, aggressive and violent episodes are common and require intervention. Specific strategies for preventing such behaviour are proposed and it is recommended that these strategies be incorporated into the in-service training programmes of the staff of mental health facilities. These strategies could prevent, or reduce, aggressive and violent behaviour in in-patient facilities.

  1. WINCO's experience with environmental compliance at 1950's vintage DOE nuclear facilities

    International Nuclear Information System (INIS)

    Porter, C.L.

    1992-01-01

    During the 1950's numerous nuclear facilities were built under the auspices of the Atomic Energy Commission (AEC). One such facility, a nuclear fuels reprocessing facility located in Idaho has operated over the past 40 years. In the late 1980's federal facilities became subject to the same environmental regulations as commercial facilities. Since the Department of Energy's mission called for continued reprocessing at the Idaho facility, compliance with current environmental standards became necessary. Certified compliance was achieved with a minimum of modifications by capitalizing upon existing building features that resulted from original AEC design criteria

  2. Environmental aspects based on operation performance of nuclear fuel fabrication facilities

    International Nuclear Information System (INIS)

    2001-07-01

    This publication was prepared within the framework of the IAEA Project entitled Development and Upgrading of Guidelines, Databases and Tools for Integrating Comparative Assessment into Energy System Analysis and Policy Making, which included the collection, review and input of data into a database on health and environmental impacts related to operation of nuclear fuel cycle facilities. The objectives of the report included assembling environmental data on operational performance of nuclear fabrication facilities in each country; compiling and arranging the data in a database, which will be easily available to experts and the public; and presenting data that may be of value for future environmental assessment of nuclear fabrication facilities

  3. Detailed description of an SSAC at the facility level for light water moderated (off-load refueled) power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-03-01

    This report is intended to provide the technical details of an effective State Systems of Accounting for and Control of Nuclear Material (SSAC) which Member States may use, if they wish, to establish and maintain their SSACs. It is expected that systems designed along the lines described would be effective in meeting the objectives of both national and international systems for nuclear material accounting and control. This document accordingly provides a detailed description of a system for the accounting for and control of nuclear material in an off-load refueled light water moderated power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  4. Implementing an environmental management system in a irradiation facility

    International Nuclear Information System (INIS)

    O'Doherty, James

    1998-01-01

    Environmental management is at different stages in the countries where there are commercial irradiation facilities. There are therefore differing perspectives on the role of an Environmental Management System, ranging from compliance with the Regulatory framework to a desire to be proactive. An effective Environmental Management System (EMS) facilitates compliance, while also providing the framework for assessment and improvement of a company's environmental impact and overall performance

  5. The importance of environmental education in the process of nuclear and environmental licensing of nuclear facilities

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges; Ribeiro, Katia Maria Bruno

    2009-01-01

    Today, there is a thread with regard to the global environment. To reduce the environmental impact due to spending supplies to meet the basic needs of the global population. Can be considered as the power of these needs and in this context, the environmental impact occurs by the use of fossil fuels and loss of land for use of water resources. To minimize these impacts, governments are establishing appropriate laws towards the use of renewable energy. However it appears that there is still a great distance between the established law and implementation in practice. In this context nuclear energy is an attractive option, both economic and environmental. The facilities that are somehow associated with nuclear power plants are classified as radioactive or nuclear. These facilities are subject to two licensing procedures: Environmental (by IBAMA) and Nuclear (by CNEN). Nuclear installations such as nuclear power plants Angra 1 and 2, deposits and tailings facilities of the nuclear fuel cycle in Rezende that are more the attention of the population. As part of these processes are reports of analysis of safety and environmental impacts and socio-economic (EIA/RIMA RFAS), which are available to the public and then discussed at public hearings, where there is the opportunity for questions on these reports. These questions are mainly related with the social-environmental and economic due to construction and operation of these facilities. This work is a research, discussing the law, identifying the difficulties in the licensing process and presents a discussion on the importance of environmental education at all school levels, for adult audiences and is a connection between the environmental education and process of environmental licensing and nuclear, showing how the popular consciousness more informed can better discuss issues associated with these licenses, understand the advantages and disadvantages and obtain benefits. (author)

  6. Discussion on the post-project assessment of environmental impact for nuclear facilities

    International Nuclear Information System (INIS)

    Shang Zhaorong

    2013-01-01

    The paper introduces the background of post-project assessment of environmental impact in the world and focuses on the characteristic of environmental impact assessment for Chinese nuclear facilities construction projects, analyzes the necessity, principle and contents of post-project assessment of environmental impact on current Chinese nuclear facilities operation. It is considered that to start the post-project assessment of environmental impact, perfect the post-project assessment mechanism, introduce the post-project assessment into environmental impact assessment system are just at the night time. (author)

  7. Radiological and environmental surveillance in front-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Khan, A.H.; Sahoo, S.K.; Tripathi, R.M.

    2004-01-01

    This paper describes the occupational and environmental radiological safety measures associated with the operations of front end nuclear fuel cycle. Radiological monitoring in the facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised

  8. Addendum to Environmental Monitoring Plan, Nevada Test Site and Support Facilities; Addendum 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-11-01

    This 1993 Addendum to the ``Environmental Monitoring Plan Nevada Test Site and Support Facilities -- 1991,`` Report No. DOE/NV/10630-28 (EMP) applies to the US Department of Energy`s (DOE`s) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Operations Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this 1993 Addendum to the EMP brings together, in one document, updated information and/or new sections to the description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA) originally published in the EMP. The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards.

  9. Environmental licensing of nuclear facilities: compatibility of technical competencies

    International Nuclear Information System (INIS)

    Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

    1996-01-01

    The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

  10. Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2008

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Wilde, Justin W.; Poston, Ted M.

    2009-09-15

    Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant, Canister Storage Building, and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

  11. Environmental assessment for the deactivation of the N Reactor facilities. Revision 1

    International Nuclear Information System (INIS)

    1994-11-01

    This environmental assessment (EA) provides information for the US Department of Energy (DOE) to decide whether the Proposed Action for the N Reactor facilities warrants a Finding of No Significant Impact or requires the preparation of an environmental impact statement (EIS). The EA describes current conditions at the N Reactor facilities, the need to take action at the facilities, the elements of the Proposed Action and alternatives, and the potential environmental impacts. The N Reactor facilities are currently in a surveillance and maintenance program, and will eventually be decontaminated and decommissioned (D and D). Operation and maintenance of the facilities resulted in conditions that could adversely impact human health or the environment if left as is until final D and D. The Proposed Action would deactivate the facilities to remove the conditions that present a potential threat to human health and the environment and to reduce surveillance and maintenance requirements. The action would include surveillance and maintenance after deactivation. Deactivation would take about three years and would involve about 80 facilities. Surveillance and maintenance would continue until final D and D, which is expected to be complete for all facilities except the N Reactor itself by the year 2018

  12. Environmental radiation monitoring around the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Woo

    2012-03-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uranium and Strontium in environmental samples showed a environmental level. The {gamma}-radionuclides such as natural radionuclides 40K or 7Be were detected in pine needle and food. The nuclear radionuclides 134Cs, 137Cs or 131I were temporarily detected in the samples of air particulate and rain in April and of fall out in 2nd quarter from the effect of Fukusima accident.

  13. Environmental monitoring for EG and G Idaho facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Tkachyk, J.W.; Wright, K.C.; Wilhelmsen, R.N.

    1990-08-01

    This report describes the 1989 environmental-monitoring activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G-operated facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Additional monitoring activities performed by Environmental Monitoring are also discussed, including drinking-water monitoring and nonradiological liquid-effluent monitoring, as well as data management. The primary purposes of monitoring are to evaluate environmental conditions and to provide and interpret data, in compliance with applicable regulations, to ensure protection of human health and the environment. This report compares 1989 environmental-monitoring data with derived concentration guides and with data from previous years. This report also presents results of sampling performed by the Radiological and Environmental Sciences Laboratory and by the United States Geological Survey. 17 refs., 49 figs., 11 tabs

  14. Benefits of improved environmental cooperation on a joint DoD/DOE facility

    International Nuclear Information System (INIS)

    Pratt, G.K.; Gibson, J.D.

    1995-01-01

    Numerous Federal facilities within the US involve multiple government agencies that face overlapping environmental concerns. This paper highlights the benefits of looking beyond the strict letter of environmental regulations that might affect a single tenant or environmental site to cooperative environmental efforts that focus on the entire facility, consistent with the missions of participating agencies. Using Kirtland Air Force Base (AFB) as a model, seven areas of Department of Defense (DoD) and Department of Energy (DOE) environmental cooperation are discussed that span technical, regulatory compliance, and administrative issues

  15. Cold Vacuum Dryer (CVD) Facility Security System Design Description. System 54

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    2000-01-01

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility security system. The system's primary purpose is to provide reasonable assurance that breaches of security boundaries are detected and assessment information is provided to protective force personnel. In addition, the system is utilized by Operations to support reduced personnel radiation goals and to provide reasonable assurance that only authorized personnel are allowed to enter designated security areas

  16. Mound facility physical characterization

    Energy Technology Data Exchange (ETDEWEB)

    Tonne, W.R.; Alexander, B.M.; Cage, M.R.; Hase, E.H.; Schmidt, M.J.; Schneider, J.E.; Slusher, W.; Todd, J.E.

    1993-12-01

    The purpose of this report is to provide a baseline physical characterization of Mound`s facilities as of September 1993. The baseline characterizations are to be used in the development of long-term future use strategy development for the Mound site. This document describes the current missions and alternative future use scenarios for each building. Current mission descriptions cover facility capabilities, physical resources required to support operations, current safety envelope and current status of facilities. Future use scenarios identify potential alternative future uses, facility modifications required for likely use, facility modifications of other uses, changes to safety envelope for the likely use, cleanup criteria for each future use scenario, and disposition of surplus equipment. This Introductory Chapter includes an Executive Summary that contains narrative on the Functional Unit Material Condition, Current Facility Status, Listing of Buildings, Space Plans, Summary of Maintenance Program and Repair Backlog, Environmental Restoration, and Decontamination and Decommissioning Programs. Under Section B, Site Description, is a brief listing of the Site PS Development, as well as Current Utility Sources. Section C contains Site Assumptions. A Maintenance Program Overview, as well as Current Deficiencies, is contained within the Maintenance Program Chapter.

  17. Proposed integrated hazardous waste disposal facility. Public environmental review

    International Nuclear Information System (INIS)

    1998-05-01

    This Public Environmental Report describes a proposal by the Health Department of Western Australia to establish a disposal facility for certain hazardous wastes and seeks comments from governments agencies and the public that will assist the EPA to make its recommendations to. The facility would only be used for wastes generated in Western Australia.The proposal specifically includes: a high temperature incinerator for the disposal of organo-chlorines (including agricultural chemicals and PCBs), and other intractable wastes for which this is the optimum disposal method; an area for the burial (after any appropriate conditioning) of low level radioactive intractable wastes arising from the processing of mineral sands (including monazite, ilmenite and zircon) and phosphate rock. Detailed information is presented on those wastes which are currently identified as requiring disposal at the facility.The proposed facility will also be suitable for the disposal of other intractable wastes including radioactive wastes (from industry, medicine and research) and other solid intractable wastes of a chemical nature including spent catalysts etc. Proposals to dispose of these other wastes at this facility in the future will be referred to the Environmental Protection Authority for separate assessment

  18. 1996 environmental monitoring report for the Naval Reactors Facility

    International Nuclear Information System (INIS)

    1996-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 1996 at the Naval Reactors Facility (NRF) are presented in this report. The NRF is located on the Idaho National Engineering and Environmental Laboratory and contains three naval reactor prototypes and the Expended Core Facility, which examines developmental nuclear fuel material samples, spent naval fuel, and irradiated reactor plant components/materials. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE)

  19. Environmental and nursing-staff factors contributing to aggressive and violent behaviour of patients in mental health facilities

    Directory of Open Access Journals (Sweden)

    Evalina van Wijk

    2014-08-01

    Objectives: The aim of the study was to describe patients’ perceptions of the possible environmental and staff factors that might contribute to their aggressive and violent behaviour after admission to a mental health facility; and to propose strategies to prevent and manage such behaviour. Research design: A qualitative, phenomenological study was utilised, in which purposefully sampled inpatients were interviewed over a six-month period. Inpatients were invited to participate if they had been admitted for at least seven days and were in touch with reality. Method: Forty inpatients in two mental health facilities in Cape Town participated in face-to-face, semi-structured interviews over a period of six months. Tesch’s descriptive method of open coding formed the framework for the data analysis and presentation of the results. Trustworthiness was ensured in accordance with the principles of credibility, confirmability, transferability and dependability. Results: Analysis of the data indicates two central categories in the factors contributing to patients’ aggressive and violent behaviour, namely, environmental factors and the attitude and behaviour of staff. Conclusion: From the perspective of the inpatients included in this study, aggressive and violent episodes are common and require intervention. Specific strategies for preventing such behaviour are proposed and it is recommended that these strategies be incorporated into the in-service training programmes of the staff of mental health facilities. These strategies could prevent, or reduce, aggressive and violent behaviour in in-patient facilities.

  20. Final generic environmental impact statement on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

  1. Potential of mediation for resolving environmental disputes related to energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    This study assesses the potential of mediation as a tool for resolving disputes related to the environmental regulation of new energy facilities and identifies possible roles the Federal government might play in promoting the use of mediation. These disputes result when parties challenge an energy project on the basis of its potential environmental impacts. The paper reviews the basic theory of mediation, evaluates specific applications of mediation to recent environmental disputes, discusses the views of environmental public-interest groups towards mediation, and identifies types of energy facility-related disputes where mediation could have a significant impact. Finally, potential avenues for the Federal government to encourage use of this tool are identified.

  2. Environmental Radiation Monitoring Around the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geun Sik; Lee, Chang Woo

    2008-05-15

    Environmental Radiation Monitoring was carried out with measurement of environment. radiation and environmental radioactivity analysis on the sites of KAERI nuclear facilities and Seoul Research Reactors and their environments. The average level of environmental radiation dose measured by an ERM and the accumulated radiation dose by a TLD were almost same level compared with the previous years. The activity of gross {alpha} and gross {beta}, Tritium, Uraniu and Strontium in environmental samples showed a environmental level. The radioactivities of most {gamma}-radionuclides in air particulate, surface water and ground water were less than MDA except {sup 40}K or {sup 7}Be which are natural radionuclides. However, not only {sup 40}K or {sup 7}Be but also {sup 137}Cs were detected at the background level in surface soil, discharge sediment and fallout or pine needle.

  3. Technical description - interim storage, encapsulation and disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    2010-07-01

    The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test

  4. Exploring Environmental Effects of Accidents During Marine Transport of Dangerous Goods by Use of Accident Descriptions

    DEFF Research Database (Denmark)

    Rømer, Hans Gottberg; Haastrup, P.; Petersen, H J Styhr

    1996-01-01

    On the basis of 1776 descriptions of water transport accidents involving dangerous goods, environmental problems in connection with releases of this kind are described and discussed. It was found that most detailed descriptions of environmental consequences concerned oil accidents, although most...... longer than broad. Gravity scales used to describe and evaluate environmental consequences were discussed....

  5. Environmental justice: Implications for siting of Federal Radioactive Waste Management Facilities

    International Nuclear Information System (INIS)

    Easterling, J.B.; Poles, J.S.

    1994-01-01

    Environmental justice is a term that has developed as a result of our need to address whether some of the environmental decisions we have made -- and others we will make -- are fair. The idea of environmental justice has been actively pursued by the Clinton Administration, and this consideration has resulted in Executive Order 12898, which was signed by President Clinton on February 11, 1994. The Executive Order calls for adverse impacts of Federal actions on minority or low-income populations to be identified before decisions implementing those actions are made. Numerous studies show that noxious facilities, such as incinerators and landfills, have been constructed in minority or low-income communities. And since the Department has not yet decided on sites for high-level waste storage or disposal facilities, it will have to take the new Executive Order into consideration as another piece in the complicated quilt of requirements that cover facility siting. An interesting twist to this is the fact that twenty Native American Indian Tribes expressed interest in voluntarily hosting a high-level radioactive waste management facility for temporary storage. They made these expressions on their own initiative, and several Tribes continue to pursue the idea of negotiations with either the Federal Government or private entities to locate a temporary storage site on Tribal land. The Executive Order goes beyond simply studying the effect of siting a facility and addresses in spirit a criticism that the Federal Government has been guilty of open-quotes environmental racismclose quotes in its siting policies -- that it has intentionally picked minority or low-income communities for waste management facilities. What Department of Energy staff and others may have considered foregone conclusions in terms of interim storage facility siting and transportation options will have to be reevaluated for compatibility with provisions of the new Executive Order

  6. Westinghouse Hanford Company risk management strategy for retired surplus facilities

    International Nuclear Information System (INIS)

    Taylor, W.E.; Coles, G.A.; Shultz, M.V.; Egge, R.G.

    1993-09-01

    This paper describes an approach that facilitates management of personnel safety and environmental release risk from retired, surplus Westinghouse Hanford Company-managed facilities during the predemolition time frame. These facilities are located in the 100 and 200 Areas of the 1,450-km 2 (570-mi 2 ) Hanford Site in Richland, Washington. The production reactors are located in the 100 Area and the chemical separation facilities are located in the 200 Area. This paper also includes a description of the risk evaluation process, shows applicable results, and includes a description of comparison costs for different risk reduction options

  7. Subsurface Facility System Description Document

    International Nuclear Information System (INIS)

    Eric Loros

    2001-01-01

    The Subsurface Facility System encompasses the location, arrangement, size, and spacing of the underground openings. This subsurface system includes accesses, alcoves, and drifts. This system provides access to the underground, provides for the emplacement of waste packages, provides openings to allow safe and secure work conditions, and interfaces with the natural barrier. This system includes what is now the Exploratory Studies Facility. The Subsurface Facility System physical location and general arrangement help support the long-term waste isolation objectives of the repository. The Subsurface Facility System locates the repository openings away from main traces of major faults, away from exposure to erosion, above the probable maximum flood elevation, and above the water table. The general arrangement, size, and spacing of the emplacement drifts support disposal of the entire inventory of waste packages based on the emplacement strategy. The Subsurface Facility System provides access ramps to safely facilitate development and emplacement operations. The Subsurface Facility System supports the development and emplacement operations by providing subsurface space for such systems as ventilation, utilities, safety, monitoring, and transportation

  8. Description of source term data on contaminated sites and buildings compiled for the waste management programmatic environmental impact statement (WMPEIS)

    International Nuclear Information System (INIS)

    Short, S.M.; Smith, D.E.; Hill, J.G.; Lerchen, M.E.

    1995-10-01

    The U.S. Department of Energy (DOE) and its predecessor agencies have historically had responsibility for carrying out various national missions primarily related to nuclear weapons development and energy research. Recently, these missions have been expanded to include remediation of sites and facilities contaminated as a result of past activities. In January 1990, the Secretary of Energy announced that DOE would prepare a Programmatic Environmental Impact Statement on the DOE's environmental restoration and waste management program; the primary focus was the evaluation of (1) strategies for conducting remediation of all DOE contaminated sites and facilities and (2) potential configurations for waste management capabilities. Several different environmental restoration strategies were identified for evaluation, ranging from doing no remediation to strategies where the level of remediation was driven by such factors as final land use and health effects. A quantitative assessment of the costs and health effects of remediation activities and residual contamination levels associated with each remediation strategy was made. These analyses required that information be compiled on each individual contaminated site and structure located at each DOE installation and that the information compiled include quantitative measurements and/or estimates of contamination levels and extent of contamination. This document provides a description of the types of information and data compiled for use in the analyses. Also provided is a description of the database used to manage the data, a detailed discussion of the methodology and assumptions used in compiling the data, and a summary of the data compiled into the database as of March 1995. As of this date, over 10,000 contaminated sites and structures and over 8,000 uncontaminated structures had been identified across the DOE complex of installations

  9. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  10. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    International Nuclear Information System (INIS)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established

  11. Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-10-17

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

  12. Environmental Assessment for Hazardous Waste Staging Facility, Pantex Plant, Amarillo, Texas

    International Nuclear Information System (INIS)

    1993-06-01

    This Environmental Assessment (EA) has been prepared pursuant to the implementing regulations to the National Environmental Policy Act (NEPA), which require federal agencies to assess the environmental impacts of a proposed action to determine whether that action requires the preparation of an Environmental Impact Statement (EIS) or if a Finding of No Significant Impact (FONSI) can be issued. The Pantex Plant does not possess permanent containerized waste staging facilities with integral secondary containment or freeze protection. Additional deficiencies associated with some existing staging facilities include: no protection from precipitation running across the staging pads; lack of protection against weathering; and facility foundations not capable of containing leaks, spills or accumulated precipitation. These shortcomings have raised concerns with respect to requirements under Section 3001 of the Resource Conservation and Recovery Act (RCRA). Deficiencies for these waste staging areas were also cited by a government audit team (Tiger Team) as Action Items. The provision for the staging of hazardous, mixed, and low level waste is part of the no-action altemative in the Programmatic Environmental Impact Statement for the integrated ER/WM program. Construction of this proposed project will not prejudice whether or not this integration will occur, or how

  13. Environmental monitoring handbook for coal conversion facilities

    Energy Technology Data Exchange (ETDEWEB)

    Salk, M.S.; DeCicco, S.G. (eds.)

    1978-05-01

    The primary objectives of the Department of Energy's (DOE) coal conversion program are to demonstrate the environmental acceptability, technical feasibility, and economic viability of various technologies for gaseous, liquid, and solid fuels from coal. The Environmental Monitoring Handbook for Coal Conversion Facilities will help accomplish the objective of environmental acceptability by guiding the planning and execution of socioeconomic and environmental monitoring programs for demonstration facilities. These programs will provide information adequate to (1) predict, insofar as is possible, the potential impacts of construction and operation of a coal conversion plant, (2) verify the occurrence of these or any other impacts during construction and operation, (3) determine the adequacy of mitigating measures to protect the environment, (4) develop effluent source terms for process discharges, and (5) determine the effectiveness of pollution control equipment. Although useful in a variety of areas, the handbook is intended primarily for contractors who, as industrial partners with DOE, are building coal conversion plants. For the contractor it is a practical guide on (1) the methodology for developing site- and process-specific environmental monitoring programs, (2) state-of-the-art sampling and analytical techniques, and (3) impact analyses.To correspond to the phases of project activity, the subject matter is divided into four stages of monitoring: (1) a reconnaissance or synoptic survey, (2) preconstruction or baseline, (3) construction, and (4) operation, including process monitoring (prepared by Radian Corp., McLean, Va.). For each stage of monitoring, guidelines are given on socioeconomics, aquatic and terrestrial ecology, air quality and meteorology, surface and groundwater quality, geohydrology and soil survey, and surface water hydrology.

  14. Environmental Control Plan for the Industrial Hygiene Field Services Facility

    International Nuclear Information System (INIS)

    Donnelly, J.W.

    2000-01-01

    This environmental control plan is for the Hanford Site's Industrial Hygiene Field Services Facility, located in the 100-N Area. This facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  15. Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

    Energy Technology Data Exchange (ETDEWEB)

    1982-09-01

    This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report.

  16. Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

    International Nuclear Information System (INIS)

    1982-09-01

    This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report

  17. Waste isolation facility description: bedded salt

    Energy Technology Data Exchange (ETDEWEB)

    1976-09-01

    The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria. (LK)

  18. Waste isolation facility description: bedded salt

    International Nuclear Information System (INIS)

    1976-09-01

    The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria

  19. Environmental implications of offshore oil and gas development in Australia. Part 5; Coastal facilities

    International Nuclear Information System (INIS)

    Black, K.P.; Brand, G.W.; Hammond, L.S.; Mourtikas, S.; Noyes-Fitzsimmons, R.L.; Smith, J.M.; Gwyther, D.; Richardson, B.J.

    1994-01-01

    It is emphasised that coastal facilities pertaining to petroleum exploration and production activities are of greater concern for potential deleterious environmental consequences than the offshore facilities. This is primarily because rates of dispersion and dilution of toxic wastes are generally lower in shallow coastal waters which are often subject to complex bathymetry, and more constricted water flows. The review found that the main processes (apart from oil spills) identified as having greatest potential environmental effect were: coastal discharges of produced water; sedimentation caused by dredging; spoil dumping; and pipe-laying activities. The review examines a wide range of marine environmental issues arising from the use of coastal-servicing facilities, including: practices and discharges during regular operation of coastal facilities; nature and extent of any environmental impact on the surrounding environment; and any deleterious effects stemming from these facilities. 194 refs., 13 tabs., 36 figs

  20. 2002 WIPP Environmental Monitoring Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2002-09-30

    DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

  1. Environmental Assessment for the NASA First Response Facility

    Science.gov (United States)

    Kennedy, Carolyn

    2003-01-01

    NASA intends to construct a First Response Facility for integrated emergency response and health management. This facility will consolidate the Stennis Space Center fire department, medical clinic, security operations, emergency operations and the energy management and control center. The alternative considered is the "No Action Alternative". The proposed action will correct existing operational weaknesses and enhance capabilities to respond to medical emergencies and mitigate any other possible threats. Environmental impacts include are emissions, wetlands disturbance, solid waste generation, and storm water control.

  2. Reconciliation with environmental quality and public health

    International Nuclear Information System (INIS)

    Malmlund, Anna

    2010-12-01

    This report is an appendix to the 'Environmental Impact Assessment - Interim storage, encapsulation and disposal of spent nuclear fuel'. The report makes a reconciliation with how the national and regional environmental quality and public health objectives are met in the construction, operation and decommissioning of the encapsulation plant and final disposal facility, and the Clink (encapsulation facility combined with CLAB). The starting point for reconciliation is the Environmental Impact Assessment (EIA). This report provides reconciliations against how the environmental and health objectives are met. A more detailed description of the business and its environmental impacts is provided in the EIA.The disposal facility is planned to be constructed in Forsmark municipality, Oesthammar and the encapsulation is constructed, combined with CLAB, in Simpevarp in Oskarshamn municipality

  3. Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  4. Environmental monitoring standardization of effluent from nuclear fuel cycle facilities in China

    International Nuclear Information System (INIS)

    Gao Mili

    1993-01-01

    China has established some environmental monitoring standards of effluent from nuclear fuel cycle facilities. Up to date 33 standards have been issued; 10 to be issued; 11 in drafting. These standards cover sampling, gross activities measurement, analytical methods and management rules and so on. They involve with almost all nuclear fuel cycle facilities and have formed a complete standards system. By the end of the century, we attempt to draft a series of analytical and determination standards in various environmental various medium, they include 36 radionuclides from nuclear fuel cycle facilities. (3 tabs.)

  5. Adolescents’ Awareness of Environmental Care: Experiences when Writing Short Descriptive Texts in English

    Directory of Open Access Journals (Sweden)

    Lorena Jaramillo Urrutia

    2011-01-01

    Full Text Available Today it is necessary to approach environmental topics with students in an interdisciplinary manner to mitigate the environmental damages that the Earth is suffering. In this paper we report an action-research and innovation study aimed at sensitizing students with respect to the care and preservation of the environment through the writing of short descriptive texts in English. The study had four stages: motivation, knowledge of ecological vocabulary, production of sentences and paragraphs, construction of short descriptive texts with the help of guidance questions and their publication in the school newspaper. The findings show that the procedure used in class promotes interdisciplinary work around environmental topics as well as the development of writing skills.

  6. Environmental restoration plan for the transfer of surplus facilities to the Facility Transition Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-08-01

    This report will provide guidance on management, coordination, and integration of plans to transition facilities to the Facility Transition Program and activities as related to the Oak Ridge National Laboratory (ORNL) Environmental Restoration Program facilities. This report gives (1) guidance on the steps necessary for identifying ORNL surplus facilities, (2) interfaces of Surveillance and Maintenance (S and M) and Isotope Facility Deactivation program managers, (3) roles and responsibilities of the facility managers, and (4) initial S and M requirements upon acceptance into the Facility Transition Program

  7. A facility for using cluster research to study environmental problems

    International Nuclear Information System (INIS)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report

  8. A facility for using cluster research to study environmental problems

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report.

