Mobility of radionuclides and trace elements in soil from legacy NORM and undisturbed naturally 232Th-rich sites.

Science.gov (United States)

Mrdakovic Popic, Jelena; Meland, Sondre; Salbu, Brit; Skipperud, Lindis

2014-05-01

Investigation of radionuclides (232Th and 238U) and trace elements (Cr, As and Pb) in soil from two legacy NORM (former mining sites) and one undisturbed naturally 232Th-rich site was conducted as a part of the ongoing environmental impact assessment in the Fen Complex area (Norway). The major objectives were to determine the radionuclide and trace element distribution and mobility in soils as well as to analyze possible differences between legacy NORM and surrounding undisturbed naturally 232Th-rich soils. Inhomogeneous soil distribution of radionuclides and trace elements was observed for each of the investigated sites. The concentration of 232Th was high (up to 1685 mg kg(-1), i.e., ∼7000 Bq kg(-1)) and exceeded the screening value for the radioactive waste material in Norway (1 Bq g(-1)). Based on the sequential extraction results, the majority of 232Th and trace elements were rather inert, irreversibly bound to soil. Uranium was found to be potentially more mobile, as it was associated with pH-sensitive soil phases, redox-sensitive amorphous soil phases and soil organic compounds. Comparison of the sequential extraction datasets from the three investigated sites revealed increased mobility of all analyzed elements at the legacy NORM sites in comparison with the undisturbed 232Th-rich site. Similarly, the distribution coefficients Kd (232Th) and Kd (238U) suggested elevated dissolution, mobility and transportation at the legacy NORM sites, especially at the decommissioned Nb-mining site (346 and 100 L kg(-1) for 232Th and 238U, respectively), while the higher sorption of radionuclides was demonstrated at the undisturbed 232Th-rich site (10,672 and 506 L kg(-1) for 232Th and 238U, respectively). In general, although the concentration ranges of radionuclides and trace elements were similarly wide both at the legacy NORM and at the undisturbed 232Th-rich sites, the results of soil sequential extractions together with Kd values supported the expected differences

Waste minimization applications at a remediation site

International Nuclear Information System (INIS)

Allmon, L.A.

1995-01-01

The Fernald Environmental Management Project (FEMP) owned by the Department of Energy was used for the processing of uranium. In 1989 Fernald suspended production of uranium metals and was placed on the National Priorities List (NPL). The site's mission has changed from one of production to environmental restoration. Many groups necessary for producing a product were deemed irrelevant for remediation work, including Waste Minimization. Waste Minimization does not readily appear to be applicable to remediation work. Environmental remediation is designed to correct adverse impacts to the environment from past operations and generates significant amounts of waste requiring management. The premise of pollution prevention is to avoid waste generation, thus remediation is in direct conflict with this premise. Although greater amounts of waste will be generated during environmental remediation, treatment capacities are not always available and disposal is becoming more difficult and costly. This creates the need for pollution prevention and waste minimization. Applying waste minimization principles at a remediation site is an enormous challenge. If the remediation site is also radiologically contaminated it is even a bigger challenge. Innovative techniques and ideas must be utilized to achieve reductions in the amount of waste that must be managed or dispositioned. At Fernald the waste minimization paradigm was shifted from focusing efforts on source reduction to focusing efforts on recycle/reuse by inverting the EPA waste management hierarchy. A fundamental difference at remediation sites is that source reduction has limited applicability to legacy wastes but can be applied successfully on secondary waste generation. The bulk of measurable waste reduction will be achieved by the recycle/reuse of primary wastes and by segregation and decontamination of secondary wastestreams. Each effort must be measured in terms of being economically and ecologically beneficial

Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation

International Nuclear Information System (INIS)

Scheblanov, V Y; Bobrov, A F; Sneve, M K

2012-01-01

This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical–Biological Agency of Russia and the Norwegian Radiation Protection Authority. (paper)

Radio-ecological characterization and radiological assessment in support of regulatory supervision of legacy sites in northwest Russia.

Science.gov (United States)

Sneve, M K; Kiselev, M; Shandala, N K

2014-05-01

The Norwegian Radiation Protection Authority has been implementing a regulatory cooperation program in the Russian Federation for over 10 years, as part of the Norwegian government's Plan of Action for enhancing nuclear and radiation safety in northwest Russia. The overall long-term objective has been the enhancement of safety culture and includes a special focus on regulatory supervision of nuclear legacy sites. The initial project outputs included appropriate regulatory threat assessments, to determine the hazardous situations and activities which are most in need of enhanced regulatory supervision. In turn, this has led to the development of new and updated norms and standards, and related regulatory procedures, necessary to address the often abnormal conditions at legacy sites. This paper presents the experience gained within the above program with regard to radio-ecological characterization of Sites of Temporary Storage for spent nuclear fuel and radioactive waste at Andreeva Bay and Gremikha in the Kola Peninsula in northwest Russia. Such characterization is necessary to support assessments of the current radiological situation and to support prospective assessments of its evolution. Both types of assessments contribute to regulatory supervision of the sites. Accordingly, they include assessments to support development of regulatory standards and guidance concerning: control of radiation exposures to workers during remediation operations; emergency preparedness and response; planned radionuclide releases to the environment; development of site restoration plans, and waste treatment and disposal. Examples of characterization work are presented which relate to terrestrial and marine environments at Andreeva Bay. The use of this data in assessments is illustrated by means of the visualization and assessment tool (DATAMAP) developed as part of the regulatory cooperation program, specifically to help control radiation exposure in operations and to support

Strategies for the cost effective treatment of Oak Ridge legacy wastes

International Nuclear Information System (INIS)

Compere, A.L.; Griffith, W.L.; Huxtable, W.P.; Wilson, D.F.

1998-03-01

Research and development treatment strategies for treatment or elimination of several Oak Ridge plant liquid, solid, and legacy wastes are detailed in this report. Treatment strategies for volumetrically contaminated nickel; enriched uranium-contaminated alkali metal fluorides; uranium-contaminated aluminum compressor blades; large, mercury-contaminated lithium isotope separations equipment; lithium process chlorine gas streams; high-concentration aluminum nitrate wastes, and high-volume, low-level nitrate wastes are discussed. Research needed to support engineering development of treatment processes is detailed

Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

International Nuclear Information System (INIS)

Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

2006-01-01

AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

Characterization of legacy low level waste at the Svafo facility using gamma non-destructive assay and X-ray non-destructive examination techniques - 59289

International Nuclear Information System (INIS)

Halliwell, Stephen; Mottershead, Gary; Ekenborg, Fredrik

2012-01-01

Document available in abstract form only. Full text of publication follows: Over 7000 drums containing legacy, low level radioactive waste are stored at four SVAFO facilities on the Studsvik site which is located near Nykoeping, Sweden. The vast majority of the waste drums (>6000) were produced between 1969 and 1979. The remainder were produced from 1980 onwards. Characterization of the waste was achieved using a combination of non-destructive techniques via mobile equipment located in the AU building at the Studsvik site. Each drum was weighed and a dose rate measurement was recorded. Gamma spectroscopy was used to measure and estimate radionuclide content. Real time xray examination was performed to identify such prohibited items as free liquids. (authors)

Overview of radium legacies in Belgium - 59367

International Nuclear Information System (INIS)

Dehandschutter, B.; Jadoul, L.; Mannaerts, K.; Pepin, S.; Poffijn, A.; Blommaert, W.; Sonck, M.

2012-01-01

The Belgian metallurgical company, Union Miniere, has been a key-player in the sector of radium production between 1922 and 1969. The factory based in Olen has extracted radium from minerals and produced radium sources during that period. The radium production facilities have been dismantled in the 70's but legacies of the former production have still to be remediated. An overview of these legacies and of their radiological characteristics will be given. Next to the sites related to radium production, other radium legacies are related to NORM industries, essentially from the phosphate sector (phosphogypsum and CaF 2 stacks). The issue of radium legacies in Belgium encompasses a variety of concrete situations. Next to the issue of the legacies of the former radium production, the other radium contaminated sites are related to current or former NORM industries, especially from the phosphate sector. The methodological and regulatory approaches towards these sites have been described elsewhere in these proceedings. The outcome differs according to the specificities of the site: it will not be the same for the legacies of former radium production where the inventory of radioactivity includes materials which have to be considered and treated as radioactive waste (for example, disused radium sources) than for phosphogypsum stacks where a sufficient level of protection may be brought by relatively simple measures such as restrictions on the use of the site. For these sites, like PG stacks, where radon is the most important exposure pathway in case of intrusion scenario, regulatory measures similar to the ones applied to 'radon-prone areas' (restrictions in the construction of buildings, compulsory radon monitoring in workplaces present on the site,...) may be implemented. In all cases, the radiological risk-assessment will be crucial for the decision-making process. The examples given showed that the probability of occurrence of 'intrusion scenario' (like construction of

Radiation and environmental monitoring at the nuclear legacy sites in Russia

Energy Technology Data Exchange (ETDEWEB)

Shandala, N.; Kiselev, S.; Titov, A.; Seregin, V.; Akhromeev, S.; Aladova, R.; Isaev, D. [SRC Burnasyan Federal Medical Biophysical Center (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority - NRPA (Norway)

2014-07-01

In 1960's, in the Northwest and Far East regions of Russia the technical bases of the Navy Fleet were built to maintain nuclear submarines by performing reloading of nuclear fuel, receiving and storing radioactive waste (RW) and spent nuclear fuel (SNF). In 2000, SevRAO enterprise in the northwest of Russia and DalRAO enterprise in the Far East were set up for the purposes of environmental remediation of the nuclear legacy sites. Regulatory supervision for radiation protection and safety at the nuclear legacy sites in Russian Far east and Northwest regions is one of regulatory functions of the Federal medical biological agency (FMBA of Russia). Improvement of the normative and regulatory basis has significant impact on effectiveness and efficiency of industrial projects aimed at reduction of nuclear and radiation hazard risk at the sites for the SNF and RW temporary storage (STS).To get unbiased comprehensive information on the current radiation conditions at the STSs and provide the effective response to changing radiation situation, the environmental radiation monitoring of the SevRAO and DalRAO facilities has been carried out during 2005-2013. The nature and peculiarity of the STS area radioactive contamination on the Kola Peninsula and in the Far East are the following: 1) high levels of radioactive contamination on the industrial site; 2) non-uniformity of the contamination distribution; 3) spread of contamination in the area of health protection zone. The following environmental components are contaminated: soil, vegetation, bottom sediments and seaweeds at the offshore sea waters. The dominant radionuclides are cesium-137 and strontium-90. At the facilities under inspection for the purpose of the dynamic control of the radiation situation the radio-ecological monitoring system was arranged. It presupposes regular radiometry inspections in-situ, their analysis and assessment of the radiation situation forecast in the course of the STS remediation main

Challenges in development of matrices for vitrification of old legacy waste and high-level radioactive waste generated from reprocessing of AHWR and FBR spent fuel

International Nuclear Information System (INIS)

Kaushik, C.P.

2012-01-01

Majority of radioactivity in entire nuclear fuel cycle is concentrated in HLW. A three step strategy for management of HLW has been adopted in India. This involves immobilization of waste oxides in stable and inert solid matrices, interim retrievable storage of the conditioned waste product under continuous cooling and disposal in deep geological formations. Glass has been accepted as most suitable matrix world-wide for immobilization of HLW, because of its attractive features like ability to accommodate wide range of waste constituents, modest processing temperatures, adequate chemical, thermal and radiation stability. Borosilicate glass matrix developed by BARC in collaboration with CGCRI has been adopted in India for immobilization of HLW. In view of compositional variation of HLW from site to site, tailor make changes in the glass formulations are often necessary to incorporate all the waste constituents and having the product of desirable characteristics. The vitrified waste products made with different glass formulations and simulated waste need to be characterized for chemical durability, thermal stability, homogeneity etc. before finalizing a suitable glass formulation. The present extended abstract summarises the studies carried out for development of glass formulations for vitrification of legacy waste and futuristic waste likely to be generated from AHWR and FBR having wide variations in their compositions. The presently stored HLW at Trombay is characterized by significant concentrations of uranium, sodium and sulphate in addition to fission products, corrosion products and small amount of other actinides

Regulatory Oversight of the Legacy Gunner Uranium Mine and Mill Site in Northern Saskatchewan, Canada - 13434

Energy Technology Data Exchange (ETDEWEB)

Stenson, Ron; Howard, Don [Canadian Nuclear Safety Commission, P.O. Box 1046, Station B, 280 Slater Street, Ottawa ON K1P 5S9 (Canada)

2013-07-01

As Canada's nuclear regulator, the Canadian Nuclear Safety Commission (CNSC) is responsible for licensing all aspects of uranium mining, including remediation activities at legacy sites. Since these sites already existed when the current legislation came into force in 2000, and the previous legislation did not apply, they present a special case. The Nuclear Safety and Control Act (NSCA), was written with cradle-to- grave oversight in mind. Applying the NSCA at the end of a 'facilities' life-cycle poses some challenges to both the regulator and the proponent. When the proponent is the public sector, even more challenges can present themselves. Although the licensing process for legacy sites is no different than for any other CNSC license, assuring regulatory compliance can be more complicated. To demonstrate how the CNSC has approached the oversight of legacy sites the history of the Commission's involvement with the Gunnar uranium mine and mill site provides a good case study. The lessons learned from the CNSC's experience regulating the Gunnar site will benefit those in the future who will need to regulate legacy sites under existing or new legislation. (authors)

Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

Energy Technology Data Exchange (ETDEWEB)

Wilmarth, William R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, Micheal R.; Thompson, Major C.; Suggs, Patricia C.; Machara, N.

2011-01-13

The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste that has been generated during the production of nuclear weapons in the United States. The vast bulk of this waste material is stored in underground tanks at the Savannah River Site in South Carolina and the Hanford Site in Washington State. The general strategy for treating the radioactive tank waste consists of first separating the waste into high-level and low-activity fractions. This initial partitioning of the waste is referred to as pretreatment. Following pretreatment, the high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for disposal at the respective site. This paper provides a review of recent developments in the application of pretreatment technologies to the processing of the Hanford and Savannah River radioactive tank wastes. Included in the review are discussions of 1) solid/liquid separations methods, 2) cesium separation technologies, and 3) other separations critical to the success of the DOE tank waste remediation effort. Also included is a brief discussion of the different requirements and circumstances at the two DOE sites that have in some cases led to different choices in pretreatment technologies.

Architectural Framework for Addressing Legacy Waste from the Cold War - 13611

Energy Technology Data Exchange (ETDEWEB)

Love, Gregory A.; Glazner, Christopher G.; Steckley, Sam [The MITRE Corporation, 7515 Colshire Drive, McLean, VA 22102 (United States)

2013-07-01

We present an architectural framework for the use of a hybrid simulation model of enterprise-wide operations used to develop system-level insight into the U.S. Department of Energy's (DOE) environmental cleanup of legacy nuclear waste at the Savannah River Site. We use this framework for quickly exploring policy and architectural options, analyzing plans, addressing management challenges and developing mitigation strategies for DOE Office of Environmental Management (EM). The socio-technical complexity of EM's mission compels the use of a qualitative approach to complement a more a quantitative discrete event modeling effort. We use this model-based analysis to pinpoint pressure and leverage points and develop a shared conceptual understanding of the problem space and platform for communication among stakeholders across the enterprise in a timely manner. This approach affords the opportunity to discuss problems using a unified conceptual perspective and is also general enough that it applies to a broad range of capital investment/production operations problems. (authors)

Architectural Framework for Addressing Legacy Waste from the Cold War - 13611

International Nuclear Information System (INIS)

Love, Gregory A.; Glazner, Christopher G.; Steckley, Sam

2013-01-01

We present an architectural framework for the use of a hybrid simulation model of enterprise-wide operations used to develop system-level insight into the U.S. Department of Energy's (DOE) environmental cleanup of legacy nuclear waste at the Savannah River Site. We use this framework for quickly exploring policy and architectural options, analyzing plans, addressing management challenges and developing mitigation strategies for DOE Office of Environmental Management (EM). The socio-technical complexity of EM's mission compels the use of a qualitative approach to complement a more a quantitative discrete event modeling effort. We use this model-based analysis to pinpoint pressure and leverage points and develop a shared conceptual understanding of the problem space and platform for communication among stakeholders across the enterprise in a timely manner. This approach affords the opportunity to discuss problems using a unified conceptual perspective and is also general enough that it applies to a broad range of capital investment/production operations problems. (authors)

MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION

International Nuclear Information System (INIS)

West, L.D.

2011-01-01

The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W and FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m 3 of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% (∼8,000 m 3 ) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

Bridging the gap between tribal risk perceptions and scientific decision-making for uranium legacy sites located in Native American communities

Science.gov (United States)

Joseph, C.; Waugh, W.; Glenn, E.; Chief, K.

2017-12-01

There are approximately 15,000 abandoned uranium mines (AUM) in the western United States, of which 500 AUMs are located in the Colorado Plateau Four-Corners region. Uranium mill tailings, referred to as legacy waste, compromise the largest volume of any category of radioactive waste in the nation. Today, the Department of Energy Legacy Management is responsible for long-term stewardship and maintenance of inactive uranium processing sites that have been remediated to prevent further migration and exposure of tailings to the environment and surrounding communities. In collaboration with the DOE-LM, I am investigating the impact of climate change and community adaptation on the long-term performance of disposal cell covers for uranium mill tailings located in Native American communities, as well as how these communities have adapted to and perceive these areas. I am interested in how abiotic engineered cell covers may be candidate sites for future conversion to vegetated evapotranspirative caps for arid to semi-arid climates. The objectives are to: 1) assess above-ground tissue of plants encroaching engineered cell covers for concentrations of uranium, radium, selenium, molybdenum, thorium, arsenic, lead, and manganese and compare them to control sites; 2) determine if above-cell plant tissue is accumulating to toxic levels that may create an exposure pathway, 3) identify climate scenarios for site locations and determine how short-and long-scale climate projections will influence spatial and temporal plant distribution for specific woody species; and 4) evaluate the risk perceptions of Hopi villages located five miles downstream of one site location. To date, risk perception and stakeholder outreach to the Hopi communities has been absent. This study will help inform how land use, water use, and sustenance practices may contribute to environmental health disparities for one of the few tribes that has maintained physical continuity within their ancestral homeland.

1997 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

International Nuclear Information System (INIS)

Segall, P.

1998-01-01

Hanford's missions are to safely clean up and manage the site's legacy wastes, and to develop and deploy science and technology. Through these missions Hanford will contribute to economic diversification of the region. Hanford's environmental management or cleanup mission is to protect the health and safety of the public, workers, and the environment; control hazardous materials; and utilize the assets (people, infra structure, site) for other missions. Hanford's science and technology mission is to develop and deploy science and technology in the service of the nation including stewardship of the Hanford Site. Pollution Prevention is a key to the success of these missions by reducing the amount of waste to be managed and identifying/implementing cost effective waste reduction projects. Hanford's original mission, the production of nuclear materials for the nation's defense programs, lasted more than 40 years, and like most manufacturing operations, Hanford's operations generated large quantities of waste and pollution. However, the by-products from Hanford operations pose unique problems like radiation hazards, vast volumes of contaminated water and soil, and many contaminated structures including reactors, chemical plants and evaporation ponds. The cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single shell storage tanks, treating 28 double shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored on site, removing numerous structures, and dealing with significant solid waste, ground water, and land restoration issues

An investigation of the suitability of the Chalk River site to host a geologic waste management facility for CRL's low and intermediate level wastes

International Nuclear Information System (INIS)

Thompson, P.; Baumgartner, P.; Chan, T.; Kitson, C.; Kozak, E.; Man, A.; Martino, J.; Stroes-Gascoyne, S.; Beaton, D.; Sharp, K.; Thivierge, R.