  9. Radiological and environmental safety in front-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Puranik, V.D.

    2011-01-01

    The front end nuclear fuel cycle comprises of mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad. The Health Physics Units (HPUs)/Environmental Survey Laboratories (ESLs) set up at each site from inception of operation to carry out regular in-plant, personnel monitoring and environmental surveillance to ensure safe working conditions, evaluate radiation exposure of workers, ensure compliance with statutory norms, help in keeping the environmental releases well within the limits and advise appropriate control measures. This paper describes the occupational and environmental radiological safety measures associated with the operations of front end of nuclear fuel cycle. Radiological monitoring in these facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised in this paper

  10. Alpha Fuels Environmental Test Facility impact gun

    International Nuclear Information System (INIS)

    Anderson, C.G.

    1978-01-01

    The Alpha Fuels Environmental Test Facility (AFETF) impact gun is a unique tool for impact testing 238 PuO 2 -fueled heat sources of up to 178-mm dia at velocities to 300 m/s. An environmentally-sealed vacuum chamber at the muzzle of the gun allows preheating of the projectile to 1,000 0 C. Immediately prior to impact, the heat source projectile is completely sealed in a vacuum-tight catching container to prevent escape of its radioactive contents should rupture occur. The impact velocity delivered by this gas-powered gun can be regulated to within +-2%

  11. Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

  12. Internal environmental protection audits: a suggested guide for US Department of Energy facilities

    International Nuclear Information System (INIS)

    Barisas, S.; Polich, J.; Habegger, L.; Surles, T.

    1983-08-01

    This manual has been prepared for use by any DOE facility as an aid for conducting an internal environmental-protection audit. The manual is organized in modular format, with each module covering a separate area of environmental protection. The questions within each module were developed from existing DOE orders, executive orders, federal statutes, and Environmental Protection Agency (EPA) regulations issued pursuant to specific environmental legislation. A bibliography of such legislation is included at the end of this section. Each module also includes questions about a facility's use of industrial standards of practice

  13. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    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

  14. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Environmental monitoring of nuclear facilities

    International Nuclear Information System (INIS)

    Papadopoulos, D.; Winter, M.

    1982-01-01

    Environmental monitoring adds to the control of emissions of radioactive substances from nuclear facilities. The radioactive substances released with the exhaust air and the liquid effluent result in impact levels in the immediate vicinity, which must be ascertained by measurement. Impact control serves for the quantitative assessment of man-made radioactivity in different media of relevant pathways and for the direct assessment of the radiation exposure of the public living in the vicinity. In this way, the radiation exposure of the environment, which can be calculated if the emission data and the meteorological diffusion parameters are known, is controlled directly. (orig./RW)

  16. An environmental testing facility for Space Station Freedom power management and distribution hardware

    Science.gov (United States)

    Jackola, Arthur S.; Hartjen, Gary L.

    1992-01-01

    The plans for a new test facility, including new environmental test systems, which are presently under construction, and the major environmental Test Support Equipment (TSE) used therein are addressed. This all-new Rocketdyne facility will perform space simulation environmental tests on Power Management and Distribution (PMAD) hardware to Space Station Freedom (SSF) at the Engineering Model, Qualification Model, and Flight Model levels of fidelity. Testing will include Random Vibration in three axes - Thermal Vacuum, Thermal Cycling and Thermal Burn-in - as well as numerous electrical functional tests. The facility is designed to support a relatively high throughput of hardware under test, while maintaining the high standards required for a man-rated space program.

  17. Radionuclide characterization of environmental air around nuclear facilities

    International Nuclear Information System (INIS)

    Gede Sutresna Wijaya; Anung Muharini

    2015-01-01

    Air is an important environmental component in human life. Presence of air pollutants or contaminants will have a negative impact on human health. According to the existence of a nuclear facility in Yogyakarta, the characterization of radionuclides in the air is absolutely necessary to ensure the safety of people and the environment and also to supervise the safe operation of the facility. In this research the characterization of radionuclides in the air was carried through the air sampling by using High Volume Air Sampler equipped with filter TFA 2133, followed by analysis using combination of a gamma and alpha spectrometers. The concentration of radioactivity in the air fluctuates depending on the time and duration of sampling. Characterization of gamma emitting radionuclides in the air is dominated by radon progeny radionuclides such as 214 Pb, 214 Bi with activity 20.09 ± 1.23 until 32.91 ± 4.87 Bq/m 3 and 31.22 ± 1.76 until 44.25 ± 4.91 Bq/m 3 . Alpha emitter radionuclide was dominated by 214 Po (7.69 MeV) which is also radon progeny and a primordial radionuclides. It can be concluded that the presence of radionuclides in the environmental air not as a product resulting from the operation of nuclear facilities in Yogyakarta. (author)

  18. Environmental Restoration Disposal Facility Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-06-01

    The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

  19. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    International Nuclear Information System (INIS)

    MITCHELL, R.M.

    2000-01-01

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey

  20. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.M.

    2000-10-12

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  1. Preoperational Environmental Survey for the Spent Nuclear Fuel (SNF) Project Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.M.

    2000-09-28

    This document represents the report for environmental sampling of soil, vegetation, litter, cryptograms, and small mammals at the Spent Nuclear Fuel Project facilities located in 100 K and 200 East Areas in support of the preoperational environmental survey.

  2. Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2007- Appendix 2

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, Craig J.; Dorsey, Michael; Mckinney, Stephen M.; Wilde, Justin W.; Duncan, Joanne P.

    2008-10-13

    Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant (PFP), Canister Storage Building (CSB), and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

  3. Environmental Control Plan for the Industrial Hygiene Field Services Facility; TOPICAL

    International Nuclear Information System (INIS)

    J. W. Donnelly

    2001-01-01

    This environmental control plan is for the Hanford Site's industrial hygiene field services facility, located in the 100-N Area. The facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  4. Environmental analysis of the operation of the ERDA facilities in Oak Ridge

    International Nuclear Information System (INIS)

    McWherter, J.R.

    1975-01-01

    An analysis of the environmental effects of current ERDA operations in Oak Ridge is being conducted to establish a baseline for the consideration of the environmental effects of additional facilities or modified operations in the future. An extensive ecological survey has been conducted for about one year; social and economic data were obtained; and an archaeological survey of the area was made. The facilities were described and the effluents associated with operations were quantified to the extent practical. The effects of effluent releases to the environment are being analyzed. The social effects of the ERDA facilities in Oak Ridge are also being studied. (auth)

  5. Detailed description of an SSAC at the facility level for a low-enriched uranium conversion and fuel fabrication facility

    International Nuclear Information System (INIS)

    Jones, R.J.

    1984-09-01

    Some States have expressed a need for more detailed guidance with regard to the technical elements in the design and operation of SSACs for both the national and the international objectives. To meet this need the present document has been prepared, describing the technical elements of an SSAC in considerable detail. The purpose of this document is therefore, to provide a detailed description of a system for the accounting for and control of nuclear material in a model low enriched uranium conversion and fuel fabrication facility which can be used by a facility operator to establish his own system in a way which will provide the necessary information for compliance with a national system for nuclear material accounting and control and for the IAEA to carry out its safeguards responsibilities

  6. 2002 Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Washington TRU Solutions LLC

    2002-01-01

    DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance

  7. EIF onshore discharges : a quantitative environmental risk assessment tool for onshore facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hagemann, R.; Smit, M.G.D.; Frost, T.K. [Statoil ASA, Stavenger (Norway); Firth, S.K. [Firth Consultants, Bristol (United Kingdom); Stone, K. [WorleyParsons, Victoria, BC (Canada)

    2009-07-01

    The proper management of environmental risk is a key requirement of StatoilHydro's governing documents and is a key consideration in all phases of StatoilHydro's activities. In order to help manage risks in an effective and sustainable manner, StatoilHydro has led the development of the environmental impact factor (EIF) risk assessment tool. The EIF is utilized by all operators on the Norwegian Continental Shelf for reporting continuous improvements in produced water management to the authorities. The EIF concept has also been applied to evaluate environmental risk from air emissions, offshore oil spills and drilling discharges, discharges from onshore facilities to sea and discharges and spills from onshore installations. In order to identify the remaining hypothetical risk from a new facility, optimized with respect to environmental protection, this paper presented a case study, where the tool was applied to an oil sands steam assisted gravity drainage facility in Alberta. The paper discussed the EIF model and results of the case study. It was concluded that as a result of the use of generic principles for environmental risk assessment, combined with databases with parameter information for common soil and aquifer types, the EIF tool could be applied to any site ranging from wetlands to deserts. 5 refs., 2 tabs., 3 figs.

  8. Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

    International Nuclear Information System (INIS)

    1994-04-01

    The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

  9. Draft supplement to final environmental statement related to construction and operation of Clinch River Breeder Reactor Plant. Docket No. 50-537

    International Nuclear Information System (INIS)

    1982-07-01

    Information is presented concerning the site and environs; facility description; environmental impacts due to construction; environmental impacts of plant operation; environmental measurement and monitoring programs; environmental impacts of postulated accidents; need for the proposed facility; alternatives; evaluation of the proposed action; and discussion of comments received on the draft environmental statement

  10. National Ignition Facility environmental protection systems

    International Nuclear Information System (INIS)

    Mintz, J.M.; Reitz, T.C.; Tobin, M.T.

    1994-06-01

    The conceptual design of Environmental Protection Systems (EPS) for the National Ignition Facility (NIF) is described. These systems encompass tritium and activated debris handling, chamber, debris shield and general decontamination, neutron and gamma monitoring, and radioactive, hazardous and mixed waste handling. Key performance specifications met by EPS designs include limiting the tritium inventory to 300 Ci and total tritium release from NIF facilities to less than 10 Ci/yr. Total radiation doses attributable to NIF shall remain below 10 mrem/yr for any member of the general public and 500 mrem/yr for NIF staff. ALARA-based design features and operational procedures will, in most cases, result in much lower measured exposures. Waste minimization, improved cycle time and reduced exposures all result from the proposed CO2 robotic arm cleaning and decontamination system, while effective tritium control is achieved through a modern system design based on double containment and the proven detritiation technology

  11. Environmental, economic, and energy impacts of material recovery facilities. A MITE Program evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This report documents an evaluation of the environmental, economic, and energy impacts of material recovery facilities (MRFs) conducted under the Municipal Solid Waste Innovative Technology Evaluation (MITE) Program. The MITE Program is sponsored by the US Environmental Protection Agency to foster the demonstration and development of innovative technologies for the management of municipal solid waste (MSW). This project was also funded by the National Renewable Energy Laboratory (NREL). Material recovery facilities are increasingly being used as one option for managing a significant portion of municipal solid waste (MSW). The owners and operators of these facilities employ a combination of manual and mechanical techniques to separate and sort the recyclable fraction of MSW and to transport the separated materials to recycling facilities.

  12. ATLAS Facility Description Report

    International Nuclear Information System (INIS)

    Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik; Cho, Seok; Choi, Ki Yong

    2009-04-01

    A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS has the same two-loop features as the APR1400 and is designed according to the well-known scaling method suggested by Ishii and Kataoka to simulate the various test scenarios as realistically as possible. It is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating loop-type. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations in detail

  13. Exploring Environmental Variation in Residential Care Facilities for Older People.

    Science.gov (United States)

    Nordin, Susanna; McKee, Kevin; Wijk, Helle; Elf, Marie

    2017-01-01

    The aim of this study was to explore variation in environmental quality in Swedish residential care facilities (RCFs) using the Swedish version of the Sheffield Care Environment Assessment Matrix (S-SCEAM). Well-designed physical environments can positively impact on health and well-being among older persons with frail health living in RCFs and are essential for supporting person-centered care. However, the evidence base for informing the design of RCFs is weak, partly due to a lack of valid and reliable instruments that could provide important information on the environmental quality. Twenty RCFs were purposively sampled from several regions, varying in their building design, year of construction, size, and geographic location. The RCFs were assessed using S-SCEAM and the data were analyzed to examine variation in environmental quality between and within facilities. There was substantial variation in the quality of the physical environment between and within RCFs, reflected in S-SCEAM scores related to specific facility locations and with regard to domains reflecting residents' needs. In general, private apartments and dining areas had high S-SCEAM scores, while gardens had lower scores. Scores on the safety domain were high in the majority of RCFs, whereas scores for cognitive support and privacy were relatively low. Despite high building standard requirements, the substantial variations regarding environmental quality between and within RCFs indicate the potential for improvements to support the needs of older persons. We conclude that S-SCEAM is a sensitive and unique instrument representing a valuable contribution to evidence-based design that can support person-centered care.

  14. Survey and assessment of radioactive waste management facilities in the United States. Section 2.5. Air-cooled vault storage facilities

    International Nuclear Information System (INIS)

    1986-01-01

    There are two basic types of air-cooled vaults for the storage of spent nuclear fuel or vitrified HLRW. The two types, differentiated by the method of air cooling used, are the open-vault concept and the closed-vault concept. The following aspects of these air-cooled vault storage facility concepts are discussed: description and operation of facilities; strucutral design considerations and analysis; nuclear design considerations and analyses; vault environmental design considerations; unique design features; and accident analysis

  15. Description of a materials/coolant laboratory for support of the Breeder Reactor Technology Shipping Program

    International Nuclear Information System (INIS)

    Rack, H.J.; Rohde, R.W.

    1979-04-01

    A description of a facility devoted to evaluating the environmental compatibility and mechanical response of materials suitable for a breeder reactor spent-fuel shipping cask is given. The facility presently consists of a closed-loop servo-controlled hydraulic, horizontal test system coupled to an environmental chamber, generalized mechanical test equipment and high-rate mechanical behavior apparatus. Future plans include the procurement of real-time computer control equipment which will be used to assess the effects of complex load-time histories on spent-fuel shipping cask materials

  16. Environmental, Health and Safety Assessment: ATS 7H Program (Phase 3R) Test Activities at the GE Power Systems Gas Turbine Manufacturing Facility, Greenville, SC

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-11-17

    International Technology Corporation (IT) was contracted by General Electric Company (GE) to assist in the preparation of an Environmental, Health and Safety (HI&3) assessment of the implementation of Phase 3R of the Advanced Turbine System (ATS) 7H program at the GE Gas Turbines facility located in Greenville, South Carolina. The assessment was prepared in accordance with GE's contractual agreement with the U.S. Department of Energy (GE/DOE Cooperative Agreement DE-FC21-95MC3 1176) and supports compliance with the requirements of the National Environmental Policy Act of 1970. This report provides a summary of the EH&S review and includes the following: General description of current site operations and EH&S status, Description of proposed ATS 7H-related activities and discussion of the resulting environmental, health, safety and other impacts to the site and surrounding area. Listing of permits and/or licenses required to comply with federal, state and local regulations for proposed 7H-related activities. Assessment of adequacy of current and required permits, licenses, programs and/or plans.

  17. Quadrant I description of current conditions

    International Nuclear Information System (INIS)

    1990-09-01

    In accordance with the requirements of the Consent Decree issued by the Ohio Attorney General's office on August 29, 1989 and with the RCRA Section 3008(h) Consent Order issued by the US Environmental Protection Agency, Region V (USEPA) on September 29, 1989, this report, which provides a Description of Current Conditions within Quadrant I of the Portsmouth Gaseous Diffusion Plant (PORTS) located in Piketon, Ohio, has been developed and submitted for approval. The objectives of this report are to provide data concerning: (1) the current state of knowledge of the environmental setting of Quadrant I of PORTS including ground water, surface water, soil and air; and (2) the extent of known, potential and suspected contamination of these segments of the environment in Quadrant I of the facility. This report is the initial step in the comprehensive RCRA Facility Investigation (RFI) currently underway at PORTS, and will provide a foundation for all subsequent activities related to the RFI in Quadrant I

  18. Environmental Restoration Disposal Facility waste acceptance criteria. Revision 1

    International Nuclear Information System (INIS)

    Corriveau, C.E.

    1996-01-01

    The Environmental Restoration Disposal Facility (ERDF) is designed to be an isolation structure for low-level radioactive remediation waste, chemically contaminated remediation waste, and remediation waste that contains both chemical and radioactive constituents (i.e., mixed remediation waste) produced during environmental remediation of Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) past-practice units at the Hanford Site. Remedial action wastes, which will become a structural component of the ERDF, include bulk soil, demolition debris, and miscellaneous wastes from burial grounds. These wastes may originate from CERCLA past-practice sites (i.e., operable units) in the 100 Areas, the 200 Areas, and the 300 Area of the Hanford Site

  19. Environmental radiation monitoring around the nuclear facilities

    International Nuclear Information System (INIS)

    Lee, H.D.; Lee, Y.B.; Lee, W.Y.; Park, D.W.; Chung, B.G.

    1980-01-01

    For the KAERI site, various environmental samples were collected three times a month, and the natural environmental radiation levels were also measured at each sampling point. Measurements for gross alpha and beta radioactivities of the samples were routinely measured for all samples. Strontium-90 concentrations were also analysed for the fallout and air samples collected daily basis on the roof of the main building. Accumulated exposure including the possibility of determination of low level environmental radiation field by employing thermoluminescent dosimeter, CaSO 4 : Dsub(y)-0.4 teflon disc type, at 6 posts in on-site of the KAERI. As for Kori site, at 19 points of ON, OFF-site, and at the same time the environmental radiation exposure rate at each sampling point were measured. Several environmental samples such as surface soil, pine needles, water samples, milk sample and pasture samples were collected and analysed on a quarterly basis. As a result of the survey it can be said that no significant release of radiation to the environment due to the operations of nuclear facilities including research reactor at the KAERI and power reactor at the Kori has been found during the period of the survey and monitoring. (author)

  20. Waste Characterization Facility at the Idaho National Engineering Laboratory. Environmental Assessment

    International Nuclear Information System (INIS)

    1995-02-01

    DOE has prepared an Environmental Assessment (EA) on the proposed construction and operation of a Waste Characterization Facility (WCF) at INEL. This facility is needed to examine and characterize containers of transuranic (TRU) waste to certify compliance with transport and disposal criteria; to obtain information on waste constituents to support proper packaging, labeling, and storage; and to support development of treatment and disposal plans for waste that cannot be certified. The proposed WCF would be constructed at the Radioactive Waste Management Complex (RWMC). In accordance with the Council on Environmental Quality (CEQ) requirements in 40 CFR Parts 1500-1508, the EA examined the potential environmental impacts of the proposed WCF and discussed potential alternatives. Based on the analyses in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, and CEQ regulations at 40 CFR 1508.18 and 1508.27. Therefore, an Environmental Impact Statement is not required, and DOE is issuing this Finding of No Significant Impact

  1. Naval Reactors Facility environmental monitoring report, calendar year 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 2001 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U. S. Environmental Protection Agency and the U. S. Department of Energy

  2. 1997 environmental monitoring report for the Naval Reactors Facility

    International Nuclear Information System (INIS)

    1997-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 1997 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE)

  3. Naval Reactors Facility Environmental Monitoring Report, Calendar Year 2003

    International Nuclear Information System (INIS)

    2003-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 2003 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency and the U.S. Department of Energy

  4. Naval Reactors Facility environmental monitoring report, calendar year 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 1999 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE)

  5. 1993 environmental monitoring report for the naval reactors facility

    International Nuclear Information System (INIS)

    1994-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 1993 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE)

  6. 1991 environmental monitoring report for the Naval Reactors Facility

    International Nuclear Information System (INIS)

    1991-01-01

    The results of the radiological and non-radiological environmental monitoring programs for 1991 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were within the guidelines established by state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or heath and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the EnVironmental Protection Agency (EPA) and the Department of Energy (DOE)

  7. Naval Reactors Facility environmental monitoring report, calendar year 2000

    International Nuclear Information System (INIS)

    2001-01-01

    The results of the radiological and nonradiological environmental monitoring programs for 2000 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE)

  8. Supplemental environmental impact statement - defense waste processing facility

    International Nuclear Information System (INIS)

    1994-11-01

    This document supplements the Final Environmental Impact Statement (EIS) DOE Issued in 1982 (DOE/EIS-0082) to construct and operate the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS), a major DOE installation in southwestern South Carolina. That EIS supported the decision to construct and operate the DWPF to immobilize high-level waste generated as a result of nuclear materials processing at SRS. The DWPF would use a vitrification process to incorporate the radioactive waste into borosilicate glass and seal it in stainless steel canisters for eventual disposal at a permanent geologic repository. The DWPF is now mostly constructed and nearly ready for full operation. However, DOE has made design changes to the DWPF since the 1982 EIS to improve efficiency and safety of the facility. Each of these modifications was subjected to appropriate NEPA review. The purpose of this Supplemental EIS is to assist DOE in deciding whether and how to proceed with operation of the DWPF as modified since 1982 while ensuring appropriate consideration of potential environmental effects. In this document, DOE assesses the potential environmental impacts of completing and operating the DWPF in light of these design changes, examines the impact of alternatives, and identifies potential actions to be taken to reduce adverse impacts. Evaluations of impacts on water quality, air quality, ecological systems, land use, geologic resources, cultural resources, socioeconomics, and health and safety of onsite workers and the public are included in the assessment

  9. Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

  10. A facility for using cluster research to study environmental problems. Workshop proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report.

  11. Hazards study of environmental protection classified facilities. Scenarios analysis; Etude de dangers des ICPE. Analyse des scenarios

    Energy Technology Data Exchange (ETDEWEB)

    Seveque, J.L. [Cour d' Appel d' Amiens, 80 (France)

    2006-04-15

    This article describes the analysis and study of the possible impacts of accidents occurring at industrial facilities classified with respect to the environment protection. The operators of such facilities have to describe the possible risks and their consequences, the measures taken to prevent them and the level of residual risk. Therefore, it consists in calculating the consequences of all possible aggressions that a facility can undergo. The receptors are of 2 type: the human body (burns, asphyxia, intoxication, shock wave, projectile), and the surrounding equipments (fire, unconfined vapour cloud explosion (UVCE), boiling liquid expanding vapour explosion (BLEVE), fireball, dispersion of toxic gases). Content: 1 - fire-type scenario: description, modeling of thermal effects, conclusion; 2 - UVCE-type scenario: description, Lannoy method (TNT equivalent), multi-energy method, conclusion; 3 - BLEVE-type scenario: description, modeling of overpressure effects, thermal effects of the fireball; 4 - toxic cloud scenario: modeling of a toxic cloud dispersion, effects and consequences; 5 - conclusions. (J.S.)

  12. Radiological environmental monitoring programs at Canadian nuclear facilities - a practical model for follow-up activities under the Canadian Environmental Assessment Act

    International Nuclear Information System (INIS)

    Tamm, J.A.; Zach, R.

    2000-01-01

    Under the Canadian Environmental Assessment Act (the Act), a federal authority, if it considers it appropriate, is to design a follow-up program for a project undergoing a federal environmental assessment and arrange for implementation of that program. Under the Act a follow-up program means a set of activities for verifying the accuracy of the environmental assessment (EA) of a project and for determining the effectiveness of any measures taken to mitigate any adverse environmental effects resulting from the project. The Act currently does not include regulations, guidelines, standards or procedures regarding the design, content and implementation requirements for follow-up programs (Canadian Environmental Assessment Agency [the Agency] 1999). Uncertainties also exist regarding the roles and responsibilities in designing, implementing, enforcing and auditing such activities. The Agency is presently specifying appropriate activities to address these issues. This paper considers the existing radiological environmental monitoring programs at nuclear facilities. Such programs consist of two types of monitoring-radioactivity releases from the facility via liquid and gaseous waste streams, and radioactivity in the environment at large, beyond the facility's immediate location. Such programs have been developed by AECL, Canadian nuclear utilities and uranium mining companies. Our analysis show that these programs can provide a good model for follow-up programs under the Act. (author)

  13. Environmental surveillance for EG ampersand G Idaho Waste Management facilities at the Idaho National Engineering Laboratory. 1993 annual report

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.; Borsella, B.W.

    1994-08-01

    This report describes calendar year 1993 environmental surveillance activities of Environmental Monitoring of EG ampersand G Idaho, Inc., performed at EG ampersand G Idaho operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1993 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years

  14. Annual report -- 1992: Environmental surveillance for EG ampersand G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

    1993-08-01

    This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years

  15. ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

    International Nuclear Information System (INIS)

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-01-01

    The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

  16. Nuclear facility projects in Finland: quality of environmental impact assessment (EIA) processes

    International Nuclear Information System (INIS)

    Vaatainen, A.

    2001-01-01

    In Finland, three public EIA hearings arranged by the contact authority concerning nuclear facilities were organised in 1999: the EIAs of two reactors planned to be constructed in Eurajoki (Olkiluoto) and in Loviisa, and the EIA of a final disposal facility of spent nuclear fuel, to be situated either in Olkiluoto, Loviisa, Romuvaara or Kivetty. Additionally, an application for a decision-in-principle concerning a final disposal facility to be constructed in Olkiluoto was submitted. The Ministry of Trade and Industry is the contact authority in all nuclear projects in Finland. Probably due to the simultaneity of the processes and the great importance of nuclear facility projects to the whole of society, the public opinions did not include only views about environmental impacts of each project, but also opposing and overall views about the use of nuclear energy and its safety. As for the final disposal project, alternative methods were introduced and opposition to the project itself was expressed instead of or in addition to the environmental impacts. (author)

  17. Annual environmental monitoring report, January-December 1985

    International Nuclear Information System (INIS)

    1986-03-01

    A general description of the Stanford Linear Accelerator Center, the site's climate, geology, facility water usage, land use, and demography of the area is given. The environmental status for 1985 is reported with respect to non-radioactive and radioactive discharge

  18. Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI).

  19. Environmental Assessment for decommissioning the Strategic Petroleum Reserve Weeks Island Facility, Iberia Parish, Louisiana

    International Nuclear Information System (INIS)

    1995-12-01

    The Strategic Petroleum Reserve (SPR) Weeks Island site is one of five underground salt dome crude oils storage facilities operated by the Department of Energy (DOE). It is located in Iberia Parish, Louisiana. The purpose of the proposed action is to decommission the Weeks Island crude oil storage after the oil inventory has been transferred to other SPR facilities. Water intrusion into the salt dome storage chambers and the development of two sinkholes located near the aboveground facilities has created uncertain geophysical conditions. This Environmental Assessment describes the proposed decommissioning operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) and has issued the Finding of No Significant Impact (FONSI)

  20. The environmental impact assessment process for nuclear facilities: An examination of the Indian experience

    International Nuclear Information System (INIS)

    Ramana, M.V.; Rao, Divya Badami

    2010-01-01

    India plans to construct numerous nuclear plants and uranium mines across the country, which could have significant environmental, health, and social impacts. The national Environmental Impact Assessment process is supposed to regulate these impacts. This paper examines how effective this process has been, and the extent to which public inputs have been taken into account. In addition to generic problems associated with the EIA process for all kinds of projects in India, there are concerns that are specific to nuclear facilities. One is that some nuclear facilities are exempt from the environmental clearance process. The second is that data regarding radiation baseline levels and future releases, which is the principle environmental concern with respect to nuclear facilities, is controlled entirely by the nuclear establishment. The third is that members of the nuclear establishment take part in almost every level of the environmental clearance procedure. For these reasons and others, the EIA process with regard to nuclear projects in India is of dubious quality. We make a number of recommendations that could address these lacunae, and more generally the imbalance of power between the nuclear establishment on the one hand, and civil society and the regulatory agencies on the other.

  1. Reconciliation with environmental quality and public health; Avstaemning mot miljoekvalitetsmaal och folkhaelsomaal

    Energy Technology Data Exchange (ETDEWEB)

    Malmlund, Anna (Structor Miljoebyraan Stockholm AB (Sweden))

    2010-12-15

    This report is an appendix to the 'Environmental Impact Assessment - Interim storage, encapsulation and disposal of spent nuclear fuel'. The report makes a reconciliation with how the national and regional environmental quality and public health objectives are met in the construction, operation and decommissioning of the encapsulation plant and final disposal facility, and the Clink (encapsulation facility combined with CLAB). The starting point for reconciliation is the Environmental Impact Assessment (EIA). This report provides reconciliations against how the environmental and health objectives are met. A more detailed description of the business and its environmental impacts is provided in the EIA.The disposal facility is planned to be constructed in Forsmark municipality, Oesthammar and the encapsulation is constructed, combined with CLAB, in Simpevarp in Oskarshamn municipality.

  2. Bettis Atomic Power Laboratory. Bettis-Pittsburgh Site environmental summary report

    International Nuclear Information System (INIS)

    None

    2000-01-01

    This summary report provides a description of the nature and environmental aspects of work and facilities at the Bettis-Pittsburgh site, an historical perspective of Bettis-Pittsburgh operations that is not provided by the annual reports, and background information pertinent to understanding the environmental aspects of Bettis-Pittsburgh operations

  3. High Exposure Facility Technical Description

    Energy Technology Data Exchange (ETDEWEB)

    Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

    2008-02-12

    The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

  4. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    International Nuclear Information System (INIS)

    Dyakova, E.; Krymskaya, L.

    1997-01-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs

  5. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dyakova, E; Krymskaya, L [Institute for Nuclear Research, National Academy of Science, Kiev (Ukraine)

    1997-09-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs.

  6. INEL environmental characterization report. Volume III. Appendices E-H

    International Nuclear Information System (INIS)

    1984-09-01

    This volume contains the following appendices: (1) INEL subsurface hydrology; (2) cultural resources assessment of two study areas on the INEL; (3) description of INEL facilities; and (4) effluent measurements and environmental monitoring programs

  7. Sandia National Laboratories, California proposed CREATE facility environmental baseline survey.

    Energy Technology Data Exchange (ETDEWEB)

    Catechis, Christopher Spyros

    2013-10-01

    Sandia National Laboratories, Environmental Programs completed an environmental baseline survey (EBS) of 12.6 acres located at Sandia National Laboratories/California (SNL/CA) in support of the proposed Collaboration in Research and Engineering for Advanced Technology and Education (CREATE) Facility. The survey area is comprised of several parcels of land within SNL/CA, County of Alameda, California. The survey area is located within T 3S, R 2E, Section 13. The purpose of this EBS is to document the nature, magnitude, and extent of any environmental contamination of the property; identify potential environmental contamination liabilities associated with the property; develop sufficient information to assess the health and safety risks; and ensure adequate protection for human health and the environment related to a specific property.

  8. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility: Volume 1. Revision 1

    International Nuclear Information System (INIS)

    Weekes, D.C.; Ford, B.H.; Jaeger, G.K.

    1996-09-01

    This site characterization report provides the results of the field data collection activities for the Environmental Restoration Disposal Facility site. Information gathered on the geology, hydrology, ecology, chemistry, and cultural resources of the area is presented. The Environmental Restoration Disposal Facility is located at the Hanford Site in Richland, Washington

  9. Environmental Assessment for the Health Protection Instrument Calibration Facility at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The purpose of this Environmental Assessment (EA) is to review the possible environmental consequences associated with the construction and operation of a Health Protection Instrument Calibration Facility on the Savannah River Site (SRS). The proposed replacement calibration facility would be located in B Area of SRS and would replace an inadequate existing facility currently located within A Area of SRS (Building 736-A). The new facility would provide laboratories, offices, test equipment and the support space necessary for the SRS Radiation Monitoring Instrument Calibration Program to comply with DOE Orders 5480.4 (Environmental Protection, Safety and Health Protection Standards) and 5480.11 (Radiation Protection for Occupational Workers). The proposed facility would serve as the central site source for the evaluation, selection, inspection, testing, calibration, and maintenance of all SRS radiation monitoring instrumentation. The proposed facility would be constructed on a currently undeveloped portion in B Area of SRS. The exact plot associated with the proposed action is a 1.2 hectare (3 acre) tract of land located on the west side of SRS Road No. 2. The proposed facility would lie approximately 4.4 km (2.75 mi) from the nearest SRS site boundary. The proposed facility would also lie within the confines of the existing B Area, and SRS safeguards and security systems. Archaeological, ecological, and land use reviews have been conducted in connection with the use of this proposed plot of land, and a detailed discussion of these reviews is contained herein. Socioeconomic, operational, and accident analyses were also examined in relation to the proposed project and the findings from these reviews are also contained in this EA.

  10. Environmental Assessment for the Health Protection Instrument Calibration Facility at the Savannah River Site

    International Nuclear Information System (INIS)

    1993-08-01

    The purpose of this Environmental Assessment (EA) is to review the possible environmental consequences associated with the construction and operation of a Health Protection Instrument Calibration Facility on the Savannah River Site (SRS). The proposed replacement calibration facility would be located in B Area of SRS and would replace an inadequate existing facility currently located within A Area of SRS (Building 736-A). The new facility would provide laboratories, offices, test equipment and the support space necessary for the SRS Radiation Monitoring Instrument Calibration Program to comply with DOE Orders 5480.4 (Environmental Protection, Safety and Health Protection Standards) and 5480.11 (Radiation Protection for Occupational Workers). The proposed facility would serve as the central site source for the evaluation, selection, inspection, testing, calibration, and maintenance of all SRS radiation monitoring instrumentation. The proposed facility would be constructed on a currently undeveloped portion in B Area of SRS. The exact plot associated with the proposed action is a 1.2 hectare (3 acre) tract of land located on the west side of SRS Road No. 2. The proposed facility would lie approximately 4.4 km (2.75 mi) from the nearest SRS site boundary. The proposed facility would also lie within the confines of the existing B Area, and SRS safeguards and security systems. Archaeological, ecological, and land use reviews have been conducted in connection with the use of this proposed plot of land, and a detailed discussion of these reviews is contained herein. Socioeconomic, operational, and accident analyses were also examined in relation to the proposed project and the findings from these reviews are also contained in this EA

  11. Annual Report for 2008 - 2009 Detection Monitoring at the Environmental Management Waste Management Facility, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Walker J.R.

    2010-03-01

    short descriptions of the facility, the hydrogeologic setting, CERCLA decision document requirements for environmental monitoring, and a summary of the EMWMF monitoring history to date. Sect. 3 identifies the respective groundwater, surface water, stormwater, and air monitoring locations at the EMWMF and outlines the associated sampling frequencies, field measurements, and laboratory analytes. Sect. 4 presents a concise technical evaluation of the groundwater, surface water, stormwater, and air monitoring data. Sect. 5 summarizes key monitoring results and data evaluation conclusions along with any recommended changes to groundwater, surface water, stormwater, or air monitoring at the EMWMF. Sect. 6 lists the documents and other technical reports referenced in the preceding narrative sections. Maps and other illustrations referenced in the narrative sections of this annual EMR are in Appendix A. Referenced summary tables of FY 2009 environmental monitoring data are in Appendix B (Groundwater), Appendix C (Surface Water), Appendix D (Stormwater), and Appendix E (Ambient Air).

  12. Disposal facility for spent nuclear fuel. Environmental impact assessment program

    International Nuclear Information System (INIS)

    1998-01-01

    The report presents the Environmental Impact Assessment (EIA) of the high level radioactive waste disposal in Finland. In EIA different alternatives concerning site selection, construction, operation and sealing of the disposal facility as well as waste transportation and encapsulation of the waste are considered

  13. Environmental Monitoring Plan, Nevada Test Site and support facilities

    International Nuclear Information System (INIS)

    1991-11-01

    This Environmental Monitoring Plan applies to the US Department of Energy's (DOE's) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this Environmental Monitoring Plan brings together in one document a description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA). The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards

  14. Environmental Monitoring Plan, Nevada Test Site and support facilities

    International Nuclear Information System (INIS)

    1991-11-01

    This Operational Area Monitoring Plan for environmental monitoring, is for EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) which operates several offsite facilities in support of activities at the Nevada Test Site (NTS). These facilities include: (1) Amador Valley Operations (AVO), Pleasanton, California; (2) Kirtland Operations (KO), Kirtland Air Force base, Albuquerque, New Mexico (KAFB); (3) Las Vegas Area Operations (LVAO), Remote Sensing Laboratory (RSL), and North Las Vegas (NLV) Complex at Nellis Air Force Base (NAFB), North Las Vegas, Nevada; (4) Los Alamos Operations (LAO), Los Alamos, New Mexico; (5) Santa Barbara Operations (SBO), Goleta, California; (6) Special Technologies Laboratory (STL), Santa Barbara, California; (7) Washington Aerial Measurements Department (WAMD), Andrews Air Force Base, Maryland; and, (8) Woburn Cathode Ray Tube Operations (WCO), Woburn, Massachusetts. Each of these facilities has an individual Operational Area Monitoring Plan, but they have been consolidated herein to reduce redundancy

  15. Portsmouth Gaseous Diffusion Plant expansion, Piketon, Ohio. Volume 2. Draft environmental statement

    Energy Technology Data Exchange (ETDEWEB)

    Pennington, W. H.

    1976-06-01

    The need for additional uranium enrichment facilities and the environmental impacts of the add-on gaseous diffusion plant proposed for the Portsmouth Gaseous Diffusion Plant are discussed. A detailed description of the proposed facilities is included and unavoidable adverse environmental effects, possible alternatives, and anticipated benefits from the proposed facilities are considered. The flora and fauna of the area are tabulated and possible effects of air and water pollution on aquatic and terrestrial ecosystems are postulated. The extent of anticipated noise impact on the vicinity and the anticipated extent of civic envolvement are discussed. (CH)

  16. Portsmouth Gaseous Diffusion Plant expansion, Piketon, Ohio. Volume 2. Draft environmental statement

    International Nuclear Information System (INIS)

    1976-06-01

    The need for additional uranium enrichment facilities and the environmental impacts of the add-on gaseous diffusion plant proposed for the Portsmouth Gaseous Diffusion Plant are discussed. A detailed description of the proposed facilities is included and unavoidable adverse environmental effects, possible alternatives, and anticipated benefits from the proposed facilities are considered. The flora and fauna of the area are tabulated and possible effects of air and water pollution on aquatic and terrestrial ecosystems are postulated. The extent of anticipated noise impact on the vicinity and the anticipated extent of civic envolvement are discussed

  17. Process Description and Operating History for the CPP-601/-640/-627 Fuel Reprocessing Complex at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Wagner, E.P.

    1999-01-01

    The Fuel Reprocessing Complex (FRC) at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory was used for reprocessing spent nuclear fuel from the early 1950's until 1992. The reprocessing facilities are now scheduled to be deactivated. As part of the deactivation process, three Resource Conservation and Recovery Act (RCRA) interim status units located in the complex must be closed. This document gathers the historical information necessary to provide a rational basis for the preparation of a comprehensive closure plan. Included are descriptions of process operations and the operating history of the FRC. A set of detailed tables record the service history and present status of the process vessels and transfer lines

  18. Learning and education on environmental radioactivity by residents of Rokkasho Site for the spent fuel recycling facilities

    International Nuclear Information System (INIS)

    Kawauchi, Kiye; Itoh, Natsuko; Ishikawa, Tomiye; Nihonyanagi, Haruko; Aratani, Michi

    2005-01-01

    The neutron criticality accident at the JCO, a private company for nuclear fuel processing facilities in Tokai has drastically changed minds and attitudes of residents toward environmental radioactivity. The accident happened on September 30, 1999. Before the accident the residents of the Rokkasho Site were not anxious about environmental radioactivity, because they thought the facilities were safe enough concerning containment policy of the radioactivity inside the facilities. Residents, however, had not been taught on a neutron. It is an unfamiliar radiation for them. So, they promptly learnt on neutrons, and some of them began the fixed point measurement of neutrons at the nearest site of the Spent Fuel Recycling Facilities of Rokkasho by the help of Prof. Kazuhisa. Komura, Kanazawa University. Members of the Reading Cicle, Rokkasho Culture Society, mainly women, learnt measurements of environmental radioactivity using simplified counters for alpha-, beta-, and gamma-ray from natural radioactive elements and prepared various kinds of environmental samples. After learning of environmental radioactivity, they began educational activities on the environmental radioactivity for boys and girls in the region. Monitoring of environmental radioactivity is performed by different institutions and with their purposes. Here is reported learning of environmental radioactivity by the residents and education of environmental radioactivity toward the young. Even with the simplest counters, we think that the monitoring of environmental radioactivity by the residents themselves is the royal road to the safety of the regional society. (author)

  19. Environmental Assessment for the Leasing of Facilities and Equipment to USEC Inc

    International Nuclear Information System (INIS)

    2002-01-01

    The U.S. Department of Energy (DOE) Oak Ridge Operations Office (DOE-ORO) has prepared this Environmental Assessment (EA) for the lease of facilities and equipment to USEC Inc. (USEC), which would be used in its Gas Centrifuge Research and Development (R and D) Project at the East Tennessee Technology Park (ETTP) [hereinafter referred to as the USEC EA]. The USEC EA analyzes the potential environmental impacts of DOE leasing facility K-101 and portions of K-1600, K-1220 and K-1037 at the ETTP to USEC for a minimum 3-year period, with additional option periods consistent with the Oak Ridge Accelerated Clean-up Plan (ACP) Agreement. In July 2002, USEC notified DOE that it intends to use certain leased equipment at an off-site facility at the Centrifuge Technology Center (CTC) on the Boeing Property. The purpose of the USEC Gas Centrifuge R and D Project is to develop an economically attractive gas centrifuge machine and process using DOE's centrifuge technology

  20. Operational environmental monitoring plan for the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Mercer, D.D.; Baker, P.L.; Cockman, J.S.; Fischer, N.T.; Flynn, D.T.; Harvill, J.P.; Knudtsen, K.L.; Louderbough, E.T.

    1989-01-01

    This plan defines the scope and extent of the WIPP effluent and environmental monitoring programs during the facility's operational life. It also discusses the quality assurance/quality control programs which ensure that samples collected and the resulting analytical data are representative of actual conditions at the WIPP site. This plan provides a comprehensive description of environmental activities at WIPP, including: a summary of environmental program information, including an update of the status of environmental permits and compliance activities; a description of the WIPP project and its mission; a description of the local environment, including demographics; a summary of applicable standards and regulatory requirements and brief discussions of potential exposure pathways, routine and accidental releases, and their consequences; a summary of the preoperational environmental monitoring and assessment activities and responses to the requirements (Appendix A) and guidelines presented in the ''Radiological Effluent Monitoring and Environmental Surveillance for US DOE Operations.'' 166 refs., 28 figs., 27 tabs

  1. Environmental Performance Report 2015

    Energy Technology Data Exchange (ETDEWEB)

    2016-07-01

    The National Renewable Energy Laboratory's (NREL's) Environmental Performance Report provides a description of the laboratory's environmental management activities for 2015, including information on environmental and sustainability performance, environmental compliance activities and status, and environmental protection programs, highlights, and successes. The purpose of this report is to ensure that U.S. Department of Energy (DOE) and the public receive timely, accurate information about events that have affected or could adversely affect the health, safety, and security of the public or workers; the environment; or the operations of DOE facilities. This report meets the requirements of the Annual Site Environmental Report and is prepared in accordance with the DOE Order 231.1B, Environment, Safety and Health Reporting.

  2. Environmental Performance Report 2016

    Energy Technology Data Exchange (ETDEWEB)

    Braus, Genevieve [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2017-09-06

    The National Renewable Energy Laboratory's (NREL's) Environmental Performance Report provides a description of the laboratory's environmental management activities for 2016, including information on environmental and sustainability performance, environmental compliance activities and status, and environmental protection programs, highlights, and successes. The purpose of this report is to ensure that U.S. Department of Energy (DOE) and the public receive timely, accurate information about events that have affected or could adversely affect the health, safety, and security of the public or workers; the environment; or the operations of DOE facilities. This report meets the requirements of the Annual Site Environmental Report and is prepared in accordance with the DOE Order 231.1B, Environment, Safety and Health Reporting.

  3. Environmental monitoring of low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Shum, E.Y.; Starmer, R.J.; Young, M.H.

    1989-12-01

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance

  4. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  5. Annual site environmental monitoring report for the Waste Isolation Pilot Plant, Calendar year 1985

    International Nuclear Information System (INIS)

    Reith, C.; Prince, K.; Fischer, T.; Rodriguez, A.; Uhland, D.; Winstanley, D.

    1986-04-01

    This is the first Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP project is operated by the US Department of Energy (DOE) for the purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes generated by the defense activities of the U.S. Government. The report provides a comprehensive description of environmental activities at WIPP during Calendar Year 1985, including: a description of the WIPP project and its mission; a description of the local environment, including demographics; a summary of environmental program information, including an update on the status of environmental permits and compliance activities; a presentation of the findings of the Radiological Baseline Program (RBP), which is a program to characterize radionuclide activities in the environment around the WIPP site; and a summary of findings of the Ecological Monitoring Program (EMP), which examines non-radiological impacts of WIPP construction on the surrounding ecosystem. The WIPP facility is under construction, and will not receive radioactive wastes before October 1988. Therefore, this report describes the status of preoperational (as opposed to operational) environmental activities. 29 refs., 17 figs., 22 tabs

  6. Environmental monitoring data review of a uranium ore processing facility in Argentina

    International Nuclear Information System (INIS)

    Bonetto, J.

    2014-01-01

    An uranium ore processing facility in the province of Mendoza (Argentina) that has produced uranium concentrate from 1954 to 1986 is currently undergoing the last steps of environmental restoration. The operator has been performing post-closure environmental monitoring since 1986, while the Nuclear Regulatory Authority (ARN) has been carrying out its own independent radiological environmental monitoring for verification purposes since its creation, in 1995. A detailed revision of ARN´s monitoring plan for uranium mining and milling facilities has been undergoing since 2013, starting with this particular site. Results obtained from long-time sampling locations (some of them currently unused) have been analyzed and potentially new sampling points have been studied and proposed. In this paper, some statistical analysis and comparison of sampling-points’ datasets are presented (specifically uranium and radium concentration in groundwater, surface water and sediments) with conclusions pertaining to their keeping or discarding as sampling points in future monitoring plans. (author)

  7. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2001-02-01

    The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

  8. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.

    Energy Technology Data Exchange (ETDEWEB)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

  9. Safety and environmental process for the design and construction of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Brereton, S.J., LLNL

    1998-05-27

    The National Ignition Facility (NIF) is a U.S. Department of Energy (DOE) laser fusion experimental facility currently under construction at the Lawrence Livermore National Laboratory (LLNL). This paper describes the safety and environmental processes followed by NIF during the design and construction activities.

  10. Webinar Presentation: Environmental Exposures and Health Risks in California Child Care Facilities: First Steps to Improve Environmental Health where Children Spend Time

    Science.gov (United States)

    This presentation, Environmental Exposures and Health Risks in California Child Care Facilities: First Steps to Improve Environmental Health where Children Spend Time, was given at the NIEHS/EPA Children's Centers 2016 Webinar Series: Exposome.

  11. Facility location decisions with environmental considerations. A case study from the petrochemical industry

    OpenAIRE

    Treitl, Stefan; Jammernegg, Werner

    2014-01-01

    The recently growing concerns of customers and governments about environmental protection and greenhouse gas reduction have forced companies to integrate the topic of environmental sustainability into their decision making. Facility location decisions are of special relevance in this respect because of their strategic nature. Furthermore, many different trade-offs must be considered, for example between operational costs and customer service. But as soon as environmental issues are concerned,...

  12. Environmental Audit at Santa Barbara Operations, Special Technologies Laboratory, Remote Sensing Laboratory, North Las Vegas Facilities

    International Nuclear Information System (INIS)

    1991-03-01

    This report documents the results of the Environmental Audit of selected facilities under the jurisdiction of the DOE Nevada Operations Office (NV) that are operated by EG and G Energy Measurements, Incorporated (EG and G/EM). The facilities included in this Audit are those of Santa Barbara Operation (SBO) at Goleta, California; the Special Technologies Laboratory (STL) at Santa Barbara, California; and Las Vegas Area Operations (LVAO) including the Remote Sensing Laboratory (RSL) at Nellis Air Force Base in Nevada, and the North Las Vegas Facilities (NLVF) at North Las Vegas, Nevada. The Environmental Audit was conducted by the US Department of Energy's (DOE) Office of Environmental Audit, commencing on January 28, 1991 and ending on February 15, 1991. The scope of the Audit was comprehensive, addressing environmental activities in the technical areas of air, surface water/drinking water, groundwater, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. Also assessed was compliance with applicable Federal, state, and local regulations and requirements; internal operating requirements; DOE Orders; and best management practices. 8 tabs

  13. Material control in nuclear fuel fabrication facilities. Part I. Fuel descriptions and fabrication processes, P.O. 1236909 Final report

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; Miller, C.L.

    1978-12-01

    The report presents information on foreign nuclear fuel fabrication facilities. Fuel descriptions and fuel fabrication information for three basic reactor types are presented: The information presented for LWRs assumes that Pu--U Mixed Oxide Fuel (MOX) will be used as fuel

  14. Facility Effluent Monitoring Plan for the 3720 Building

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

  15. Analysis of federal and state policies and environmental issues for bioethanol production facilities.

    Science.gov (United States)

    McGee, Chandra; Chan Hilton, Amy B

    2011-03-01

    The purpose of this work was to investigate incentives and barriers to fuel ethanol production from biomass in the U.S. during the past decade (2000-2010). In particular, we examine the results of policies and economic conditions during this period by way of cellulosic ethanol activity in four selected states with the potential to produce different types of feedstocks (i.e., sugar, starch, and cellulosic crops) for ethanol production (Florida, California, Hawaii, and Iowa). Two of the four states, Iowa and California, currently have commercial ethanol production facilities in operation using corn feedstocks. While several companies have proposed commercial scale facilities in Florida and Hawaii, none are operating to date. Federal and state policies and incentives, potential for feedstock production and conversion to ethanol and associated potential environmental impacts, and environmental regulatory conditions among the states were investigated. Additionally, an analysis of proposed and operational ethanol production facilities provided evidence that a combination of these policies and incentives along with the ability to address environmental issues and regulatory environment and positive economic conditions all impact ethanol production. The 2000-2010 decade saw the rise of the promise of cellulosic ethanol. Federal and state policies were enacted to increase ethanol production. Since the initial push for development, expansion of cellulosic ethanol production has not happened as quickly as predicted. Government and private funding supported the development of ethanol production facilities, which peaked and then declined by the end of the decade. Although there are technical issues that remain to be solved to more efficiently convert cellulosic material to ethanol while reducing environmental impacts, the largest barriers to increasing ethanol production appear to be related to government policies, economics, and logistical issues. The numerous federal and state

  16. Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

  17. Development of BWR [boiling water reactor] and PWR [pressurized water reactor] event descriptions for nuclear facility simulator training

    International Nuclear Information System (INIS)

    Carter, R.J.; Bovell, C.R.

    1987-01-01

    A number of tools that can aid nuclear facility training developers in designing realistic simulator scenarios have been developed. This paper describes each of the tools, i.e., event lists, events-by-competencies matrices, and event descriptions, and illustrates how the tools can be used to construct scenarios

  18. Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

    International Nuclear Information System (INIS)

    Pettersson, Stig; Forsgren, Ebbe; Lange, Fritz

    2002-04-01

    This report documents a proposal for the design of the deep repository for spent nuclear fuel. The proposal is based on the principles that were formulated in the original KBS-3 study, but has been supplemented by investigations and experience to reflect current knowledge. The purpose of the report is to provide an integrated picture of the deep repository, as a basis for SKB's other work, e.g. environmental impact assessments, transport systems, safety issues and alternative locations, and to provide a co-ordinated account of the conditions and requirements concerning all of the necessary functions in the deep repository in order to have a well functioning facility. In addition, it should be possible to use the report as: a tool in the task of achieving a co-ordinated, safe and accepted design for the facility, a basis for further planning and costing, a basis for adaptation to geographic and other conditions for the particular location, a basis for information material, both within SKB and for interested parties outside, such as public authorities, municipalities and the general public. The capacity of the deep repository has been chosen on the basis of 40 years of operation of the Swedish nuclear power reactors, which will produce approximately 9,000 tons of uranium, equivalent to approximately 4,500 canisters. The design outlined is based on theoretical analyses of functions, safety requirements, procedures etc. that can be identified during the various phases of the construction and operation of the repository. In addition, preliminary organisation and staffing plans have been drawn up, for use as the basis for planning the necessary buildings. The report gives a vision of the overall layout and function of the facility, and a proposal for the design of all individual parts of the repository. The relationships between the various parts of the repository are described, both above and below ground, as is the interplay between the part above ground and part below

  19. Deep repository for spent nuclear fuel. Facility description - Layout E. Spiral ramp with one operational area

    Energy Technology Data Exchange (ETDEWEB)

    Pettersson, Stig [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Forsgren, Ebbe [SwedPower AB, Stockholm (Sweden); Lange, Fritz [Lange Art AB, Stockholm (Sweden)

    2002-04-01

    This report documents a proposal for the design of the deep repository for spent nuclear fuel. The proposal is based on the principles that were formulated in the original KBS-3 study, but has been supplemented by investigations and experience to reflect current knowledge. The purpose of the report is to provide an integrated picture of the deep repository, as a basis for SKB's other work, e.g. environmental impact assessments, transport systems, safety issues and alternative locations, and to provide a co-ordinated account of the conditions and requirements concerning all of the necessary functions in the deep repository in order to have a well functioning facility. In addition, it should be possible to use the report as: a tool in the task of achieving a co-ordinated, safe and accepted design for the facility, a basis for further planning and costing, a basis for adaptation to geographic and other conditions for the particular location, a basis for information material, both within SKB and for interested parties outside, such as public authorities, municipalities and the general public. The capacity of the deep repository has been chosen on the basis of 40 years of operation of the Swedish nuclear power reactors, which will produce approximately 9,000 tons of uranium, equivalent to approximately 4,500 canisters. The design outlined is based on theoretical analyses of functions, safety requirements, procedures etc. that can be identified during the various phases of the construction and operation of the repository. In addition, preliminary organisation and staffing plans have been drawn up, for use as the basis for planning the necessary buildings. The report gives a vision of the overall layout and function of the facility, and a proposal for the design of all individual parts of the repository. The relationships between the various parts of the repository are described, both above and below ground, as is the interplay between the part above ground and part

  20. Waste Management Systems Requirements and Descriptions (SRD)

    International Nuclear Information System (INIS)

    Conner, C.W.

    1986-01-01

    The Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a system for the management of high-level radioactive waste and spent fuel in accordance with the Nuclear Waste Policy Act of 1982. The Waste Management system requirements and description document is the program-level technical baseline document. The requirements include the functions that must be performed in order to achieve the system mission and performance criteria for those functions. This document covers only the functional requirements of the system; it does not cover programmatic or procedural requirements pertaining to the processes of designing, siting and licensing. The requirements are largely based on the Nuclear Waste Policy Act of 1982, Environmental Protection Agency standards, Nuclear Regulatory Commission regulations, and DOE orders and guidance. However, nothing in this document should be construed as to relieve the DOE or its contractors from their responsibilities to comply with applicable statutes, regulations, and standards. This document also provides a brief description of the system being developed to meet the requirements. In addition to the described ''authorized system,'' a system description is provided for an ''improved-performance system'' which would include a monitored retrievable storage (MRS) facility. In the event that an MRS facility is approved by Congress, the improved-performance system will become the reference system. Neither system description includes Federal Interim Storage (FIS) capabilities. Should the need for FIS be identified, it will be included as an additional system element. The descriptions are focused on the interfaces between the system elements, rather than on the detail of the system elements themselves

  1. ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

    2011-06-07

    Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear

  2. Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

    International Nuclear Information System (INIS)

    Hegde, A.G.; Verma, P.C.; Rajan, M.P.

    2009-02-01

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  3. Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hegde, A G; Verma, P C; Rajan, M P [Health Safety and Environment Group, Bhabha Atomic Research Centre, Mumbai (India)

    2009-02-15

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  4. Replacement Power Facility site selection report

    Energy Technology Data Exchange (ETDEWEB)

    Wike, L.D.; Toole, G.L.; Specht, W.L.

    1992-06-01

    The Department of Energy (DOE) has proposed the construction and operation of a Replacement Power Facility (RPF) for supplementing and replacing existing sources of steam and possibly electricity at the Savannah River Site (SRS). DOE is preparing an Environmental Impact Statement (EIS) for this project As part of the impact analysis of the proposed action, the EIS will include a detailed description of the environment where the RPF will be constructed. This description must be specific to the recommended site at SRS, which contains more than 300 square miles of land including streams, lakes, impoundments, wetlands, and upland areas. A formal site-selection process was designed and implemented to identify the preferred RPF site.

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    International Nuclear Information System (INIS)

    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

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. 77 FR 38077 - Notice of Intent To Prepare an Environmental Impact Statement on a Proposed Boat-House Facility...

    Science.gov (United States)

    2012-06-26

    ... DEPARTMENT OF THE INTERIOR National Park Service [NPS-NCR-GWMP-1202-9483: 3310-0250-471] Notice of Intent To Prepare an Environmental Impact Statement on a Proposed Boat-House Facility for Non-Motorized... identify a preferred site for construction of an environmentally sustainable facility for non-motorized...