2011-01-01

Atomic Energy of Canada Limited (AECL) is investigating the suitability of the Chalk River Laboratories (CRL) site for hosting a Geologic Waste Management Facility (GWMF) as part of the Nuclear Legacy Liabilities Program (NLLP) funded through Natural Resources Canada (NRCan). The GWMF is envisioned to be an underground engineered-geological repository consisting of shafts, access tunnels and emplacement caverns located at a nominal depth of 500 to 1000 m in the bedrock at the CRL site. A 5-year-long pre-project study was started in 2006 to assess the feasibility of the bedrock at the CRL site to host a GWMF. The pre-project feasibility study began with a review of various previous geological investigations performed in the bedrock at the CRL site. The 2006-2010 pre-project feasibility study involved exploring the geoscience and engineering characteristics of the bedrock to depths of over one kilometre at the CRL site through surface investigations and the drilling and testing of seven new deep characterization boreholes into the CRL bedrock. The collected information and interpretations were used to construct three-dimensional (3D) deterministic computer models of the geology of the bedrock at the CRL site and surrounding area and of the associated groundwater-flow regime. In order to technically assess the suitability of the CRL site, the GWMF feasibility study has conservatively assumed that all of the legacy and forecast Low and Intermediate Level Waste (LILW) at CRL would report to it. The 3D deterministic models were used within a preliminary performance and safety assessment model to assess the long-term safety of a hypothetical GWMF at the CRL site on the basis of future radionuclide and toxic substance releases. Other items important to a preliminary performance and safety assessment include an inventory of CRL's radioactive wastes and other contaminants that could be placed in the GWMF, the creation of the engineered waste emplacement rooms and

Life cycle assessment of integrated waste management systems for alternative legacy scenarios of the London Olympic Park

Energy Technology Data Exchange (ETDEWEB)

Parkes, Olga, E-mail: o.parkes@ucl.ac.uk; Lettieri, Paola, E-mail: p.lettieri@ucl.ac.uk; Bogle, I. David L.

2015-06-15

Highlights: • Application of LCA in planning integrated waste management systems. • Environmental valuation of 3 legacy scenarios for the Olympic Park. • Hot-spot analysis highlights the importance of energy and materials recovery. • Most environmental savings are achieved through materials recycling. • Sensitivity analysis shows importance of waste composition and recycling rates. - Abstract: This paper presents the results of the life cycle assessment (LCA) of 10 integrated waste management systems (IWMSs) for 3 potential post-event site design scenarios of the London Olympic Park. The aim of the LCA study is to evaluate direct and indirect emissions resulting from various treatment options of municipal solid waste (MSW) annually generated on site together with avoided emissions resulting from energy, materials and nutrients recovery. IWMSs are modelled using GaBi v6.0 Product Sustainability software and results are presented based on the CML (v.Nov-10) characterisation method. The results show that IWMSs with advanced thermal treatment (ATT) and incineration with energy recovery have the lowest Global Warming Potential (GWP) than IWMSs where landfill is the primary waste treatment process. This is due to higher direct emissions and lower avoided emissions from the landfill process compared to the emissions from the thermal treatment processes. LCA results demonstrate that significant environmental savings are achieved through substitution of virgin materials with recycled ones. The results of the sensitivity analysis carried out for IWMS 1 shows that increasing recycling rate by 5%, 10% and 15% compared to the baseline scenario can reduce GWP by 8%, 17% and 25% respectively. Sensitivity analysis also shows how changes in waste composition affect the overall result of the system. The outcomes of such assessments provide decision-makers with fundamental information regarding the environmental impacts of different waste treatment options necessary for

Testing contamination risk assessment methods for toxic elements from mine waste sites

Science.gov (United States)

Abdaal, A.; Jordan, G.; Szilassi, P.; Kiss, J.; Detzky, G.

2012-04-01

Major incidents involving mine waste facilities and poor environmental management practices have left a legacy of thousands of contaminated sites like in the historic mining areas in the Carpathian Basin. Associated environmental risks have triggered the development of new EU environmental legislation to prevent and minimize the effects of such incidents. The Mine Waste Directive requires the risk-based inventory of all mine waste sites in Europe by May 2012. In order to address the mining problems a standard risk-based Pre-selection protocol has been developed by the EU Commission. This paper discusses the heavy metal contamination in acid mine drainage (AMD) for risk assessment (RA) along the Source-Pathway-Receptor chain using decision support methods which are intended to aid national and regional organizations in the inventory and assessment of potentially contaminated mine waste sites. Several recognized methods such as the European Environmental Agency (EEA) standard PRAMS model for soil contamination, US EPA-based AIMSS and Irish HMS-IRC models for RA of abandoned sites are reviewed, compared and tested for the mining waste environment. In total 145 ore mine waste sites have been selected for scientific testing using the EU Pre-selection protocol as a case study from Hungary. The proportion of uncertain to certain responses for a site and for the total number of sites may give an insight of specific and overall uncertainty in the data we use. The Pre-selection questions are efficiently linked to a GIS system as database inquiries using digital spatial data to directly generate answers. Key parameters such as distance to the nearest surface and ground water bodies, to settlements and protected areas are calculated and statistically evaluated using STATGRAPHICS® in order to calibrate the RA models. According to our scientific research results, of the 145 sites 11 sites are the most risky having foundation slope >20o, 57 sites are within distance 66 (class VI

A radiological legacy. Radioactive residues of the Cold War period

International Nuclear Information System (INIS)

Gonzalez, A.J.

1998-01-01

A dominating feature of the historical period known as the Cold War was the large-scale production and testing, of nuclear weapons. These military activities brought with them an unprecedented generation of radioactive substances. A fraction of these 'Cold War residues' ended up in the atmosphere and were dispersed throughout the world. Some remained in relatively isolated states in underground geological environments at the production or test site. Others have contaminated areas at times accessible to humans. Augmenting this picture are other scenes of a Cold War legacy. Large amounts of radioactive waste and byproducts are in storage from the production of weapons material. At some point, they are expected to be converted to peaceful applications or sent for final disposal. Over the past decade, the IAEA has been asked to play a greater role in helping countries address this Cold War legacy. A number of scientific assessments of radiological situations created by the Cold War have been carried out by experts convened by the IAEA - at nuclear test sites, nuclear production facilities, and waste dumping sites. This edition of the IAEA Bulletin highlights these cooperative activities in the context of international developments and concerns

Federal facilities compliance act waste management

International Nuclear Information System (INIS)

Bowers, J.; Gates-Anderson, D.; Hollister, R.; Painter, S.

1999-01-01

Site Treatment Plans (STPs) developed through the Federal Facilities Compliance Act pose many technical and administrative challenges. Legacy wastes managed under these plans require Land Disposal Restriction (LDR) compliance through treatment and ultimate disposal. Although capacity has been defined for most of the Department of Energy wastes, many waste streams require further characterization and many need additional treatment and handling beyond LDR criteria to be able to dispose of the waste. At Lawrence Livermore National Laboratory (LLNL), the Hazardous Waste Management Division has developed a comprehensive Legacy Waste Program. The program directs work to manage low level and mixed wastes to ensure compliance with nuclear facility rules and its STP. This paper provides a survey of work conducted on these wastes at LLNL. They include commercial waste treatment and disposal, diverse forms of characterization, inventory maintenance and reporting, on-site treatment, and treatability studies. These activities are conducted in an integrated fashion to meet schedules defined in the STP. The processes managing wastes are dynamic due to required integration of administrative, regulatory, and technical concerns spanning the gamut to insure safe proper disposal

Independent regulatory control and monitoring of the environment at the uranium legacy sites under reclamation

International Nuclear Information System (INIS)

Shandala, N.K.; Titov, A.V.; Kiselev, S.M.; Isaev, D.V.; Aladova, R.A.

2012-01-01

Full text: Radiation safety at areas affected by the natural uranium mining and milling facilities is very important for the environment protection and human health. For this purpose the close operator-regulator contact is required during remedial operations. One of the key mechanisms of the operating regulatory supervision of radiation safety at uranium legacy sites is organization of independent radiation control and monitoring in the course of reclamation and after its completion. The main stages of this strategy include: detailed radiation survey at the area and in the vicinity of the former uranium mining sites; threat assessment in order to identify the regulatory priorities; environmental radiation control and monitoring. Tailings and shallow disposal sites of the uranium mining wastes are the most critical areas in terms of potential hazard for the environment. Tailings are the source of contamination of the near-land air due to the radionuclide dust resuspension from the tailing surface; surface and ground water due to washing out from by precipitation and surface streams of toxic and radioactive elements. Frequently, contamination of surface and ground waters results in some problems, especially when using the leaching fluids for the solution mining and draining hydraulic fluids. Radiation risk for the residents of areas near not operating uranium mining and milling facilities depends on the following factors: radon exhalation from the surface of dumps and tailing; radioactive dust transfer; using radioactive material in building; contamination of surface water streams and aquifers used for drinking water supply; contamination of open ponds used for fish breeding and catching; contamination of foodstuffs grown in the nuclear legacy areas. Radiation monitoring is necessary for the up-to-date response to changing radiation situation during reclamation and arrangement of adequate countermeasures. We mean here comprehensive dynamic surveillance including long

Removal of Legacy Low-Level Waste Reactor Moderator De-ionizer Resins Highly Contaminated with Carbon-14 from the 'Waste with no Path to Disposal List' Through Innovative Technical Analysis and Performance Assessment Techniques

International Nuclear Information System (INIS)

Goldston, W.T.; Hiergesell, R.A.; Kaplan, D.I.; Pope, H.L.

2006-01-01

At the Savannah River Site (SRS), nuclear production reactors used de-ionizers to control the chemistry of the reactor moderator during their operation to produce nuclear materials primarily for the weapons program. These de-ionizers were removed from the reactors and stored as a legacy waste and due to the relatively high carbon-14 (C-14) contamination (i.e., on the order of 740 giga becquerel (GBq) (20 curies) per de-ionizer) were considered a legacy 'waste with no path to disposal'. Considerable progress has been made in consideration of a disposal path for the legacy reactor de-ionizers. Presently, 48 - 50 de-ionizers being stored at SRS have 'no path to disposal' because the disposal limit for C-14 in the SRS's low-level waste disposal facility's Intermediate Level Vault (ILV) is only 160 GBq (4.2 curies) per vault. The current C-14 ILV disposal limit is based on a very conservative analysis of the air pathway. The paper will describe the alternatives that were investigated that resulted in the selection of a route to pursue. This paper will then describe SRS's efforts to reduce the conservatism in the analysis, which resulted in a significantly larger C-14 disposal limit. The work consisted of refining the gas-phase analysis to simulate the migration of C-14 from the waste to the ground surface and evaluated the efficacy of carbonate chemistry in cementitious environment of the ILV for suppressing the volatilization of C-14. During the past year, a Special Analysis was prepared for Department of Energy approval to incorporate the results of these activities that increased the C-14 disposal limits for the ILV, thus allowing for disposal of the Reactor Moderator De-ionizers. Once the Special Analysis is approved by DOE, the actual disposal would be dependent on priority and funding, but the de-ionizers will be removed from the 'waste with no path to disposal list'. (authors)

MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION

Energy Technology Data Exchange (ETDEWEB)

WEST LD

2011-01-13

The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m{sup 3} of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% ({approx}8,000 m{sup 3}) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues

Directory of Open Access Journals (Sweden)

A. Schwenk-Ferrero

2013-01-01

Full Text Available Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content and the nuclide composition of this inventory have been done. The methodology used applies advanced nuclear fuel cycle simulation techniques in order to reproduce the operation of the German nuclear power plants from 1969 till 2022. NFCSim code developed by LANL was adopted for this purpose. It was estimated that ~10,300 tonnes of unreprocessed nuclear spent fuel will be generated until the shut-down of the ultimate German reactor. This inventory will contain ~131 tonnes of plutonium, ~21 tonnes of minor actinides, and 440 tonnes of fission products. Apart from this, ca.215 tonnes of vitrified HLW will be present. As fission products and transuranium elements remain radioactive from 104 to 106 years, the characteristics of spent fuel legacy over this period are estimated, and their impacts on decay storage and final repository are discussed.

A Waste of a Desert: Nevada and the Cold War Chemical Legacy

Directory of Open Access Journals (Sweden)

Cinzia Scarpino

2009-12-01

Full Text Available Taking the lead from Don DeLillo’s epic novel Underworld (1997 – with its overarching theme of “waste” functioning as its unifying metaphor and its picture of the American deserts turned into hazardous waste dumps or missile depots – this essay provides a close reading of the empty spaces of the Nevada desert, spaces that bear the mark left by the nuclear exploitation and the hazardous waste which have plagued Nevada since the Fifties. By linking the history of Nevada to the Cold War, and to the chemical legacy of those years, with its notions of “containment” and “weather control”, Scarpino argues that they be read as interwoven threads of the same discourse.

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

Hanford Site Tank Waste Remediation System

International Nuclear Information System (INIS)

1993-05-01

The US Department of Energy's (DOE) Hanford Site in southeastern Washington State has the most diverse and largest amount of highly radioactive waste of any site in the US. High-level radioactive waste has been stored in large underground tanks since 1944. A Tank Waste Remediation System Program has been established within the DOE to safely manage and immobilize these wastes in anticipation of permanent disposal in a geologic repository. The Hanford Site Tank Waste Remediation System Waste Management 1993 Symposium Papers and Viewgraphs covered the following topics: Hanford Site Tank Waste Remediation System Overview; Tank Waste Retrieval Issues and Options for their Resolution; Tank Waste Pretreatment - Issues, Alternatives and Strategies for Resolution; Low-Level Waste Disposal - Grout Issue and Alternative Waste Form Technology; A Strategy for Resolving High-Priority Hanford Site Radioactive Waste Storage Tank Safety Issues; Tank Waste Chemistry - A New Understanding of Waste Aging; Recent Results from Characterization of Ferrocyanide Wastes at the Hanford Site; Resolving the Safety Issue for Radioactive Waste Tanks with High Organic Content; Technology to Support Hanford Site Tank Waste Remediation System Objectives

Taking the Next Step: Confronting the Legacies of Slavery at Historic Sites

Science.gov (United States)

Grim, Linnea; Wickens, K. Allison; Jecha, Jackie; Powell, Linda; Hawkins, Callie; Flanagan, Candra

2017-01-01

"Slavery is the ground zero of race relations," declared James and Lois Horton in their groundbreaking book, "Slavery and Public History." Engaging the history and legacy of slavery is a crucial step in understanding current U.S. society especially race relations. Historic sites that have connections to slavery have begun to…

Main Principles of the Organization of Decommissioning Activities for Legacy Sites

Energy Technology Data Exchange (ETDEWEB)

Mikheykin, S.V., E-mail: Mikheykin@rosrao.ru [Department of Techniques for Remediation, Federal State Unitary Enterprise ' RosRAO' , Moscow (Russian Federation)

2013-08-15

As a result of more than 60 years development of nuclear industry in the former Soviet Union and in the Russian Federation there has accumulated a number of unresolved problems associated with contamination of facilities and environment during the early stages of research and industrial activities. Prior to the year 2000 most of the problems were solved slowly; the main decisions were postponed for the future. During that time were done the local works for the rehabilitation of contaminated sites. The Federal Target Programme ''Nuclear and Radiation Safety for 2008 and for the period to 2015'' was adopted in 2008. Analysis of accumulated experience as result of previous work on decontamination to develop new project management system for the rehabilitation of the nuclear legacy is needed. This CRP contribution is aimed at solving the tasks of the rehabilitation of the nuclear legacy. (author)

Analyzing Patterns of Community Interest at a Legacy Mining Waste Site to Assess and Inform Environmental Health Literacy Efforts

Science.gov (United States)

Ramirez-Andreotta, Monica D.; Lothrop, Nathan; Wilkinson, Sarah T.; Root, Robert A.; Artiola, Janick F.; Klimecki, Walter; Loh, Miranda

2015-01-01

Understanding a community’s concerns and informational needs is crucial to conducting and improving environmental health research and literacy initiatives. We hypothesized that analysis of community inquiries over time at a legacy mining site would be an effective method for assessing environmental health literacy efforts and determining whether community concerns were thoroughly addressed. Through a qualitative analysis, we determined community concerns at the time of being listed as a Superfund site. We analyzed how community concerns changed from this starting point over the subsequent years, and whether: 1) communication materials produced by the USEPA and other media were aligned with community concerns; and 2) these changes demonstrated a progression of the community’s understanding resulting from community involvement and engaged research efforts. We observed that when the Superfund site was first listed, community members were most concerned with USEPA management, remediation, site-specific issues, health effects, and environmental monitoring efforts related to air/dust and water. Over the next five years, community inquiries shifted significantly to include exposure assessment and reduction methods and issues unrelated to the site, particularly the local public water supply and home water treatment systems. Such documentation of community inquiries over time at contaminated sites is a novel method to assess environmental health literacy efforts and determine whether community concerns were thoroughly addressed. PMID:27595054

Drought-induced legacy effects in wood growth across the Eastern and Midwestern U.S. are mediated by site climate, tree age, and drought sensitivity

Science.gov (United States)

Kannenberg, S.; Maxwell, J. T.; Pederson, N.; D'Orangeville, L.; Phillips, R.

2017-12-01

While it is widely known that drought reduces carbon (C) uptake in temperate forests, tree growth can also remain stagnant post-drought despite favorable climatic conditions. While such "legacy effects" are well established, the degree to which these effects depend on species identity or variability in site conditions is poorly quantified. We sought to uncover how site, species, climate, and tree age interact to affect the presence and magnitude of legacy effects in temperate trees following drought. To do this, we assembled dendrochronological records of 18 common species across 94 sites in Eastern and Midwestern U.S. forests and quantified drought-induced changes in wood growth in the year of the drought (hereafter "drought sensitivity") and the years after the drought (i.e., legacy effects). We predicted that species particularly prone to hydraulic damage (e.g., oaks) would have the least drought sensitivity yet experience larger legacy effects, and that this effect would be exacerbated at arid sites. Across all species and sites, wood growth was reduced by 14% in the year of the drought and by 7% post-drought. Surprisingly, legacy effects were smaller for oak species and larger across species known to be more drought sensitive (e.g. tulip poplar, maple, birch). As a result, we observed a positive relationship between a species' drought sensitivity and that species' legacy effect. These legacy effects were similar in size across a range of drought severities. Surprisingly, legacy effects were smaller in more arid sites - contrary to previous investigations in dryland ecosystems - perhaps indicating the role of adaptation in mediating a tree's recovery from drought. In addition, many species actually decreased the size of their legacy effects as they aged, despite no change in drought responses. Our results run contrary to our predictions, as species with the greatest drought sensitivity had the least ability to recover, and that younger mesic forests- not arid

Transuranic (TRU) Waste Repackaging at the Nevada Test Site

International Nuclear Information System (INIS)

Di Sanza, E.F.; Pyles, G.; Ciucci, J.; Arnold, P.

2009-01-01

This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada Test Site's (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M and O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum

Ultrasonic techniques for the in situ characterisation of 'legacy' Waste sludges and dispersions - 59111

International Nuclear Information System (INIS)

Hunter, Timothy; Biggs, Simon; Young, James; Fairweather, Michael; Peakall, Jeff

2012-01-01

Research being undertaken at the University of Leeds, as part of the DIAMOND university consortium, is exploring the effectiveness of various ultrasonic technologies as in situ probes to characterize and monitor nuclear waste slurries, such as the 'Legacy' Magnesium hydroxide sludges found in Sellafield, U.K. Through use of a commercial Acoustic Backscatter Sensor (ABS) with 1 - 5 MHz transducers, various properties of free-settling oxide simulant sludges were determined. Work was focused upon characterizing essentially 'static' sludges (to give prospective use as tools for the wastes in current deposits); although, the sensors also have potential as dispersion monitors during any future processing and storage of the Legacy wastes, as well as many other storage, clarifier or thickener systems across a wide range of industrial processing operations. ABS data of mixed glass powder dispersions was analysed and compared to scattering theory, to understand the correlations between acoustic attenuation and particulate concentration. The ABS was also calibrated to measure changes in average particulate concentration within a settling suspension over time, and showed the depth-wise segregation of the dispersion through the settling column at different particular time intervals. It was found that observed hindered settling also led to an increase in particulate concentration over the sludge zone and significant segregation occurred at moderate time intervals, due to the broad size distribution of the aggregates measured. It is hoped in future that these sensors may be able to be fitted to robotic handlers that have been installed onsite (and previously used for sampling), allowing fully automatic in situ sludge analysis. (authors)

Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255

Energy Technology Data Exchange (ETDEWEB)

Rogers, Ben C.; Heacker, Fred K.; Shannon, Christopher [Wastren Advantage, Inc., Transuranic Waste Processing Center, 100 WIPP Road, Lenoir City, Tennessee 37771 (United States); and others

2013-07-01

The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sites and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct

Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255

International Nuclear Information System (INIS)

Rogers, Ben C.; Heacker, Fred K.; Shannon, Christopher

2013-01-01

The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sites and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct and install

Fabrication of a Sludge-Conditioning System for processing legacy wastes from the Gunite and Associated Tanks

International Nuclear Information System (INIS)

Randolph, J.D.; Lewis, B.E.; Farmer, J.R.; Johnson, M.A.