  8. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  9. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    International Nuclear Information System (INIS)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

  10. Description of the terrestrial ecology of the Oak Ridge Environmental Research Park

    Energy Technology Data Exchange (ETDEWEB)

    Kitchings, T.; Mann, L.K.

    1976-10-01

    The Environmental Sciences Division at Oak Ridge National Laboratory has begun to develop research and administrative foundations necessary to establish and operate an Environmental Research Park (ERP) on the Energy Research and Development Administration Reservation at Oak Ridge, Tennessee. Important in developing a functional research area is a description and inventory of the species and ecosystems which comprise the Research Park. This report describes some of the floral and faunal components of the Oak Ridge Reservation. Emphasis is placed on the relationship of faunal communities to the vegetation type in which they occur. Unique vegetational areas and rare and endangered species are also discussed.

  11. Description of the terrestrial ecology of the Oak Ridge Environmental Research Park

    International Nuclear Information System (INIS)

    Kitchings, T.; Mann, L.K.

    1976-10-01

    The Environmental Sciences Division at Oak Ridge National Laboratory has begun to develop research and administrative foundations necessary to establish and operate an Environmental Research Park (ERP) on the Energy Research and Development Administration Reservation at Oak Ridge, Tennessee. Important in developing a functional research area is a description and inventory of the species and ecosystems which comprise the Research Park. This report describes some of the floral and faunal components of the Oak Ridge Reservation. Emphasis is placed on the relationship of faunal communities to the vegetation type in which they occur. Unique vegetational areas and rare and endangered species are also discussed

  12. Technical description - interim storage, encapsulation and disposal of spent nuclear fuel; Teknisk beskrivning - mellanlagring, inkapsling och slutfoervaring av anvaent kaernbraensle

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-15

    The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test

  13. Current significant challenges in the decommissioning and environmental remediation of radioactive facilities: A perspective from outside the nuclear industry.

    Science.gov (United States)

    Gil-Cerezo, V; Domínguez-Vilches, E; González-Barrios, A J

    2017-05-01

    This paper presents the results of implementing an extrajudicial environmental mediation procedure in the socioenvironmental conflict associated with routine operation of the El Cabril Disposal Facility for low- and medium- activity radioactive waste (Spain). We analyse the socio-ethical perspective of this facility's operation with regard to its nearby residents, detailing the structure and development of the environmental mediation procedure through the participation of society and interested parties who are or may become involved in such a conflict. The research, action, and participation method was used to apply the environmental mediation procedure. This experience provides lessons that could help improve decision-making processes in nuclear or radioactive facility decommissioning projects or in environmental remediation projects dealing with ageing facilities or with those in which nuclear or radioactive accidents/incidents may have occurred. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Environmental impact assessment for a radioactive waste facility: A case study

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

    A 77-ha site, known as the Niagara Falls Storage Site and located in northwestern New York State, holds about 190, 000 m 3 of soils, wastes, and residues contaminated with radium and uranium. The facility is owned by the US Department of Energy. The storage of residues resulting from the processing of uranium ores started in 1944, and by 1950 residues from a number of plants were received at the site. The residues, with a volume of about 18,000 m 3 , account for the bulk of the radioactivity, which is primarily due to Ra-226; because of the extraction of uranium from the ore, the amount of uranium remaining in the residues is quite small. An analysis of the environmental impact assessment and environmental compliance actions taken to date at this site and their effectiveness are discussed. This case study provides an illustrative example of the complexity of technical and nontechnical issues for a large radiative waste facility. 11 refs., 7 figs., 2 tabs

  15. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

    International Nuclear Information System (INIS)

    2015-01-01

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  16. Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii

    International Nuclear Information System (INIS)

    Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

    2005-01-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b)

  17. Environmental Audit of the Coal-Fired Flow Facility (CFFF)

    International Nuclear Information System (INIS)

    1992-12-01

    The scope of the audit at the CFFF was comprehensive, addressing environmental activities in the technical areas of air; soils, sediments, and biota; surface water/drinking water; groundwater; waste management; toxic and chemical materials; quality assurance; radiation; inactive waste sites; environmental management; and environmental monitoring programs. Specifically assessed was the compliance of CFFF operations and activities with Federal, state, and local regulations; DOE Orders; internal operating standards; and best management practices. Onsite activities included inspection of CFFF facilities and operations; review of site documents; interviews with DOE and contractor personnel, as well as representatives from state regulatory agencies; and reviews of previous appraisals. Using these sources of information, the environmental audit team developed findings, which fell into two general categories: compliance findings and best management practice findings. Each finding also identifies apparent causal factor(s) that contributedto the finding and will assist line management in developing ''root causes'' for implementing corrective actions. The overall conclusion of the audit is that The University of Space Institute's Energy Conversion Research and Development Programs (ECP) management of the CFFF has not kept pace with DOE's increasing expectation for environmental performance. ECP has not applied the same door and formality to environmental compliance and protection activities as they apply to their research and development activities.A total of 31 findings were identified in this audit

  18. System requirements and design description for the environmental requirements management interface (ERMI)

    International Nuclear Information System (INIS)

    Biebesheimer, E.

    1997-01-01

    This document describes system requirements and the design description for the Environmental Requirements Management Interface (ERMI). The ERMI database assists Tank Farm personnel with scheduling, planning, and documenting procedure compliance, performance verification, and selected corrective action tracking activities for Tank Farm S/RID requirements. The ERMI database was developed by Science Applications International Corporation (SAIC). This document was prepared by SAIC and edited by LMHC

  19. Nevada Test Site Environmental Report 2009, Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills, ed.

    2010-09-13

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  20. Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-04-01

    Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

  1. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  2. Configuration system development of site and environmental information for radwaste disposal facility

    International Nuclear Information System (INIS)

    Park, Se-Moon; Yoon, Bong-Yo; Kim, Chang-Lak

    2005-01-01

    License for the nuclear facilities such as radioactive waste repository demands documents of site characterization, environmental assessment and safety assessment. This performance will produce bulk of the relevant data. For the safe management of radioactive waste repository, data of the site and environment have to be collected and managed systematically. Particularly for the radwaste repository, which has to be institutionally controlled for a long period after closure, the data will be collected and maintained through the monitoring programme. To meet this requirement, a new programme called 'Site Information and Total Environmental data management System (SITES)' has been developed. The scope and function of the SITES is issued in data DB, safety assessment and monitoring system. In this respect, SITES is designed with two modules of the SITES Database Module (SDM) and the Monitoring and Assesment (M and A). The SDM module is composed of three sub-modules. One is the Site Information Management System (SIMS), which manages data of site characterization such as topography, geology, hydrogeology, engineering geology, etc. The other is the ENVironmental Information management System (ENVIS) and Radioactive ENVironmental Information management System (RENVIS), which manage environmental data required for environmental assessment performance. ENVIS and RENVIS covered almost whole items of environmental assessment report required by Korean government. The SDM was constructed based on Entity Relationship Diagram produced from each item. Also using ArcGIS with the spatial characteristics of the data, it enables groundwater and water property monitoring networks, etc. To be analyzed in respect of every theme. The sub-modules of M and A called the Site and Environment Monitoring System (SEMS) and the Safety Assessment System (SAS) were developed. SEMS was designed to manage the inspection records of the individual measuring instruments and facilities, and the on

  3. 2010 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Mike lewis

    2011-02-01

    This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2009, through October 31, 2010. The report contains the following information: • Site descriptionFacility and system description • Permit required monitoring data and loading rates • Status of special compliance conditions • Discussion of the facility’s environmental impacts. During the 2010 permit year, approximately 2.2 million gallons of treated wastewater was land-applied to the irrigation area at Central Facilities Area Sewage Treatment plant.

  4. Environmental Assessment for the LGF Spill Test Facility at Frenchman Flat, Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Patton, S.E.; Novo, M.G.; Shinn, J.H.

    1986-04-01

    The LGF Spill Test Facility at Frenchman Flat, Nevada Test Site, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated.

  5. Environmental Assessment for the LGF Spill Test Facility at Frenchman Flat, Nevada Test Site

    International Nuclear Information System (INIS)

    Patton, S.E.; Novo, M.G.; Shinn, J.H.

    1986-04-01

    The LGF Spill Test Facility at Frenchman Flat, Nevada Test Site, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated

  6. Programme for the Environmental Control at the Swedish Nuclear Facilities, Revision

    International Nuclear Information System (INIS)

    Linden, Ann-Marie

    2004-12-01

    This report contains a revised version of the Environmental Monitoring Programme for the Swedish Nuclear Facilities. The revision is based on earlier experiences and evaluations. Some samples have been excluded. Some have been added, for example spruce cone and the food products apple and currant. The sediment samples of 2 cm length have been completed with samples of 10 cm length every fourth year to follow the migration of radio nuclides down the sediment layers over time. The revised Environmental Monitoring Programme is valid from the 1st of January 2005

  7. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

    International Nuclear Information System (INIS)

    Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

    1991-09-01

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3

  8. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

    Energy Technology Data Exchange (ETDEWEB)

    Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

    1991-09-01

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3.

  9. 2013 Annual Site Environmental Report for Sandia National Laboratories Tonopah Test Range Nevada & Kauai Test Facility Hawaii

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, Stacy Rene [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Agogino, Karen [National Nuclear Security Administration (NNSA), Washington, DC (United States); Li, Jun [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); White, Nancy [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Minitrez, Alexandra [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Avery, Penny [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bailey-White, Brenda [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bonaguidi, Joseph [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Catechis, Christopher [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); duMond, Michael [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Eckstein, Joanna [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Evelo, Stacie [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Forston, William [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Herring, III, Allen [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Lantow, Tiffany [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Martinez, Reuben [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Mauser, Joseph [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Miller, Amy [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Miller, Mark [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Payne, Jennifer [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Peek, Dennis [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Reiser, Anita [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Ricketson, Sherry [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Roma, Charles [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Salinas, Stephanie [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Ullrich, Rebecca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2014-08-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities managed and operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Field Office (SFO), in Albuquerque, New Mexico, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Navarro Research and Engineering subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report summarizes data and the compliance status of the sustainability, environmental protection, and monitoring program at TTR and KTF through Calendar Year 2013. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, Environmental Restoration (ER) cleanup activities, and the National Environmental Policy Act. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Field Office retains responsibility for the cleanup and management of TTR ER sites. Environmental monitoring and surveillance programs are required by DOE Order 231.1B, Environment, Safety, and Health Reporting (DOE 2012).

  10. Canadian Environmental Assessment Act - comprehensive study report: new Grand-Mere hydroelectric facility proposed by Hydro-Quebec

    International Nuclear Information System (INIS)

    1999-06-01

    A description is given of the hydroelectric construction project as well as the environment surrounding it, the outcome of consultations with interest parties in the public, the overall environmental impacts and cumulative impacts with associated problems that may occur in carrying out the project, attempts at project and environmental mitigation, measuring the importance of the cumulative and environmental effects, conditions for project acceptance, and the overall acceptance of the project or its rejection. The older hydroelectric project was constructed in the post-1910 period and being out of date is experiencing operational problems. There are four problem areas that are important including a need for major repairs to the turbine-generators, lack of flexibility and low electrical capacity that affect the working of the sending-end substation, a state of deterioration affecting operation of the spillways concrete structure, and a bottleneck problem on the Saint-Maurice river caused by the low flow design of the Grand-Mere power station in comparison with that of the Saint-Maurice station. Considering economical, social and environmental factors, of the three options of abandoning the site, upgrading the existing site or constructing a new one, the third option is the preferred one, a conclusion based on considering the out of date state of Grand-Mere facilities and the bottleneck flow condition created on the Saint-Maurice river by the older station. Given the proposed efforts at mitigation, and the follow-up operations stated by the third option advocate, the Department of Fisheries and Oceans is of the opinion that the proposed plans will not affect the environment in an adverse manner. 7 refs

  11. A study on environmental regulation and public inquiry system of nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Chang Sun; Son, Ki Yon; Cho, Young Ho; Yang, Ji Won; Lee, Young Wook; Ko, Hyun Suk

    2000-03-01

    Public hearing system for domestic and foreign nuclear facilities are investigated and analyzed. As a result, Korean public hearing system are developed. Atomic Energy Act, Environmental Impact Assessment Act and Administrative Procedure Act of Korea are reviewed and appropriate acts, regulations, procedures and mandates of foreign countries including U.S.A are reviewed and analyzed. On the basis of these results the role of device to collect public opinion is identified for nuclear facility of Korea and the elementary principle of the system and recommendations are developed

  12. A study on environmental regulation and public inquiry system of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Kang, Chang Sun; Son, Ki Yon; Cho, Young Ho; Yang, Ji Won; Lee, Young Wook; Ko, Hyun Suk [Seoul National Univ., Seoul (Korea, Republic of)

    2000-03-15

    Public hearing system for domestic and foreign nuclear facilities are investigated and analyzed. As a result, Korean public hearing system are developed. Atomic Energy Act, Environmental Impact Assessment Act and Administrative Procedure Act of Korea are reviewed and appropriate acts, regulations, procedures and mandates of foreign countries including U.S.A are reviewed and analyzed. On the basis of these results the role of device to collect public opinion is identified for nuclear facility of Korea and the elementary principle of the system and recommendations are developed.

  13. Cold Vacuum Drying (CVD) Facility Vacuum Purge System Chilled Water System Design Description. System 47-4

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    This system design description (SDD) addresses the Vacuum Purge System Chilled Water (VPSCHW) system. The discussion that follows is limited to the VPSCHW system and its interfaces with associated systems. The reader's attention is directed to Drawings H-1-82162, Cold Vacuum Drying Facility Process Equipment Skid PandID Vacuum System, and H-1-82224, Cold Vacuum Drying Facility Mechanical Utilities Process Chilled Water PandID. Figure 1-1 shows the location and equipment arrangement for the VPSCHW system. The VPSCHW system provides chilled water to the Vacuum Purge System (VPS). The chilled water provides the ability to condense water from the multi-canister overpack (MCO) outlet gases during the MCO vacuum and purge cycles. By condensing water from the MCO purge gas, the VPS can assist in drying the contents of the MCO

  14. Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

  15. Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    International Nuclear Information System (INIS)

    1994-06-01

    DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft 2 waste storage facility for RCRA waste, one 42,000 ft 2 waste storage facility for toxic waste (TSCA), and one 200,000 ft 2 mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required

  16. Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

    International Nuclear Information System (INIS)

    Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

    2016-01-01

    This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. 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 program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 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. The appendix contains a list of frequently used acronyms and abbreviations.

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    International Nuclear Information System (INIS)

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

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. 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 program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 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. The appendix contains a list of frequently used acronyms and abbreviations

  19. ATLAS Facility and Instrumentation Description Report

    International Nuclear Information System (INIS)

    Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik

    2009-06-01

    A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating looptype. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations which are specific to the simulation of 50% DVI line break accident of the APR1400 for supporting the 50 th OECD/NEA International Standard Problem Exercise (ISP-50)

  20. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, Marcel Y.; Gervais, Todd L.

    2004-11-15

    located downstream of control technologies and just before discharge to the atmosphere. The need for monitoring airborne emissions of hazardous chemicals is established in the Hanford Site Air Operating Permit and in notices of construction. Based on the current potential-to-emit, the Hanford Site Air Operating Permit does not contain general monitoring requirements for BOP facilities. However, the permit identifies monitoring requirements for specific projects and buildings. Needs for future monitoring will be established by future permits issued pursuant to the applicable state and federal regulations. A number of liquid-effluent discharge systems serve the BOP facilities: sanitary sewer, process sewer, retention process sewer, and aquaculture system. Only the latter system discharges to the environment; the rest either discharge to treatment plants or to long-term storage. Routine compliance sampling of liquid effluents is only required at the Environmental Molecular Sciences Laboratory. Liquid effluents from other BOP facilities may be sampled or monitored to characterize facility effluents or to investigate discharges of concern. Effluent sampling and monitoring for the BOP facilities depends on the inventories, activities, and environmental permits in place for each facility. A description of routine compliance monitoring for BOP facilities is described in the BOP FEMP.

  1. Radiation protection and environmental surveillance programme in and around Nuclear Fuel Cycle Facilities in India

    International Nuclear Information System (INIS)

    Tripathi, R.M.

    2018-01-01

    Radiation safety is an integral part of the operation of the Indian nuclear fuel cycle facilities and safety culture has been inculcated in all the spheres of its operation. Nuclear fuel cycle comprises of mineral exploration, mining, ore processing, fuel fabrication, power plants, reprocessing, waste management and accelerator facilities. Health Physics Division of BARC is entrusted with the responsibility of radiation protection and environmental surveillance in all the nuclear fuel cycle facilities

  2. The Saskatchewan Environmental Assessment Act Guide to Proposal Development : oil and natural gas projects

    International Nuclear Information System (INIS)

    1999-02-01

    The manner in which requests for review of oil and natural gas projects are to be provided under the Environmental Assessment Act in Saskatchewan is described. The provisions of the Guide apply to all seismic projects on private or Crown lands, all drilling projects, flowline projects, access routes and production facilities on any land, except where the project is on cultivated land where it does not interfere with water bodies or endangered species. It also applies to any project that has the potential to meet the definition of 'development' under the Environmental Assessment Act. Basically, the following information is required for all proposals: (1) project description, (2) project evaluation, (3) description of proposed waste management practices, and (4) description of the proposed environmental monitoring. 4 refs

  3. Final environmental impact statement. Proton--Proton Storage Accelerator Facility (ISABELLE), Brookhaven National Laboratory, Upton, New York

    International Nuclear Information System (INIS)

    1978-08-01

    An Environmental Impact Statement for a proposed research facility (ISABELLE) to be built at Brookhaven National Laboratory (BNL) is presented. It was prepared by the Department of Energy (DOE) following guidelines issued for such analyses. In keeping with DOE policy, this statement presents a concise and issues-oriented analysis of the significant environmental effects associated with the proposed action. ISABELLE is a proposed physics research facility where beams of protons collide providing opportunities to study high energy interactions. The facility would provide two interlaced storage ring proton accelerators, each with an energy up to 400 GeV intersecting in six experimental areas. The rings are contained in a tunnel with a circumference of 3.8 km (2.3 mi). The facility will occupy 250 ha (625 acres) in the NW corner of the existing BNL site. A draft Environmental Impact Statement for this proposed facility was issued for public review and comment by DOE on February 21, 1978. The principal areas of concern expressed were in the areas of radiological impacts and preservation of cultural values. After consideration of these comments, appropriate actions were taken and the text of the statement has been amended to reflect the comments. The text was annotated to indicate the origin of the comment. The Appendices contain a glossary of terms and listings of metric prefixes and conversions and symbols and abbreviations

  4. The Green Dialysis Survey: Establishing a Baseline for Environmental Sustainability across Dialysis Facilities in Victoria, Australia.

    Science.gov (United States)

    Barraclough, Katherine A; Gleeson, Alice; Holt, Stephen G; Agar, John Wm

    2017-11-02

    The Green Dialysis Survey aimed to 1) establish a baseline for environmental sustainability (ES) across Victorian dialysis facilities, and 2) guide future initiatives to reduce the environmental impact of dialysis delivery. Nurse unit managers of all Victorian public dialysis facilities received an online link to the survey, which asked 107 questions relevant to the ES of dialysis services. Responses were received from 71/83 dialysis facilities in Victoria (86%), representing 628/660 dialysis chairs (95%). Low energy lighting was present in 13 facilities (18%), 18 (25%) recycled reverse osmosis water and 7 (10%) reported use of renewable energy. Fifty-six facilities (79%) performed comingled recycling but only 27 (38%) recycled polyvinyl chloride plastic. A minority educated staff in appropriate waste management (n=30;42%) or formally audited waste generation and segregation (n=19;27%). Forty-four (62%) provided secure bicycle parking but only 33 (46%) provided shower and changing facilities. There was limited use of tele- or video-conferencing to replace staff meetings (n=19;27%) or patient clinic visits (n=13;18%). A minority considered ES in procurement decisions (n=28;39%) and there was minimal preparedness to cope with climate change. Only 39 services (49%) confirmed an ES policy and few had ever formed a green group (n=14; 20%) or were currently undertaking a green project (n=8;11%). Only 15 facilities (21%) made formal efforts to raise awareness of ES. This survey provides a baseline for practices that potentially impact the environmental sustainability of dialysis units in Victoria, Australia. It also identifies achievable targets for attention. This article is protected by copyright. All rights reserved.

  5. Artificial climate experiment facility in Institute for Environmental Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Hisamatsu, Shunichi [Department of Radioecology, Institute for Environmental Sciences, Rokkasho, Aomori (Japan)

    1999-03-01

    The Institute for Environmental Sciences is now constructing the artificial climate experiment facility (ACEF) to research the effect of climate on movement of elements in the various environments. The ACEF will have one large, and five small artificial climate experiment chambers. The large chamber is designed to simulate climate conditions in all Japan. It will equip systems to simulate sunshine, rainfall (including acid rain), snowfall and fog (including acid fog). `Yamase` condition will also be reproduced in it. Yamase is a Japanese term describing the characteristic weather condition occurring mainly on the Pacific Ocean side at the northern Japan. While the small chamber will not have rainfall, snowfall and fog systems, radioisotopes will be used in the two small chambers which will be set up in a radioisotope facility. We describe here the outline of the ACEF and the preliminary research programs being undertaken using both kinds of chambers. (author)

  6. Artificial climate experiment facility in Institute for Environmental Sciences

    International Nuclear Information System (INIS)

    Hisamatsu, Shunichi

    1999-01-01

    The Institute for Environmental Sciences is now constructing the artificial climate experiment facility (ACEF) to research the effect of climate on movement of elements in the various environments. The ACEF will have one large, and five small artificial climate experiment chambers. The large chamber is designed to simulate climate conditions in all Japan. It will equip systems to simulate sunshine, rainfall (including acid rain), snowfall and fog (including acid fog). 'Yamase' condition will also be reproduced in it. Yamase is a Japanese term describing the characteristic weather condition occurring mainly on the Pacific Ocean side at the northern Japan. While the small chamber will not have rainfall, snowfall and fog systems, radioisotopes will be used in the two small chambers which will be set up in a radioisotope facility. We describe here the outline of the ACEF and the preliminary research programs being undertaken using both kinds of chambers. (author)

  7. Radiocesium Discharges and Subsequent Environmental Transport at the Major U.S. Weapons Production Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Garten, Jr. C.T.; Hamby, D.M.; Schreckhise, R.G.

    1999-11-14

    Radiocesium is one of the more prevalent radionuclides in the environment as a result of weapons production related atomic projects in the United States and the former Soviet Union. Radiocesium discharges during the 1950's account for a large fraction of the historical releases from U.S. weapons production facilities. Releases of radiocesium to terrestrial and aquatic ecosystems during the early ,years of nuclear weapons production provided the opportunity to conduct multidisciplinary studies on the transport mechanisms of this potentially hazardous radionuclide. The major U.S. Department of Energy facilities (Oak Ridge Reservation in Tennessee, Hanford Site near Richland, Washington, and Savannah River Site near Aiken, South Carolina) are located in regions of the country that have different geographical characteristics. The facility siting provided diverse backgrounds for the development of an understanding of environmental factors contributing to the fate and transport of radiocesium. In this paper, we summarize the significant environmental releases of radiocesium in the early -years of weapons production and then discuss the historically significant transport mechanisms for r37Cs at the three facilities that were part of the U.S. nuclear weapons complex.

  8. Database for environmental monitoring in nuclear facilities

    International Nuclear Information System (INIS)

    Raceanu, Mircea; Varlam, Carmen; Iliescu, Mariana; Enache, Adrian; Faurescu, Ionut

    2006-01-01

    To ensure that an assessment could be made of the impact of nuclear facilities on the local environment, a program of environmental monitoring must be established well before of nuclear facility commissioning. Enormous amount of data must be stored and correlated starting with: location, meteorology, type sample characterization from water to different kind of foods, radioactivity measurement and isotopic measurement (e.g. for C-14 determination, C-13 isotopic correction it is a must). Data modelling is a well known mechanism describing data structures at a high level of abstraction. Such models are often used to automatically create database structures, and to generate the code structures used to access the databases. This has the disadvantage of losing data constraints that might be specified in data models for data checking. Embodiment of the system of the present application includes a computer-readable memory for storing a definitional data table for defining variable symbols representing the corresponding measurable physical quantities. Developing a database system implies setting up well-established rules of how the data should be stored and accessed what is commonly called the Relational Database Theory. This consists of guidelines regarding issues as how to avoid duplicating data using the technique called normalization and how to identify the unique identifier for a database record. (authors)

  9. Discussion of some issues in environmental impact reports of nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Pan Ziqiang

    1995-01-01

    The author discusses some issues in compilation and evaluation of environmental impact reports of nuclear and radiation facilities which should be noticeable. Some recommendations are made to improve the quality of the reports as well

  10. Nevada Test Site Environmental Report 2008 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2009-09-01

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  11. Nevada Test Site Environmental Report 2007 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills

    2008-09-01

    This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  12. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    International Nuclear Information System (INIS)

    Cathy A. Wills

    2006-01-01

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report

  13. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy A. Wills

    2006-10-01

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  14. Calendar year 2007 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii,

    Energy Technology Data Exchange (ETDEWEB)

    Agogino, Karen [Department of Energy, Albuquerque, NM (United States). National Nuclear Security Administration (NNSA); Sanchez, Rebecca [Sandia Corp., Albuquerque, NM (United States)

    2008-09-30

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation (Sandia), a wholly owned subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE)/National Nuclear Security Administration (NNSA), through the Sandia Site Offi ce (SSO), in Albuquerque, NM, administers the contract and oversees contractor operations at TTR and KTF. Sandia manages and conducts operations at TTR in support of the DOE/NNSA’s Weapons Ordnance Program and has operated the site since 1957. Washington Group International subcontracts to Sandia in administering most of the environmental programs at TTR. Sandia operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2007. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia is responsible only for those environmental program activities related to its operations. The DOE/NNSA/Nevada Site Offi ce (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2007a) and DOE Manual 231.1-1A, Environment, Safety, and Health Reporting Manual (DOE 2007).

  15. Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

    2003-09-01

    Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

  16. Environmental restoration contractor facility safety plan -- MO-561 100-D site remediation project

    International Nuclear Information System (INIS)

    Donahoe, R.L.

    1996-11-01

    This safety plan is applicable to Environmental Restoration Contractor personnel who are permanently assigned to MO-561 or regularly work in the facility. The MO-561 Facility is located in the 100-D Area at the Hanford Site in Richland, Washington. This plan will: (a) identify hazards potentially to be encountered by occupants of MO-561; (b) provide requirements and safeguards to ensure personnel safety and regulatory compliance; (c) provide information and actions necessary for proper emergency response

  17. Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

    Energy Technology Data Exchange (ETDEWEB)

    Tonnessen, K.; Tewes, H.A.

    1982-08-01

    The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

  18. Berkeley Nuclear Laboratories Reactor Physics Mk. III Experimental Programme. Description of facility and programme for 1971

    Energy Technology Data Exchange (ETDEWEB)

    Nunn, R M; Waterson, R H; Young, J D

    1971-01-15

    Reactor physics experiments have been carried out at Berkeley Nuclear Laboratories during the past few years in support of the Civil Advanced Gas-Cooled Reactors (Mk. II) the Generating Board is building. These experiments are part of an overall programme whose objective is to assess the accuracy of the calculational methods used in the design and operation of these reactors. This report provides a description of the facility for the Mk. III experimental programme and the planned programme for 1971.

  19. Heber Ethanol Fuel Facility, Imperial Valley, California. Quarterly report No. 2, March 1981-May 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The purposed project is a commercial-scale ethanol-fuel facility with a capacity of twenty million gallons per year of fuel-grade ethanol. In addition, 70,000 tons per year of distillers dried grains will be produced. The following tasks and issues are addressed: process engineering - process descriptions, plant layout, and design; economics and finance - overview of capital and operating costs; environmental analysis - preliminary project description; and permit processing and legal issues. (MHR)

  20. Facility model for the Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

    1986-01-01

    The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

  1. Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    1986-02-01

    This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs

  2. 1995 Baseline solid waste management system description

    International Nuclear Information System (INIS)

    Anderson, G.S.; Konynenbelt, H.S.

    1995-09-01

    This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

  3. Environmental risk analysis of oil handling facilities in port areas. Application to Tarragona harbor (NE Spain).

    Science.gov (United States)

    Valdor, Paloma F; Gómez, Aina G; Puente, Araceli

    2015-01-15

    Diffuse pollution from oil spills is a widespread problem in port areas (as a result of fuel supply, navigation and loading/unloading activities). This article presents a method to assess the environmental risk of oil handling facilities in port areas. The method is based on (i) identification of environmental hazards, (ii) characterization of meteorological and oceanographic conditions, (iii) characterization of environmental risk scenarios, and (iv) assessment of environmental risk. The procedure has been tested by application to the Tarragona harbor. The results show that the method is capable of representing (i) specific local pollution cases (i.e., discriminating between products and quantities released by a discharge source), (ii) oceanographic and meteorological conditions (selecting a representative subset data), and (iii) potentially affected areas in probabilistic terms. Accordingly, it can inform the design of monitoring plans to study and control the environmental impact of these facilities, as well as the design of contingency plans. Copyright © 2014 Elsevier Ltd. All rights reserved.

  4. Final environmental assessment and Finding-of-No-Significant-Impact - drum storage facility for interim storage of materials generated by environmental restoration operations

    International Nuclear Information System (INIS)

    1994-09-01

    The Department of Energy (DOE) has prepared an Environmental Assessment (EA), DOE/EA-0995, for the construction and operation of a drum storage facility at Rocky Flats Environmental Technology Site, Golden, Colorado. The proposal for construction of the facility was generated in response to current and anticipated future needs for interim storage of waste materials generated by environmental restoration operations. A public meeting was held on July 20, 1994, at which the scope and analyses of the EA were presented. The scope of the EA included evaluation of alternative methods of storage, including no action. A comment period from July 5, 1994 through August 4, 1994, was provided to the public and the State of Colorado to submit written comment on the EA. No written comments were received regarding this proposed action, therefore no comment response is included in the Final EA. Based on the analyses in the EA, DOE has determined that the proposed action would not significantly affect the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an Environmental Impact Statement is not required and the Department is issuing this Finding of No Significant Impact

  5. Evolution of authorised limits for environmental releases from nuclear facilities in India

    International Nuclear Information System (INIS)

    Subramanian, Chitra; Narayanan, K.K.; Sharma, R.M.

    2002-01-01

    Full text: The controlled environmental releases of radioactive effluents from any nuclear facility is primarily based on the effective dose limits for the general public, recommended by the international commission on radiation protection (ICRP). To meet the dose limit criteria for members of the public, regulatory-limits are set for the discharges of radioactive effluents from nuclear facilities, which are known as the authorised limits (ALs). The paper presents the evolution of ALs in India applicable to nuclear power plant sites, starting from Tarapur Atomic Power Station (TAPS) commissioned in 1969, when the dose limit used to be 5 mSv/yr for the public, to the present generation pressurised heavy water reactors, when the population dose limit has been revised downward to 1 mSv/yr. The paper also presents the changes in the philosophy of dose apportionment for multifacility sites like Tarapur, Rawatbhata and Kalpakkam over the years. The operating experience with respect to environmental discharges from operating nuclear power plants (NPPs) in the country was reviewed vis-a-vis the applicable discharge limits, which shows that the actual releases constitute only a small percentage of the discharge limits. A strong case for lowering the dose apportionment for NPPs is suggested on the basis of latest data on site meteorology, dosimetry of radionuclides and environmental dose assessment methodology and operating experience. It is established in the paper that there is scope for reduction in the dose apportionment of NPPs for most of the radionuclides, without major changes in the existing discharge limits. The lowering of dose apportionment will be critically important at multifacility sites like Tarapur, Rawatbhata and Kalpakkam where many new facilities are being planned. At present the dose reserve available at these sites is only 0.14 mSv/yr, 0.06 mSv/yr and 0.16 mSv/yr, respectively at Tarapur, Rawatbhata and Kalpakkam. With the programme of siting

  6. Environmental risk assessment for start-up of a new consolidated maintenance facility

    Energy Technology Data Exchange (ETDEWEB)

    Heubach, J.G.; Wise, J.A.

    1992-10-01

    This paper summarizes a case study of a risk assessment for a consolidated maintenance facility (CMF). An interdisciplinary team was formed to identify and evaluate showstopper'' risks which could delay or prevent ontime, safe, and economical operation of a CMF and to recommend ways to mitigate the risks. The risk assessment was constrained by time, information, incomplete plans and facilities, and a concomitant major transition in manufacturing process, organization, and technology. Working within these constraints, the team integrated convergent findings into estimates of high, medium, and low risks based on the subjective likelihood of occurrence and predicted consequences of potential hazard events. The team also made risk-reduction recommendations for facility detail design and production start-up. The findings and recommendations reported in this study focus on risks related to environmental design and workstation ergonomics. Findings from the risk assessment effort should aid other constrained risk assessments and applied research on similar facilities.

  7. INEL environmental characterization report. Volume I. Summary

    International Nuclear Information System (INIS)

    1984-09-01

    This environmental characterization report contains general information on environmental aspects of the INEL, and specific information on two areas within the INEL which have been tentatively selected for NPR siting. The objective is to present environmental information but not assess environmental impacts. Impacts will be addressed specifically at a later date when an EIS is prepared. The information in this report will be used to evaluate the siting of various reactor types at each of the three reservation alternatives. The report covers geography, physiography, and demography of the INEL, ecology, climatology overview, geology and seismology, hydrology, cultural resources assessment, baseline socioeconomic data, description of INEL facilities and capabilities, effluent and environmental measurements and monitoring programs, exposure pathways, and environmental laws and regulations

  8. Waste minimization and the goal of an environmentally benign plutonium processing facility: A strategic plan

    International Nuclear Information System (INIS)

    Pillay, K.K.S.

    1994-02-01

    To maintain capabilities in nuclear weapons technologies, the Department of Energy (DOE) has to maintain a plutonium processing facility that meets all the current and emerging standards of environmental regulations. A strategic goal to transform the Plutonium Processing Facility at Los Alamos into an environmentally benign operation is identified. A variety of technologies and systems necessary to meet this goal are identified. Two initiatives now in early stages of implementation are described in some detail. A highly motivated and trained work force and a systems approach to waste minimization and pollution prevention are necessary to maintain technical capabilities, to comply with regulations, and to meet the strategic goal

  9. Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

    International Nuclear Information System (INIS)

    Liverman, J.L.

    1977-09-01

    This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

  10. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Westinghouse Electric Company Waste Isolation Division

    1999-01-01

    DOE Order 5400.1, General Environmental Protection Program Requirements (DOE, 1990a), requires each DOE facility to prepare an EMP. This document is prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment (DOE, 1990b); Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) 834, Radiation Protection of the Public and Environment (Draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1 (DOE, 1995), which is the driver for the Annual Site Environmental Report (ASER) and the guidance source for preparing many environmental program documents. The WIPP project is operated by Westinghouse Electric Company, Waste Isolation Division (WID), for the DOE. This plan defines the extent and scope of the WIPP's effluent and environmental monitoring programs during the facility's operational life and also discusses the WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE, 1991). This document references DOE orders and other federal and state regulations affecting environmental monitoring programs at the site. WIPP procedures, which implement

  11. Nevada National Security Site Environmental Report 2011 Attachment A: Site Description

    International Nuclear Information System (INIS)

    Wills, Cathy

    2012-01-01

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2011. Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  12. Generic description of facilities at the shaft head (auxiliary entrance installations) of deep geological repositories

    International Nuclear Information System (INIS)

    2016-10-01

    In a deep geological repository, the access structures function as the link between the surface and the installations and structures at the disposal level. In the planned implementation scenarios, at least two access structures will be in operation up to the time of closure of the repository. The radioactive waste will be transported via the main access from the surface to the disposal level during emplacement operations. For the construction and operation of a deep geological repository, additional access structures are required. These auxiliary accesses and the associated surface infrastructure (e.g. shaft head installations) form the subject of this report. To provide as broad and comprehensive a description as possible, seven types of auxiliary access facilities are defined; these are characterised in line with the current status of planning and their functions and impacts are described. During construction, operation and dismantling of auxiliary access facilities, the usual conventional safety measures (inter alia) have to be observed (e.g. groundwater protection, fire prevention, facility security, accident prevention). Regarding the 'Ordinance on Protection against Major Accidents' no large quantities of hazardous materials, i.e. above the corresponding threshold quantities, are to be expected in the auxiliary access facilities. Proper handling and compliance with applicable regulations in all phases will ensure no hazard to humans and the environment. As no handling of radioactive materials is foreseen in the auxiliary access facilities, and because exhaust air and waste water from the controlled zones of a repository will, in principle, be removed via the main access and not the auxiliary accesses, a safety-relevant emission of radioactive substances and transport of contaminated material can be ruled out for the auxiliary access facilities during both normal operation and also in the case of an accident. Based on the information presented in

  13. Database for environmental monitoring at nuclear facilities

    International Nuclear Information System (INIS)

    Raceanu, M.; Varlam, C.; Enache, A.; Faurescu, I.

    2006-01-01

    To ensure that an assessment could be made of the impact of nuclear facilities on the local environment, a program of environmental monitoring must be established well in advance of nuclear facilities operation. Enormous amount of data must be stored and correlated starting with: location, meteorology, type sample characterization from water to different kind of food, radioactivity measurement and isotopic measurement (e.g. for C-14 determination, C-13 isotopic correction it is a must). Data modelling is a well known mechanism describing data structures at a high level of abstraction. Such models are often used to automatically create database structures, and to generate code structures used to access databases. This has the disadvantage of losing data constraints that might be specified in data models for data checking. Embodiment of the system of the present application includes a computer-readable memory for storing a definitional data table for defining variable symbols representing respective measurable physical phenomena. The definitional data table uniquely defines the variable symbols by relating them to respective data domains for the respective phenomena represented by the symbols. Well established rules of how the data should be stored and accessed, are given in the Relational Database Theory. The theory comprise of guidelines such as the avoidance of duplicating data using technique call normalization and how to identify the unique identifier for a database record. (author)

  14. Investigating walking environments in and around assisted living facilities: a facility visit study.

    Science.gov (United States)

    Lu, Zhipeng

    2010-01-01

    This study explores assisted living residents' walking behaviors, locations where residents prefer to walk, and walking environments in and around assisted living facilities. Regular walking is beneficial to older adults' physical and psychological health. Yet frail older residents in assisted living are usually too sedentary to achieve these benefits. The physical environment plays an important role in promoting physical activity. However, there is little research exploring this relationship in assisted living settings. The researcher visited 34 assisted living facilities in a major Texas city. Methods included walk-through observation with the Assisted Living Facility Walking Environment Checklist, and interviews with administrators by open- and close-ended questions. The data from 26 facilities were analyzed using descriptive statistics (for quantitative data) and content analysis (for qualitative data). The results indicate that (a) residents were walking both indoors and outdoors for exercise or other purposes (e.g., going to destinations); (b) assisted living facility planning and design details-such as neighborhood sidewalk conditions, facility site selection, availability of seating, walking path configuration (e.g., looped/nonlooped path), amount of shading along the path, presence of handrails, existence of signage, etc.-may influence residents' walking behaviors; and (c) current assisted living facilities need improvement in all aspects to make their environments more walkable for residents. Findings of the study provide recommendations for assisted living facilities to improve the walkability of environments and to create environmental interventions to promote regular walking among their residents. This study also implies several directions for future research.

  15. 76 FR 51957 - Notice of Intent To Prepare an Environmental Impact Statement for the Medical Facilities...

    Science.gov (United States)

    2011-08-19

    ... Statement for the Medical Facilities Development and University Expansion at Naval Support Activity Bethesda...: Notice. SUMMARY: Pursuant to section (102)(2)(c) of the National Environmental Policy Act (NEPA) of 1969, the regulations implemented by the Council on Environmental Quality (40 Code of Federal Regulations...

  16. The transportation operations system: A description

    International Nuclear Information System (INIS)

    Best, R.E.; Danese, F.L.; Dixon, L.D.; Peterson, R.W.; Pope, R.B.

    1990-01-01

    This paper presents a description of the system for transporting radioactive waste that may be deployed to accomplish the assigned system mission, which includes accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from waste generator sites and transporting them to the FWMS destination facilities. The system description presented here contains, in part, irradiated fuel and waste casks, ancillary equipments, truck, rail, and barge transporters, cask and vehicle traffic management organizations, maintenance facilities, and other operations elements. The description is for a fully implemented system, which is not expected to be achieved, however, until several years after initial operations. 6 figs

  17. A Study on an appropriate operating system of environmental basic facility service industry

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Hyun Joo [Korea Environment Institute, Seoul (Korea)

    1998-12-01

    The environmental basic facility service industry is designed to have a structural reorganization of general operating system and the efficient and effective participation of private industry and regulation of industry in connection with the general system. 35 refs., 9 figs., 20 tabs.

  18. Facility overview for commercial application of selected Rocky Flats facilities

    International Nuclear Information System (INIS)

    1996-11-01

    The purpose of this Facility Overview is to support the Rocky Flats Local Impacts Initiative's Request for Interest, to solicit interest from commercial corporations for utilizing buildings 865 and 883, and the equipment contained within each building, for a commercial venture. In the following sections, this document describes the Rocky Flats Site, the buildings available for lease, the equipment within these buildings, the site services available to a tenant, the human resources available to support operations in buildings 865 and 883, and the environmental condition of the buildings and property. In addition, a brief description is provided of the work performed to date to explore the potential products that might be manufactured in Buildings 865 and 883, and the markets for these products

  19. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S ampersand M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed

  20. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S. III; Baum, J.W.

    1998-03-01

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

  1. Integrated numerical platforms for environmental dose assessments of large tritium inventory facilities

    International Nuclear Information System (INIS)

    Castro, P.; Ardao, J.; Velarde, M.; Sedano, L.; Xiberta, J.

    2013-01-01

    Related with a prospected new scenario of large inventory tritium facilities [KATRIN at TLK, CANDUs, ITER, EAST, other coming] the prescribed dosimetric limits by ICRP-60 for tritium committed-doses are under discussion requiring, in parallel, to surmount the highly conservative assessments by increasing the refinement of dosimetric-assessments in many aspects. Precise Lagrangian-computations of dosimetric cloud-evolution after standardized (normal/incidental/SBO) tritium cloud emissions are today numerically open to the perfect match of real-time meteorological-data, and patterns data at diverse scales for prompt/early and chronic tritium dose assessments. The trends towards integrated-numerical-platforms for environmental-dose assessments of large tritium inventory facilities under development.

  2. Summary description of the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Cabell, C.P.

    1980-12-01

    This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like

  3. 2013 Annual Wastewater Reuse Report for the Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at the Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2012, through October 31, 2013. The report contains, as applicable, the following information: • Site descriptionFacility and system description • Permit required monitoring data and loading rates • Status of compliance conditions and activities • Discussion of the facility’s environmental impacts. During the 2013 permit year, no wastewater was land-applied to the irrigation area of the Central Facilities Area Sewage Treatment Plant and therefore, no effluent flow volumes or samples were collected from wastewater sampling point WW-014102. However, soil samples were collected in October from soil monitoring unit SU-014101.

  4. Environmental performances of different configurations of a material recovery facility in a life cycle perspective.

    Science.gov (United States)

    Ardolino, Filomena; Berto, Chiara; Arena, Umberto

    2017-10-01

    The study evaluated the environmental performances of an integrated material recovery facility (MRF) able to treat 32kt/y of unsorted mixed waste, made of residuals from household source separation and separate collection. The facility includes a mechanical sorting platform for the production of a solid recovered fuel (SRF) utilized in an external waste-to-energy plant, bio-cells for tunnel composting of organic fraction, and a sanitary landfill for the safe disposal of ultimate waste. All the MRF sub-units have been analysed in depth in order to acquire reliable data for a life cycle assessment study, focused on the environmental performances of different configurations of the facility. The study investigated a "past" configuration, including just mechanical sorting, landfilling and biogas combustion in a gas engine, and the "present" one, which includes also a composting unit. Two possible "future" configurations, having a gasifier inside the MRF battery limits, have been also analysed, assessing the performances of two fluidized bed reactors of different size, able to gasify only the residues generated by the sorting platform or the whole amount of produced SRF, respectively. The analysis evaluated the contributions of each unit in the different configurations and allowed a reliable assessment of the technological evolution of the facility. The results quantified the positive effect of the inclusion of an aerobic treatment of the waste organic fraction. The SRF gasification in situ appears to improve the MRF environmental performances in all the impact categories, with the exclusion of that of global warming. Copyright © 2017 Elsevier Ltd. All rights reserved.

  5. Low background germanium detectors: From environmental laboratory to underground counting facility

    Energy Technology Data Exchange (ETDEWEB)

    Ceuppens, M [Canberra Semiconductor N.V., Geel (Belgium); [Canberra Industries, Inc., Meriden (United States); Verplancke, J [Canberra Semiconductor N.V., Geel (Belgium); [Canberra Industries, Inc., Meriden (United States); Tench, O [Canberra Semiconductor N.V., Geel (Belgium); [Canberra Industries, Inc., Meriden (United States)

    1997-03-01

    Presentation and overview of different Low Level measuring systems ranging from the environmental lab to low-background detection systems and to the deep underground counting facility. Examples and performances for each of these will be given. Attention will be given to the standardised ultra low-background detectors and shields which provide excellent performance without the high cost in time and money associated with custom designed systems. (orig./DG)

  6. Low background germanium detectors: From environmental laboratory to underground counting facility

    International Nuclear Information System (INIS)

    Ceuppens, M.; Verplancke, J.; Tench, O.

    1997-01-01

    Presentation and overview of different Low Level measuring systems ranging from the environmental lab to low-background detection systems and to the deep underground counting facility. Examples and performances for each of these will be given. Attention will be given to the standardised ultra low-background detectors and shields which provide excellent performance without the high cost in time and money associated with custom designed systems. (orig./DG)

  7. A summary of the geotechnical and environmental investigations pertaining to the Vaalputs national radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Hambleton-Jones, B.B.; Levin, M.; Camisani-Calzolari, F.A.G.M.

    1986-08-01

    This report describes the geological environmental surveys that lead to the choice and final evaluation of the Vaalputs national facility for the disposal of radioactive waste. This survey looked at the geography, demography, ecology, meteorology, geology, geohydrology and background radiological characteristics of the Vaalputs radioactive waste facility

  8. Atomics International environmental monitoring and facility effluent annual report, 1976

    International Nuclear Information System (INIS)

    Moore, J.D.

    1977-01-01

    Environmental and facility effluent radioactivity monitoring at Atomics International (AI) is performend by the Radiation and Nuclear Safety Unit of the Health, Safety, and Radiation Services Department. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from AI sites. Continuous ambient air sampling and thermoluminescent dosimetry are performed on site for monitoring airborne radioactivity and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from AI facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituents in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1976. The results of a special soil plutonium survey performed during the year are also summarized

  9. Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs

  10. Nevada National Security Site Environmental Report 2011 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Cathy Wills, ed.

    2012-09-12

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2011. Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  11. Nevada National Security Site Environmental Report 2012 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Wills, Cathy A

    2013-09-11

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2012 (National Security Technologies, LLC [NSTec], 2013). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  12. Nevada National Security Site Environmental Report 2016, Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Wills, Cathy [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

    2017-09-07

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2016 (prepared by National Security Technologies, LLC [NSTec], 2017). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological settings and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  13. Nevada National Security Site Environmental Report 2013 Attachment A: Site Description

    Energy Technology Data Exchange (ETDEWEB)

    Wills, C.

    2014-09-09

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2012 (National Security Technologies, LLC [NSTec], 2013). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  15. Objectives, Extent and Organization of Radiological and Environmental Protection in Relation to the Nature and Size of Nuclear Facilities

    International Nuclear Information System (INIS)

    Kathren, R.L.

    1979-01-01

    Radiological and environmental protection programs for nuclear facilities have similar goals and objectives, which are basically to protect people and the environment from adverse effects. To be effective, the programs must have organizational independence and a strong commitment from management. In return, the programs should ensure that the facility is operating in full compliance with law and good practice. The scope and elements of radiological environmental protection programs will vary according to facility type and size, with the larger and more complex facilities having a diversity of staff and functions. Examples of good and poor organization charts are given and discussed from the standpoint of program effectiveness along with a discussion of the role of the radiation protection committee. (author)

  16. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W.

    1998-01-01

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report

  17. Hanford site near-facility environmental monitoring annual report, calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, C.J.

    1997-08-05

    This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

  18. Use of nuclear facilities at Argonne-West to support new environmental missions

    International Nuclear Information System (INIS)

    Black, D.B.; Dwight, C.C.; Lineberry, M.J.

    1994-08-01

    At Argonne National Laboratory-West, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used to meet the environmental and waste management need of the US Department of Energy. These needs include waste characterization, waste testing, and waste treatment technology development. Waste characterization and repackaging activities are being performed in the Hot Fuel Examination Facility for the Waste Isolation Pilot Plant (WIPP) Experimental Test Program. Characterization activities include sampling the gas in actual waste containers, categorizing waste contents for their gas generation potential, and extracting solid samples. A new waste testing project will utilize the Zero Powered Physics Reactor facility. In the workroom of these facility, laboratory gas generation experiments will be conducted with contact-handled transuranic waste. Both the characterization and waste testing activities are part of the effort to prepare the WIPP performance assessment. Waste treatment demonstrations have or will be conducted at the Transient Reactor Test facility and involve private sector participants. The demonstrations involve the development of thermal treatment for materials containing residual amounts of plutonium using plasma-arc technology. The success of these new programs is largely due to experience gained from past missions in such areas as radiological control and nuclear safety

  19. Contested environmental policy infrastructure: Socio-political acceptance of renewable energy, water, and waste facilities

    International Nuclear Information System (INIS)

    Wolsink, Maarten

    2010-01-01

    The construction of new infrastructure is hotly contested. This paper presents a comparative study on three environmental policy domains in the Netherlands that all deal with legitimising building and locating infrastructure facilities. Such infrastructure is usually declared essential to environmental policy and claimed to serve sustainability goals. They are considered to serve (proclaimed) public interests, while the adverse impact or risk that mainly concerns environmental values as well is concentrated at a smaller scale, for example in local communities. The social acceptance of environmental policy infrastructure is institutionally determined. The institutional capacity for learning in infrastructure decision-making processes in the following three domains is compared: 1.The implementation of wind power as a renewable energy innovation; 2.The policy on space-water adaptation, with its claim to implement a new style of management replacing the current practice of focusing on control and 'hard' infrastructure; 3.Waste policy with a focus on sound waste management and disposal, claiming a preference for waste minimization (the 'waste management hierarchy'). All three cases show a large variety of social acceptance issues, where the appraisal of the impact of siting the facilities is confronted with the desirability of the policies. In dealing with environmental conflict, the environmental capacity of the Netherlands appears to be low. The policies are frequently hotly contested within the process of infrastructure decision-making. Decision-making on infrastructure is often framed as if consensus about the objectives of environmental policies exists. These claims are not justified, and therefore stimulating the emergence of environmental conflicts that discourage social acceptance of the policies. Authorities are frequently involved in planning infrastructure that conflicts with their officially proclaimed policy objectives. In these circumstances, they are

  20. Environmental Performance Report 2013: Annual Site Environmental Report per the U.S. Department of Energy Order 231.1-1B (Management Publication)

    Energy Technology Data Exchange (ETDEWEB)

    Schlomberg, K.; Eickhoff, J.; Beatty, B.; Braus, G.; Durbin, L.; Fiehweg, R.; Ray, M.; Ryon, T.; Schmitz, E.

    2014-08-01

    The National Renewable Energy Laboratory's (NREL's) Environmental Performance Report provides a description of the laboratory's environmental management activities for 2013, including information on environmental and sustainability performance, environmental compliance activities and status, and environmental protection programs, highlights, and successes. The purpose of this report is to ensure that U.S. Department of Energy (DOE) and the public receive timely, accurate information about events that have affected or could adversely affect the health, safety, and security of the public or workers; the environment; or the operations of DOE facilities. This report meets the requirements of the Annual Site Environmental Report and is prepared in accordance with the DOE Order 231.1B, Environment, Safety and Health Reporting.

  1. Contested environmental policy infrastructure: socio-political acceptance of renewable energy, water, and waste facilities

    NARCIS (Netherlands)

    Wolsink, M.

    2010-01-01

    The construction of new infrastructure is hotly contested. This paper presents a comparative study on three environmental policy domains in the Netherlands that all deal with legitimising building and locating infrastructure facilities. Such infrastructure is usually declared essential to

  2. Over facility design description for the CPDF [Centrifuge Plant Demonstration Facility]: SDD-1 [System Design Description

    International Nuclear Information System (INIS)

    1987-04-01

    The Centrifuge Plant Demonstration Facility (CPDF) is an essential part of the continuing development of first-production-plant centrifuge technology that will integrate centrifuge machines into a process and enrichment plant design. The CPDF will provide facilities for testing and continued development of a unit cascade in direct support of the commercial Gas Centrifuge Enrichment Plant (GCEP). The basic cascade-oriented equipment, feed, withdrawal, drive system, process piping, utility piping, and other auxiliary and support equipment will be tested in an operating configuration that represents, to the extent possible, GCEP arrangement and operating conditions. The objective will be to demonstrate procedures for production cascade installation, start-up, operation, and maintenance, and to provide proof of overall cascade and associated system design, construction, and operating and maintenance concepts. To the maximum possible extent, all equipment for the CPDF will be procured from commercial sources. Centrifuges will be procured from industry using government-supplied specifications and drawings. The existing Component Preparation Laboratory (CPL) located near the CPDF site will be used for centrifuge component receiving, inspection, assembly, and qualification testing of pre-production test machines. Later in the test program, samples of production machines planned for use in the GCEP will be tested in the CPDF

  3. Manitoba Hydro's environmental management system and its application to hydraulic facilities and operations

    International Nuclear Information System (INIS)

    Windsor, D. C.

    1996-01-01

    Development at Manitoba Hydro of a series of environmental practices manuals, as part of the public utilities' approach to environmental management, were described. Experiences gained during the process of developing these manuals were described. It has been found that to be accepted environmental practices must: (1) support existing facilities, operations and procedures, (2) be presented in an easily accessible form, (3) have an evident purpose, (4) be stated clearly; (5) be practical and feasible, and (6) have implementation clearly defined. The audience level of detail, style of presentation, implementation, frequency of revision and update were also summarized. A detailed outline of the current policy of Manitoba Hydro was included in the appendices

  4. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 7

    International Nuclear Information System (INIS)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.; Fowler, J.W.

    1986-09-01

    The 644 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the seventh 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, 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 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, 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. References are arranged alphabetically by leading 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. The appendix contains a list of frequently used acronyms and abbreviations

  5. Hanford Site near-facility environmental monitoring data report for calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    DIEDIKER, L.P.

    1999-07-29

    This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

  6. Hanford Site near-facility environmental monitoring data report for calendar year 1998

    International Nuclear Information System (INIS)

    DIEDIKER, L.P.

    1999-01-01

    This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years

  7. Public perception of odour and environmental pollution attributed to MSW treatment and disposal facilities: A case study

    International Nuclear Information System (INIS)

    De Feo, Giovanni; De Gisi, Sabino; Williams, Ian D.