2000-01-01

The Sludge Conditioning System (SCS) for the Gunite and Associated Tanks (GAATs) is designed to receive, monitor, characterize and process legacy waste materials from the South Tank Farm tanks in preparation for final transfer of the wastes to the Melton Valley Storage Tanks (MVSTs), which are located at Oak Ridge National Laboratory. The SCS includes (1) a Primary Conditioning System (PCS) Enclosure for sampling and particle size classification, (2) a Solids Monitoring Test Loop (SMTL) for slurry characterization, (3) a Waste Transfer Pump to retrieve and transfer waste materials from GAAT consolidation tank W-9 to the MVSTs, (4) a PulsAir Mixing System to provide mixing of consolidated sludges for ease of retrieval, and (5) the interconnecting piping and valving. This report presents the design, fabrication, cost, and fabrication schedule information for the SCS

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

International Nuclear Information System (INIS)

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

2005-01-01

This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

A proposed alternative approach for protection of inadvertent human intruders from buried Department of Energy low level radioactive wastes

International Nuclear Information System (INIS)

Cochran, J.R.

1995-01-01

The burial of radioactive wastes creates a legacy. To limit the impact of this legacy on future generations, we establish and comply with performance objectives. This paper reviews performance objectives for the long-term isolation of buried radioactive wastes; identifies regulatorly-defined performance objectives for protecting the inadvertent human intruder (IHI) from buried low-level radioactive waste (LLW); (3) discusses a shortcoming of the current approach; and (4) offers an alternative approach for protecting the IHI. This alternative approach is written specifically for the burial of US Department of Energy (DOE) wastes at the Nevada Test Site (NTS), although the approach might be applied at other DOE burial sites

Bulk monitoring and segregation of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M., E-mail: helen.beddow@nuvia.co.uk [Nuvia Limited, Harwell Oxford, Didcot, Oxfordshire (United Kingdom)

2014-07-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

Bulk monitoring and segregation of radioactive wastes

International Nuclear Information System (INIS)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M.

2014-01-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

Mobile hot cell transition design phase study for radioactive waste treatment on the Hanford reservation site

International Nuclear Information System (INIS)

Pons, Y.

2010-01-01

Full text of publication follows: At the US Department of Energy's Hanford Reservation site, 4 caissons in under ground storage contain approximately 23 cubic meters of Transuranic (TRU) waste, in over 5,000 small packages. The retrieval of these wastes presents a number of very difficult issues, including the configuration of the vaults, approximately 50,000 curies of activity, high dose rates, and damaged/degraded waste packages. The waste will require remote retrieval and processing sufficient to produce certifiable RH-TRU waste packages. This RH-TRU will be packaged for staging on site until certification by CCP is completed to authorize shipment to the Waste Isolation Pilot Plant (WIPP). The project has introduced AREVA' s innovative Hot Mobile Cell (HMC) technology to perform size reduction, sorting, characterization, and packaging of the RH waste stream at the point of generation, the retrieval site in the field. This approach minimizes dose and hazard exposure to workers that is usually associated with this operation. The HMC can also be used to provide employee protection, weather protection, and capacity improvements similar to those realized in general burial ground. AREVA TA and his partner AFS will provide this technology based on the existing HMCs developed and operated in France: - ERFB (Bituminized Waste Drum Retrieval Facility): ERFB was built specifically for retrieving the bituminized waste drums (approximately 6,000 stored in trenches in the North zone on the Marcoule site (in operation since 2001). - ERCF (Waste Drum Recovery and Packaging Facility): The ERCF was built specifically to retrieve bituminized waste drums stored in 35 pits located in the south area on Marcoule site (in operation) - FOSSEA (Legacy Waste Removal and Trench Cleanup): The FOSSEA project consists of the retrieval of waste stored on the Basic Nuclear Facility. Waste from the 56 trenches will be inspected, characterised, and if necessary processed or repackaged, and

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

Regulatory Framework for Salt Waste Disposal and Tank Closure at the Savannah River Site - 13663

Energy Technology Data Exchange (ETDEWEB)

Thomas, Steve; Dickert, Ginger [Savannah River Remediation LLC, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01

The end of the Cold War has left a legacy of approximately 37 million gallons of radioactive waste in the aging waste tanks at the Department of Energy's Savannah River Site (SRS). A robust program is in place to remove waste from these tanks, treat the waste to separate into a relatively small volume of high-level waste and a large volume of low-level waste, and to actively dispose of the low-level waste on-site and close the waste tanks and associated ancillary structures. To support performance-based, risk-informed decision making and to ensure compliance with all regulatory requirements, the U.S. Department of Energy (DOE) and its current and past contractors have worked closely with the South Carolina Department of Health and Environmental Control (SCDHEC), the U.S. Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC) to develop and implement a framework for on-site low-level waste disposal and closure of the SRS waste tanks. The Atomic Energy Act of 1954, as amended, provides DOE the authority to manage defense-related radioactive waste. DOE Order 435.1 and its associated manual and guidance documents detail this radioactive waste management process. The DOE also has a requirement to consult with the NRC in determining that waste that formerly was classified as high-level waste can be safely managed as either low-level waste or transuranic waste. Once DOE makes a determination, NRC then has a responsibility to monitor DOE's actions in coordination with SCDHEC to ensure compliance with the Title 10 Code of Federal Regulations Part 61 (10CFR61), Subpart C performance objectives. The management of hazardous waste substances or components at SRS is regulated by SCDHEC and the EPA. The foundation for the interactions between DOE, SCDHEC and EPA is the SRS Federal Facility Agreement (FFA). Managing this array of requirements and successfully interacting with regulators, consultants and stakeholders is a challenging task but

Hanford site transuranic waste certification plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)

History of Hanford Site Defense Production (Brief)

Energy Technology Data Exchange (ETDEWEB)

GERBER, M S

2001-02-01

This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history.

History of Hanford Site Defense Production (Brief)

International Nuclear Information System (INIS)

GERBER, M.S.

2001-01-01

This paper acquaints the audience with the history of the Hanford Site, America's first full-scale defense plutonium production site. The paper includes the founding and basic operating history of the Hanford Site, including World War II construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), a brief production spurt from 1984-86, the end of the Cold War, and the beginning of the waste cleanup mission. The paper also delineates historical waste practices and policies as they changed over the years at the Hanford Site, past efforts to chemically treat, ''fractionate,'' and/or immobilize Hanford's wastes, and resulting major waste legacies that remain today. This paper presents original, primary-source research into the waste history of the Hanford Site. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

Hanford site waste tank characterization

International Nuclear Information System (INIS)

De Lorenzo, D.S.; Simpson, B.C.

1994-08-01

This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order

Hanford Site Waste management units report

International Nuclear Information System (INIS)

1992-01-01

This report summarizes the operable units in several areas of the Hanford Site Waste Facility. Each operable unit has several waste units (crib, ditch, pond, etc.). The operable units are summarized by describing each was unit. Some of the descriptions are unit name, unit type, waste category start data, site description, etc. The descriptions will vary for each waste unit in each operable unit and area of the Hanford Site

Biological field stations: research legacies and sites for serendipity

Science.gov (United States)

William K. Michener; Keith L. Bildstein; Arthur McKee; Robert R. Parmenter; William W. Hargrove; Deedra McClearn; Mark Stromberg

2009-01-01

Biological field stations are distributed throughout North America, capturing much of the ecological variability present at the continental scale and encompassing many unique habitats. In addition to their role in supporting research and education, field stations offer legacies of data, specimens, and accumulated knowledge. Such legacies often provide the only...

Historical genesis of Hanford Site wastes

International Nuclear Information System (INIS)

Gerber, M.S.

1991-01-01

This paper acquaints the audience with historical waste practices and policies as they changed over the years at the Hanford Site, and with the generation of the major waste streams of concern in Hanford Site clean-up today. The paper also describes the founding and basic operating history of the Hanford Site, including World War 11 construction and operations, three major postwar expansions (1947-55), the peak years of production (1956-63), production phase downs (1964-the present), and some past suggestions and efforts to chemically treat, open-quotes fractionate,close quotes and/or immobilize Hanford's wastes. Recent events, including the designation of the Hanford Site as the open-quotes flagshipclose quotes of Department of Energy (DOE) waste remediation efforts and the signing of the landmark Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), have generated new interest in Hanford's history. Clean-up milestones dictated in this agreement demand information about how, when, in what quantities and mixtures, and under what conditions, Hanford Site wastes were generated and released. This paper presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Finally, the paper places the current Hanford Site waste remediation endeavors in the broad context of American and world history

Implementation of SAP Waste Management System

International Nuclear Information System (INIS)

Frost, M.L.; LaBorde, C.M.; Nichols, C.D.

2008-01-01

The Y-12 National Security Complex (Y-12) assumed responsibility for newly generated waste on October 1, 2005. To ensure effective management and accountability of newly generated waste, Y-12 has opted to utilize SAP, Y-12's Enterprise Resource Planning (ERP) tool, to track low-level radioactive waste (LLW), mixed waste (MW), hazardous waste, and non-regulated waste from generation through acceptance and disposal. SAP Waste will include the functionality of the current waste tracking system and integrate with the applicable modules of SAP already in use. The functionality of two legacy systems, the Generator Entry System (GES) and the Waste Information Tracking System (WITS), and peripheral spreadsheets, databases, and e-mail/fax communications will be replaced by SAP Waste. Fundamentally, SAP Waste will promote waste acceptance for certification and disposal, not storage. SAP Waste will provide a one-time data entry location where waste generators can enter waste container information, track the status of their waste, and maintain documentation. A benefit of the new system is that it will provide a single data repository where Y-12's Waste Management organization can establish waste profiles, verify and validate data, maintain inventory control utilizing hand-held data transfer devices, schedule and ship waste, manage project accounting, and report on waste handling activities. This single data repository will facilitate the production of detailed waste generation reports for use in forecasting and budgeting, provide the data for required regulatory reports, and generate metrics to evaluate the performance of the Waste Management organization and its subcontractors. SAP Waste will replace the outdated and expensive legacy system, establish tools the site needs to manage newly generated waste, and optimize the use of the site's ERP tool for integration with related business processes while promoting disposition of waste. (authors)

Hanford Site Waste Management Plan

International Nuclear Information System (INIS)

1988-12-01

The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

Hanford Site Solid Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

1993-11-17

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

Hanford Site Solid Waste Acceptance Criteria

International Nuclear Information System (INIS)

1993-01-01

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

Hanford Site Waste Management Units Report

Energy Technology Data Exchange (ETDEWEB)

Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

2012-02-29

The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2012 version of the HSWMUR contains a comprehensive inventory of the 3389 sites and 540 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

Hanford Site Waste Management Units Report

Energy Technology Data Exchange (ETDEWEB)

Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

2013-02-13

The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2013 version of the HSWMUR contains a comprehensive inventory of the 3427 sites and 564 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

Hanford Site Waste Management Units Report

Energy Technology Data Exchange (ETDEWEB)

Shearer, Jeffrey P. [Hanford Site (HNF), Richland, WA (United States)

2014-02-19

The Hanford Site Waste Management Units Report (HSWMUR) has been created to meet the requirements of the Tri-Party Agreement (TPA) Action Plan, Section 3.5, which states: “The Hanford Site Waste Management Units Report shall be generated, in a format agreed upon by the Parties, as a calendar year report and issued annually by the DOE by the end of February of each year, and posted electronically for regulator and public access. This report shall reflect all changes made in waste management unit status during the previous year.” This February 2013 version of the HSWMUR contains a comprehensive inventory of the 3438 sites and 569 subsites in the Waste Information Data System (WIDS). The information for each site contains a description of each unit and the waste it contains, where applicable. The WIDS database provides additional information concerning the sites contained in this report and is maintained with daily changes to these sites.

Lessons Learned and Present Day Challenges of Addressing 20th Century Radiation Legacies of Russia and the United States

International Nuclear Information System (INIS)

KRISTOFZSKI, J.G.

2000-01-01

The decommissioning of nuclear submarines, disposal of highly-enriched uranium and weapons-grade plutonium, and processing of high-level radioactive wastes represent the most challenging issues facing the cleanup of 20th century radiation legacy wastes and facilities. The US and Russia are the two primary countries dealing with these challenges, because most of the world's fissile inventory is being processed and stored at multiple industrial sites and nuclear weapons production facilities in these countries

Legacy material work-off project

International Nuclear Information System (INIS)

Sloan, T.J.; Baker, D.H. IV

1999-01-01

Los Alamos National Laboratory (LANL) and its subcontractors recently completed a nine-month legacy material clean-up effort. Legacy materials were defined as chemicals, hazardous, non-hazardous, and both hazardous and radioactive (mixed), that no longer served a programmatic use and had no identified individual owner within the Laboratory. Once personnel identified the legacy materials, the items were transferred to Solid Waste Operation's (EM-SWO) control. Upon completing this process, the responsible division-level manager was required to certify that all non-radioactive hazardous and non-hazardous materials and acceptable mixed legacy materials had been identified and transferred to EM-SWO for proper handling or disposal. The major expense in this project was the cost of actual chemical and radiological analysis. This expense was the result of items not having an identified individual owner. The major benefit of this project is that LANL is now in an excellent position to implement its Integrated Safety Management (ISM) Plan, which requires the implementation of safe work practices, including requirements for removing unused items when vacating workspaces. Effective implementation of ISM will go a long way toward ensuring that legacy materials are no longer an issue at the Laboratory

Hanford site transuranic waste sampling plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed

Hazardous waste sites and housing appreciation rates

OpenAIRE

McCluskey, Jill Jennifer; Rausser, Gordon C

2000-01-01

The dynamic effect of a hazardous waste site is analyzed by investigating the causal relationship between housing appreciation rates and house location in relation to a hazardous waste site using resale data from individual sales transactions in Dallas County, Texas. The results indicate that in the period in which the hazardous waste site was identified and cleanup occurred, residential property owners in close proximity to the hazardous waste site experienced lower housing appreciation rate...

Legend and legacy: Fifty years of defense production at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S.

1992-09-01

Today, the Hanford Site is engaged in the largest waste cleanup effort ever undertaken in human history. That in itself makes the endeavor historic and unique. The Hanford Site has been designated the ``flagship`` of Department of Energy (DOE) waste remediation endeavors. And, just as the wartime Hanford Project remains unmatched in history, no counterpart exists for the current waste cleanup enterprise. This report provides a summary of the extensive historical record, however, which does give a partial road map. The science of environmental monitoring pioneered at the Hanford Site, and records of this type are the most complete of any in the world, from private companies or public agencies, for the early years of Site operations. The Hanford Site was unique for establishing a detailed, scientific, and multi-faceted environmental monitoring program.

Legend and legacy: Fifty years of defense production at the Hanford Site

International Nuclear Information System (INIS)

Gerber, M.S.

1992-09-01

Today, the Hanford Site is engaged in the largest waste cleanup effort ever undertaken in human history. That in itself makes the endeavor historic and unique. The Hanford Site has been designated the ''flagship'' of Department of Energy (DOE) waste remediation endeavors. And, just as the wartime Hanford Project remains unmatched in history, no counterpart exists for the current waste cleanup enterprise. This report provides a summary of the extensive historical record, however, which does give a partial road map. The science of environmental monitoring pioneered at the Hanford Site, and records of this type are the most complete of any in the world, from private companies or public agencies, for the early years of Site operations. The Hanford Site was unique for establishing a detailed, scientific, and multi-faceted environmental monitoring program

Quantifying and Predicting Reactive Transport of Uranium in Waste Plumes: Are Colloids and Nanoparticles Important?

International Nuclear Information System (INIS)

Jiamin Wan; Tetsu Tokunaga; Carl Steefel; Peter Burns

2006-01-01

The Hanford Site is the DOE's largest legacy waste site, with uranium (U) from plutonium processing being a major contaminant in its subsurface. Accidental release of highly concentrated high-level wastes left large quantities of U in the vadose zone under tank farms. The U contamination has been found in groundwater beneath the tank farms, indicating U is mobile

Radiation legacy of nuclear tests at the Semipalatinsk test site in the light of requirements ensuring radiation safety performance

International Nuclear Information System (INIS)

Logachev, V.A.; Logacheva, L.A.

2005-01-01

Peculiarities of nuclear tests radiation legacy at the Semipalatinsk test site (STS) are shown in the light of performance of requirements ensuring radiation safety, decrease radiation contamination levels in environment and minimize exposure of radiation for population residing contaminated areas by radioactive fallout. The paper provides data on characterization of peculiarities of the STS operation legacy based on review of archival data of the former 3-d General Administration under USSR Ministry of Health. (author)

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

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

2005-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION and PLANNING FOR REVRIEVAL TREATMENT and EVENTUAL DISPOSAL AT WIPP

International Nuclear Information System (INIS)

KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

2006-01-01

The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP)

Corrective Action Decision Document/Closure Report for Corrective Action Unit 190: Contaminated Waste Sites, Nevada Test Site, Nevada, Revision 0

International Nuclear Information System (INIS)

Alfred Wickline

2008-01-01

This Corrective Action Decision Document/Closure Report has been prepared for Corrective Action Unit (CAU) 190, Contaminated Waste Sites, Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy, Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended January 2007). Corrective Action Unit 190 is comprised of the following four corrective action sites (CASs): (1) 11-02-01, Underground Centrifuge; (2) 11-02-02, Drain Lines and Outfall; (3) 11-59-01, Tweezer Facility Septic System; (4) 14-23-01, LTU-6 Test Area The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 190 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from March 21 through June 26, 2007. All CAI activities were conducted as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 190: Contaminated Waste Sites, Nevada Test Site, Nevada (NNSA/NSO, 2006). The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: (1) Determine whether contaminants of concern (COCs) are present. (2) If COCs are present, determine their nature and extent. (3) Provide sufficient information and data to complete appropriate corrective actions. The CAU 190 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the data quality objective data needs

Nevada Test Site Waste Acceptance Criteria, December 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

Nevada Test Site Waste Acceptance Criteria, December 2000

International Nuclear Information System (INIS)

2000-01-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

A Report to Congress on Long-Term Stewardship. Volume II, Site Summaries

Energy Technology Data Exchange (ETDEWEB)

None, None

2001-01-01

During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as for other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over a 100 sites in 30 States and one U.S. Territory. Hundreds of thousand of acres of residually contaminated soils, contaminated groundwater, surface water and sediment contamination, and contaminated buildings are present at many sites across the country. These sites range in size from less than one acre, containing only a single facility, to large sites spanning over 100,000 acres with huge uranium enrichment plants and plutonium processing canyons. Since 1989, the U.S. Department of Energy’s (DOE) Environmental Management (EM) program has made significant progress in addressing this environmental legacy. Millions of cubic meters of waste have been removed, stabilized, or disposed of, resulting in significant risk and cost reduction. In addition, DOE began disposing of transuranic (i.e., plutonium-contaminated) waste in the nation’s first deep geologic repository – the Waste Isolation Pilot Plant in New Mexico. DOE is now carrying out its long-term stewardship obligations at dozens of sites, including smaller sites where DOE has completed cleanup work for the entire site and many larger sites where DOE has remediated portions of the site.

Legacy management: An old challenge with a new focus

International Nuclear Information System (INIS)

Gillogly, Mari; ); Sneve, Malgorzata; Smith, Graham

2017-01-01

The NEA Expert Group on Legacy Management (EGLM) aims to promote a practical and optimised approach for the regulatory supervision of nuclear legacy sites and installations. NEA member countries share their experiences and approaches on legacy management and have submitted case studies to the EGLM that illustrate the common challenges and approaches of many countries. The first report of the expert group will be based on these case studies and will be released in late 2017. A new, broader focus on decommissioning and legacy management issues within the NEA is expected to take shape in early 2018, carrying forward the mission to develop and promote a practical and optimised approach for the regulatory supervision of nuclear legacy sites and installations

Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

Hanford Site Solid Waste Landfill permit application

International Nuclear Information System (INIS)

1991-01-01

Daily activities at the Hanford Site generate sanitary solid waste (nonhazardous and nonradioactive) that is transported to and permanently disposed of at the Hanford Site Solid Waste Landfill. This permit application describes the manner in which the solid Waste Landfill will be operated under Washington State Department of Ecology Minimum Functional Standards for Solid Waste Handling, Washington Administrative Code 173-304. The solid Waste Landfill is owned by the US Department of Energy -- Richland Operations Office and is used for disposal of solid waste generated at the US Department of Energy Hanford Site. The jurisdictional health department's permit application form for the Solid Waste Landfill is provided in Chapter 1.0. Chapter 2.0 provides a description of the Hanford Site and the Solid Waste Landfill and reviews applicable locational, general facility, and landfilling standards. Chapter 3.0 discusses the characteristics and quantity of the waste disposed of in the Solid Waste Landfill. Chapter 4.0 reviews the regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill. Chapters 5.0, 6.0, and 7.0 contain the plan of operation, closure plan, and postclosure plan, respectively. The plan of operation describes the routine operation and maintenance of the Solid Waste Landfill, the environmental monitoring program, and the safety and emergency plans. Chapter 5.0 also addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The postclosure plan describes requirements for final cover maintenance and environmental monitoring equipment following final closure. Chapter 8.0 discusses the integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill. 76 refs., 48 figs, 15 tabs

Old radioactive waste storage sites

International Nuclear Information System (INIS)

2008-01-01

After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

Problems of developing remedial strategy for the uranium ore processing legacy site Pridneprovsky Chemical Plant site (Dneprodzerginsk, Ukraine)

International Nuclear Information System (INIS)

Riazantsev, V.; Bugai, D.; Skalskyy, A.; Tkachenko, E.

2014-01-01

In this paper we present results of works and studies carried out in the frame of ongoing national and international projects aimed at developing the remedial strategy for the Soviet era legacy uranium production site Pridneprovsky Chemical Plant, Dneprodzerginsk, Ukraine. The site includes several uranium mill tailings, contaminated buildings, ore storage grounds and other contaminated facilities. Taking into account the necessity to implement provisions of the new IAEA standards (Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, No. GSR Part 3 (Interim) and others) as well as the provisions of the ICRP 103 publication, the State Nuclear Regulatory Inspectorate Ukraine developed the draft of the new licensing requirements for activities of uranium ores processing.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2012-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2012-02-28

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2010-09-03

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2010-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2011-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN

International Nuclear Information System (INIS)

Heenan, T. F.; Kelly, S.

2002-01-01

The past five years have witnessed a remarkable transition in the pace and scope of waste management activities at SRS. At the start of the new M and O contract in 1996, little was being done with the waste generated at the site apart from storing it in readiness for future treatment and disposal. Large volumes of legacy waste, particularly TRU and Low Level Waste, had accumulated over many years of operation of the site's nuclear facilities, and the backlog was increasing. WSRC proposed the use of the talents of the ''best in class'' partners for the new contract which, together with a more commercial approach, was expected to deliver more results without a concomitant increase in cost. This paper charts the successes in the Solid Waste arena and analyzes the basis for success

Radioactive legacies from medicine and industry

International Nuclear Information System (INIS)

Linder, R.; Rodriguez, J.

2005-01-01

Due to the unintended disposal of radioactive legacies (waste from medicine, industry or private persons) radioactive material occasionally enters the disposal ways of conventional waste. The Swiss Federal Office of Public Health (SFOPH) and the Swiss accident Insurance Fund (Swiss) are the licensing authorities and regulatory agencies of the handling with radioactive materials for non-nuclear use. The aim is to avoid such incidents with concrete measures and so to preserve men and environment from the negative effect of not correctly disposed radioactive waste. (orig.)

Closure Report for Corrective Action Unit 562: Waste Systems, Nevada National Security Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2012-08-15

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 562, Waste Systems, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 562 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 562 consists of the following 13 Corrective Action Sites (CASs), located in Areas 2, 23, and 25 of the Nevada National Security Site: · CAS 02-26-11, Lead Shot · CAS 02-44-02, Paint Spills and French Drain · CAS 02-59-01, Septic System · CAS 02-60-01, Concrete Drain · CAS 02-60-02, French Drain · CAS 02-60-03, Steam Cleaning Drain · CAS 02-60-04, French Drain · CAS 02-60-05, French Drain · CAS 02-60-06, French Drain · CAS 02-60-07, French Drain · CAS 23-60-01, Mud Trap Drain and Outfall · CAS 23-99-06, Grease Trap · CAS 25-60-04, Building 3123 Outfalls Closure activities began in October 2011 and were completed in April 2012. Activities were conducted according to the Corrective Action Plan for CAU 562 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The corrective actions included No Further Action and Clean Closure. Closure activities generated sanitary waste and hazardous waste. Some wastes exceeded land disposal limits and required offsite treatment prior to disposal. Other wastes met land disposal restrictions and were disposed in appropriate onsite or offsite landfills. NNSA/NSO requests the following: · A Notice of Completion from the Nevada Division of Environmental Protection to NNSA/NSO for closure of CAU 562 · The transfer of CAU 562 from Appendix III to Appendix IV, Closed Corrective Action Units, of the FFACO

Hanford Site annual waste reduction report

International Nuclear Information System (INIS)

Nichols, D.H.

1992-03-01

The US Department of Energy (DOE), Richland Field Office (RL) has developed and implemented a Hanford Site Waste Minimization and Pollution Prevention Awareness Plan that provides overall guidance and direction on waste minimization and pollution prevention awareness to the four contractors who manage and operate the Hanford Site for the RL. Waste reduction at the RL will be accomplished by following a hierarchy of environmental protection practices. First, waste generation will be eliminated or minimized through source reduction. Second, potential waste materials that cannot be eliminated or minimized will be recycled (i.e., used, reused, or reclaimed). Third, all waste that is nevertheless generated will be treated to reduce volume, toxicity, or mobility before storage or disposal. The scope of this waste reduction program will include nonhazardous, hazardous, radioactive mixed, and radioactive wastes

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

1999-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

Hazardous waste disposal sites: Report 2

International Nuclear Information System (INIS)

1979-12-01

Arkansas, like virtually every other state, is faced with a deluge of hazardous waste. There is a critical need for increased hazardous waste disposal capacity to insure continued industrial development. Additionally, perpetual maintenance of closed hazardous waste disposal sites is essential for the protection of the environment and human health. Brief descriptions of legislative and regulatory action in six other states are provided in this report. A report prepared for the New York State Environmental Facilities Corp. outlines three broad approaches states may take in dealing with their hazardous waste disposal problems. These are described. State assistance in siting and post-closure maintenance, with private ownership of site and facility, appears to be the most advantageous option

Vitrification technology for Hanford Site tank waste

International Nuclear Information System (INIS)

Weber, E.T.; Calmus, R.B.; Wilson, C.N.

1995-04-01

The US Department of Energy's (DOE) Hanford Site has an inventory of 217,000 m 3 of nuclear waste stored in 177 underground tanks. The DOE, the US Environmental Protection Agency, and the Washington State Department of Ecology have agreed that most of the Hanford Site tank waste will be immobilized by vitrification before final disposal. This will be accomplished by separating the tank waste into high- and low-level fractions. Capabilities for high-capacity vitrification are being assessed and developed for each waste fraction. This paper provides an overview of the program for selecting preferred high-level waste melter and feed processing technologies for use in Hanford Site tank waste processing

Site-Specific Waste Management Instruction - 100-DR-1 Group 2 Sites

International Nuclear Information System (INIS)

Jackson, R.W.

1998-01-01

This site-specific waste management instruction (SSWMI) provides guidance for the management of wastes that may be generated during the excavation and remediation of the 100-DR-1 Group 2 sites. The management of waste generated as a result of these activities will be as directed in this SSWMI. This SSWMI will be revised to incorporate guidance for management of wastes encountered that are not addressed in this SSWMI

Waste site grouping for 200 Areas soil investigations

International Nuclear Information System (INIS)

1997-01-01

The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models

Lessons learned in planning the Canadian Nuclear Legacy Liabilities Program

International Nuclear Information System (INIS)

Stephens, Michael E.; Brooks, Sheila M.; Miller, Joan M.; Mason, Robert A.

2011-01-01

In 2006, Atomic Energy of Canada Limited (AECL) and Natural Resources Canada (NRCan) began implementing a $7B CDN, 70-year Nuclear Legacy Liabilities Program (NLLP) to deal with legacy decommissioning and environmental issues at AECL nuclear sites. The objective of the NLLP is to safely and cost-effectively reduce the nuclear legacy liabilities and associated risks based on sound waste management and environmental principles in the best interest of Canadians. The liabilities include shutdown research and prototype power reactors, fuel handling facilities, radiochemical laboratories, support buildings, radioactive waste storage facilities, and contaminated lands at several sites located across eastern Canada from Quebec to Manitoba. The largest site, Chalk River Laboratories (CRL) in Ontario, will continue as an operational nuclear site for the foreseeable future. Planning and delivery of the Program is managed by the Liability Management Unit (LMU), a group that was formed within AECL for the purpose. The composition and progress of the NLLP has been reported in recent conferences. The NLLP comprises a number of interlinked decommissioning, waste management and environmental restoration activities that are being executed at different sites, and by various technical groups as suppliers to the LMU. Many lessons about planning and executing such a large, diverse Program have been learned in planning the initial five-year 'start-up' phase (which will conclude 2011 March), in planning the five-year second phase (which is currently being finalized), and in planning individual and interacting activities within the Program. The activities to be undertaken in the start-up phase were planned by a small group of AECL technical experts using the currently available information on the liabilities. Progress in executing the Program was slower than anticipated due to less than ideal alignment between some planned technical solutions and the actual requirements, as well as the

Intruder scenarios for site-specific waste classification

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.

1988-01-01

The US Department of Energy (DOE) is currently revising its low-level radioactive waste (LLW) management requirements and guidelines for waste generated at its facilities that support defense missions. Specifically, draft DOE 5820.2A, Chapter 3, describes the purpose, policy, and requirements necessary for the management of defense LLW. The draft DOE policy calls for DOE LLW operations to be managed to protect the health and safety of the public, preserve the environment, and ensure that no remedial action will be necessary after termination of operations. The requirements and guidelines apply to radioactive wastes but are also intended to apply to mixed hazardous and radioactive wastes as defined in draft DOE 5400.5, Hazardous and Radioactive Mixed Waste. The basic approach used by DOE is to establish overall performance objectives in terms of ground-water protection and public radiation dose limits and to require site-specific performance assessments to determine compliance. As a result of these performance assessments, each site shall develop waste acceptance criteria that define the allowable quantities and concentrations of specific radioisotopes. Additional limitations on waste disposal design, waste form, and waste treatment shall also be developed on a site-specific basis. As a key step in the site-specific performance assessments, an evaluation must be conducted of potential radiation doses to intruders who may inadvertently move onto a closed DOE LLW disposal site after loss of institutional controls must be conducted. This paper describes the types of intruder scenarios that should be considered when performing this step of the site-specific performance assessment

Hazardous waste operational plan for site 300

International Nuclear Information System (INIS)

Roberts, R.S.

1982-01-01

This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department

Strategy for managing mixed waste at a plant site

International Nuclear Information System (INIS)

Fentiman, A.

1991-01-01

No waste disposal site is currently accepting mixed waste, but facilities across the country continue to generate it. The waste manager at each site is faced with two problems: how to manage the mixed waste already on-site and how to minimize the amount of new waste generated. A strategy has been developed to address each problem. A key element of the strategy is a building-by-building survey of the site. The survey provides information on how and where mixed waste is generated and stored. This paper describes a method for planning and conducting a site-wide mixed-waste survey. It then outlines approaches to managing existing mixed waste and to minimizing mixed-waste generation using information from the survey

Cleanup around an old waste site

International Nuclear Information System (INIS)

Vandergaast, G.; Moffett, D.; Lawrence, B.E.

1988-01-01

42,500 m 3 of contaminated soil were removed from off-site areas around an old, low-level radioactive waste site near Port Hope, Ontario. The cleanup was done by means of conventional excavation equipment to criteria developed by Eldorado specific to the land use around the company's waste management facility. These cleanup criteria were based on exposure analyses carried out for critical receptors in two different scenarios. The excavated soils, involving eight different landowners, were placed on the original burial area of the waste management facility. Measures were also undertaken to stabilize the soils brought on-site and to ensure that there would be no subsequent recontamination of the off-site areas

The Drigg low-level waste site

International Nuclear Information System (INIS)

1992-01-01

Safe disposal of waste is a vital aspect of any industrial operation whether it be production of plastics, steel or chemicals or handling of radioactive materials. Appropriate methods must be used in every case. Radioactive waste falls into three distinct categories - high, intermediate and low-level. It is the solid low-level waste making up over 90% of the total which this booklet discusses. British Nuclear Fuels plc (BNFL) operates a site for the disposal of solid low-level waste at Driggs, some six kilometres south of Sellafield in West Cumbria. The daily operations and control of the site, the responsibility of the BNFL Waste Management Unit is described. (author)

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

International Nuclear Information System (INIS)

2010-01-01

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-10-04

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

The Approach to Cleanup at West Cumbria's Nuclear Sites

International Nuclear Information System (INIS)

Price, T.

2006-01-01

The cleanup of West Cumbria's nuclear sites is one of the most important and demanding managerial, technical and environmental challenges facing the UK over the next century. Considerable progress has already been made in cleaning up the Sellafield, Calder Hall, and Low-level Waste Repository (LLWR) sites but there remains significant challenge ahead. There are more than 200 nuclear facilities at the sites including redundant fuel storage ponds, redundant chemical plants and silos of solid waste and sludge. These legacy buildings exist alongside commercially operating reprocessing and fuel fabrication facilities. They are all linked together by a complex network of services including gas supplies, water supplies, waste disposal routes, and chemical supply routes. Many of the buildings requiring cleanup are very old and date back to the early years of the British nuclear industry. They were not designed with decommissioning in mind, and some require substantial improvement to provide a safe foundation from which to retrieve waste and decommission. The cleanup of these legacy facilities must be carefully balanced with the ongoing operations that provide services to commercial customers. Cleanup must be carried out safely and efficiently, without impacting upon commercial operations whose revenue is vital to funding the Cleanup organizations scope of work. This paper will introduce the cleanup approach at West Cumbria's Sellafield nuclear site. It will provide an overview of what is being done in preparation to meet the formidable but rewarding challenge ahead. (authors)

Independent technical evaluation and recommendations for contaminated groundwater at the department of energy office of legacy management Riverton processing site

Energy Technology Data Exchange (ETDEWEB)

Looney, Brain B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Denham, Miles E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Eddy-Dilek, Carol A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-04-01

The U.S. Department of Energy Office of Legacy Management (DOE-LM) manages the legacy contamination at the Riverton, WY, Processing Site – a former uranium milling site that operated from 1958 to 1963. The tailings and associated materials were removed in 1988-1989 and contaminants are currently flushing from the groundwater. DOE-LM commissioned an independent technical team to assess the status of the contaminant flushing, identify any issues or opportunities for DOE-LM, and provide key recommendations. The team applied a range of technical frameworks – spatial, temporal, hydrological and geochemical – in performing the evaluation. In each topic area, an in depth evaluation was performed using DOE-LM site data (e.g., chemical measurements in groundwater, surface water and soil, water levels, and historical records) along with information collected during the December 2013 site visit (e.g., plant type survey, geomorphology, and minerals that were observed, collected and evaluated).

Final vegetative cover for closed waste sites

International Nuclear Information System (INIS)

Cook, J.R.; Salvo, S.K.

1993-01-01

Low-level, hazardous, and mixed waste disposal sites normally require some form of plant material to prevent erosion of the final closure cap. Waste disposal sites are closed and capped in a complex scientific manner to minimize water infiltration and percolation into and through the waste material. Turf type grasses are currently being used as an interim vegetative cover for most sites. This coverage allows for required monitoring of the closure cap for settlement and maintenance activities. The purpose of this five year study was to evaluate plant materials for use on wastes sites after the post-closure care period that are quickly and easily established and economically maintained, retard water infiltration, provide maximum year-round evapotranspiration, are ecologically acceptable and do not harm the closure cap. The results of the study suggest that two species of bamboo (Phyllostachys (P.) bissetii and P. rubromarginata) can be utilized to provide long lived, low maintenance, climax vegetation for the waste sites after surveillance and maintenance requirements have ceased

Environmental remediation of the Wismut legacy and utilization of the reclaimed areas, waste rock piles and tailings ponds

International Nuclear Information System (INIS)

Hagen, M.; Jakubick, A.T.

2006-01-01

Between 1945 and reunification (1989) of Germany more than 232 000 t of U 3 O 8 has been produced in Saxony and Thuringia, East Germany. This affected an area of approximately 100 km 2 and left behind an extensive legacy of contaminated operations areas, underground and open pit mines, waste rock piles and tailings ponds. Following reunification, DM 13 billion (Euro 6.6 billion) were committed (and later revised to Euro 6.2 billion) to remediation of the liabilities and the government owned corporation, Wismut GmbH entrusted with the implementation of the Environmental Remediation (ER) of the liabilities. The prime goal of the ER Project follows from the legal requirements to abate health risks, mitigate existing and prevent future environmental damages. During the investigations and assessment of risks, development of remediation concepts, adoption of suitable technologies and work procedures as well as physical implementation of the remedial measures extensive use was made of international (mostly US and Canadian) ER experience. The extent of remedial measures was based on object-specific Environmental Assessments rather than on uniformly applied health/environmental standards. The ER workflow is more an iterative process than a linear succession of tasks, such as common for civil engineering projects. The internal (technical) parts of the problems were partly resolved by using Conceptual Site Models (CSM) for selection and prioritization of remedial measures. Reclamation of the waste rock piles is by covering in situ, relocation to a central pile or backfilling into an open pit. The backfilling of the open pit at Ronneburg with acid generating waste rock has been optimized from a geochemical point of view. For tailings ponds reclamation in form of dry landforms is being followed. To increase release (and reuse) of scrap metal from demolition, a fast and reliable method of discrimination of the non-contaminated metal has been developed. The flooding of

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

International Nuclear Information System (INIS)

1994-01-01

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation

Nuclear waste repository siting

International Nuclear Information System (INIS)

Soloman, B.D.; Cameron, D.M.

1987-01-01

This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

Macroencapsulated and elemental lead mixed waste sites report

International Nuclear Information System (INIS)

Kalia, A.; Jacobson, R.

1996-09-01

The purpose of this study was to compile a list of the Macroencapsulated (MACRO) and Elemental Lead (EL) Mixed Wastes sites that will be treated and require disposal at the Nevada Test Site within the next five to ten years. The five sites selected were: Hanford Site, Richland, Washington; Idaho National Engineering Laboratory (INEL), Idaho Falls, Idaho; Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee; Rocky Flats Environmental Technology (RF), Golden, Colorado; and Savannah River (SRS), Charleston, South Carolina. A summary of total lead mixed waste forms at the five selected DOE sites is described in Table E-1. This table provides a summary of total waste and grand total of the current inventory and five-year projected generation of lead mixed waste for each site. This report provides conclusions and recommendations for further investigations. The major conclusions are: (1) the quantity of lead mixed current inventory waste is 500.1 m 3 located at the INEL, and (2) the five sites contain several other waste types contaminated with mercury, organics, heavy metal solids, and mixed sludges

Low-level waste disposal site selection demonstration

International Nuclear Information System (INIS)

Rogers, V.C.

1984-01-01

This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

Lessons learned in planning the Canadian Nuclear Legacy Liabilities Program

International Nuclear Information System (INIS)

Stephens, M.; Brooks, S.; Miller, J.; Neal, P.; Mason, R.

2011-01-01

In 2006, Atomic Energy of Canada Limited (AECL) and Natural Resources Canada (NRCan) began implementing a $7B CDN, 70-year Nuclear Legacy Liabilities Program (NLLP) to deal with legacy decommissioning and environmental issues at AECL nuclear sites. The objective of the NLLP is to safely and cost-effectively reduce the nuclear legacy liabilities and associated risks based on sound waste management and environmental principles in the best interest of Canadians. The NLLP comprises a number of interlinked decommissioning, waste management and environmental restoration activities that are being executed at different sites by various technical groups. Many lessons about planning and executing such a large, diverse Program have been learned in planning the initial five-year 'start-up' phase (concluded 2011 March), in planning the three-year second phase (currently being commenced), and in planning individual and interacting activities within the Program. The activities to be undertaken in the start-up phase were planned by a small group of AECL technical experts using the currently available information on the liabilities. Several internal and external reviews of the Program during the start-up phase examined progress and identified several improvements to planning. These improvements included strengthening communications among the groups within the Program, conducting more detailed advance planning of the interlinked activities, and being cautious about making detailed commitments for activities for which major decisions had yet to be made. The second phase was planned by a dedicated core team. More and earlier input was solicited from the suppliers than in the planning for the first phase. This was to ensure that the proposed program of work was feasible, and to be able to specify in more detail the resources that would be required to carry it out. The NLLP has developed several processes to assist in the detailed planning of the numerous projects and

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

International Nuclear Information System (INIS)

1994-01-01

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

International Nuclear Information System (INIS)

2010-01-01

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles (mi)) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan

Geohydrology of industrial waste disposal site

International Nuclear Information System (INIS)

Gaynor, R.K.