    2013-01-01

    Highlights: ► Effects of closing MSW facilities on perception of odour and pollution studied. ► Residents’ perception of odour nuisance considerably diminished post closure. ► Odour perception showed an association with distance from MSW facilities. ► Media coverage increased knowledge about MSW facilities and how they operate. ► Economic compensation possibly affected residents’ views and concerns. - Abstract: If residents’ perceptions, concerns and attitudes towards waste management facilities are either not well understood or underestimated, people can produce strong opposition that may include protest demonstrations and violent conflicts such as those experienced in the Campania Region of Italy. The aim of this study was to verify the effects of the closure of solid waste treatment and disposal facilities (two landfills and one RDF production plant) on public perception of odour and environmental pollution. The study took place in four villages in Southern Italy. Identical questionnaires were administered to residents during 2003 and after the closure of the facilities occurred in 2008. The residents’ perception of odour nuisance considerably diminished between 2003 and 2009 for the nearest villages, with odour perception showing an association with distance from the facilities. Post closure, residents had difficulty in identifying the type of smell due to the decrease in odour level. During both surveys, older residents reported most concern about the potentially adverse health impacts of long-term exposure to odours from MSW facilities. However, although awareness of MSW facilities and concern about potentially adverse health impacts varied according to the characteristics of residents in 2003, substantial media coverage produced an equalisation effect and increased knowledge about the type of facilities and how they operated. It is possible that residents of the village nearest to the facilities reported lower awareness of and concern about

  8. Public perception of odour and environmental pollution attributed to MSW treatment and disposal facilities: A case study

    Energy Technology Data Exchange (ETDEWEB)

    De Feo, Giovanni, E-mail: g.defeo@unisa.it [Department of Industrial Engineering, University of Salerno, via Ponte don Melillo 1, 84084 Fisciano (Italy); De Gisi, Sabino [Department of Industrial Engineering, University of Salerno, via Ponte don Melillo 1, 84084 Fisciano (Italy); Williams, Ian D. [Waste Management Research Group, Faculty of Engineering and the Environment, University of Southampton, Highfield, Southampton SO17 1BJ (United Kingdom)

    2013-04-15

    Highlights: ► Effects of closing MSW facilities on perception of odour and pollution studied. ► Residents’ perception of odour nuisance considerably diminished post closure. ► Odour perception showed an association with distance from MSW facilities. ► Media coverage increased knowledge about MSW facilities and how they operate. ► Economic compensation possibly affected residents’ views and concerns. - Abstract: If residents’ perceptions, concerns and attitudes towards waste management facilities are either not well understood or underestimated, people can produce strong opposition that may include protest demonstrations and violent conflicts such as those experienced in the Campania Region of Italy. The aim of this study was to verify the effects of the closure of solid waste treatment and disposal facilities (two landfills and one RDF production plant) on public perception of odour and environmental pollution. The study took place in four villages in Southern Italy. Identical questionnaires were administered to residents during 2003 and after the closure of the facilities occurred in 2008. The residents’ perception of odour nuisance considerably diminished between 2003 and 2009 for the nearest villages, with odour perception showing an association with distance from the facilities. Post closure, residents had difficulty in identifying the type of smell due to the decrease in odour level. During both surveys, older residents reported most concern about the potentially adverse health impacts of long-term exposure to odours from MSW facilities. However, although awareness of MSW facilities and concern about potentially adverse health impacts varied according to the characteristics of residents in 2003, substantial media coverage produced an equalisation effect and increased knowledge about the type of facilities and how they operated. It is possible that residents of the village nearest to the facilities reported lower awareness of and concern about

  9. Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-02-01

    This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs.

  10. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 2, Revision 2

    International Nuclear Information System (INIS)

    Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

    1996-12-01

    This document is Volume 2 in a two-volume series that comprise the site characterization report, the Preoperational Baseline and Site Characterization Report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; preoperational baseline chemical data and aquifer test data. Five groundwater monitoring wells, six deep characterization boreholes, and two shallow characterization boreholes were drilled at the Environmental Restoration Disposal Facility (ERDF) site to directly investigate site-specific hydrogeologic conditions

  11. A Facility for Long-Term Mars Simulation Experiments: The Mars Environmental Simulation Chamber (MESCH)

    Science.gov (United States)

    Jensen, Lars Liengaard; Merrison, Jonathan; Hansen, Aviaja Anna; Mikkelsen, Karina Aarup; Kristoffersen, Tommy; Nørnberg, Per; Lomstein, Bente Aagaard; Finster, Kai

    2008-06-01

    We describe the design, construction, and pilot operation of a Mars simulation facility comprised of a cryogenic environmental chamber, an atmospheric gas analyzer, and a xenon/mercury discharge source for UV generation. The Mars Environmental Simulation Chamber (MESCH) consists of a double-walled cylindrical chamber. The double wall provides a cooling mantle through which liquid N2 can be circulated. A load-lock system that consists of a small pressure-exchange chamber, which can be evacuated, allows for the exchange of samples without changing the chamber environment. Fitted within the MESCH is a carousel, which holds up to 10 steel sample tubes. Rotation of the carousel is controlled by an external motor. Each sample in the carousel can be placed at any desired position. Environmental data, such as temperature, pressure, and UV exposure time, are computer logged and used in automated feedback mechanisms, enabling a wide variety of experiments that include time series. Tests of the simulation facility have successfully demonstrated its ability to produce temperature cycles and maintain low temperature (down to -140°C), low atmospheric pressure (5 10 mbar), and a gas composition like that of Mars during long-term experiments.

  12. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    International Nuclear Information System (INIS)

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D ampersand D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. 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 in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D ampersand D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword

  13. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. 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 in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  14. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    International Nuclear Information System (INIS)

    Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-01-01

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

  15. Bayesian evidence and epidemiological implications of environmental contamination from acute respiratory infection in long-term care facilities.

    Science.gov (United States)

    Diaz-Decaro, J D; Launer, B; Mckinnell, J A; Singh, R; Dutciuc, T D; Green, N M; Bolaris, M; Huang, S S; Miller, L G

    2018-05-01

    Skilled nursing home facilities (SNFs) house a vulnerable population frequently exposed to respiratory pathogens. Our study aims to gain a better understanding of the transmission of nursing home-acquired viral respiratory infections in non-epidemic settings. Symptomatic surveillance was performed in three SNFs for residents exhibiting acute respiratory symptoms. Environmental surveillance of five high-touch areas was performed to assess possible transmission. All resident and environmental samples were screened using a commercial multiplex polymerase chain reaction platform. Bayesian methods were used to evaluate environmental contamination. Among nursing home residents with respiratory symptoms, 19% had a detectable viral pathogen (parainfluenza-3, rhinovirus/enterovirus, RSV, or influenza B). Environmental contamination was found in 20% of total room surface swabs of symptomatic residents. Environmental and resident results were all concordant. Target period prevalence among symptomatic residents ranged from 5.5 to 13.3% depending on target. Bayesian analysis quantifies the probability of environmental shedding due to parainfluenza-3 as 92.4% (95% CI: 86.8-95.8%) and due to rhinovirus/enterovirus as 65.6% (95% CI: 57.9-72.5%). Our findings confirm that non-epidemic viral infections are common among SNF residents exhibiting acute respiratory symptoms and that environmental contamination may facilitate further spread with considerable epidemiological implications. Findings further emphasise the importance of environmental infection control for viral respiratory pathogens in long-term care facilities.

  16. Facility Registry Service (FRS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) provides an integrated source of comprehensive (air, water, and waste) environmental information about facilities across EPA,...

  17. Climatic Environmental Test Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — RTTC has an extensive suite of facilities for supporting MIL-STD-810 testing, toinclude: Temperature/Altitude, Rapid Decompression, Low/High Temperature,Temperature...

  18. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

    1998-03-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

  19. Environmental monitoring for low-level radioactive waste-disposal facilities

    International Nuclear Information System (INIS)

    Shum, E.Y.; Starmer, R.J.; Westbrook, K.; Young, M.H.

    1990-01-01

    The U.S. Nuclear Regulatory Commission prepared a Branch Technical Position (BTP) paper on environmental monitoring of a low-level radioactive waste-disposal facility. The BTP provides guidance on what is required in Section 61.53 of 10 CFR Part 61 for those submitting a license application. Guidance is also provided on choosing constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance. The environmental monitoring program generally consists of three phases: preoperational, operational, and postoperational. Each phase should be designed to fulfill specific objectives defined in the BTP. During the preoperational phase, program objectives are to provide site characterization information, demonstrate site suitability and acceptability, and obtain background or baseline information. Emphasis during the operational phase is on measurement shifts. Monitoring data are obtained to demonstrate compliance with regulations, with dose limits of 10 CFR Part 61, or with applicable U.S. Environmental Protection Agency standards. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational phase emphasizes measurements to demonstrate compliance with site closure requirements and continued compliance with the performance objective for release. Data are used to support evaluation of long-term impacts to the general public and for public information

  20. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  1. Environmental fate of hexabromocyclododecane from a new Canadian electronic recycling facility.

    Science.gov (United States)

    Tomko, Geoffrey; McDonald, Karen M

    2013-01-15

    An electronics recycling facility began operation at the municipal landfill site for the City of Edmonton, Canada in March 2008 with the goal of processing 30,000 tonnes of electronic wastes per year. Of the many by-products from the process, brominated fire retardants such as hexabromocyclododecane (HBCD) can evolve off of e-wastes and be released into the environmental media. HBCD has been identified by many countries and international bodies as a chemical of concern because of its ability to bioaccumulate in the ecosystem. An evaluation of the potential emission of HBCD indicates that up to 500 kg per year may be released from a landfill and recycling facility such as that operating in Edmonton. A multimedia fugacity model was used to evaluate the dispersion and fate of atmospherically emitted HBCD traveling into surrounding agricultural land and forested parkland. The model indicates that the three isomers of HBCD partitioned into environmental media similarly. Much of the HBCD is lost through atmospheric advection, but it is also found in soil and sediment. Modeled air concentrations are similar to those measured at locations with a history of e-waste recycling. Since HBCD has been shown to bioaccumulate, the HBCD released from this source has the long-term potential to affect agricultural food crops and the park ecosystem. Copyright © 2012 Elsevier Ltd. All rights reserved.

  2. Environmental Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility: Environmental report

    International Nuclear Information System (INIS)

    1987-04-01

    The Environmental Standard Review Plan (ESRP) (NUREG-1300) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform environmental reviews of environmental reports prepared by applicants in support of license applications to construct and operate new low-level radioactive waste disposal facilities. The individual ESRPs that constitute this document identify the information considered necessary to conduct the review, the purpose and scope of the review, the analysis procedure and evaluation, the formal input to the environmental statement, and the references considered appropriate for each review. The ESRP is intended to ensure quality and uniformity of approach in individual reviews as well as compliance with the National Environmental Policy Act of 1969. In addition, the ESRP will make information about the environmental component of the licensing process more readily available and thereby will serve to improve the understanding of this process among the public, States and regional compacts, and the regulated community

  3. Pollution control and environmental monitoring efforts at DOE's Coal-Fired Flow Facility

    International Nuclear Information System (INIS)

    Attig, R.C.; Crawford, L.W.; Lynch, T.P.; Sheth, A.C.

    1991-01-01

    Proof-of-Concept (POC) scale demonstration of such technology is currently being carried out at the US Department of Energy's (DOE's) Coal-Fired Flow Facility (CFFF), located at The University of Tennessee Space Institute (UTSI) in Tullahoma, Tennessee and at the Component Development and Integration Facility in Butte, Montana. The CFFF is dedicated to the evaluation of downstream (steam cycle) components and technology that may be considered for a full-scale MHD system. The objectives of the CFFF testing include the demonstration of various pollution control devices and techniques at a scale sufficient for future scale-up. The CFFF offers a unique test environment in which emissions control techniques can be developed and evaluated through emissions and environmental monitoring. Results thus far have demonstrated the ability of sulfur oxide (SO x ), nitrogen oxide (NO x ) and particulate emissions well below the New Source Performance Standards (NSPS). Regeneration of the potassium sulfate to produce sulfur-free compounds also has been demonstrated. The experimental program at the CFFF is now aimed at determining the optimum conditions for future commercial scale designs. Because of increased interests in Air Toxics, measurements of nitrous oxide (N 2 O), a potential greenhouse gas, priority pollutants (inorganic as well as organics), and chlorine-containing species (Cl 2 and HCl) are also included in our ongoing efforts. Environmental monitoring activities are being pursued to develop an environmental impact assessment data base. These include the use of three ambient air sites to determine the impacts of gaseous and particulate emissions, five lake water sites to determine impacts due to process water discharges and seven sites to collect terrestrial data on possible soil contamination and tree growth. In this paper, we will summarize the status of our ongoing environmental program. 16 refs., 15 figs., 3 tabs

  4. Development and implementation of a construction environmental protection program at a solid radioactive waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Wong, T.S. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Bishop, T. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada); Hickman, C.N. [Point Lepreau Generating Station, Saint John, New Brunswick (Canada)

    2007-07-01

    Refurbishment of ageing nuclear stations has great economic and environmental benefits, including reduced greenhouse gas emissions. The Government of New Brunswick (NB) decided in 2005 to refurbish the Point Lepreau Generating Station with Atomic Energy of Canada Limited (AECL) as the general contractor. The project includes construction of additional radioactive waste management facilities. AECL developed, for the construction project, an environmental protection program to comply with commitments made during the environmental assessment process, and regulatory requirements. The program covers detailed environmental plans, training courses, and engagement of consultants to provide training and conduct monitoring of the construction activities. Construction related environmental effects have been successfully mitigated and the monitoring results indicate compliance with all environmental requirements. (author)

  5. Hanford Facility contingency plan

    International Nuclear Information System (INIS)

    Sutton, L.N.; Miskho, A.G.; Brunke, R.C.

    1993-10-01

    The Hanford Facility Contingency Plan, together with each TSD unit-specific contingency plan, meets the WAC 173-303 requirements for a contingency plan. This plan includes descriptions of responses to a nonradiological hazardous materials spill or release at Hanford Facility locations not covered by TSD unit-specific contingency plans or building emergency plans. This plan includes descriptions of responses for spills or releases as a result of transportation activities, movement of materials, packaging, and storage of hazardous materials

  6. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

  7. Barge loading facilities in conjunction with wood chipping and sawlog mill, Tennessee River Mile 145. 9R: Environmental assessment

    Energy Technology Data Exchange (ETDEWEB)

    1990-08-01

    The purpose of this Environmental Assessment (EA) is to evaluate the environmental consequences of approving, denying, or adopting reasonable alternatives to a request for barge loading facilities. These facilities would serve a proposed wood chipping and sawlog products operation at Tennessee River Mile (TRM) 145.9, right descending bank, (Kentucky Lake), in Perry County, Tennessee. The site is located between Short Creek and Peters Landing. The applicant is Southeastern Forest Products, L.P. (SFP), Box 73, Linden, Tennessee and the proposed facilities would be constructed on or adjacent to company owned land. Portions of the barge terminal would be constructed on land over which flood easement rights are held by the United States of America and administered by the Tennessee Valley Authority (TVA). The US Army Corps of Engineers (CE) and TVA have regulatory control over the proposed barge terminal facilities since the action would involve construction in the Tennessee River which is a navigable water of the United States. The wood chipping and sawlog products facilities proposed on the upland property are not regulated by the CE or TVA. On the basis of the analysis which follows, it has been determined that a modified proposal (as described herein) would not significantly affect the quality of the human environment, and does not require the preparation of an environmental impact statement. 8 refs.

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

    International Nuclear Information System (INIS)

    Armstrong, D.L.

    1994-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, D.L.

    1994-08-01

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

  10. The Impact of Environmental Design on Teamwork and Communication in Healthcare Facilities: A Systematic Literature Review.

    Science.gov (United States)

    Gharaveis, Arsalan; Hamilton, D Kirk; Pati, Debajyoti

    2018-01-01

    The purpose of this systematic review is to investigate the current knowledge about the impact of healthcare facility design on teamwork and communication by exploring the relevant literature. Teamwork and communication are behavioral factors that are impacted by physical design. However, the effects of environmental factors on teamwork and communication have not been investigated extensively in healthcare design literature. There are no published systematic reviews on the current topic. Searches were conducted in PubMed and Google Scholar databases in addition to targeted design journals including Health Environmental Research & Design, Environment and Behavior, Environmental Psychology, and Applied Ergonomics. Inclusion criteria were (a) full-text English language articles related to teamwork and communication and (b) involving any healthcare built environment and space design published in peer-reviewed journals between 1984 and 2017. Studies were extracted using defined inclusion and exclusion criteria. In the first phase, 26 of the 195 articles most relevant to teamwork and 19 studies of the 147 were identified and reviewed to understand the impact of communication in healthcare facilities. The literature regarding the impact of built environment on teamwork and communication were reviewed and explored in detail. Eighteen studies were selected and succinctly summarized as the final product of this review. Environmental design, which involves nurses, support staff, and physicians, is one of the critical factors that promotes the efficiency of teamwork and collaborative communication. Layout design, visibility, and accessibility levels are the most cited aspects of design which can affect the level of communication and teamwork in healthcare facilities.

  11. Environmental Management Assessment of the Continuous Electron Beam Accelerator Facility (CEBAF)

    International Nuclear Information System (INIS)

    1993-03-01

    This report documents the results of the Environmental Management Assessment performed at the Continuous Electron Beam Accelerator Facility (CEBAF) in Newport News, Virginia. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the CEBAF Site Office; the CEBAF management and operating contractor (M ampersand O), Southeastern Universities Research Association, Inc. (SURA); the Oak Ridge Field Office (OR); and the responsible DOE Headquarters Program Office, the Office of Energy Research (ER). The onsite portion of the assessment was conducted from March 8 through March 19, 1993, by the US Department of Energy's (DOE's) Office of Environmental Audit (EH-24) located within the office of Environment, Safety and Health (EH). DOE 5482.1 B, ''Environment, Safety and Health Appraisal Program,'' and Secretary of Energy Notice (SEN)-6E-92, ''Departmental Organizational and Management Arrangements,'' establish the mission of EH-24 to provide comprehensive, independent oversight of Department-wide environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is enhancement of environmental protection and minimization of risk to public health and the environment. EH-24 accomplishes its mission utilizing systematic and periodic evaluations of the Department's environmental programs within line organizations, and through use of supplemental activities which serve to strengthen self-assessment and oversight functions within program, field, and contractor organizations

  12. Evaluation of environmental change and its effects on the radiological performance of a hypothetical shallow engineered disposal facility at Elstow, Bedfordshire

    International Nuclear Information System (INIS)

    1988-03-01

    The results of a project designed to evaluate aspects of a hypothetical facility for disposal of radioactive wastes at Elstow, Bedfordshire, are described. The project included modelling of environmental change using the TIME2 code, groundwater flow modelling, biosphere modelling and risk analysis using the SYVAC A/C code. The aims of the work were to demonstrate use of TIME2, investigate the evolution of the facility's environment and to evaluate the influence of environmental change on estimates of radiological risk. Risk analysis of several time-independent environmental system states, using data obtained from the other tasks, indicated that environmental changes significantly influence estimates of radiological risk. (author)

  13. Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site

    International Nuclear Information System (INIS)

    1995-07-01

    DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed

  14. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    International Nuclear Information System (INIS)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  15. State Environmental Policy Act (SEPA) Checklist for the 105-DR Large Sodium Fire Facility Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the DR defense reactor, which was shut down in 1964. The LSFF is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Clean closure is the proposed method of closure for the LSFF. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989). This closure plan presents a description of the facility, the history of wastes managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  16. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    Warner, C.L.

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  17. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  18. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2013-01-11

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

  19. EPA Facility Registry Service (FRS): Facility Interests Dataset

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

  20. Environmental impacts of electricity self-consumption from organic photovoltaic battery systems at industrial facilities in Denmark

    DEFF Research Database (Denmark)

    Chatzisideris, Marios Dimos; Laurent, Alexis; Hauschild, Michael Zwicky

    2017-01-01

    investigate the life cycle environmental impacts of electricity self-consumption from an OPV system coupled with a sodium/nickel chloride battery at an iron/metal industry in Denmark. Results show that an OPV system without storage could decrease the carbon footprint of the industry; installation......Organic photovoltaics (OPV) show promise of greatly improving the environmental and economic performance of PV compared to conventional silicon. Life cycle assessment studies have assessed the environmental impacts of OPV, but not under a self-consumption scheme for industrial facilities. We...

  1. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Weekes, D.C.; Ford, B.H.; Jaeger, G.K.

    1996-09-01

    This document Volume 2 in a two-volume series that comprise the site characterization report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; and preoperational baseline chemical data and aquifer test data. This does not represent the entire body of data available. Other types of information are archived at BHI Document Control. Five ground water monitoring wells were drilled at the Environmental Restoration Disposal Facility site to directly investigate site- specific hydrogeologic conditions. Well and borehole activity summaries are presented in Volume 1. Field borehole logs and geophysical data from the drilling are presented in this document. Well development and pump installation sheets are presented for the groundwater monitoring wells. Other data presented in this document include borehole geophysical logs from existing wells; chemical data from the sampling of soil, vegetation, and mammals from the ERDF to support the preoperational baseline; ERDF surface radiation surveys;a nd aquifer testing data for well 699-32-72B

  2. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

    1998-01-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report.

  3. 1991 Annual performance report for environmental oversight and monitoring at Department of Energy Facilities in New Mexico

    International Nuclear Information System (INIS)

    1994-01-01

    On October 22, 1990 an agreement was entered into between the US DOE and the State of New Mexico. The agreement was designed to assure the citizens of New Mexico that the environment is protected and that public health, as related to the environment is also protected. The Agreement reflects the understanding and commitments between the parties regarding environmental oversight, monitoring, remediation and emergency response at the following DOE facilities: the Inhalation Toxicology Research Institute (ITRI); Los Alamos National Laboratory (LANL); Sandia National Laboratory (SNL); and the Waste Isolation Pilot Plant (WIPP). These provision are ongoing through a vigorous program of independent monitoring and oversight; prioritization of clean-up and compliance activities; and new commitments by DOE. While the initial assessment of the quality and effectiveness of the facilities' environmental monitoring and surveillance programs is not yet complete, preliminary findings are presented regarding air quality monitoring, environmental monitoring, and groundwater monitoring

  4. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    International Nuclear Information System (INIS)

    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

  5. Preliminary Hanford technical input for the Department of Energy programmatic spent nuclear fuel management and Idaho National Engineering Laboratory environmental restoration and waste management programs environmental impact statement

    International Nuclear Information System (INIS)

    Bergsman, K.H.

    1995-03-01

    The US Department of Energy (DOE) is currently evaluating its programmatic options for the safe management of its diverse spent nuclear fuel (SNF) inventory in the Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Environmental Impact Statement (SNF and INEL EIS). In the SNF and INEL EIS, the DOE is assessing five alternatives for SNF management, which consider at which of the DOE sites each of the various SNF types should be managed until ultimate disposition. The range of SNF inventories considered for management at the Hanford Site in the SNF and INEL EIS include the current Hanford Site inventory, only the current Hanford Site defense production SNF inventory, the DOE complex-wide SNF inventory, or none at all. Site-specific SNF management decisions will be evaluated in separate National Environmental Policy Act evaluations. Appendixes A and B include information on (1) additional facilities required to accommodate inventories of SNF within each management alternative, (2) existing and new SNF management facility descriptions, (3) facility costs for construction and operation, (4) facility workforce requirements for construction and operation, and (5) facility discharges. The information was extrapolated from existing analyses to the extent possible. New facility costs, manpower requirements, and similar information are based on rough-order-of-magnitude estimates

  6. Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

    International Nuclear Information System (INIS)

    Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

    2012-01-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W PandT) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012

  7. Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Freeman-Pollard, Jhivaun R. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-11-14

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

  8. Environmental restoration disposal facility applicable or relevant and appropriate requirements study report. Revision 00

    International Nuclear Information System (INIS)

    Roeck, F.V.; Vedder, B.L.; Rugg, J.E.

    1995-10-01

    The Environmental Restoration Disposal Facility (ERDF) will be a landfill authorized under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and will comply with the Resource Conservation and Recovery Act of 1976 (RCRA) substantive requirements. The facility will also comply with applicable or relevant and appropriate requirements (ARAR), including portions of the U.S. Environmental Protection Agency (EPA) regulations, Washington Administrative Code (WAC), and to-be-considered (TBC) elements such as U.S. Department of Energy (DOE) Orders. In considering the requirements of CERCLA, a detailed analysis of various alternatives for ERDF was completed using the nine CERCLA criteria, National Environmental Policy Act of 1969 (NEPA), and public comments. The ERDF record of decision (ROD) selected an alternative that includes a RCRA-compliant double-lined trench for the disposal of radioactive, hazardous, and mixed wastes resulting from the remediation of operable units (OU) within the National Priorities List (NPL) sites in the 100, 200, and 300 Areas. Only wastes resulting from the remediation of Hanford NPL sites will be allowed in the ERDF. Of the various siting and design alternatives proposed for ERDF, the selected alternative provides the best combination of features by balancing the nine CERCLA criteria, ARAR compliance, environmentally protective site, and various stakeholder and public recommendations. The ERDF trench design, compliant with RCRA Subtitle C minimum technical requirements (MTR), will be double lined and equipped with a leachate collection system. This design provides a more reliable system to protect groundwater than other proposed alternatives. The ERDF is located on the Hanford Site Central Plateau, southeast of the 200 West Area

  9. Radioactive discharges and environmental monitoring at the Swedish nuclear facilities 2001; Utslaepps- och omgivningskontroll vid de kaerntekniska anlaeggningarna 2001

    Energy Technology Data Exchange (ETDEWEB)

    Sandwall, Johanna

    2002-11-01

    This report contains an evaluation of the discharge and environmental programme for the Swedish nuclear facilities. It also contains the work on quality control performed by SSI. This is done as random sampling of discharge water and environmental samples.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    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

  12. The exploratory studies facility (ESF) at Yucca Mountain - Description and status

    International Nuclear Information System (INIS)

    Simecka, W.B.; Replogle, J.M.; Mckenzie, D.G.

    1994-01-01

    The Exploratory Studies Facility (ESF) at Yucca Mountain, Nevada will be a 25 kilometer underground network of inclined ramps, tunnels, and test alcoves. It will serve as an underground laboratory for the execution of a testing program conceived to assess the suitability of Yucca Mountain as a site to host a potential high level nuclear waste repository. This paper contains a description of the ESF, a summary of the major types of tests currently planned, and a report on the current status of the ongoing design and construction activities. The ESF is being designed and constructed in phases. Currently, the Detailed Design, or open-quotes Title II Designclose quotes is centered on the second of ten major design packages. Construction has begun on excavation of the open-quotes starter tunnelclose quotes for a Tunnel Boring Machine (TBM) expected to begin operation in late FY 1994. The EFS program will provide information critical to the evaluation of Yucca Mountain as a potential repository site, and will house a suite of state-of-the-art tests designed to gather this information. The ESF is a one of a kind opportunity to examine, in minute detail, all facets of a sites' geology; its thermal, mechanical, and hydrologic properties; and to study the linkages between these properties

  13. Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 4

    International Nuclear Information System (INIS)

    1993-10-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered is July through September 1993 (fourth quarter of FY 1993). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1994 commitments

  14. The Impact of Pollution Prevention on Toxic Environmental Releases from U.S. Manufacturing Facilities.

    Science.gov (United States)

    Ranson, Matthew; Cox, Brendan; Keenan, Cheryl; Teitelbaum, Daniel

    2015-11-03

    Between 1991 and 2012, the facilities that reported to the U.S. Environmental Protection Agency's Toxic Release Inventory (TRI) Program conducted 370,000 source reduction projects. We use this data set to conduct the first quasi-experimental retrospective evaluation of how implementing a source reduction (pollution prevention) project affects the quantity of toxic chemicals released to the environment by an average industrial facility. We use a differences-in-differences methodology, which measures how implementing a source reduction project affects a facility's releases of targeted chemicals, relative to releases of (a) other untargeted chemicals from the same facility, or (b) the same chemical from other facilities in the same industry. We find that the average source reduction project causes a 9-16% decrease in releases of targeted chemicals in the year of implementation. Source reduction techniques vary in effectiveness: for example, raw material modification causes a large decrease in releases, while inventory control has no detectable effect. Our analysis suggests that in aggregate, the source reduction projects carried out in the U.S. since 1991 have prevented between 5 and 14 billion pounds of toxic releases.

  15. Environmental monitoring and mitigation plan for site characterization: Revision 1

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of the EMMP is: to identify, in consultation with the affected states and Indian tribes, potentially significant adverse environmental impacts that could result from site characterization activities, to describe data collection methods that will be used to monitor any such identified impacts, and procedures for mitigating them. Chapter 2 of the EMMP provides an overview of the background and scope of the document. Chapter 3 of the EMMP provides a description of site characterization phase activities planned to assess the geologic condition of the site and construct the exploratory shafts and surface support facilities. The rationale for developing environmental monitoring studies is presented in Chapeter 4. Chapter 5 contains descriptions of the environmental monitoring and mitigation procedures whenever they are applicable. Additionally, in Chapter 6, the EMMP includes a procedure for modifying the monitoring and mitigation program and an approach for reporting monitoring results to interested parties. 21 figs., 10 tabs

  16. Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico

    International Nuclear Information System (INIS)

    1993-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required

  17. The ANTARES accelerator: a facility for environmental monitoring and materials characterisation

    International Nuclear Information System (INIS)

    Tuniz, C.