1984-01-01

An existing desert site for hazardous chemical and low-level radioactive waste disposal is evaluated for suitability. This site is characterized using geologic, geohydrologic, geochemical, and other considerations. Design and operation of the disposal facility is considered. Site characteristics are also evaluated with respect to new and proposed regulatory requirements under the Resource Conservation and Recovery Act (1976) regulations, 40 CFR Part 264, and the ''Licensing Requirements for Landfill Disposal of Radioactive Waste,'' 10 CRF Part 61. The advantages and disadvantages of siting new disposal facilities in similar desert areas are reviewed and contrasted to siting in humid locations

Cleanup Verification Package for the 600-259 Waste Site

Energy Technology Data Exchange (ETDEWEB)

J. M. Capron

2006-02-09

This cleanup verification package documents completion of remedial action for the 600-259 waste site. The site was the former site of the Special Waste Form Lysimeter, consisting of commercial reactor isotope waste forms in contact with soils within engineered caissons, and was used by Pacific Northwest National Laboratory to collect data regarding leaching behavior for target analytes. A Grout Waste Test Facility also operated at the site, designed to test leaching rates of grout-solidified low-level radioactive waste.

Cleanup Verification Package for the 600-259 Waste Site

International Nuclear Information System (INIS)

Capron, J.M.

2006-01-01

This cleanup verification package documents completion of remedial action for the 600-259 waste site. The site was the former site of the Special Waste Form Lysimeter, consisting of commercial reactor isotope waste forms in contact with soils within engineered caissons, and was used by Pacific Northwest National Laboratory to collect data regarding leaching behavior for target analytes. A Grout Waste Test Facility also operated at the site, designed to test leaching rates of grout-solidified low-level radioactive waste

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kendrick, C.M.

1994-01-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ''legacy'' wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL's strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

National Legislation and Regulations in the Uranium Legacy Radiation Safety of the Former USSR

International Nuclear Information System (INIS)

Romanov, V.V.; Shandala, N.K.; Titov, A.V.; Seregin, V.A.; Kiselev, S.M.

2012-01-01

There are many uranium legacy sites in Russia and ex-Soviet republics in the Central Asia, which are decommissioned now. In Russia, there is a number of operating uranium mines and ore milling facilities to be decommissioned after termination of their life cycle. Today, the list of Russian subsoil areas of the federal significance includes 135 uranium deposits. The uranium legacy management is accompanied with the environmental impact. The intensity of such impact depends on the amount of generated waste, degree of its confining and dispersion in the environment. The whole question reduces itself to the following: to what extent this impact is harmful to the environment and human health. The proper regulation of this problem is a criterion for the safe work. Today, the advanced guidance document is under development 'Health-care requirements for design and operation of facilities for uranium ore mining and milling'. In order to enhance the regulatory framework, the following tasks are urgent: introduction of the existing exposure situation in the national laws and regulations in compliance with the ICRP statutory system; development criteria for remediation of sites and their gradual return to uncontrolled use. The similar criteria have been developed within the Russian-Norwegian cooperation for the purpose of remediation of the sites for temporary SNF and Radioactive Wastes storage; review of possibilities and methods for optimization of the remediation strategies under development; identification of the special category - R W originated from the uranium ore mining and milling. Some regulatory problems assume to be solved under the Eurasian Economic Community inter-state target programme 'Reclamation of areas of the Eurasian Economic Community member-states affected by the uranium mines'. Within this programme, by examples of the uranium legacy facilities in Kyrgyzstan and in Tajikistan, posed to trans-border disasters and required urgent remediation, the

Hanford Site Waste Managements Units reports

International Nuclear Information System (INIS)

1992-01-01

The Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC 1984). This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in this report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. The information in this report is extracted from the Waste Information Data System (WIDS). The WIDS provides additional information concerning the waste management units contained in this report and is maintained current with changes to these units. This report is updated annually if determined necessary per the Hanford Federal Facility Agreement and Consent Order Order (commonly referred to as the Tri-Party Agreement, Ecology et al. 1990). This report identifies 1,414 waste management units. Of these, 1,015 units are identified as solid waste management units (SWMU), and 342 are RCRA treatment, storage, and disposal units. The remaining 399 are comprised mainly of one-time spills to the environment, sanitary waste disposal facilities (i.e., septic tanks), and surplus facilities awaiting decontamination and decommissioning

Ten Years of Legacy Management: U.S. DOE Office of Legacy Management Accomplishments - 13246

Energy Technology Data Exchange (ETDEWEB)

Carter, Tony [U.S. Department of Energy Office of Legacy Management, 1000 Independence Ave. SW, Washington, DC 20585 (United States); Miller, Judith [S.M. Stoller Corporation, 2597 Legacy Way, Grand Junction, CO 81503 (United States)

2013-07-01

The U.S. Department of Energy (DOE) established the Office of Legacy Management (LM) to provide a long-term, sustainable solution to environmental impacts that remain from nuclear weapons production during World War II and the Cold War. The production activities created adverse environmental conditions at over 100 sites. When LM was established on December 15, 2003, it became responsible for 33 sites where active environmental remediation was complete. Currently, LM is responsible for long-term surveillance and maintenance of environmental remedies, promotion of beneficial reuse of land and buildings, and management of records and information at 89 sites in 29 states and Puerto Rico. LM is also responsible for meeting contractual obligations associated with former contractor workers' pensions and post-retirement benefits. Effectively addressing this environmental and human legacy will continue to require a focused and well-managed effort. (authors)

Ten Years of Legacy Management: U.S. DOE Office of Legacy Management Accomplishments - 13246

International Nuclear Information System (INIS)

Carter, Tony; Miller, Judith

2013-01-01

The U.S. Department of Energy (DOE) established the Office of Legacy Management (LM) to provide a long-term, sustainable solution to environmental impacts that remain from nuclear weapons production during World War II and the Cold War. The production activities created adverse environmental conditions at over 100 sites. When LM was established on December 15, 2003, it became responsible for 33 sites where active environmental remediation was complete. Currently, LM is responsible for long-term surveillance and maintenance of environmental remedies, promotion of beneficial reuse of land and buildings, and management of records and information at 89 sites in 29 states and Puerto Rico. LM is also responsible for meeting contractual obligations associated with former contractor workers' pensions and post-retirement benefits. Effectively addressing this environmental and human legacy will continue to require a focused and well-managed effort. (authors)

Environmental Remediation and Radioactivity Monitoring of Uranium Mining Legacy in Portugal

Energy Technology Data Exchange (ETDEWEB)

Carvalho, F.P., E-mail: carvalho@itn.pt [Nuclear and Technological Institute, Sacavém (Portugal)

2014-05-15

The main legacy site of uranium mining and milling in Portugal, located near the town of Canas de Senhorim, contained around 15 million tones of solid waste in various mill tailings and spoil heaps. Approval of an environmental remediation plan for this area was followed by the start of engineering works, including the transportation of several wastes to the main tailings pile, re shaping and contouring the waste heap and placing a multi layer cap. These works were mostly performed in 2006 and 2007. During part of this period, monitoring of radioactivity was performed in the surface air, surface waters from the area including the monitoring of the small river that receives drainage from the mill tailings area, and agriculture products. This paper presents the results of measurements of the main alpha emitting radionuclides of uranium series in water and compares them with previous data for the region. Implications for the radiological protection of the population are discussed. (author)

Mixed waste disposal facilities at the Savannah River Site

International Nuclear Information System (INIS)

Wells, M.N.; Bailey, L.L.

1991-01-01

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission

Remaining Sites Verification Package for the 600-233 Waste Site, Vertical Pipe Near 100-B Electrical Laydown Area. Attachment to Waste Site Reclassification Form 2005-041

International Nuclear Information System (INIS)

Carlson, R.A.

2005-01-01

The 600-233 waste site consisted of three small-diameter pipelines within the 600-232 waste site, including previously unknown diesel fuel supply lines discovered during site remediation. The 600-233 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

Closure Strategy Nevada Test Site Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2007-03-01

This paper presents an overview of the strategy for closure of part of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada (Figure 1). The Area 5 RWMS is in the northern part of Frenchman Flat, approximately 14 miles north of Mercury. The Area 5 RWMS encompasses 732 acres subdivided into quadrants, and is bounded by a 1,000-foot (ft)-wide buffer zone. The northwest and southwest quadrants have not been developed. The northeast and southeast quadrants have been used for disposal of unclassified low-level radioactive waste (LLW) and indefinite storage of classified materials. This paper focuses on closure of the 38 waste disposal and classified material storage units within the southeast quadrant of the Area 5 RWMS, called the ''92-Acre Area''. The U.S Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently planning to close the 92-Acre Area by 2011. Closure planning for this site must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. For ease of discussion, the 92-Acre Area has been subdivided into six closure units defined by waste type, location, and similarity in regulatory requirements. Each of the closure units contains one or more waste disposal units; waste disposal units are also called waste disposal cells. The paper provides a brief background of the Area 5 RWMS, identifies key closure issues for the 92-Acre Area, recommends actions to address the issues, and provides the National Security Technologies, LLC (NSTec), schedule for closure.

Rock solid: the geology of nuclear waste disposal

International Nuclear Information System (INIS)

Reid, Elspeth.

1990-01-01

With a number of nuclear submarines and power stations due to be decommissioned in the next decade, stores of radioactive waste, and arguments about storage increase. Whatever the direction taken by the nuclear industry in Britain, the legacy of waste remains for the foreseeable future. Geology is at the heart of the safety argument for nuclear wastes. It is claimed that rocks should act as the main safety barrier, protecting present and future generations from radiation. Rock Solid presents a clear, accessible and up to date account of the geological problems involved in building a nuclear waste repository. The author describes the geology of some of the possible UK repository sites (Sellafield, Dounreay, Altnabreac, Billingham), explains how sites are investigated (including computer models), and finally considers the crucial question: 'would geological containment of radioactive waste actually work?'. (author)

Hanford Site Transuranic (TRU) Waste Certification Plan

Energy Technology Data Exchange (ETDEWEB)

GREAGER, T.M.

1999-09-09

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

Site suitability analysis and route optimization for solid waste ...

African Journals Online (AJOL)

Solid waste management system is a tedious task that is facing both developing and developed countries. Site Suitability analysis and route optimization for solid waste disposal can make waste management cheap and can be used for sustainable development. However, if the disposal site(s) is/are not sited and handle ...

Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

Solid waste dumping site suitability analysis using geographic ...

African Journals Online (AJOL)

Solid waste dumping is a serious problem in the urban areas because most solid wastes are not dumped in the suitable areas. Bahir Dar Town has the problem of solid waste dumping site identification. The main objective of this study was to select potential areas for suitable solid waste dumping sites for Bahir Dar Town, ...

Waste reduction at the Savannah River Site

International Nuclear Information System (INIS)

Stevens, W.E.; Lee, R.A.; Reynolds, R.W.

1990-01-01

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities

Hanford Site Waste Management Units Report

International Nuclear Information System (INIS)

1991-01-01

This Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC). The report provides a comprehensive inventory of all types of waste management units at the Hanford Site and consists of waste disposal units, including (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structure, (5) RCRA treatment and storage units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. In support of the Hanford RCRA permit, a field was added to designate whether the waste management unit is a solid waste management unit (SWMU). As SWMUs are identified, they will added to the Hanford Waste Information Data System (WIDS), which is the database supporting this report, and added to the report at its next annual update. A quality review of the WIDS was conducted this past year. The review included checking all data against their reference and making appropriate changes, updating the data elements using the most recent references, marking duplicate units for deletion, and addition additional information. 6 refs

Hanford Site Waste Management Units Report

International Nuclear Information System (INIS)

1991-01-01

This Hanford Site Waste Management Units Report (HSWMUR) was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments (HSWA) of the 1984 United States Code (USC). The report provides a comprehensive inventory of all types of waste management units at the Hanford Site and consists of waste disposal units, including (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment and storage units, and (6) other storage areas. Because of the comprehensive nature of this report, the listing of sites is more extensive than required by Section 3004(u) of HSWA. In support of the Hanford RCRA permit, a field was added to designate whether the waste management unit is a solid waste management unit (SWMU). As SWMUs are identified, they will added to the Hanford Waste Information Data System (WIDS), which is the database supporting this report, and added to the report at its next annual update. A quality review of the WIDS was conducted this past year. The review included checking all data against their reference and making appropriate changes, updating the data elements using the most recent references, marking duplicate units for deletion, and adding additional information. 6 refs

Hanford Site annual dangerous waste report: Volume 3, Part 2, Waste Management Facility report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1944-12-31

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling and containment vessel, waste number, waste designation and amount of waste.

Low-level radioactive waste disposal at a humid site

International Nuclear Information System (INIS)

Lee, D.W.

1987-03-01

Waste management in humid environments poses a continuing challenge because of the potential contamination of groundwater in the long term. Short-term needs for waste disposal, regulatory uncertainty, and unique site and waste characteristics have led to the development of a site-specific waste classification and management system proposed for the Oak Ridge Reservation. The overlying principle of protection of public health and safety is used to define waste classes compatible with generated waste types, disposal sites and technologies, and treatment technologies. 1 fig., 1 tab

Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation, and amount of waste.

Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation, and amount of waste

Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation

Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

Disposal of Hanford site tank wastes

International Nuclear Information System (INIS)

Kupfer, M.J.

1993-09-01

Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West areas, currently contain about 1.4 x 10 5 m 3 of solid and liquid wastes. Wastes in the SSTs contain about 5.7 x 10 18 Bq (170 MCi) of various radionuclides including 90 Sr, 99 Tc, 137 Cs, and transuranium (TRU) elements. The 28 DSTs also located in the 200 East and West areas contain about 9 x 10 4 m 3 of liquid (mainly) and solid wastes; approximately 4 x 10 18 Bq (90 MCi) of radionuclides are stored in the DSTs. Important characteristics and features of the various types of SST and DST wastes are described in this paper. However, the principal focus of this paper is on the evolving strategy for final disposal of both the SST and DST wastes. Also provided is a chronology which lists key events and dates in the development of strategies for disposal of Hanford Site tank wastes. One of these strategies involves pretreatment of retrieved tank wastes to separate them into a small volume of high-level radioactive waste requiring, after vitrification, disposal in a deep geologic repository and a large volume of low-level radioactive waste which can be safely disposed of in near-surface facilities at the Hanford Site. The last section of this paper lists and describes some of the pretreatment procedures and processes being considered for removal of important radionuclides from retrieved tank wastes

On-site waste storage assuring the success of on-site, low-level nuclear waste storage

International Nuclear Information System (INIS)

Preston, E.L.

1986-01-01

Waste management has reached paramount importance in recent years. The successful management of radioactive waste is a key ingredient in the successful operation of any nuclear facility. This paper discusses the options available for on-site storage of low-level radioactive waste and those options that have been selected by the Department of Energy facilities operated by Martin Marietta Energy Systems, Inc. in Oak Ridge, Tennessee. The focus of the paper is on quality assurance (QA) features of waste management activities such as accountability and retrievability of waste materials and waste packages, retrievability of data, waste containment, safety and environmental monitoring. Technical performance and careful documentation of that performance are goals which can be achieved only through the cooperation of numerous individuals from waste generating and waste managing organizations, engineering, QA, and environmental management

Waste minimization - Hanford's strategy for sustainability

International Nuclear Information System (INIS)

Merry, D.S.

1998-01-01

The Hanford Site cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single-shell storage tanks, treating waste stored in 28 double-shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored onsite, removing thousands of structures, and dealing with significant solid waste, groundwater, and land restoration issues. The Pollution Prevention/Waste Minimization (P2/WMin) Program supports the Hanford Site mission to safely clean up and manage legacy waste and to develop and deploy science and technology in many ways. Once such way is through implementing and documenting over 231 waste reduction projects during the past five years, resulting in over $93 million in cost savings/avoidances. These savings/avoidances allowed other high priority cleanup work to be performed. Another way is by exceeding the Secretary of Energy's waste reduction goals over two years ahead of schedule, thus reducing the amount of waste to be stored, treated and disposed. Six key elements are the foundation for these sustained P2/WMin results

On the road to WIPP: Or remote packaging of transuranic waste

International Nuclear Information System (INIS)

Ledbetter, J.M.; Field, L.R.

1994-01-01

At the Los Alamos National Laboratory (LANL) Hot Cell facility, highly productive programs in reactor research spanning three decades have generated appreciable quantities of legacy waste. Hot cell capability had become virtually useless due to the storage of this waste. As a result of concentrated efforts by LANL staff, in cooperation with Westinghouse Waste Isolation Pilot Plant (WIPP), a solution was arrived at that allowed the facility to become productive once again. Equipment has been designed and fabricated to remotely handle 55-gal. waste drums, load waste canisters, perform canister weld closure, leak test welds, grapple the waste canister and transport the canister to an interim storage site. It is our contention that the technology and acquired equipment produced from this effort should be used to further benefit other DOE sites

Radionuclide metrology research for nuclear site decommissioning

Science.gov (United States)

Judge, S. M.; Regan, P. H.

2017-11-01

The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.

Screening criteria for siting waste management facilities: Regional Management Plan

International Nuclear Information System (INIS)

1986-01-01

The Midwest Interstate Low-Level Radioactive Waste Commission (Midwest Compact) seeks to define and place into operation a system for low-level waste management that will protect the public health and safety and the environment from the time the waste leaves its point of origin. Once the system is defined it will be necessary to find suitable sites for the components of that waste management system. The procedure for siting waste management facilities that have been chosen by the compact is one in which a host state is chosen for each facility. The host state is then given the freedom to select the site. Sites will be needed of low-level waste disposal facilities. Depending on the nature of the waste management system chosen by the host state, sites may also be needed for regional waste treatment facilities, such as compactors or incinerators. This report provides example criteria for use in selecting sites for low-level radioactive waste treatment and disposal facilities. 14 refs

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2009-07-31

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

2009-01-01

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was

Hanford site implementation plan for buried, transuranic-contaminated waste

International Nuclear Information System (INIS)

1987-05-01

The GAO review of DOE's Defense Waste Management Plan (DWMP) identified deficiencies and provided recommendations. This report responds to the GAO recommendations with regard to the Hanford Site. Since the issuance of the DWMP, an extensive planning base has been developed for all high-level and transuranic waste at the Hanford Site. Thirty-three buried sites have been identified as possibly containing waste that can be classified as transuranic waste. Inventory reports and process flowsheets were used to provide an estimate of the radionuclide and hazardous chemical content of these sites and approximately 370 additional sites that can be classified as low-level waste. A program undertaken to characterize select sites suspected of having TRU waste to refine the inventory estimates. Further development and evaluation are ongoing to determine the appropriate remedial actions, with the objectives of balancing long-term risks with costs and complying with regulations. 18 refs., 7 figs., 6 tabs

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Kendrick, C.M.

1994-03-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ``legacy`` wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL`s strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies.

Managing soil moisture on waste burial sites

International Nuclear Information System (INIS)

Anderson, J.E.; Ratzlaff, T.D.

1991-11-01

Shallow land burial is a common method of disposing of industrial, municipal, and low-level radioactive waste. The exclusion of water from buried wastes is a primary objective in designing and managing waste disposal sites. If wastes are not adequately isolated, water from precipitation may move through the landfill cover and into the wastes. The presence of water in the waste zone may promote the growth of plant roots to that depth and result in the transport of toxic materials to above-ground foliage. Furthermore, percolation of water through the waste zone may transport contaminants into ground water. This report presents results from a field study designed to assess the the potential for using vegetation to deplete soil moisture and prevent water from reaching buried wastes at the Idaho National Engineering Laboratory (INEL). Our results show that this approach may provide an economical means of limiting the intrusion of water on waste sites

Historical research in the Hanford site waste cleanup

International Nuclear Information System (INIS)

Gerber, Michele S.