    1997-01-01

    An analytical facility for Accelerator Mass Spectrometry (AMS) and Ion Beam Analysis (IBA) has been under development since 1989 on the 8-MV tandem accelerator ANTARES at the Lucas Heights Science and Technology Centre. Three beamlines are presently dedicated to the AMS analysis of long-lived radionuclides and one is used for the study of multilayered semiconductor structures by heavy ion recoil spectrometry. Having accomplished the task of transforming the old nuclear physics accelerator from Rutgers University into a world-class analytical facility, ANSTO scientists are now promoting research projects based on the capability of the ANTARES instruments. New instruments are being constructed on the ANTARES accelerator for future programs in environmental monitoring, safeguards, nuclear waste disposal and applications in advanced materials. A new AMS beamline has been designed that is expected to be capable of measuring rare heavy radionuclides, such as 236 U, 229 , 230T h and 244 Pu, in natural samples with ultra-high sensitivity. A novel, heavy ion microprobe will allow IBA of surfaces with a spatial resolution of 10 μm for high-energy ions (20-100 MeV) from chlorine to iodine. These instruments are complementary to other advanced analytical tools developed by ANSTO, such as the synchrotron radiation beamline at the Australian National Beamline Facility

  18. Site descriptions for preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

    Burgess, W.E.; Jones, C.H.; Sumerling, T.J.; Ashton, J.

    1988-07-01

    The environmental contexts of four sites, previously under investigation by UK Nirex Ltd. as potential locations for low-level waste disposal facilities, are described. Information on geographical setting, climate, surface hydrology, land use, agriculture, fisheries, geology and hydrogeology is presented. The geological and hydrogeological data are interpreted with the support of deterministic modelling of groundwater conditions. The routes by which radionuclides may migrate from the site are identified and reduced to 1D statistical descriptions suitable for use in probabilistic risk assessments. Additional data required to improve the assessment of the performance of the site are identified. (author)

  19. Descriptions of reference LWR facilities for analysis of nuclear fuel cycles. Appendixes

    International Nuclear Information System (INIS)

    Schneider, K.J.; Kabele, T.J.

    1979-09-01

    The appendixes present the calculations that were used to derive the release factors discussed for each fuel cycle facility in Volume I. Appendix A presents release factor calculations for a surface mine, underground mine, milling facility, conversion facility, diffusion enrichment facility, fuel fabrication facility, PWR, BWR, and reprocessing facility. Appendix B contains additional release factors calculated for a BWR, PWR, and a reprocessing facility. Appendix C presents release factors for a UO 2 fuel fabrication facility

  20. Requirements of on-site facilities

    International Nuclear Information System (INIS)

    Burchardt, H.

    1977-01-01

    1) Requirements of on-site facilities: a) brief description of supplying the site with electricity and water; communication facilities, b) necessary facilities for containment and pipeline installation, c) necessary facilities for storage, safety, accommodation of personnel, housing; workshops; 2) Site management: a) Organisation schedules for 'turn-key-jobs' and 'single commission', b) Duties of the supervisory staff. (orig.) [de

  1. Environmental assessment related to the operation of Argonne National Laboratory, Argonne, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    1982-08-01

    In order to evaluate the environmental impacts of Argonne National Laboratory (ANL) operations, this assessment includes a descriptive section which is intended to provide sufficient detail to allow the various impacts to be viewed in proper perspective. In particular, details are provided on site characteristics, current programs, characterization of the existing site environment, and in-place environmental monitoring programs. In addition, specific facilities and operations that could conceivably impact the environment are described at length. 77 refs., 16 figs., 47 tabs.

  2. EPA Facility Registry Service (FRS): Facility Interests Dataset Download

    Data.gov (United States)

    U.S. Environmental Protection Agency — This downloadable data package consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are...

  3. Quadrant I RCRA Facility Investigation Work Plan

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this Facility Investigation (FRI) at the Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data which will: (1) characterize the environmental setting including ground water, surface water and sediment, soil and air; (2) define and characterize sources of contamination; (3) characterize the vertical and horizontal extent and degree of contamination of the environment; (4) assess the risk to human health and the environment resulting from possible exposure to contaminants; and, (5) support the Corrective Measures Study (CMS) which will follow the RFI. Investigations to characterize the environmental setting, sources of contamination, and vertical and horizontal extent and degree of contamination will be conducted relative to individual potential sources which have been identified in the Quadrant I Description of Current Conditions. These unit investigations will follow the systematic approach which is outlined below

  4. Space Station Environmental Control and Life Support System Test Facility at Marshall Space Flight Center

    Science.gov (United States)

    Springer, Darlene

    1989-01-01

    Different aspects of Space Station Environmental Control and Life Support System (ECLSS) testing are currently taking place at Marshall Space Flight Center (MSFC). Unique to this testing is the variety of test areas and the fact that all are located in one building. The north high bay of building 4755, the Core Module Integration Facility (CMIF), contains the following test areas: the Subsystem Test Area, the Comparative Test Area, the Process Material Management System (PMMS), the Core Module Simulator (CMS), the End-use Equipment Facility (EEF), and the Pre-development Operational System Test (POST) Area. This paper addresses the facility that supports these test areas and briefly describes the testing in each area. Future plans for the building and Space Station module configurations will also be discussed.

  5. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

    Energy Technology Data Exchange (ETDEWEB)

    Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, P.O. Box 1600, MSIN R4-41, 99352 (United States)

    2013-07-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

  6. Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

    International Nuclear Information System (INIS)

    Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J.

    2013-01-01

    CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

  7. 303-K Storage Facility closure plan

    International Nuclear Information System (INIS)

    1993-01-01

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

  8. Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

    International Nuclear Information System (INIS)

    1998-01-01

    This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D ampersand D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D ampersand D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS

  9. EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

  10. Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

    International Nuclear Information System (INIS)

    1995-08-01

    This EA evaluates the proposed action to decontaminate and decommission GA's hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R ampersand D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required

  11. Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This EA evaluates the proposed action to decontaminate and decommission GA`s hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R&D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required.

  12. Intakes and outfalls for seawater reverse-osmosis desalination facilities innovations and environmental impacts

    CERN Document Server

    Jones, Burton; Maliva, Robert

    2015-01-01

    The book assembles the latest research on new design techniques in water supplies using desalinated seawater. The authors examine the diverse issues related to the intakes and outfalls of these facilities. They clarify how and why these key components of the facilities impact the cost of operation and subsequently the cost of water supplied to the consumers. The book consists of contributed articles from a number of experts in the field who presented their findings at the “Desalination Intakes and Outfalls” workshop held at King Abdullah University of Science and Technology (KAUST) in Saudi Arabia in October, 2013. The book integrates coverage relevant to a wide variety of researchers and professionals in the general fields of environmental engineering and sustainable development.

  13. Thermionic system evaluated test (TSET) facility description

    Science.gov (United States)

    Fairchild, Jerry F.; Koonmen, James P.; Thome, Frank V.

    1992-01-01

    A consortium of US agencies are involved in the Thermionic System Evaluation Test (TSET) which is being supported by the Strategic Defense Initiative Organization (SDIO). The project is a ground test of an unfueled Soviet TOPAZ-II in-core thermionic space reactor powered by electrical heat. It is part of the United States' national thermionic space nuclear power program. It will be tested in Albuquerque, New Mexico at the New Mexico Engineering Research Institute complex by the Phillips Laboratoty, Sandia National Laboratories, Los Alamos National Laboratory, and the University of New Mexico. One of TSET's many objectives is to demonstrate that the US can operate and test a complete space nuclear power system, in the electrical heater configuration, at a low cost. Great efforts have been made to help reduce facility costs during the first phase of this project. These costs include structural, mechanical, and electrical modifications to the existing facility as well as the installation of additional emergency systems to mitigate the effects of utility power losses and alkali metal fires.

  14. EPA Facility Registry Service (FRS): AIRS_AFS Sub Facilities

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Air Facility System (AFS) contains compliance and permit data for stationary sources regulated by EPA, state and local air pollution agencies. The sub facility...

  15. Environmental assessment: Continuous Electron Beam Accelerator Facility, Newport News, Virginia

    International Nuclear Information System (INIS)

    1987-01-01

    This Environmental Assessment has been prepared by the US Department of Energy (DOE) to fulfill its obligations pursuant to Sect. 102 of the National Environmental Policy Act (NEPA) of 1969 (Public Law 91-190). The proposed federal action addressed in this document is DOE's funding of a Continuous Electron Beam Accelerator Facility (CEBAF) at Newport News, Virginia. DOE intends to contract with the Southeastern Universities Research Association (SURA) for operation of CEBAF, a continuous wave (CW) linear accelerator system (linac) capable of providing high-duty-factor beams throughout the energy range from 0.5 to 4.0 GeV. CEBAF will be the first of its kind worldwide and will offer a multi-GeV energy, high-intensity, high-duty-factor electron beam for use by the US nuclear physics community in research on the states of nuclear matter and the short-distance behavior of nuclei. The CEBAF project is largely in the conceptual design stage, with some components in the preliminary design stage. Construction is anticipated to begin in 1987 and be completed by 1992

  16. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI).

  17. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    International Nuclear Information System (INIS)

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    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

  20. Cold Vacuum Drying facility effluent drain system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) effluent drain system (EFS). The primary function of the EFS is to collect and transport fire suppression water discharged into a CVDF process bay to a retention basin located outside the facility. The EFS also provides confinement of spills that occur inside a process bay and allows non-contaminated water that drains to the process bay sumps to be collected until sampling and analysis are complete

  1. Cold Vacuum Drying facility deionized water system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) de-ionized water system. The de-ionized water system is used to provide clean, conditioned water, free from contaminants, chlorides and iron for the CVD Facility. Potable water is supplied to the deionized water system, isolated by a backflow prevention device. After the de-ionization process is complete, via a packaged de-ionization unit, de-ionized water is supplied to the process deionization unit

  2. Molecular Environmental Science and Synchrotron Radiation Facilities An Update of the 1995 DOE-Airlie Report on Molecular Environmental Science

    Energy Technology Data Exchange (ETDEWEB)

    Bargar, John R

    1999-05-07

    This workshop was requested by Dr. Robert Marianelli, Director of the DOE-BES Chemical Sciences Division, to update the findings of the Workshop on Molecular Environmental Sciences (MES) held at Airlie, VA, in July 1995. The Airlie Workshop Report defined the new interdisciplinary field referred to as Molecular Environmental Science (MES), reviewed the synchrotron radiation methods used in MES research, assessed the adequacy of synchrotron radiation facilities for research in this field, and summarized the beam time requirements of MES users based on a national MES user survey. The objectives of MES research are to provide information on the chemical and physical forms (speciation), spatial distribution, and reactivity of contaminants in natural materials and man-made waste forms, and to develop a fundamental understanding of the complex molecular-scale environmental processes, both chemical and biological, that affect the stability, transformations, mobility, and toxicity of contaminant species. These objectives require parallel studies of ''real'' environmental samples, which are complicated multi-phase mixtures with chemical and physical heterogeneities, and of simplified model systems in which variables can be controlled and fundamental processes can be examined. Only by this combination of approaches can a basic understanding of environmental processes at the molecular-scale be achieved.

  3. Molecular Environmental Science and Synchrotron Radiation Facilities An Update of the 1995 DOE-Airlie Report on Molecular Environmental Science

    International Nuclear Information System (INIS)

    Bargar, John R

    1999-01-01

    This workshop was requested by Dr. Robert Marianelli, Director of the DOE-BES Chemical Sciences Division, to update the findings of the Workshop on Molecular Environmental Sciences (MES) held at Airlie, VA, in July 1995. The Airlie Workshop Report defined the new interdisciplinary field referred to as Molecular Environmental Science (MES), reviewed the synchrotron radiation methods used in MES research, assessed the adequacy of synchrotron radiation facilities for research in this field, and summarized the beam time requirements of MES users based on a national MES user survey. The objectives of MES research are to provide information on the chemical and physical forms (speciation), spatial distribution, and reactivity of contaminants in natural materials and man-made waste forms, and to develop a fundamental understanding of the complex molecular-scale environmental processes, both chemical and biological, that affect the stability, transformations, mobility, and toxicity of contaminant species. These objectives require parallel studies of ''real'' environmental samples, which are complicated multi-phase mixtures with chemical and physical heterogeneities, and of simplified model systems in which variables can be controlled and fundamental processes can be examined. Only by this combination of approaches can a basic understanding of environmental processes at the molecular-scale be achieved

  4. Description of pelletizing facility

    Directory of Open Access Journals (Sweden)

    Čokorilo Vojin

    2006-01-01

    Full Text Available A lot of electrical energy in Serbia was used for heating, mainly for domes- tics. As it is the most expensive source for heating the government announced a National Program of Energy Efficiency with only one aim, to reduce the consumption of electric energy for the heating. One of the contributions to mentioned reduction is production of coal pellets from the fine coal and its use for domestic heating but also for heating of schools, hospitals, military barracks, etc. Annual production of fine coal in Serbia is 300,000 tons. The stacks of fine coal make a lot difficulties to the each mine because of environmental pollution, spontaneous combustion, low price, smaller market, etc. To prevent the difficulties and to give the contribution to National Program of Energy Efficiency researchers from the Department of Mining Engineering, University of Belgrade, designed and realized the project of fine coal pelletizing. This paper describes technical aspect of this project.

  5. Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

    International Nuclear Information System (INIS)

    Fujine, Sachio; Murata, Mikio; Abe, Hitoshi

    1999-09-01

    This report is the summary of the cause finding experiments and environmental analysis on the accident of the fire and explosion occurred at March 11th, 1997, in TRP bituminization facility of PNC (Power Reactor and Nuclear Fuel Development Corporation). Regarding the cause finding experiments, chemical components have been analyzed for the effluent samples taken from PNC's facility, bituminized mock waste has been produced using the simulated salt effluent prepared according to the results of chemical analysis, thermal analysis and experiment of runaway exothermic reaction have been conducted using the mock waste, and the component of flammable gases emitted from the heated waste have been collected and analyzed. Regarding environmental analysis on the accident, the amount of radioactive cesium released by the accident has been calculated by the comparative analysis using the atmospheric dispersion simulation code SPEEDI with the data of environmental monitoring and the public dose has been assessed. (author)

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    Energy Technology Data Exchange (ETDEWEB)

    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.

  7. Selection of facility location under environmental damage priority and using ELECTRE method.

    Science.gov (United States)

    Gundogdu, Ceren Erdin

    2011-03-01

    In the recent years, the environmental problems have reached to a vital extent, which is pushing the boundaries and far beyond daily evaluations. Industrial plants, the energy sources and uncontrolled release of pollutant gases (SO2, CO2 etc.) in the production stage have the greatest share in the occurrence of unfavorable environmental conditions. For this reason, the dimension of the problems that may arise in the production stage of industrial plants is directly related to the selection of facility location. In this study, geographical regions (a total of 7 regions) of our country have been analyzed in terms of environmental values based on their basins and the unfavorable environmental problems that are currently being experienced. Considered as such, with the directives of an expert group composed of nature scientists, the criteria and alternative areas are determined using the data gathered on ecosystem, basin characteristics, and land types. Since the primary goal is to keep the environmental damages at the minimum level, comprehensive definition of the problem is constructed by consultation of the expert group and the criteria are determined. Considering the fact that it will prevent the drawbacks generated by making decisions depending on certain stereotypes toa great extent, ELECTRE (Elimination and Choice Translating Reality English - Elimination Et Choix Traduisant la Realite) method is used to determine in which geographic region our country's industrial plants should be located.

  8. EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet Download

    Data.gov (United States)

    U.S. Environmental Protection Agency — This downloadable data package consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are...

  9. Outline of a fuel treatment facility in NUCEF

    International Nuclear Information System (INIS)

    Sugikawa, Susumu; Umeda, Miki; Kokusen, Junya

    1997-03-01

    This report presents outline of the nuclear fuel treatment facility for the purpose of preparing solution fuel used in Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF), including descriptions of process conditions and dimensions of major process equipments on dissolution system of oxide fuel, chemical adjustment system, purification system, acid recovery system, solution fuel storage system, and descriptions of safety design philosophy such as safety considerations of criticality, solvent fire, explosion of hydrogen and red-oil and so on. (author)

  10. SURF II: Characteristics, facilities, and plans

    International Nuclear Information System (INIS)

    Madden, R.P.; Canfield, R.; Furst, M.; Hamilton, A.; Hughey, L.

    1992-01-01

    This facility report describes the Synchrotron Ultraviolet Radiation Facility (SURF II) operated by the National Institute of Standards and Technology, Gaithersburg, Maryland. SURF II is a 300-MeV electron storage ring which provides well characterized continuum radiation from the far infrared to the soft x-ray region with the critical wavelength at 17.4 nm. Brief descriptions are given of the user facilities, the characteristics of the synchrotron radiation, the main storage ring, the injector system and each of the operating beam lines, and associated instruments. Further description is given of expansion plans for additional beam lines

  11. Waste isolation facility description for the spent fuel cycle, bedded salt

    International Nuclear Information System (INIS)

    1977-05-01

    Details are given on surface facilities, shafts and hoists, mine facilities, ventilation systems, land improvements, and utilities. Accidents, confinement, and safety criteria are covered. Appendices are provided on mine layout and development, mine operations, shaft construction information, and analysis concerning canister rupture inside the proposed waste isolation facility

  12. Waste Isolation Pilot Plant 2001 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, Inc.

    2002-09-20

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

  13. Waste Isolation Pilot Plant 2001 Site Environmental Report

    International Nuclear Information System (INIS)

    Westinghouse TRU Solutions, Inc.

    2002-01-01

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

  14. Waste Isolation Pilot Plant 1999 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

    2000-09-30

    The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

  15. Continuous monitoring system of environmental γ radiation near nuclear facility

    International Nuclear Information System (INIS)

    Jin Hua; Yue Qingyu; Wang Wenhai

    1996-01-01

    The continuous monitoring system for the environmental γ radiation and accident emergency near nuclear facility is described. The continuous monitoring system consists of high pressurized ionization chamber, integrated weak current amplifier, V-F converter and intelligent data recorder. PC 486 microcomputer with standard RS-232C interface is used for data handling and graph plotting. This intelligent data recorder has the functions of alarm over threshold and records the output signal of detector and temperature. The measuring range is from 10 nGy h -1 to 10 mGy h -1 because a high insulation switch automatical changing the measuring ranges is used. The monitoring system has been operating continuously for a long time with high stability and reliability

  16. Overview of the facility accident analysis for the U.S. Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    Mueller, C.; Habegger, L.; Huizenga, D.

    1994-01-01

    An integrated risk-based approach has been developed to address the human health risks of radiological and chemical releases from potential facility accidents in support of the U.S. Department of Energy (DOE) Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Accordingly, the facility accident analysis has been developed to allow risk-based comparisons of EM PEIS strategies for consolidating the storage and treatment of wastes at different sites throughout the country. The analysis has also been developed in accordance with the latest DOE guidance by considering the spectrum of accident scenarios that could occur in implementing the various actions evaluated in the EM PEIS. The individual waste storage and treatment operations and inventories at each site are specified by the functional requirements defined for each waste management alternative to be evaluated. For each alternative, the accident analysis determines the risk-dominant accident sequences and derives the source terms from the associated releases. This information is then used to perform health effects and risk calculations that are used to evaluate the various alternatives

  17. Facilities of Environmental Distinction

    Science.gov (United States)

    Pascopella, Angela

    2011-01-01

    Three of nine school buildings that have won the latest Educational Facility Design Awards from the American Institute of Architects (AIA) Committee on Architecture for Education stand out from the crowd of other school buildings because they are sustainable and are connected to the nature that surrounds them. They are: (1) Thurston Elementary…

  18. EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet Download

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

  19. EPA Linked Open Data: Facility Registry Service

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) identifies facilities, sites, or places subject to environmental regulation or of environmental interest to EPA programs or...

  20. Synchrotron radiation facilities

    CERN Multimedia

    1972-01-01

    Particularly in the past few years, interest in using the synchrotron radiation emanating from high energy, circular electron machines has grown considerably. In our February issue we included an article on the synchrotron radiation facility at Frascati. This month we are spreading the net wider — saying something about the properties of the radiation, listing the centres where synchrotron radiation facilities exist, adding a brief description of three of them and mentioning areas of physics in which the facilities are used.

  1. Physics Detector Simulation Facility Phase II system software description

    International Nuclear Information System (INIS)

    Scipioni, B.; Allen, J.; Chang, C.; Huang, J.; Liu, J.; Mestad, S.; Pan, J.; Marquez, M.; Estep, P.

    1993-05-01

    This paper presents the Physics Detector Simulation Facility (PDSF) Phase II system software. A key element in the design of a distributed computing environment for the PDSF has been the separation and distribution of the major functions. The facility has been designed to support batch and interactive processing, and to incorporate the file and tape storage systems. By distributing these functions, it is often possible to provide higher throughput and resource availability. Similarly, the design is intended to exploit event-level parallelism in an open distributed environment

  2. Description and Results: Antenna Measurement Facility Comparisons [Measurements Corner

    DEFF Research Database (Denmark)

    Alberica Saporetti, Maria; Foged, Lars; Sierra Castañer, Manuel

    2017-01-01

    In recent years, formalized facility comparison activities have become important for the documentation and validation of laboratory proficiency and competence and mandatory for achieving accreditation such as that of the International Organization for Standardization (ISO) 17025 or similar...... for Antennas (VISTA) IC1102, including still ongoing campaigns [3]-[5]. Results of these activities have led to improvements in antenna measurement procedures and protocols in facilities and standards [6], [7]. Due to the direct benefits available to the participants, the activities have been very successful...

  3. Disposal facility in Olkiluoto, description of above ground facilities in tunnel transport alternative

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-11-01

    The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or a by vehicle along the access tunnel. (orig.)

  4. Disposal facility in olkiluoto, description of above ground facilities in lift transport alternative

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-11-01

    The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m 3 . The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or by a vehicle along the access tunnel. (orig.)

  5. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A

    International Nuclear Information System (INIS)

    Bowman, R.C.

    1994-04-01

    This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification

  6. Chemical Transfer (Single Small-Scale) Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Description/History: Chemistry laboratoryThe Chemical Transfer Facility (CTF)  is the only U.S. single small-scale  facility, a single repository for the Army’s...

  7. Environmental research and environmental protection

    International Nuclear Information System (INIS)

    1975-01-01

    At the request of the Ministry for Research and Technology, the 'Arbeitsgemeinschaft der Grossforschungseinrichtungen' (AGF) presented in 1972 an information brochure called 'Activities in the field of environmental research and environmental protection', closely associated with the environmental programme of the Federal government (1971). The information brochure reports on those activities of the working group's members which are closely, or less closely, connected with questions concerning environmental research and protection, however, investments for the protection of the individual facilities in internal operation are excluded. The AGF programme 'Environmental research and environmental protection' comprises contributions, brought up to date, of member companies. From the 'AGF programme survey 1974' it contains 'Environmental research' as well as aspects of nuclear development with environmental relevance. Technologies not harmful to the environment developed by the research facilities are only mentioned very briefly. (orig.) [de

  8. NTES laser facility for physics experiments

    International Nuclear Information System (INIS)

    Christie, D.J.; Foley, R.J.; Frank, D.N.

    1989-01-01

    This paper discusses the following topics on the NTES laser facility: Mission Statement and Project Description; Experiment Area; High-Energy, Double-Pass Laser; Facilities; Laser Control and Data Acquisition; and Auxiliary Lasers

  9. A retrospective tiered environmental assessment of the Mount Storm Wind Energy Facility, West Virginia,USA

    Energy Technology Data Exchange (ETDEWEB)

    Efroymson, Rebecca Ann [ORNL; Day, Robin [No Affiliation; Strickland, M. Dale [Western EcoSystems Technology

    2012-11-01

    Bird and bat fatalities from wind energy projects are an environmental and public concern, with post-construction fatalities sometimes differing from predictions. Siting facilities in this context can be a challenge. In March 2012 the U.S. Fish and Wildlife Service (USFWS) released Land-based Wind Energy Guidelines to assess collision fatalities and other potential impacts to species of concern and their habitats to aid in siting and management. The Guidelines recommend a tiered approach for assessing risk to wildlife, including a preliminary site evaluation that may evaluate alternative sites, a site characterization, field studies to document wildlife and habitat and to predict project impacts, post construction studies to estimate impacts, and other post construction studies. We applied the tiered assessment framework to a case study site, the Mount Storm Wind Energy Facility in Grant County, West Virginia, USA, to demonstrate the use of the USFWS assessment approach, to indicate how the use of a tiered assessment framework might have altered outputs of wildlife assessments previously undertaken for the case study site, and to assess benefits of a tiered ecological assessment framework for siting wind energy facilities. The conclusions of this tiered assessment for birds are similar to those of previous environmental assessments for Mount Storm. This assessment found risk to individual migratory tree-roosting bats that was not emphasized in previous preconstruction assessments. Differences compared to previous environmental assessments are more related to knowledge accrued in the past 10 years rather than to the tiered structure of the Guidelines. Benefits of the tiered assessment framework include good communication among stakeholders, clear decision points, a standard assessment trajectory, narrowing the list of species of concern, improving study protocols, promoting consideration of population-level effects, promoting adaptive management through post

  10. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  11. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  12. DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

    International Nuclear Information System (INIS)

    C.E. Sanders

    2005-01-01

    This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

  13. 30 CFR 780.38 - Support facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 780.38 Section 780.38... Support facilities. Each applicant for a surface coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within the...

  14. 30 CFR 784.30 - Support facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Support facilities. 784.30 Section 784.30... Support facilities. Each applicant for an underground coal mining and reclamation permit shall submit a description, plans, and drawings for each support facility to be constructed, used, or maintained within the...

  15. Structuring the Environmental Experience Design Research Framework through Selected Aged Care Facility Data Analyses in Victoria

    Directory of Open Access Journals (Sweden)

    Nan Ma

    2017-11-01

    Full Text Available Humans relate to the living environment physically and psychologically. Environmental psychology has a rich developed history while experience design emerged recently in the industrial design domain. Nonetheless, these approaches have barely been merged, understood or implemented in architectural design practices. This study explored the correlation between experience design and environmental psychology. Moreover, it conducted literature reviews on theories about emotion, user experience design, experience design and environmental psychology, followed by the analyses of spatial settings and environmental quality data of a selected aged care facility in Victoria, Australia, as a case study. Accordingly, this study led to proposing a research framework on environmental experience design (EXD. It can be defined as a deliberate attempt that affiliates experience design and environmental psychology with creation of the built environment that should accommodate user needs and demands. The EXD research framework proposed in this study was tailored for transforming related design functions into the solutions that contribute to improving the built environment for user health and wellbeing.

  16. Gamma Irradiation Facility at Sandia National Laboratories, Albuquerque, New Mexico. Final environmental assessment

    International Nuclear Information System (INIS)

    1995-11-01

    The US Department of Energy (DOE) has prepared an environmental assessment (EA) on the proposed construction and operation of a new Gamma Irradiation Facility (GIF) at Sandia National Laboratories/New Mexico (SNL/NM). This facility is needed to: enhance capabilities to assure technical excellence in nuclear weapon radiation environments testing, component development, and certification; comply with all applicable ES and H safeguards, standards, policies, and regulations; reduce personnel radiological exposure to comply with ALARA limits in accordance with DOE orders and standards; consolidate major gamma ray sources into a central, secured area; and reduce operational risks associated with operation of the GIF and LICA in their present locations. This proposed action provides for the design, construction, and operation of a new GIF located within TA V and the removal of the existing GIF and Low Intensity Cobalt Array (LICA). The proposed action includes potential demolition of the gamma shield walls and removal of equipment in the existing GIF and LICA. The shielding pool used by the existing GIF will remain as part of the ACRR facility. Transportation of the existing 60 Co sources from the existing LICA and GIF to the new facility is also included in the proposed action. Relocation of the gamma sources to the new GIF will be accomplished by similar techniques to those used to install the sources originally

  17. Environmental Monitoring, Water Quality - Water Pollution Control Facilities

    Data.gov (United States)

    NSGIC Education | GIS Inventory — A Water Pollution Control Facility is a DEP primary facility type related to the Water Pollution Control Program. The sub-facility types related to Water Pollution...

  18. STREAMLINED APPROACH FOR ENVIRONMENTAL RESTORATION PLAN FOR CORRECTIVE ACTION UNIT 116: AREA 25 TEST CELL C FACILITY NEVADA TEST SITE, NEVADA

    International Nuclear Information System (INIS)

    2006-01-01

    This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada Test Site approximately 25 miles northwest of Mercury, Nevada

  19. Environmental assessment for the proposed construction and operation of a Genome Sequencing Facility in Building 64 at Lawrence Berkeley Laboratory, Berkeley, California

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This document is an Environmental Assessment (EA) for a proposed project to modify 14,900 square feet of an existing building (Building 64) at Lawrence Berkeley Laboratory (LBL) to operate as a Genome Sequencing Facility. This EA addresses the potential environmental impacts from the proposed modifications to Building 64 and operation of the Genome Sequencing Facility. The proposed action is to modify Building 64 to provide space and equipment allowing LBL to demonstrate that the Directed DNA Sequencing Strategy can be scaled up from the current level of 750,000 base pairs per year to a facility that produces over 6,000,000 base pairs per year, while still retaining its efficiency.