1992-01-01

This paper will acquaint the audience with role of historical research in the Hanford Site waste cleanup - the largest waste cleanup endeavor ever undertaken in human history. There were no comparable predecessors to this massive waste remediation effort, but the Hanford historical record can provide a partial road map and guide. It can be, and is, a useful tool in meeting the goal of a successful, cost-effective, safe and technologically exemplary waste cleanup. The Hanford historical record is rich and complex. Yet, it poses difficult challenges, in that no central and complete repository or data base exists, records contain obscure code words and code numbers, and the measurement systems and terminology used in the records change many times over the years. Still, these records are useful to the current waste cleanup in technical ways, and in ways that extend beyond a strictly scientific aspect. Study and presentations of Hanford Site history contribute to the huge educational and outreach tasks of helping the Site's work force deal with 'culture change' and become motivated for the cleanup work that is ahead, and of helping the public and the regulators to place the events at Hanford in the context of WWII and the Cold War. This paper traces historical waste practices and policies as they changed over the years at the Hanford Site, and acquaints the audience with the generation of the major waste streams of concern in Hanford Site cleanup today. It presents original, primary-source research into the waste history of the Hanford Site. The earliest, 1940s knowledge base, assumptions and calculations about radioactive and chemical discharges, as discussed in the memos, correspondence and reports of the original Hanford Site (then Hanford Engineer Works) builders and operators, are reviewed. The growth of knowledge, research efforts, and subsequent changes in Site waste disposal policies and practices are traced. Examples of the strengths and limitations of the

Method of draining water through a solid waste site without leaching

Science.gov (United States)

Treat, Russell L.; Gee, Glendon W.; Whyatt, Greg A.

1993-01-01

The present invention is a method of preventing water from leaching solid waste sites by preventing atmospheric precipitation from contacting waste as the water flows through a solid waste site. The method comprises placing at least one drain hole through the solid waste site. The drain hole is seated to prevent waste material from entering the drain hole, and the solid waste site cover material is layered and graded to direct water to flow toward the drain hole and to soil beneath the waste site.

The importance of stakeholder involvement in a successful waste management program

International Nuclear Information System (INIS)

Goidell, L.C.; Hagen, T.D.; Thompson, T.; Sattler, J.

1998-01-01

The Fernald Environmental Management Project has been transporting legacy low-level radioactive waste to the Nevada Test Site for disposal since 1985. Additionally, several records of decision have been issued regarding Fernald Environmental Management Project remediation waste disposal on-site, at the Nevada Test Site, or at a permitted commercial disposal facility. Under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended, once of the criteria that must be evaluated prior to issuance of a record of decision is public acceptance. The Fernald Environmental Management Project has made a concerted effort to gain stakeholder support both locally and in Nevada for these records of decision. The Fernald Environmental Management Project's approach towards stakeholder interaction can provide a valuable framework for other sites that need to dispose of operations or remediation waste at remote, off-site locations. This approach has also been invaluable in allowing the public to understand the actual effects of waste management incidents

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Ellefson, M.D.

1998-01-01

Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

Closure Report for Corrective Action Unit 537: Waste Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

NSTec Environmental Restoration

2007-01-01

Corrective Action Unit (CAU) 537 is identified in the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 as Waste Sites. CAU 537 is located in Areas 3 and 19 of the Nevada Test Site, approximately 65 miles northwest of Las Vegas, Nevada, and consists of the following two Corrective Action Sites (CASs): CAS 03-23-06, Bucket; Yellow Tagged Bags; and CAS 19-19-01, Trash Pit. CAU 537 closure activities were conducted in April 2007 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2003). At CAS 03-23-06, closure activities included removal and disposal of a 15-foot (ft) by 15-ft by 8-ft tall wooden shed containing wood and metal debris and a 5-gallon plastic bucket containing deteriorated plastic bags with yellow radioactive contamination tape. The debris was transported to the Area 9 U10c Landfill for disposal after being screened for radiological contamination according to the ''NV/YMP Radiological Control Manual'' (NNSA/NSO, 2004). At CAS 19-19-01, closure activities included segregation, removal, and disposal of non-friable, non-regulated asbestos-containing material (ACM) and construction debris. The ACM was determined to be non-friable by waste characterization samples collected prior to closure activities. The ACM was removed and double-bagged by licensed, trained asbestos workers and transported to the Area 9 U10c Landfill for disposal. Construction debris was transported in end-dump trucks to the Area 9 U10c Landfill for disposal. Closure activities generated sanitary waste/construction debris and ACM. Waste generated during closure activities was appropriately managed and disposed. Waste characterization sample results are included as Appendix A of this report, and waste disposition documentation is included as Appendix B of this report. Copies of the Sectored Housekeeping Site Closure

Risky business: Assessing cleanup plans for waste sites

International Nuclear Information System (INIS)

Blaylock, B.

1995-01-01

ORNL was chosen to perform human health and ecological risk assessments for DOE because of its risk assessment expertise. The U.S. Department of Energy's many production and research sites contain radioactive and hazardous wastes. These waste sites pose potential risks to the health and safety of remediation and waste management workers and the public. The risks, however, vary from site to site. Some sites undoubtedly present larger risks than others and should be cleaned up first. However, before the cleanup begins, DOE is required by law to prepare an environmental impact statement on any actions that may significantly affect the environment-even actions that would clean it up

Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Wickline, Alfred

2005-01-01

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

Progress on Footprint Reduction at the Hanford Site - 12406

Energy Technology Data Exchange (ETDEWEB)

McKenney, Dale E. [CH2M HILL, Plateau Remediation Company, Richland, Washington 99352 (United States); Seeley, Paul [Cenibark International, Inc., Richland, Washington 99352 (United States); Farabee, Al [U.S. Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)

2012-07-01

The Department of Energy (DOE) Office of Environmental Management (EM) continues to reduce the footprint of legacy sites throughout the EM complex. Footprint reduction is being accomplished by focusing cleanup activities on decontamination and demolition of excess contaminated facilities, soil and groundwater remediation, and solid waste disposition. All of these initiatives are being accomplished with established technologies in proven regulatory frameworks. Ultimately, completion of these environmental cleanup activities will reduce the monitoring and maintenance costs associated with managing large federal facilities, allowing EM to place more focus on other high priority cleanup efforts and facilitate a successful transition to land-term stewardship of these sites. Through the American Recovery and Reinvestment Act (ARRA) investment, the Department's cleanup footprint has been reduced by 45 percent to date, from 2411 km{sup 2} (931 mi{sup 2}) to 1336 km{sup 2} (516 mi{sup 2}s). With this significant progress on footprint reduction, the Department is on track towards their goal to reduce its overall footprint by approximately 90 percent by 2015. In addition, some areas cleaned up may become available for alternate uses (i.e. recreation, conservation, preservation, industrialization or development). Much of the work to reduce the complex's footprint occurred at the Savannah River Site in South Carolina and the Hanford Site in Washington, but cleanup continues across the complex. Footprint reduction is progressing well at the Hanford Site, supported predominantly through ARRA investment. To date, 994 km{sup 2} (384 mi{sup 2}) (65%) of footprint reduction have been achieved at Hanford, with a goal to achieve a 90% reduction by Fiscal Year 2015. The DOE EM and DOE Richland Operations Office, continue to make great progress to reduce the legacy footprint of the Hanford Site. Footprint reduction is being accomplished by focusing cleanup activities on

Waste minimization -- Hanford`s strategy for sustainability

Energy Technology Data Exchange (ETDEWEB)

Merry, D.S.

1998-01-30

The Hanford Site cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single-shell storage tanks, treating waste stored in 28 double-shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored onsite, removing thousands of structures, and dealing with significant solid waste, groundwater, and land restoration issues. The Pollution Prevention/Waste Minimization (P2/WMin) Program supports the Hanford Site mission to safely clean up and manage legacy waste and to develop and deploy science and technology in many ways. Once such way is through implementing and documenting over 231 waste reduction projects during the past five years, resulting in over $93 million in cost savings/avoidances. These savings/avoidances allowed other high priority cleanup work to be performed. Another way is by exceeding the Secretary of Energy`s waste reduction goals over two years ahead of schedule, thus reducing the amount of waste to be stored, treated and disposed. Six key elements are the foundation for these sustained P2/WMin results.

Site specific plan. [Environmental Restoration and Waste Management, Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Hutchison, J.; Jernigan, G.

1989-12-01

The Environmental Restoration and Waste Management Five-Year Plan (FYP) covers the period for FY 1989 through FY 1995. The plan establishes a Department of Energy -- Headquarters (DOE-HQ) agenda for cleanup and compliance against which overall progress can be measured. The FYP covers three areas: Corrective Activities, Environmental Restoration, and Waste Management Operations. Corrective Activities are those activities necessary to bring active or standby facilities into compliance with local, state, and federal environmental regulations. Environmental restoration activities include the assessment and cleanup of surplus facilities and inactive waste sites. Waste management operations includes the treatment, storage, and disposal of wastes which are generated as a result of ongoing operations. This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show how environmental restoration and waste management activities that were identified during the preparation of the FYP will be implemented, tracked, and reported. The SSP describes DOE Savannah River (DOE-SR) and operating contractor, Westinghouse Savannah River Company (WSRC), organizations that are responsible, for undertaking the activities identified in this plan. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. 8 refs., 46 figs., 23 tabs.

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class-C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types. The paper discusses site selection; establishment of the Radioactive Waste Management Project; operations with respect to low-level radioactive wastes, transuranic waste storage, greater confinement disposal test, and mixed waste management facility; and related research activities such as tritium migration studies, revegetation studies, and in-situ monitoring of organics

Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

This report contains information on hazardous materials at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation

Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

This report contains information on hazardous materials at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

none,

2013-06-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2013-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Mixed waste disposal facility at the Nevada Test Site

International Nuclear Information System (INIS)

Dickman, P.T.; Kendall, E.W.

1987-01-01

In 1984, a law suit brought against DOE resulted in the requirement that DOE be subject to regulation by the state and US Environmental Protection Agency (EPA) for all hazardous wastes, including mixed wastes. Therefore, all DOE facilities generating, storing, treating, or disposing of mixed wastes will be regulated under the Resource Conservation and Recovery Act (RCTA). In FY 1985, DOE Headquarters requested DOE low-level waste (LLW) sites to apply for a RCRA Part B Permit to operate radioactive mixed waste facilities. An application for the Nevada Test Site (NTS) was prepared and submitted to the EPA, Region IX in November 1985 for review and approval. At that time, the state of Nevada had not yet received authorization for hazardous wastes nor had they applied for regulatory authority for mixed wastes. In October 1986, DOE Nevada Operations Office was informed by the Rocky Flats Plant that some past waste shipments to NTS contained trace quantities of hazardous substances. Under Colorado law, these wastes are defined as mixed. A DOE Headquarters task force was convened by the Under Secretary to investigate the situation. The task force concluded that DOE has a high priority need to develop a permitted mixed waste site and that DOE Nevada Operations Office should develop a fast track project to obtain this site and all necessary permits. The status and issues to be resolved on the permit for a mixed waste site are discussed

Hazardous waste shipment data collection from DOE sites

International Nuclear Information System (INIS)

Page, L.A.; Kirkpatrick, T.D.; Stevens, L.

1992-01-01

Past practices at the US Department of Energy (DOE) sites for offsite release of hazardous waste are being reviewed to determine if radioactively contaminated hazardous wastes were released to commercial treatment, storage, and disposal facilities. Records indicating the presence of radioactivity in waste shipped to and treated at a commercial incineration facility led to a ban on offsite hazardous waste shipments and investigation of past practices for offsite release of hazardous waste from the DOE sites. A House of Representatives Interior and Insular Affairs Committee oversight hearing on potentially contaminated waste shipments to commercial facilities concluded that the main issue was the lack of a uniform national standard to govern disposal of mixed waste

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2009-05-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

International Nuclear Information System (INIS)

2009-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Evaluating the potential of process sites for waste heat recovery

International Nuclear Information System (INIS)

Oluleye, Gbemi; Jobson, Megan; Smith, Robin; Perry, Simon J.

2016-01-01

Highlights: • Analysis considers the temperature and duties of the available waste heat. • Models for organic Rankine cycles, absorption heat pumps and chillers proposed. • Exploitation of waste heat from site processes and utility systems. • Concept of a site energy efficiency introduced. • Case study presented to illustrate application of the proposed methodology. - Abstract: As a result of depleting reserves of fossil fuels, conventional energy sources are becoming less available. In spite of this, energy is still being wasted, especially in the form of heat. The energy efficiency of process sites (defined as useful energy output per unit of energy input) may be increased through waste heat utilisation, thereby resulting in primary energy savings. In this work, waste heat is defined and a methodology developed to identify the potential for waste heat recovery in process sites; considering the temperature and quantity of waste heat sources from the site processes and the site utility system (including fired heaters and, the cogeneration, cooling and refrigeration systems). The concept of the energy efficiency of a site is introduced – the fraction of the energy inputs that is converted into useful energy (heat or power or cooling) to support the methodology. Furthermore, simplified mathematical models of waste heat recovery technologies using heat as primary energy source, including organic Rankine cycles (using both pure and mixed organics as working fluids), absorption chillers and absorption heat pumps are developed to support the methodology. These models are applied to assess the potential for recovery of useful energy from waste heat. The methodology is illustrated for an existing process site using a case study of a petroleum refinery. The energy efficiency of the site increases by 10% as a result of waste heat recovery. If there is an infinite demand for recovered energy (i.e. all the recoverable waste heat sources are exploited), the site

Solid waste management complex site development plan

International Nuclear Information System (INIS)

Greager, T.M.

1994-01-01

The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated

Solid waste management complex site development plan

Energy Technology Data Exchange (ETDEWEB)

Greager, T.M.

1994-09-30

The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated.

Area 5 Radioactive Waste Management Site Safety Assessment Document

International Nuclear Information System (INIS)

Horton, K.K.; Kendall, E.W.; Brown, J.J.

1980-02-01

The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. C. Khamankar

2000-06-20

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. C. Khamankar

2000-01-01

The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

Legacy sample disposition project. Volume 2: Final report

International Nuclear Information System (INIS)

Gurley, R.N.; Shifty, K.L.

1998-02-01

This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions

Technical summary of groundwater quality protection program at the Savannah River Site, 1952--1986. Volume 1, Site geohydrology and waste sites

Energy Technology Data Exchange (ETDEWEB)

Heffner, J.D. [ed.] [Exploration Resources, Inc., Athens, GA (United States)

1991-11-01

This report provides information regarding the status of and groundwater quality at the waste sites at the Department of Energy`s (DOE) Savannah River Site (SRS). Specific information provided for each waste site at SRS includes its location, size, inventory (when known), and history. Many waste sites at SRS are considered to be of little environmental concern because they contain nontoxic or inert material such as construction rubble and debris. Other waste sites, however, either are known to have had an effect on groundwater quality or are suspected of having the potential to affect groundwater. Monitoring wells have been installed at most of these sites; monitoring wells are scheduled for installation at the remaining sites. Results of the groundwater analyses from these monitoring wells, presented in the appendices, are used in the report to help identify potential contaminants of concern, if any, at each waste site. The list of actions proposed for each waste site in Christensen and Gordon`s 1983 report are summarized, and an update is provided for each site. Planned actions for the future are also outlined.

Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

International Nuclear Information System (INIS)

Feo, Giovanni De; Gisi, Sabino De

2014-01-01

Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method

Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal

Energy Technology Data Exchange (ETDEWEB)

Feo, Giovanni De, E-mail: g.defeo@unisa.it [Department of Industrial Engineering, University of Salerno, via Giovanni Paolo II, 132, 84084 Fisciano, SA (Italy); Gisi, Sabino De [Italian National Agency for New Technologies, Energy and Sustainable Economic Development, ENEA, Water Resource Management Lab., via Martiri di Monte Sole 4, 40129 Bologna, BO (Italy)

2014-11-15

Highlights: • Wasting land for the siting of hazardous waste landfills must be avoided. • The siting procedure is based on a land use map of potentially suitable areas. • All the waste facilities of the management system are simultaneously considered. • A case study is developed considering two multi-criteria techniques. • An innovative criteria weighting tool (PSW) is used in combination with the AHP. - Abstract: The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a “land use map of potentially suitable areas” for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the “Priority Scale”) in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method.

Hanford Site radioactive mixed waste thermal treatment initiative

International Nuclear Information System (INIS)

Place, B.G.; Riddelle, J.G.

1993-03-01

This paper is a progress report of current Westinghouse Hanford Company engineering activities related to the implementation of a program for the thermal treatment of the Hanford Site radioactive mixed waste. Topics discussed include a site-specific engineering study, the review of private sector capability in thermal treatment, and thermal treatment of some of the Hanford Site radioactive mixed waste at other US Department of Energy sites

Hazardous and mixed waste management at UMTRA sites

International Nuclear Information System (INIS)

Hampill, H.G.

1988-01-01

During the early stages of the Uranium Mill Tailings Remedial Action Project, there were some serious questions regarding the ownership of and consequently the responsibility for disposal of hazardous wastes at UMTRA sites. In addition to State and Indian Tribe waste disposal regulations, UMTRA must also conform to guidelines established by the NRC, OSHA, EPA, and DOT. Because of the differing regulatory thrusts of these agencies, UMTRA has to be vigilant in order to ensure that the disposal of each parcel of waste material is in compliance with all regulations. Mixed-waste disposal presents a particularly difficult problem. No single agency is willing to lay claim to the regulation of mixed-wastes, and no conventional waste disposal facility is willing to accept it. Consequently, the disposal of each lot of mixed-waste at UMTRA sites must be handled on a case by case basis. A recently published position paper which spells out UMTRA policy on waste materials indicates that wastes found at UMTRA sites are either residual radioactive wastes, or mixed-wastes, or for the disposal of hazardous waste is determined by the time the original material arrived. If it arrived prior to the termination of the AEC uranium supply contract, its disposal is the responsibility of UMTRA. If it arrived after the end of the contract, the responsibility for disposal lies with the former operator

CHARACTERIZATION OF CURRENTLY GENERATED TRANUSRANIC WASTE AT THE LOS ALAMOS NATIONAL LABORATORY'S PLUTONIUM PRODUCTION FACILITY

International Nuclear Information System (INIS)

Dodge, Robert L.; Montoya, Andy M.

2003-01-01

By the time the Waste Isolation Pilot Plant (WIPP) completes its Disposal Phase in FY 2034, the Department of Energy (DOE) will have disposed of approximately 109,378 cubic meters (m3) of Transuranic (TRU) waste in WIPP (1). If DOE adheres to its 2005 Pollution Prevention Goal of generating less than 141m3/yr of TRU waste, approximately 5000 m3 (4%) of that TRU waste will be newly generated (2). Because of the overwhelming majority (96%) of TRU waste destined for disposal at WIPP is legacy waste, the characterization and certification requirements were developed to resolve those issues related to legacy waste. Like many other DOE facilities Los Alamos National Laboratory (LANL) has a large volume (9,010m3) of legacy Transuranic Waste in storage (3). Unlike most DOE facilities LANL will generate approximately 140m3 of newly generated TRU waste each year3. LANL's certification program was established to meet the WIPP requirements for legacy waste and does not take advantage of the fundamental differences in waste knowledge between newly generated and legacy TRU waste

Low-Level Radioactive Waste siting simulation information package

International Nuclear Information System (INIS)

1985-12-01

The Department of Energy's National Low-Level Radioactive Waste Management Program has developed a simulation exercise designed to facilitate the process of siting and licensing disposal facilities for low-level radioactive waste. The siting simulation can be conducted at a workshop or conference, can involve 14-70 participants (or more), and requires approximately eight hours to complete. The exercise is available for use by states, regional compacts, or other organizations for use as part of the planning process for low-level waste disposal facilities. This information package describes the development, content, and use of the Low-Level Radioactive Waste Siting Simulation. Information is provided on how to organize a workshop for conducting the simulation. 1 ref., 1 fig

Hanford Site waste management units report

International Nuclear Information System (INIS)

1993-04-01

The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part

Avoidable waste management costs

International Nuclear Information System (INIS)

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP

Avoidable waste management costs

Energy Technology Data Exchange (ETDEWEB)

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Ecological and human impact assessment in the legacy enhanced and naturally occurring radiation areas - human and ecological impact assessment in the legacy enhanced and naturally occurring radiation areas

Energy Technology Data Exchange (ETDEWEB)

Mrdakovic Popic, Jelena [Norwegian Radiation Protection Authority, P.O. Box 55, N-1332 Oesteraas (Norway); Salbu, Brit; Skipperud, Lindis [Norwegian University of Life Sciences, Centre for Environmental radioactivity CERAD, P.O. Box 5003, 1430 Aas (Norway)

2014-07-01

The Fen Complex in Norway is an area well-known with its specific magmatic bedrock rich in thorium (Th), iron (Fe), niobium (Nb) and rare earth elements (REE). During several past centuries, intensive mining was conducted at sites in the area, giving rise to enhanced radioactivity levels. Previous human health studies demonstrated exposure doses among the highest in Europe. In the current work, contamination status with respect to radionuclides ({sup 232}Th, uranium ({sup 238}U)) and trace elements (arsenic (As), chromium (Cr) and lead (Pb)) and possible impact on humans and biota were investigated at legacy NORM and undisturbed surrounding NOR rich sites in the Fen Complex area. Significantly heterogeneous radionuclides ({sup 232}Th, {sup 238}U, and daughters) distribution was found in soil at both legacy NORM and undisturbed NOR rich sites. Thorium activity concentration levels exceeded screening levels for radioactive waste material given by Norwegian Pollution Control Act. Based on sequential extraction results, mobility of {sup 232}Th and trace elements were low, although higher at legacy NORM than at undisturbed NOR rich sites. Uranium was present at considerable levels (up to 50 %) in pH and redox sensitive soil fraction, as well as bound to soil organic compounds. However, no further transport towards biggest water source Norsjoe Lake was observed, as concentration levels of all investigated elements in water samples were extremely low. Long-term surveys of outdoor terrestrial gamma dose rates, thoron ({sup 220}Rn) and radon ({sup 222}Rn) concentrations in the air demonstrated elevated values (up to 9.2 μGy/h, 5000 Bq/m{sup 3} and 200 Bq/m{sup 3}, respectively) with significant seasonal variation. Calculated annual exposure doses to humans due to outdoor exposure could exceed 10 mSv, i.e., be higher than 1 mSv dose constraint given by ICRP. Roughly summarized with previously published data on indoor doses for Fen village population, total annual exposure

Review of Analytes of Concern and Sample Methods for Closure of DOE High Level Waste Storage Tanks

International Nuclear Information System (INIS)

Thomas, T.R.

2002-01-01

Sampling residual waste after tank cleaning and analysis for analytes of concern to support closure and cleaning targets of large underground tanks used for storage of legacy high level radioactive waste (HLW) at Department of Energy (DOE) sites has been underway since about 1995. The DOE Tanks Focus Area (TFA) has been working with DOE tank sites to develop new sampling plans, and sampling methods for assessment of residual waste inventories. This paper discusses regulatory analytes of concern, sampling plans, and sampling methods that support closure and cleaning target activities for large storage tanks at the Hanford Site, the Savannah River Site (SRS), the Idaho National Engineering and Environmental Laboratory (INEEL), and the West Valley Demonstration Project (WVDP)

Tracking legacy radionuclides in St. Louis, Missouri, via unsupported "2"1"0Pb

International Nuclear Information System (INIS)

Kaltofen, Marco P.J.; Alvarez, Robert; Hixson, Lucas

2016-01-01

Analysis of 287 soil, sediment and house dust samples collected in a 200 km"2-zone in northern St. Louis County, Missouri, establish that offsite migration of radiological contaminants from Manhattan Project-era uranium processing wastes has occurred in this populated area. Specifically, 48% of samples (111 of a subset of 229 soils and sediments tested) had "2"1"0Pb concentrations above the risk-based soil cleanup limits for residential farming established by the US Department of Energy at the Fernald, OH, uranium plant, which handled and stored the same concentrated Manhattan Project-era wastes; the geographical distribution of the exceedances are consistent with water and radon gas releases from a landfill and related sites used to store and dispose of legacy uranium wastes; and offsite soil and house dust samples proximal to the landfill showed distinctive secular disequilibrium among uranium and its progeny indicative of uranium ore processing wastes. The secular disequilibrium of uranium progeny in the environment provides an important method for distinguishing natural uranium from industrial uranium wastes. In this study, the detection of unsupported "2"1"0Pb beyond expected atmospheric deposition rates is examined as a possible indicator of excessive radon emissions from buried uranium and radium-containing wastes. - Highlights: • We sampled and analyzed 287 urban soils and sediments for uranium processing wastes. • Radium and unsupported "2"1"0Pb were the primary tracers for wastes. • The goal was to track Manhattan Project wastes around St. Louis, MO. • Activity levels in the environment peaked around land disposal sites. • Unsupported "2"1"0Pb and isotopic uranium & thorium were also found in house dusts.

Site Management Guide (Blue Book)

International Nuclear Information System (INIS)

2014-01-01

The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department's postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE's postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site

Application for Permit to Operate a Class II Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-03-31

The Nevada Test Site (NTS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NTS and National Security Technologies LLC (NSTec) is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The site will be used for the disposal of refuse, rubbish, garbage, sewage sludge, pathological waste, Asbestos-Containing Material (ACM), industrial solid waste, hydrocarbon-burdened soil, hydrocarbon-burdened demolition and construction waste, and other inert waste (hereafter called permissible waste). Waste containing free liquids or regulated under Subtitle C of the Resource Conservation and Recovery Act (RCRA) will not be accepted for disposal at the site. Waste regulated under the Toxic Substance Control Act (TSCA), excluding Polychlorinated Biphenyl [PCB], Bulk Product Waste (see Section 6.2.5) and ACM (see Section 6.2.2.2) will not be accepted for disposal at the site. The disposal site will be used as the sole depository of permissible waste which is: (1) Generated by entities covered under the U.S. Environmental Protection Agency (EPA) Hazardous Waste Generator Identification Number for the NTS; (2) Generated at sites identified in the Federal Facilities Agreement and Consent Order (FFACO); (3) Sensitive records and media, including documents, vugraphs, computer disks, typewriter ribbons, magnetic tapes, etc., generated by NNSA/NSO or its contractors; (4) ACM generated by NNSA/NSO or its contractors according to Section 6.2.2.2, as necessary; (5) Hydrocarbon-burdened soil and solid waste from areas covered under the EPA Hazardous Waste Generator Identification Number for the NTS; (6) Other waste on a case-by-case concurrence by

Fate of nuclear waste site remains unclear

International Nuclear Information System (INIS)

Anderson, E.V.

1980-01-01

The only commercial nuclear fuel reprocessing plant in the U.S., located in West Valley, N.Y., has been shut down since 1972, and no efforts have yet been made to clean up the site. The site contains a spent-fuel pool, high level liquid waste storage tanks, and two radioactive waste burial grounds. Nuclear Fuel Services, Inc., has been leasing the site from the New York State Energy RandD Authority. Federal litigation may ensue, prompted by NRC and DOE, if the company refuses to decontaminate the area when its lease expires at the end of 1980. DOE has developed a plan to solidify the liquid wastes at the facility but needs additional legislation and funding to implement the scheme

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2010

Energy Technology Data Exchange (ETDEWEB)

Mamatey, A.; Dunaway-Ackerman, J.

2011-08-16

This report was prepared in accordance with U.S. Department of Energy (DOE) Order 231.1A, 'Environment, Safety and Health Reporting,' to present summary environmental data for the purpose of: (a) characterizing site's environmental management performance; (b) summarizing environmental occurrences and responses reported during the calendar year; (c) describing compliance status with respect to environmental standards and requirements; and (d) highlighting significant site programs and efforts. This report is the principal document that demonstrates compliance with the requirements of DOE Order 5400.5, 'Radiation Protection of the Public and the Environment,' and is a key component of DOE's effort to keep the public informed of environmental conditions at Savannah River Site (SRS). SRS has four primary missions: (1) Environmental Management - Cleaning up the legacy of the Cold War efforts and preparing decommissioned facilities and areas for long-term stewardship; (2) Nuclear Weapons Stockpile Support - Meeting the needs of the U.S. nuclear weapons stockpile through the tritium programs of the National Nuclear Security Administration (NNSA); (3) Nuclear Nonproliferation Support - Meeting the needs of the NNSA's nuclear nonproliferation programs by safely storing and dispositioning excess special nuclear materials; and (4) Research and Development - Supporting the application of science by the Savannah River National Laboratory (SRNL) to meet the needs of SRS, the DOE complex, and other federal agencies During 2010, SRS worked to fulfill these missions and position the site for future operations. SRS continued to work with the South Carolina Department of Health and Environmental Control (SCDHEC), the Environmental Protection Agency (EPA), and the Nuclear Regulatory Commission to find and implement solutions and schedules for waste management and disposition. As part of its mission to clean up the Cold War legacy, SRS will continue

Description of the Northwest hazardous waste site data base and preliminary analysis of site characteristics

International Nuclear Information System (INIS)

Woodruff, D.L.; Hartz, K.E.; Triplett, M.B.

1988-08-01

The Northwest Hazardous Waste RD and D Center (the Center) conducts research, development, and demonstration (RD and D) activities for hazardous and radioactive mixed-waste technologies applicable to remediating sites in the states of Idaho, Montana, Oregon, and Washington. To properly set priorities for these RD and D activities and to target development efforts it is necessary to understand the nature of the sites requiring remediation. A data base of hazardous waste site characteristics has been constructed to facilitate this analysis. The data base used data from EPA's Region X Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) and from Preliminary Assessment/Site Investigation (PA/SI) forms for sites in Montana. The Center's data base focuses on two sets of sites--those on the National Priorities List (NPL) and other sites that are denoted as ''active'' CERCLIS sites. Active CERCLIS sites are those sites that are undergoing active investigation and analysis. The data base contains information for each site covering site identification and location, type of industry associated with the site, waste categories present (e.g., heavy metals, pesticides, etc.), methods of disposal (e.g., tanks, drums, land, etc.), waste forms (e.g., liquid, solid, etc.), and hazard targets (e.g., surface water, groundwater, etc.). As part of this analysis, the Northwest region was divided into three geographic subregions to identify differences in disposal site characteristics within the Northwest. 2 refs., 18 figs., 5 tabs

Site and facility waste transportation services planning documents

International Nuclear Information System (INIS)

Ratledge, J.E.; Schmid, S.; Danese, L.

1991-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and maintenance of Site- and Facility-Specific Transportation Services Planning Documents (SPDs) and Site-Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities, with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations

327 legacy waste processing plan

International Nuclear Information System (INIS)

Henderson, J.F.

1998-01-01

The B and W Hanford Company's (BWHC) 327 Facility [Postirradiation Testing Laboratory (PTL)] houses 10 hot cells in which a variety of postirradiation examinations have been performed since its construction in the mid 1950s. Over the years, the waste that was generated in these cells has been collected in one gallon buckets. These buckets are essentially one gallon cylindrical cans made of thin wall stainless steel with welded bottoms and slip fit lids. They contain assorted compactable waste (i.e., Wipe-Alls, Q-tips, towels, etc.) as well as non-compactable waste (i.e., small tools, pieces of metal tubing, etc.). There is a FY-98 BWHC Performance Agreement (PA) milestone in place to package 200 of these buckets in drums and ship them from the 327 facility to the Central Waste Complex (CWC) by September 30, 1998

Safety assessment for Area 5 radioactive-waste-management site

International Nuclear Information System (INIS)

Hunter, P.H.; Card, D.H.; Horton, K.

1982-09-01

The Area 5 Radioactive Waste Management Safety Assessment Document contains evaluations of site characteristics, facilities, and operating practices that contribute to the safe handling, storage, and disposal of low-level radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. A separate section considers facilities and operating practices such as monitoring, storage/disposal criteria, site maintenance, equipment, and support. The section also considers the transportation and waste handling requirements supporting the new Greater Confinement Disposal Facility (GCDF), GCDF demonstration project, and other requirements for the safe handling, storage, and disposal of low-level radioactive wastes. Finally, the document provides an analysis of releases and an assessment of the near-term operational impacts and dose commitments to operating personnel and the general public from normal operations and anticipated accidental occurrences. The conclusion of this report is that the Area 5 Radioactive Waste Management Site is suitable for low-level radioactive waste handling, storage, and disposal. Also, the new GCDF demonstration project will not affect the overall safety of the Area 5 Radioactive Waste Management Site

Characterization recommendations for waste sites at the Savannah River Plant

International Nuclear Information System (INIS)

Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

1987-11-01

One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil

Hanford Site Solid Waste Landfill permit application. Revision 1

International Nuclear Information System (INIS)

1993-01-01

Both nonhazardous and nonradioactive sanitary solid waste are generated at the Hanford Site. This permit application describes the manner in which the Solid Waste Landfill will be operated. A description is provided of the landfill, including applicable locational, general facility, and landfilling standards. The characteristics and quantity of the waste disposed of are discussed. The regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill are reviewed. A plan is included of operation, closure, and postclosure. This report addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill is discussed

Pre-1970 transuranic solid waste at the Hanford Site

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1995-01-01

The document is based on a search of pre-1970 Hanford Solid Waste Records. The available data indicates seven out of thirty-one solid waste burial sites used for pre-1970 waste appear to be Transuranic (TRU). A burial site defined to be TRU contains >100 nCi/gm Transuranic nuclides

Modular risk analysis for assessing multiple waste sites

International Nuclear Information System (INIS)

Whelan, G.; Buck, J.W.; Nazarali, A.

1994-06-01

Human-health impacts, especially to the surrounding public, are extremely difficult to assess at installations that contain multiple waste sites and a variety of mixed-waste constituents (e.g., organic, inorganic, and radioactive). These assessments must address different constituents, multiple waste sites, multiple release patterns, different transport pathways (i.e., groundwater, surface water, air, and overland soil), different receptor types and locations, various times of interest, population distributions, land-use patterns, baseline assessments, a variety of exposure scenarios, etc. Although the process is complex, two of the most important difficulties to overcome are associated with (1) establishing an approach that allows for modifying the source term, transport, or exposure component as an individual module without having to re-evaluate the entire installation-wide assessment (i.e., all modules simultaneously), and (2) displaying and communicating the results in an understandable and useable maimer to interested parties. An integrated, physics-based, compartmentalized approach, which is coupled to a Geographical Information System (GIS), captures the regional health impacts associated with multiple waste sites (e.g., hundreds to thousands of waste sites) at locations within and surrounding the installation. Utilizing a modular/GIS-based approach overcomes difficulties in (1) analyzing a wide variety of scenarios for multiple waste sites, and (2) communicating results from a complex human-health-impact analysis by capturing the essence of the assessment in a relatively elegant manner, so the meaning of the results can be quickly conveyed to all who review them

Determination of total cyanide in Hanford Site high-level wastes

Energy Technology Data Exchange (ETDEWEB)

Winters, W.I. [Westinghouse Hanford Co., Richland, WA (United States); Pool, K.H. [Pacific Northwest Lab., Richland, WA (United States)

1994-05-01

Nickel ferrocyanide compounds (Na{sub 2-x}Cs{sub x}NiFe (CN){sub 6}) were produced in a scavenging process to remove {sup 137}Cs from Hanford Site single-shell tank waste supernates. Methods for determining total cyanide in Hanford Site high-level wastes are needed for the evaluation of potential exothermic reactions between cyanide and oxidizers such as nitrate and for safe storage, processing, and management of the wastes in compliance with regulatory requirements. Hanford Site laboratory experience in determining cyanide in high-level wastes is summarized. Modifications were made to standard cyanide methods to permit improved handling of high-level waste samples and to eliminate interferences found in Hanford Site waste matrices. Interferences and associated procedure modifications caused by high nitrates/nitrite concentrations, insoluble nickel ferrocyanides, and organic complexants are described.

Determination of total cyanide in Hanford Site high-level wastes

International Nuclear Information System (INIS)

Winters, W.I.; Pool, K.H.

1994-05-01

Nickel ferrocyanide compounds (Na 2-x Cs x NiFe (CN) 6 ) were produced in a scavenging process to remove 137 Cs from Hanford Site single-shell tank waste supernates. Methods for determining total cyanide in Hanford Site high-level wastes are needed for the evaluation of potential exothermic reactions between cyanide and oxidizers such as nitrate and for safe storage, processing, and management of the wastes in compliance with regulatory requirements. Hanford Site laboratory experience in determining cyanide in high-level wastes is summarized. Modifications were made to standard cyanide methods to permit improved handling of high-level waste samples and to eliminate interferences found in Hanford Site waste matrices. Interferences and associated procedure modifications caused by high nitrates/nitrite concentrations, insoluble nickel ferrocyanides, and organic complexants are described

Defense waste management operations at the Nevada Test Site

International Nuclear Information System (INIS)

Williams, R.E.; Kendall, E.W.

1988-01-01

Waste management activities were initiated at the Nevada Test Site (NTS) to dispose of low-level wastes (LLW) produced by the Department of Energy's (DOE's) weapons testing program. Disposal activities have expanded from the burial of atmospheric weapons testing debris to demonstration facilities for greater-than-Class C (GTCC) waste, transuranic (TRU) waste storage and certification, and the development of a mixed waste (MW) facility. Site specific operational research projects support technology development required for the various disposal facilities. The annual cost of managing the facilities is about $6 million depending on waste volumes and types

Managing Hanford Site solid waste through strict acceptance criteria

International Nuclear Information System (INIS)

Jasen, W.G.; Pierce, R.D.; Willis, N.P.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

DISPOSAL OF LOW AND INTERMEDIATE LEVEL WASTE IN HUNGARY

Directory of Open Access Journals (Sweden)

Bálint Nős

2012-07-01

Full Text Available There are two operating facilities for management of low and intermediate level radioactive waste in Hungary. Experience with radioactive waste has a relatively long history and from its legacy some problems are to be solved, like the question of the historical waste in the Radioactive Waste Treatment and Disposal Facility (RWTDF. Beside the legacy problems the current waste arising from the Nuclear Power Plant (NPP has to be dealt with a safe and economically optimized way.

Technologies to remediate hazardous waste sites

International Nuclear Information System (INIS)

Falco, J.W.

1990-03-01

Technologies to remediate hazardous wastes must be matched with the properties of the hazardous materials to be treated, the environment in which the wastes are imbedded, and the desired extent of remediation. Many promising technologies are being developed, including biological treatment, immobilization techniques, and in situ methods. Many of these new technologies are being applied to remediate sites. The management and disposal of hazardous wastes is changing because of federal and state legislation as well as public concern. Future waste management systems will emphasize the substitution of alternatives for the use of hazardous materials and process waste recycling. Onsite treatment will also become more frequently adopted. 5 refs., 7 figs

Developing and initiating a public engagement process for a nuclear decommissioning and waste management program

International Nuclear Information System (INIS)

Badke, C.; Johnson, C.; Brooks, S.; MacCafferty, M.

2011-01-01

Public consultation is key to any major nuclear initiative, but how do you engage the public in a complex multi-site nuclear decommissioning and environmental restoration program that will last 70 years? A clear message of sound environmental stewardship throughout the process is critical to building the trust required to attract public interest and support. The Nuclear Legacy Liabilities Program (NLLP) manages Canada's nuclear legacy liabilities at Atomic Energy of Canada Limited (AECL) sites and is funded by the Government of Canada through Natural Resources Canada (NRCan). The objective of the NLLP is to safely and cost-effectively reduce the federal legacy liabilities and associated risks, based on sound waste management and environmental principles, in the best interest of Canadians. An important area of focus for the NLLP in both the short- and long-term is to inform the public, stakeholders and Aboriginal people about the Program, and to gather input on the long-term strategy for site restoration and waste management. This paper describes progress made to date on developing and initiating a public engagement process for the NLLP in the initial phase of the Program. Furthermore, it examines general best practices for public participation, specific challenges and opportunities which have been identified, as well as the next steps for communications activities related to the Program. (author)

Hanford Site Composite Analysis Technical Approach Description: Radionuclide Inventory and Waste Site Selection Process.

Energy Technology Data Exchange (ETDEWEB)

Nichols, Will E.; Mehta, Sunil

2017-09-13

The updated Hanford Site Composite Analysis will provide an all-pathways dose projection to a hypothetical future member of the public from all planned low-level radioactive waste disposal facilities and potential contributions from all other projected end-state sources of radioactive material left at Hanford following site closure. Its primary purpose is to support the decision-making process of the U.S. Department of Energy (DOE) under DOE O 435.1-1, Radioactive Waste Management (DOE, 2001), related to managing low-level waste disposal facilities at the Hanford Site.

Lessons learned and present day challenges of addressing 20th century radiation legacies of Russia and the United States

International Nuclear Information System (INIS)

Rengel, M.T.; Kristofzski, J.G.; Schubert, A.L.