  20. Corrective action management unit application for the Environmental Restoration Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ``Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.`` The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ``package`` for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package.

  1. Corrective action management unit application for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Evans, G.C.

    1994-06-01

    The Environmental Restoration Disposal Facility (ERDF) is to accept both CERCLA (EPA-regulated) and RCRA (Ecology-regulated) remediation waste. The ERDF is considered part of the overall remediation strategy on the Hanford Site, and as such, determination of ERDF viability has followed both RCRA and CERCLA decision making processes. Typically, determination of the viability of a unit, such as the ERDF, would occur as part of record of decision (ROD) or permit modification for each remediation site before construction of the ERDF. However, because construction of the ERDF may take a significant amount of time, it is necessary to begin design and construction of the ERDF before final RODs/permit modifications for the remediation sites. This will allow movement of waste to occur quickly once the final remediation strategy for the RCRA and CERCLA past-practice units is determined. Construction of the ERDF is a unique situation relative to Hanford Facility cleanup, requiring a Hanford Facility specific process be developed for implementing the ERDF that would satisfy both RCRA and CERCLA requirements. While the ERDF will play a significant role in the remediation process, initiation of the ERDF does not preclude the evaluation of remedial alternatives at each remediation site. To facilitate this, the January 1994 amendment to the Tri-Party Agreement recognizes the necessity for the ERDF, and the Tri-Party Agreement states: ''Ecology, EPA, and DOE agree to proceed with the steps necessary to design, approve, construct, and operate such a ... facility.'' The Tri-Party Agreement requires the DOE-RL to prepare a comprehensive ''package'' for the EPA and Ecology to consider in evaluating the ERDF. The package is to address the criteria listed in 40 CFR 264.552(c) for corrective action management unit (CAMU) designation and a CERCLA ROD. This CAMU application is submitted as part of the Tri-Party Agreement-required information package

  2. EPA Geospatial Data Download: Facility and Site Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — Contains information about facilities or sites subject to environmental regulation, including key facility information along with associated environmental interests...

  3. Annual Status Report (FY2016) Performance Assessment for the Environmental Restoration Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Casbon, M. A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2017-03-15

    DOE O 435.1, Radioactive Waste Management, and DOE M 435.1-1, Radioactive Waste Management Manual, require that a determination of continued adequacy of the performance assessment (PA), composite analysis (CA), and disposal authorization statement (DAS) be made on an annual basis, and it must consider the results of data collection and analysis from research, field studies, and monitoring. Annual summaries of low-level waste (LLW) disposal operations must be prepared with respect to the conclusions and recommendations of the PA and CA, and a determination of the need to revise the PA or CA must be made. The annual summary requirement provides a structured approach for demonstrating the continued adequacy of the PA and CA in demonstrating a reasonable expectation that the performance objectives will be met. This annual summary addresses only the status of the Environmental Restoration Disposal Facility (ERDF) PA (CP-60089, Performance Assessment for the Environmental Restoration Disposal Facility, Hanford Site, Washington, formerly WCH-520 Rev. 1)1. The CA for ERDF is supported by DOE/RL-2016-62, Annual Status Report (FY 2016): Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site. The ERDF PA portion of the CA document is found in Section 3.1.4, and the ERDF operations portion is found in Section 3.3.3.2 of that document.

  4. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  5. Environmental assessment as a planning tool for the decommissioning of a nuclear research facility in Canada

    International Nuclear Information System (INIS)

    Klukas, M.H.; Grondin, D.J.; Helbrecht, R.A.

    2002-01-01

    Whiteshell Laboratories, a nuclear research facility operated by Atomic Energy of Canada Ltd. (AECL), have provided research facilities for the Canadian Nuclear Industry since the early 1960's. In 1997, AECL made a business decision to discontinue research programs and operations at the laboratories. Shortly thereafter the decision was made in agreement with the Federal Government of Canada to decommission the laboratories. In compliance with its own policy and to meet the requirements of the Canadian Legislation, AECL assessed the potential environmental effects of the project. The Environmental Assessment included studies to evaluate he feasibility of leaving two major project components in place; low-level radioactive waste in trenches located at the Whiteshell Laboratories site and river sediments contaminated from operational effluent releases. For both project components, it was determined that managing the wastes in the existing location was environmentally sound. An extensive follow-up program, comprising of additional monitoring and analysis to verify these findings will be implemented. As a result of these assessments and the assessments for other project components it was concluded that the project was not likely to cause significant adverse effects. The assessment decision was accepted by the Minister of the Environment in 2002 April. (author)

  6. Contribution to draft generic environmental impact statement on commercial waste management: radioactive waste isolation in geologic formations

    International Nuclear Information System (INIS)

    1978-04-01

    This document concentrates on deep geologic isolation of wastes in bedded salt, granite, shale, and basalt with emphasis on wastes from three fuel cycles: reprocessing wastes from uranium and plutonium recycling, reprocessing wastes from uranium-only recycling, and spent unreprocessed fuel with no recycling. The analyses presented in this document are based on preconceptual repository designs. As the repository designs progress through future phases, refinements will occur which might modify some of these results. The 12 sections in the report are: introduction; selection and description of generic repository sites; LWR wastes to be isolated in geologic formations; description of waste isolation facilities; effluents from the waste isolation facility; assessment of environment impacts for various geographical locations of a waste isolation facility; environmental monitoring; decommissioning; mine decommissioning site restoration; deep geologic alternative actions; potential mechanisms of containment failure; and considerations relevant to provisional versus final storage

  7. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

    International Nuclear Information System (INIS)

    2003-01-01

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF 6 ) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF 6 stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF 6 conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF 6 conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (DandD) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products

  8. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility; TOPICAL

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  9. 1994 Site environmental report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Fernald site is a Department of Energy (DOE)-owned facility that produced high-quality uranium metals for military defense for nearly 40 years. DOE suspended production at the site in 1989 and formally ended production in 1991. Although production activities have ceased, the site continues to examine the air and liquid pathways as possible routes through which pollutants from past operations and current remedial activities may leave the site. The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, General Environmental Protection Program. This 1994 SER provides the general public as well as scientists and engineers with the results from the site`s ongoing Environmental Monitoring Program. Also included in this report is information concerning the site`s progress toward achieving full compliance with requirements set forth by DOE, U.S. Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in this Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here. All information presented in this summary is discussed more fully in the main body of this report.

  10. 1994 Site environmental report

    International Nuclear Information System (INIS)

    1995-07-01

    The Fernald site is a Department of Energy (DOE)-owned facility that produced high-quality uranium metals for military defense for nearly 40 years. DOE suspended production at the site in 1989 and formally ended production in 1991. Although production activities have ceased, the site continues to examine the air and liquid pathways as possible routes through which pollutants from past operations and current remedial activities may leave the site. The Site Environmental Report (SER) is prepared annually in accordance with DOE Order 5400.1, General Environmental Protection Program. This 1994 SER provides the general public as well as scientists and engineers with the results from the site's ongoing Environmental Monitoring Program. Also included in this report is information concerning the site's progress toward achieving full compliance with requirements set forth by DOE, U.S. Environmental Protection Agency (USEPA), and Ohio EPA (OEPA). For some readers, the highlights provided in this Executive Summary may provide sufficient information. Many readers, however, may wish to read more detailed descriptions of the information than those which are presented here. All information presented in this summary is discussed more fully in the main body of this report

  11. Access to Sanitation Facilities among Nigerian Households: Determinants and Sustainability Implications

    Directory of Open Access Journals (Sweden)

    Ismaila Rimi Abubakar

    2017-04-01

    Full Text Available Access to improved sanitation facilities is key to the socioeconomic wellbeing and sustainable development of any society. This study examines access to sanitation facilities in Nigeria and explores the socioeconomic and locational factors that influence the type of facility used by households. The study utilizes cross-sectional data from the 2013 Nigeria Demographic and Health Survey, and employs descriptive and inferential statistics for data analyses. The results indicated that 44.2% of households used various kinds of pit latrines, followed by toilets that flush to septic tanks (10.3%. While only 5.3% of the respondents used toilets that connect to sewer systems, about a third (31.5% lacked sanitation facility and the remaining 8.7% used other types of sanitation facilities. Results from chi-square analysis and ANOVA revealed significant statistical differences between the type of sanitation facility households used and their place of residence, geopolitical zone, ethnicity, educational attainment and wealth. Multivariate regression results indicated that the type of household sanitation facility is significantly associated with the mentioned factors as well as household size, gender of the head of the household, type of water sources, number of rooms and access to electricity. Age of the head of the household and type of cooking fuel used were not significant. The study concludes by underscoring the implications of using unimproved sanitation facilities on human health and environmental sustainability.

  12. Concerning results of environmental monitoring around the reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1989-01-01

    The Central Evaluation Expert Group for Environmental radiation Monitoring has been engaged in examinations of plants for and results of the environmental radiation monitoring performed by Power Reactor and Nuclear Fuel Development Corporation around its reprocessing facilities. The present report outlines an examination of the results of monitoring carried out in 1987 (January to December). It is concluded that the methods used for the monitoring and its technical level are satisfactory in meeting the objectives of the monitoring plans. Expept for tritium in seawater, the level of radiations stays within the normal variation determined based on preliminary measurements of the background radiation. The procedure used for the calculation of exposure dose is also satisfactory in meeting the requirements specified in the monitoring plants. It is confirmed that the exposure dose of the residents around the facilities is well below the permissible exposure dose limite specified in law. (Nogami. K.)

  13. Environmental assessment [of nuclear installations

    International Nuclear Information System (INIS)

    Townsley, M.

    1989-01-01

    The European Community has introduced a directive which instructs that for all projects likely to have a significant effect on the environment consent should only be given after a rigorous assessment of such effects has been carried out and presented as an environmental statement. Projects requiring environmental assessment include nuclear power stations, any thermal power station over 300MW, any radioactive waste storage or disposal facility, any installation which produces electricity, power lines, installations for fuel production, fuel reprocessing, radioactive waste processing and fuel enrichment. The statement must include a description of the likely effects, direct and indirect, on the environment of the development, with reference to human beings, flora, fauna, soil, water, air, climate, landscape, interactions of two or more of these, material assets and cultural heritage. Measures to avoid or remedy the impact must be included. (U.K.)

  14. Socioeconomic information, Plainsboro area, New Jersey: Supplementary documentation for an environmental assessment for the CIT [Compact Ignition Tokamak] at PPPL

    International Nuclear Information System (INIS)

    Bentz, L.K.; Bender, D.S.

    1987-07-01

    This report contains socioeconomic information on the Plainsboro, New Jersey, area, the proposed location of the Compact Ignition Tokamak (CIT) facility. It was prepared as supplemental information for an environmental assessment for the CIT at Princeton Plasma Physics Laboratory (PPPL). The report contains descriptions of the demographic, economic, and community resource characteristics, and, based on information available in early 1987, considers the socioeconomic effect of the proposed facility. In all areas examined, the anticipated socioeconomic impacts of the proposed CIT facility at PPPL are negligible or minimal. 29 refs., 8 figs., 24 tabs

  15. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Oak Ridge Gaseous Diffusion Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) technology, with the near-term goal to provide the necessary information to make a deployment decision by November 1992. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. A programmatic document for use in screening DOE sites to locate the U-AVLIS production plant was developed and implemented in two parts (Wolsko et al. 1991). The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were then subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the ORGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use, socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3. Following the site description and additional data requirements, Sec. 4 provides a short, qualitative assessment of potential environmental issues. 37 refs., 20 figs., 18 tabs.

  16. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Oak Ridge Gaseous Diffusion Plant Site

    International Nuclear Information System (INIS)

    1991-09-01

    In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) technology, with the near-term goal to provide the necessary information to make a deployment decision by November 1992. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. A programmatic document for use in screening DOE sites to locate the U-AVLIS production plant was developed and implemented in two parts (Wolsko et al. 1991). The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were then subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the ORGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use, socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3. Following the site description and additional data requirements, Sec. 4 provides a short, qualitative assessment of potential environmental issues. 37 refs., 20 figs., 18 tabs

  17. Final Environmental Assessment: Consolidated Dining Facility at Joint Base McGuire-Dix-Lakehurst, New Jersey

    Science.gov (United States)

    2013-05-01

    intended to ‘provide a cornerstone of integrated mission, services, and recreational activities that is a walkable , convenient, and attractive...Training areas are intended to enhance existing or grow into walkable campuses with barracks, dining facilities, administrative support functions and...preserve natural lands and critical environmental areas, and protect water and ai r quality by encouraging developments that are mixed-use, walkable

  18. Executive Order 12898 and Social, Economic, and Sociopolitical Factors Influencing Toxic Release Inventory Facility Location in EPA Region 6: A Multi-Scale Spatial Assessment of Environmental Justice

    Science.gov (United States)

    Moore, Andrea Lisa

    2013-01-01

    Toxic Release Inventory facilities are among the many environmental hazards shown to create environmental inequities in the United States. This project examined four factors associated with Toxic Release Inventory, specifically, manufacturing facility location at multiple spatial scales using spatial analysis techniques (i.e., O-ring statistic and…

  19. Design of environmental monitoring system of nuclear facility based on a method of pattern recognition

    Energy Technology Data Exchange (ETDEWEB)

    Katoh, N; Kiyose, R; Yamamoto, Y [Tokyo Univ. (Japan). Faculty of Engineering

    1977-10-01

    The problem to optimize the number and locations of environmental radiation monitoring detectors is formulated by taking the specifically defined distance measures as a performance index and solved numerically using heuristic programming such as branch and bound method. An ideal numerical example neglecting noises due to background radiation, shows that the desirable number and locations of detectors are determined mainly by the atmospheric conditions and are not significantly influenced by the variation of the rate and pattern of activity release from the nuclear facility. It is shown also that the appropriate and sufficient number of monitoring detectors to be located around the facility will be from three to six at most, if considered from the viewpoint of pattern recognition.

  20. Environmental conditions in health care facilities in low- and middle-income countries: Coverage and inequalities.

    Science.gov (United States)

    Cronk, Ryan; Bartram, Jamie

    2018-04-01

    Safe environmental conditions and the availability of standard precaution items are important to prevent and treat infection in health care facilities (HCFs) and to achieve Sustainable Development Goal (SDG) targets for health and water, sanitation, and hygiene. Baseline coverage estimates for HCFs have yet to be formed for the SDGs; and there is little evidence describing inequalities in coverage. To address this, we produced the first coverage estimates of environmental conditions and standard precaution items in HCFs in low- and middle-income countries (LMICs); and explored factors associated with low coverage. Data from monitoring reports and peer-reviewed literature were systematically compiled; and information on conditions, service levels, and inequalities tabulated. We used logistic regression to identify factors associated with low coverage. Data for 21 indicators of environmental conditions and standard precaution items were compiled from 78 LMICs which were representative of 129,557 HCFs. 50% of HCFs lack piped water, 33% lack improved sanitation, 39% lack handwashing soap, 39% lack adequate infectious waste disposal, 73% lack sterilization equipment, and 59% lack reliable energy services. Using nationally representative data from six countries, 2% of HCFs provide all four of water, sanitation, hygiene, and waste management services. Statistically significant inequalities in coverage exist between HCFs by: urban-rural setting, managing authority, facility type, and sub-national administrative unit. We identified important, previously undocumented inequalities and environmental health challenges faced by HCFs in LMICs. The information and analyses provide evidence for those engaged in improving HCF conditions to develop evidence-based policies and efficient programs, enhance service delivery systems, and make better use of available resources. Copyright © 2018 The Authors. Published by Elsevier GmbH.. All rights reserved.

  1. Construction and operation of an improved radiation calibration facility at Brookhaven National Laboratory. Environmental assessment

    International Nuclear Information System (INIS)

    1994-10-01

    Calibration of instruments used to detect and measure ionizing radiation has been conducted over the last 20 years at Brookhaven National Laboratory's (BNL) Radiation Calibration Facility, Building 348. Growth of research facilities, projects in progress, and more stringent Department of Energy (DOE) orders which involve exposure to nuclear radiation have placed substantial burdens on the existing radiation calibration facility. The facility currently does not meet the requirements of DOE Order 5480.4 or American National Standards Institute (ANSI) N323-1978, which establish calibration methods for portable radiation protection instruments used in the detection and measurement of levels of ionizing radiation fields or levels of radioactive surface contaminations. Failure to comply with this standard could mean instrumentation is not being calibrated to necessary levels of sensitivity. The Laboratory has also recently obtained a new neutron source and gamma beam irradiator which can not be made operational at existing facilities because of geometry and shielding inadequacies. These sources are needed to perform routine periodic calibrations of radiation detecting instruments used by scientific and technical personnel and to meet BNL's substantial increase in demand for radiation monitoring capabilities. To place these new sources into operation, it is proposed to construct an addition to the existing radiation calibration facility that would house all calibration sources and bring BNL calibration activities into compliance with DOE and ANSI standards. The purpose of this assessment is to identify potential significant environmental impacts associated with the construction and operation of an improved radiation calibration facility at BNL

  2. 303-K Storage Facility closure plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-15

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  3. System description of the Repository-Only System for the FY 1990 systems integration program studies

    International Nuclear Information System (INIS)

    McKee, R.W.; Young, J.R.; Konzek, G.J.

    1991-07-01

    This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs

  4. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    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

  5. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    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.

  6. On results of monitoring of environmental radiation around Rokkasho reprocessing facilities (fiscal year 1995) (acknowledgement)

    International Nuclear Information System (INIS)

    1997-01-01

    The Nuclear Safety Commission received the report on this matter from the expert committee on environmental radiation monitoring central evaluation on August 30, 1996, and acknowledged it after the deliberation. The report was recognized as appropriate. The monitoring was carried out according to the monitoring plan for environmental radiation around Rokkasho reprocessing facilities. The monitoring plan is outlined. At the time of the deliberation, the propriety of the techniques of monitoring and technical level carried out by Japan Nuclear Fuel Service Co. was examined. As the result, it was confirmed that the techniques of monitoring and technical level were appropriate. The results of monitoring are reported. (K.I.)

  7. Draft CSA standard on environmental risk assessments at class I nuclear facilities and uranium mines and mills

    International Nuclear Information System (INIS)

    Hart, D.; Garisto, N.; Parker, R.; Kovacs, R.; Thompson, B.

    2012-01-01

    The Canadian Standards Association (CSA) is preparing a draft Standard on environmental risk assessments (ERAs) at Class I nuclear facilities and uranium mines and mills (CSA N288.6). It is being prepared by a technical subcommittee of the CSA N288 Technical Committee, including experts from across the nuclear industry, government and regulatory authorities, and environmental service providers, among others. It addresses the design, implementation, and management of environmental risk assessment programs, and is intended to standardize practice across the industry. This paper outlines the scope of the draft Standard and highlights key features. It is under development and subject to change. (author)

  8. Alternative disposal technologies for new low-level radioactive waste disposal/storage facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.

    1987-01-01

    A Draft Environmental Impact Statement for Waste Management Activities for groundwater protection has been prepared for the Savannah River Plant. Support documentation for the DEIS included an Environmental Information Document on new radioactive waste disposal and storage facilities in which possible alternative disposal technologies were examined in depth. Six technologies that would meet the needs of the Savannah River Plant that selected for description and analysis include near surface disposal, near surface disposal with exceptions, engineered storage, engineered disposal, vault disposal of untreated waste, and a combination of near surface disposal, engineered disposal, and engineered storage. 2 refs

  9. Forsmark - site descriptive model version 0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-10-01

    During 2002, the Swedish Nuclear Fuel and Waste Management Company (SKB) is starting investigations at two potential sites for a deep repository in the Precambrian basement of the Fennoscandian Shield. The present report concerns one of those sites, Forsmark, which lies in the municipality of Oesthammar, on the east coast of Sweden, about 150 kilometres north of Stockholm. The site description should present all collected data and interpreted parameters of importance for the overall scientific understanding of the site, for the technical design and environmental impact assessment of the deep repository, and for the assessment of long-term safety. The site description will have two main components: a written synthesis of the site, summarising the current state of knowledge, as documented in the databases containing the primary data from the site investigations, and one or several site descriptive models, in which the collected information is interpreted and presented in a form which can be used in numerical models for rock engineering, environmental impact and long-term safety assessments. The site descriptive models are devised and stepwise updated as the site investigations proceed. The point of departure for this process is the regional site descriptive model, version 0, which is the subject of the present report. Version 0 is developed out of the information available at the start of the site investigation. This information, with the exception of data from tunnels and drill holes at the sites of the Forsmark nuclear reactors and the underground low-middle active radioactive waste storage facility, SFR, is mainly 2D in nature (surface data), and is general and regional, rather than site-specific, in content. For this reason, the Forsmark site descriptive model, version 0, as detailed in the present report, has been developed at a regional scale. It covers a rectangular area, 15 km in a southwest-northeast and 11 km in a northwest-southeast direction, around the

  10. S. 1462: This Act may be cited as the Federal Nuclear Facilities Environmental Response Act. Introduced in the Senate of the United States, One Hundredth First Congress, First Session, August 1, 1989

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    S. 1462 is a bill to create a Federal nuclear facility environmental response fund, to create and Office of Environmental Management and Remedial Action, to require the Secretary of Energy and the Administrator of the Environmental Protection Agency to cooperate with affected States and Indian tribes, to provide for research and development to address environmental problems at Federal nuclear facilities, and for other purposes. The basic purpose of the act is to provide and adequate, long-term source of funding for environmental restoration, decontamination, decommissioning, and management of Federal nuclear facilities and sites

  11. Annual Radiological Environmental Monitoring Program Report for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation

    International Nuclear Information System (INIS)

    Hall, Gregory Graham

    2002-01-01

    This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the two predominant radiation exposure pathways, potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

  12. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    International Nuclear Information System (INIS)

    Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

    2001-01-01

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse

  13. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

    2001-12-31

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no

  14. Levels of tritium in soils and vegetation near Canadian nuclear facilities releasing tritium to the atmosphere: implications for environmental models

    International Nuclear Information System (INIS)

    Thompson, P.A.; Kwamena, N.-O.A.; Ilin, M.; Wilk, M.; Clark, I.D.

    2015-01-01

    Concentrations of organically bound tritium (OBT) and tritiated water (HTO) were measured over two growing seasons in vegetation and soil samples obtained in the vicinity of four nuclear facilities and two background locations in Canada. At the background locations, with few exceptions, OBT concentrations were higher than HTO concentrations: OBT/HTO ratios in vegetation varied between 0.3 and 20 and values in soil varied between 2.7 and 15. In the vicinity of the four nuclear facilities OBT/HTO ratios in vegetation and soils deviated from the expected mean value of 0.7, which is used as a default value in environmental transfer models. Ratios of the OBT activity concentration in plants ([OBT] plant ) to the OBT activity concentration in soils ([OBT] soil ) appear to be a good indicator of the long-term behaviour of tritium in soil and vegetation. In general, OBT activity concentrations in soils were nearly equal to OBT activity concentrations in plants in the vicinity of the two nuclear power plants. [OBT] plant /[OBT] soil ratios considerably below unity observed at one nuclear processing facility represents historically higher levels of tritium in the environment. The results of our study reflect the dynamic nature of HTO retention and OBT formation in vegetation and soil during the growing season. Our data support the mounting evidence suggesting that some parameters used in environmental transfer models approved for regulatory assessments should be revisited to better account for the behavior of HTO and OBT in the environment and to ensure that modelled estimates (e.g., plant OBT) are appropriately conservative. - Highlights: • We measured tritium in soils and plants near four nuclear facilities in Canada. • OBT/HTO ratios in plants are higher than default value in environmental models. • OBT/HTO ratios in background soils reflect historically higher atmospheric tritium. • Implications for environmental transfer models are discussed

  15. Lepreau 2 environmental impact statement

    International Nuclear Information System (INIS)

    1984-05-01

    Maritime Nuclear, a joint undertaking of Atomic Energy of Canada Limited and the New Brunswick Electric Power Commission, proposes to construct a second CANDU 600 MW nuclear-powered generating unit at the site of the existing Point Lepreau Generating Station, in New Brunswick. A feasibility study is now underway and guidelines issued by the Lepreau 2 Environmental Assessment Panel identified six priority issues and concerns. These are: impacts on the biological environment, impacts of radiation on humans, impacts on the socio-economic environment, monitoring, emergency planning, and decommissioning. These factors as well as a description of the site and proposed facility are described in this report

  16. Lawrence Livermore National Laboratory Decontamination and Waste Treatment Facility: Documentation of impact analysis for design alternatives presented in the Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1988-05-01

    Lawrence Livermore National Laboratory (LLNL) is proposing to construct and operate a new Decontamination and Waste Treatment Facility (DWTF). The proposed DWTF would replace the existing Hazardous Waste Management (HWM) facilities at LLNL. The US Department of Energy (DOE) is preparing a Draft Environmental Impact Statement (DEIS) to assess the environmental consequences of the proposed DWTF and its alternatives. This report presents the assumptions, methodologies, and analyses used to estimate the waste flows, air emissions, ambient air quality impacts, and public health risks that are presented in the DEIS. Two DWTF design alternatives (Level I and Level II) have been designated as reasonable design alternatives considering available technologies, environmental regulations, and current and future LLNL waste generation. Both design alternatives would include new, separate radioactive and nonradioactive liquid waste treatment systems, a solidification unit, a new decontamination facility, storage and treatment facilities for reactive materials, a radioactive waste storage area, receiving and classification areas, and a uranium burn pan. The Level I design alternative would include a controlled-air incinerator system, while the Level II design alternative would include a rotary kiln incinerator system. 43 refs., 4 figs., 24 tabs

  17. WRAP Module 1 data management system (DMS) software design description (SDD)

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1996-01-01

    Revision 2 of the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) Preliminary Software Design Description (PSDD) provides a high-level design description of the system. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility. The WRAP 1 DMS SDD is used as the primary medium for communication software design information. This release provides design descriptions for the following process modules produced under Phase 1 of the development effort: Receiving Drum or Box Containers Process Routing and Picklists; Waste Inventory by Location and/or Container Relationships; LLW Process Glovebox Facility Radiologic Material Inventory Check (partial); Shipping (partial production); Drum or Box NDE Operations; and Drum or Box NDA Operations Data Review (partial production). In addition, design descriptions are included for the following process modules scheduled for development under Phases 2 and 3: Activity Comment; LLW RWM Glovebox Sample Management; TRU Process Glovebox; TRU RWM Glovebox; and TRUPACT Processing. Detailed design descriptions for Reports and Facility Metrics have also been provided for in Revision 2 of this document

  18. Environmental Compliance and Pollution Prevention Training Manual for Campus-Based Organizations--Operational and Facility Maintenance Personnel.

    Science.gov (United States)

    New York State Dept. of Environmental Conservation, Albany.

    This manual was designed to be used as part of the Workshop on Environmental Compliance and Pollution Prevention for campus-based facilities. It contains basic information on New York state and federal laws, rules, and regulations for protecting the environment. The information presented is a summary with emphasis on those items believed to be…

  19. Waste Receiving and Processing Facility Module 1: Volume 1, Preliminary Design report

    International Nuclear Information System (INIS)

    1992-03-01

    The Preliminary Design Report (Title 1) for the Waste Receiving and Processing (WRAP) Module 1 provides a comprehensive narrative description of the proposed facility and process systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title 1 design. The primary mission of the WRAP 1 Facility is to characterize and certify contact-handled (CH) waste in 55-gallon drums for disposal. Its secondary function is to certify CH waste in Standard Waste Boxes (SWBs) for disposal. The preferred plan consist of retrieving the waste and repackaging as necessary in the Waste Receiving and Processing (WRAP) facility to certify TRU waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. WIPP is a research and development facility designed to demonstrate the safe and environmentally acceptable disposal of TRU waste from National Defense programs. Retrieved waste found to be Low-Level Waste (LLW) after examination in the WRAP facility will be disposed of on the Hanford site in the low-level waste burial ground. The Hanford Site TRU waste will be shipped to the WIPP for disposal between 1999 and 2013

  20. Armament Technology Facility (ATF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....