2002-01-01

Decommissioning of nuclear submarines, disposal of highly enriched uranium and defense plutonium as well as processing of high-level wastes are among the most challenging issues of addressing radiation legacy of the 20th century. USA and Russia are the two primary countries that have to deal with the challenge and where most of the fissile materials to be processed are concentrated, nuclear fuel and high-level radioactive waste are stored, and multiple industrial sites and nuclear weapons production facilities are located. In the US, CH2M HILL is managing two of the most important nuclear projects being conducted by the US Department of Energy at the Rocky Flats Environmental Technology Site and at the DOE Hanford Site (177 underground tanks at this site contain 60 percent of the United States' high-level radioactive wastes). Within the framework of the Russian Federal special program 'Radioactive Waste and Spent Nuclear Materials Management, Utilization and Disposal for 1996-2005' works were carried out on the Karachai lake covering with soil, highly active radwaste vitrification and fractionation at the 'Mayak' combine. Currently there is a discussion of launching joint Russian-American initiatives including comparative studies of environmental and public health impacts from high-level waste vitrification and plutonium stabilization processes in Russia and high-level waste removal from tanks in the USA and of continuing comprehensive research with the RADSITE project (USA, European Union, Japan, China and India) using coordinated approaches in 2000-2003. This paper presents comparative studies, technical approaches, and regulatory strategies to address the challenges of managing and closing highly enriched uranium, plutonium, and high level waste sites. (author)

On-site gamma dose rates at the Andreeva Bay shore technical base, northwest Russia

NARCIS (Netherlands)

Reistad, O.; Dowdall, M.; Standring, W. J. F.; Selnaes, O. G.; Hustveit, S.; Steinhusen, F.; Sorlie, A.

The spent nuclear fuel (SNF) and radioactive waste (RAW) storage facility at Andreeva Bay shore technical base (STB) is one of the largest and most hazardous nuclear legacy sites in northwest Russia. Originally commissioned in the 1960s the facility now stores large amounts of SNF and RAW associated

Using MCDA and GIS for hazardous waste landfill siting considering land scarcity for waste disposal.

Science.gov (United States)

De Feo, Giovanni; De Gisi, Sabino

2014-11-01

The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a "land use map of potentially suitable areas" for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the "Priority Scale") in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method. Copyright © 2014 Elsevier Ltd. All rights reserved.

Microbial effects on radioactive wastes at SLB sites

International Nuclear Information System (INIS)

Colombo, P.

1982-01-01

The objectives of this study are to determine the significance of microbial degradation of organic wastes on radionuclide migration on shallow land burial for humid and arid sites, establish which mechanisms predominate and ascertain the conditions under which these mechanisms operate. Factors contolling gaseous eminations from low-level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide and possibly hydrogen from the site stems from the inclusion of tritium and/or 14 C into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste materials, primary emphasis of the study involved on examination of the biochemical pathways producing methane, carbon dioxide and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Although the methane and carbon dioxide production rate indicates the degradation rate of the organic substances in the waste, it does not predict the methane evolution rate from the trench site. Methane fluxes from the soil surface are equivalent to the net synthesis minus the quantity oxidized by the microbial community as the gas passes through the soil profile. Gas studies were performed at three commercial low-level radioactive waste disposal sites (West Valley, New York; Beatty, Nevada; Maxey Flats, Kentucky) during the period 1976 to 1978. The results of these studies are presented. 3 tables

Hanford Site waste management and environmental restoration integration plan

International Nuclear Information System (INIS)

Merrick, D.L.

1990-01-01

The ''Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs

Detecting hot spots at hazardous-waste sites

International Nuclear Information System (INIS)

Zirschky, J.; Gilbert, R.O.

1984-01-01

Evaluating the need for remedial cleanup at a waste site involves both finding the average contaminant concentration and identifying highly contaminated areas, or hot spots. A nomographic procedure to determine the sample configuration needed to locate a hot spot is presented. The technique can be used to develop a waste-site sampling plant - to determine either the grid spacing required to detect a hot spot at a given level of confidence, or the probability of finding a hot spot of a certain size, given a particular grid spacing. The method and computer program (ELIPGRID) were developed for locating geologic deposits, but the basic procedure can also be used to detect hot spots at chemical- or nuclear-waste disposal sites. Nomographs based on the original program are presented for three sampling-grid configurations - square, rectangular and triangular

Hanford Site waste management units report

International Nuclear Information System (INIS)

1993-04-01

The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part.Volume two contains Sections 4.0 through 6.0 and the following appendices: Appendix A -- acronyms and definition of terms; Appendix B -- unplanned releases that are not considered to be units; and Appendix C -- operable unit maps

Comprehensive waste characterization and organic pollution co-occurrence in a Hg and As mining and metallurgy brownfield

Energy Technology Data Exchange (ETDEWEB)

Gallego, J.R., E-mail: jgallego@uniovi.es [Environmental Technology, Biotechnology and Geochemistry Group, C/Gonzalo Gutiérrez Quirós s/n, 33600 Mieres, Asturias (Spain); Esquinas, N.; Rodríguez-Valdés, E.; Menéndez-Aguado, J.M. [Environmental Technology, Biotechnology and Geochemistry Group, C/Gonzalo Gutiérrez Quirós s/n, 33600 Mieres, Asturias (Spain); Sierra, C. [Environmental Technology, Biotechnology and Geochemistry Group, C/Gonzalo Gutiérrez Quirós s/n, 33600 Mieres, Asturias (Spain); Escuela Superior Politécnica del Litoral, Guayaquil (Ecuador)

2015-12-30

Highlights: • Complex legacy of contamination afflicts As–Hg brownfields. • As- and Hg-rich waste analyzed in a paradigmatic study site. • Co-ocurrence of a complex speciation of As and Hg, and organic pollution (PAHs). • Arsenolite was determined to be the main source of risk at the site. • Unexpected Hg organo-compounds found. - Abstract: The abandonment of Hg–As mining and metallurgy sites, together with long-term weathering, can dramatically degrade the environment. In this work it is exemplified the complex legacy of contamination that afflicts Hg–As brownfields through the detailed study of a paradigmatic site. Firstly, an in-depth study of the former industrial process was performed to identify sources of different types of waste. Subsequently, the composition and reactivity of As- and Hg-rich wastes (calcines, As-rich soot, stupp, and flue dust) was analyzed by means of multielemental analysis, mineralogical characterization (X-ray diffraction, electronic, and optical microscopy, microbrobe), chemical speciation, and sequential extractions. As-rich soot in the form of arsenolite, a relatively mobile by-product of the pyrometallurgical process, and stupp, a residue originated in the former condensing system, were determined to be the main risk at the site. In addition, the screening of organic pollution was also aimed, as shown by the outcome of benzo(a) pyrene and other PAHs, and by the identification of unexpected Hg organo-compounds (phenylmercury propionate). The approach followed unravels evidence from waste from the mining and metallurgy industry that may be present in other similar sites, and identifies unexpected contaminants overlooked by conventional analyses.

Next Generation Waste Tracking: Linking Legacy Systems with Modern Networking Technologies

International Nuclear Information System (INIS)

Walker, Randy M.; Resseguie, David R.; Shankar, Mallikarjun; Gorman, Bryan L.; Smith, Cyrus M.; Hill, David E.

2010-01-01

of existing legacy hazardous, radioactive and related informational databases and systems using emerging Web 2.0 technologies. These capabilities were used to interoperate ORNL s waste generating, packaging, transportation and disposal with other DOE ORO waste management contractors. Importantly, the DOE EM objectives were accomplished in a cost effective manner without altering existing information systems. A path forward is to demonstrate and share these technologies with DOE EM, contractors and stakeholders. This approach will not alter existing DOE assets, i.e. Automated Traffic Management Systems (ATMS), Transportation Tracking and Communications System (TRANSCOM), the Argonne National Laboratory (ANL) demonstrated package tracking system, etc.

Remaining Sites Verification Package for the 128-B-2, 100-B Burn Pit No.2 Waste Site. Attchment to Waste Site Reclassification Form 2005-038

International Nuclear Information System (INIS)

Carlson, R.A.

2005-01-01

The 128-B-2 waste site was a burn pit historically used for the disposal of combustible and noncombustible wastes, including paint and solvents, office waste, concrete debris, and metallic debris. This site has been remediated by removing approximately 5,627 bank cubic meters of debris, ash, and contaminated soil to the Environmental Restoration Disposal Facility. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River

Siting process for disposal site of low level radiactive waste in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K.

1992-01-01

The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand

Small mammal populations at hazardous waste disposal sites near Houston, Texas, USA

Science.gov (United States)

Robbins, C.S.

1990-01-01

Small mammals were trapped, tagged and recaptured in 0?45 ha plots at six hazardous industrial waste disposal sites to determine if populations, body mass and age structures were different from paired control site plots. Low numbers of six species of small mammals were captured on industrial waste sites or control sites. Only populations of hispid cotton rats at industrial waste sites and control sites were large enough for comparisons. Overall population numbers, age structure, and body mass of adult male and female cotton rats were similar at industrial waste sites and control sites. Populations of small mammals (particularly hispid cotton rats) may not suffice as indicators of environments with hazardous industrial waste contamination.

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

Implementation of Waste Minimization at a complex R ampersand D site

International Nuclear Information System (INIS)

Lang, R.E.; Thuot, J.R.; Devgun, J.S.

1995-01-01

Under the 1994 Waste Minimization/Pollution Prevention Crosscut Plan, the Department of Energy (DOE) has set a goal of 50% reduction in waste at its facilities by the end of 1999. Each DOE site is required to set site-specific goals to reduce generation of all types of waste including hazardous, radioactive, and mixed. To meet these goals, Argonne National Laboratory (ANL), Argonne, IL, has developed and implemented a comprehensive Pollution Prevention/Waste Minimization (PP/WMin) Program. The facilities and activities at the site vary from research into basic sciences and research into nuclear fuel cycle to high energy physics and decontamination and decommissioning projects. As a multidisciplinary R ampersand D facility and a multiactivity site, ANL generates waste streams that are varied, in physical form as well as in chemical constituents. This in turn presents a significant challenge to put a cohesive site-wide PP/WMin Program into action. In this paper, we will describe ANL's key activities and waste streams, the regulatory drivers for waste minimization, and the DOE goals in this area, and we will discuss ANL's strategy for waste minimization and it's implementation across the site

Status of Environmental Management Initiatives to Accelerate the Reduction of Environmental Risks and Challenges Posed by the Legacy of the Cold War

International Nuclear Information System (INIS)

2009-01-01

Fifty years of nuclear weapons production and energy research in the United States during the Cold War generated large amounts of radioactive wastes, spent nuclear fuel (SNF), excess plutonium and uranium, thousands of contaminated facilities, and contaminated soil and groundwater. During most of that half century, the Nation did not have the environmental regulatory structure or nuclear waste cleanup technologies that exist today. The result was a legacy of nuclear waste that was stored and disposed of in ways now considered unacceptable. Cleaning up and ultimately disposing of these wastes is the responsibility of the U.S. Department of Energy (DOE). In 1989, DOE established the Office of Environmental Management (EM) to solve the large scale and technically challenging risks posed by the world's largest nuclear cleanup. This required EM to build a new nuclear cleanup infrastructure, assemble and train a technically specialized workforce, and develop the technologies and tools required to safely decontaminate, disassemble, stabilize, disposition, and remediate unique radiation hazards. The sites where nuclear activities produced legacy waste and contamination include the original Manhattan Project sites--Los Alamos, New Mexico; Hanford, Washington; and Oak Ridge, Tennessee--as well as major Cold War sites, such as Savannah River Site, South Carolina; the Idaho National Laboratory, Idaho; Rocky Flats Plant, Colorado; and Fernald, Ohio. Today EM has responsibility for nuclear cleanup activities at 21 sites covering more than two million acres in 13 states, and employs more than 30,000 Federal and contractor employees, including scientists, engineers and hazardous waste technicians. This cleanup poses unique, technically complex problems, which must be solved under the most hazardous of conditions, and which will require billions of dollars a year for several more decades. The EM program focus during its first 10 years was on managing the most urgent risks and

Status of Environmental Management Initiatives to Accelerate the Reduction of Environmental Risks and Challenges Posed by the Legacy of the Cold War

Energy Technology Data Exchange (ETDEWEB)

None

2009-01-01

Fifty years of nuclear weapons production and energy research in the United States during the Cold War generated large amounts of radioactive wastes, spent nuclear fuel (SNF), excess plutonium and uranium, thousands of contaminated facilities, and contaminated soil and groundwater. During most of that half century, the Nation did not have the environmental regulatory structure or nuclear waste cleanup technologies that exist today. The result was a legacy of nuclear waste that was stored and disposed of in ways now considered unacceptable. Cleaning up and ultimately disposing of these wastes is the responsibility of the U.S. Department of Energy (DOE). In 1989, DOE established the Office of Environmental Management (EM) to solve the large scale and technically challenging risks posed by the world's largest nuclear cleanup. This required EM to build a new nuclear cleanup infrastructure, assemble and train a technically specialized workforce, and develop the technologies and tools required to safely decontaminate, disassemble, stabilize, disposition, and remediate unique radiation hazards. The sites where nuclear activities produced legacy waste and contamination include the original Manhattan Project sites--Los Alamos, New Mexico; Hanford, Washington; and Oak Ridge, Tennessee--as well as major Cold War sites, such as Savannah River Site, South Carolina; the Idaho National Laboratory, Idaho; Rocky Flats Plant, Colorado; and Fernald, Ohio. Today EM has responsibility for nuclear cleanup activities at 21 sites covering more than two million acres in 13 states, and employs more than 30,000 Federal and contractor employees, including scientists, engineers and hazardous waste technicians. This cleanup poses unique, technically complex problems, which must be solved under the most hazardous of conditions, and which will require billions of dollars a year for several more decades. The EM program focus during its first 10 years was on managing the most urgent risks and

Incentives and the siting of radioactive waste facilities

Energy Technology Data Exchange (ETDEWEB)

Carnes, S.A.; Copenhaver, E.D.; Reed, J.H.; Soderstrom, E.J.; Sorensen, J.H.; Peelle, E.; Bjornstad, D.J.

1982-08-01

The importance of social and institutional issues in the siting of nuclear waste facilities has been recognized in recent years. Limited evidence from a survey of rural Wisconsin residents in 1980 indicates that incentives may help achieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward) and the conditions which may be prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives in nuclear waste repository siting are developed. Incentive packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. Without careful attention to prerequisites in the siting process it is not likely that incentives will facilitate the siting process.

Incentives and the siting of radioactive waste facilities

International Nuclear Information System (INIS)

Carnes, S.A.; Copenhaver, E.D.; Reed, J.H.; Soderstrom, E.J.; Sorensen, J.H.; Peelle, E.; Bjornstad, D.J.

1982-08-01

The importance of social and institutional issues in the siting of nuclear waste facilities has been recognized in recent years. Limited evidence from a survey of rural Wisconsin residents in 1980 indicates that incentives may help achieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward) and the conditions which may be prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives in nuclear waste repository siting are developed. Incentive packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. Without careful attention to prerequisites in the siting process it is not likely that incentives will facilitate the siting process

Remaining Sites Verification Package for the 128-B-3 Burn Pit Site, Waste Site Reclassification Form 2006-058

Energy Technology Data Exchange (ETDEWEB)

L. M. Dittmer

2006-11-17

The 128-B-3 waste site is a former burn and disposal site for the 100-B/C Area, located adjacent to the Columbia River. The 128-B-3 waste site has been remediated to meet the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results of sampling at upland areas of the site also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

Public reactions to nuclear waste: Citizens' views of repository siting

International Nuclear Information System (INIS)

Rosa, E.A.

1993-01-01

This book presents revised and updated papers from a panel of social scientists, at the 1989 AAAS meetings, that examined the public's reactions to nuclear waste disposal and the repository siting process. The papers report the results of original empirical research on citizens' views of nuclear waste repository siting. Topics covered include the following: content analysis of public testimony; sources of public concern about nuclear waste disposal in Texas agricultural communities; local attitudes toward high-level waste repository at Hanford; perceived risk and attitudes toward nuclear wastes; attitudes of Nevada urban residents toward a nuclear waste repository; attitudes of rural community residents toward a nuclear waste respository. An introductory chapter provides background and context, and a concluding chapter summarizes the implications of the reports. Two additional chapters cover important features of high-level waste disposal: long term trends in public attitudes toward nuclear energy and nuclear waste policy and assessment of the effects on the Los Vegas convention business if a high-level nuclear waste depository were sited in Nevada

Buying time: Franchising hazardous and nuclear waste cleanup

Energy Technology Data Exchange (ETDEWEB)

Hale, D.R. [Dept. of Energy, Washington, DC (United States)

1997-05-01

This paper describes a private franchise approach to long-term custodial care, monitoring and eventual cleanup of hazardous and nuclear waste sites. The franchise concept could be applied to Superfund sites, decommissioning commercial reactors and safeguarding their wastes and to Department of Energy sites. Privatization would reduce costs by enforcing efficient operations and capital investments during the containment period, by providing incentives for successful innovation and by sustaining containment until the cleanup`s net benefits exceed its costs. The franchise system would also permit local governments and citizens to demand and pay for more risk reduction than provided by the federal government. In principle, they would have the option of taking over site management. The major political drawback of the idea is that it requires society to be explicit about what it is willing to pay for now to protect current and future generations. Hazardous waste sites are enduring legacies of energy development. Abandoned mines, closed refineries, underground storage tanks and nuclear facilities have often become threats to human health and water quality. The policy of the United States government is that such sites should quickly be made nonpolluting and safe for unrestricted use. That is, the policy of the United States is prompt cleanup. Orphaned commercial hazardous waste sites are addressed by the US Environmental Protection Agency`s Superfund program. 17 refs., 2 tabs.

Legacies of the Manhattan Project

Science.gov (United States)

Kevles, Daniel

2017-01-01

The Manhattan Project of World War II mobilized thousands of people, including many of the nation's leading physicists, and extensive material resources to design, develop, and manufacture the world's first nuclear weapons. It also established sprawling new facilities for the production of fissionable fuels - notably at Oak Ridge, Tennessee, and Hanford, Washington. It left a set of powerful legacies in the context of the Cold War - endowing scientists with conscience-taxing responsibilities in the nuclear arms race; promoting enormous patronage of academic research by defense and defense-related federal agencies, notably the Office of Naval Research and the Atomic Energy Commission; and turning its wartime facilities into major national laboratories that advanced the fields of high-energy and nuclear physics and stimulated local industrial economies but that in some cases, notably at Hanford, severely polluted the surrounding environment with radioactive waste and disrupted the livelihoods of native peoples. ``Legacies of the Manhattan Project''

A data base for low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Daum, M.L.; Moskowitz, P.D.

1989-07-01

A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs

TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE

International Nuclear Information System (INIS)

DODD, R.A.

2006-01-01

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the US Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60% of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring the waste to the DST system since 1997 as part of the interim stabilization program. Retrieval of SST saltcake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. This paper presents lessons learned from retrieval of tank waste at the Hanford Site and discusses how this information is used to optimize retrieval system efficiency, improve overall cost effectiveness of retrieval operations, and ensure that HFFACO requirements are met

Legacy sediment storage in New England river valleys: anthropogenic processes in a postglacial landscape

Science.gov (United States)

Snyder, N. P.; Johnson, K. M.; Waltner, M.; Hopkins, A. J.; Dow, S.; Ames, E.; Merritts, D. J.; Walter, R. C.; Rahnis, M. A.

2016-12-01

Walter and Merritts (2008, and subsequent papers) show that legacy sediment associated with deposition in millponds is a common feature in river valleys of the Mid-Atlantic Piedmont region, with 1-5 m of fine sand and silt overlying Holocene soil and Pleistocene periglacial deposits. For this project, we seek to test the hypothesis that these field relationships are seen in New England, a formerly glaciated region with similar history and intensity of forest clearing and milldam construction during the 17-19th centuries. We study three watersheds, using field observations of bank stratigraphy, radiocarbon dating, and mapping of terraces and floodplains using lidar digital elevation models and other GIS datasets. The 68 km2 South River watershed in western Massachusetts exhibits the most extensive evidence for legacy sediment storage. We visited 17 historic dam sites in the watershed and found field evidence for fine sand and silt legacy sediment storage at 14, up to 2.2 m thick. In the 558 km2 Sheepscot River watershed in coastal Maine, we visited 12 historic dam sites, and found likely legacy sediment at six, up to 2.3 m thick. In the 171 km2 upper Charles River watershed in eastern Massachusetts, we investigated 14 dam sites, and found legacy sediment at two, up to 1.8 m thick. Stratigraphically, we identified the base of legacy sediment from a change in grain size to gravel at most sites, or to Pleistocene marine clay at some Sheepscot River sites. In the Sheepscot River, we observed cut timbers underlying historic sediment at several locations, likely associated with sawmill activities. Only at the Charles River were we able to radiocarbon date the underlying gravel (1281-1391 calibrated CE). At no site did we find a buried Holocene soil, in contrast to the field relations commonly observed in the Mid-Atlantic region. This may indicate that the New England sites have eroded to the pre-historic river bed, not floodplain surfaces. We attribute the variation in

The legacy and future of radioactive waste management at the Millenium

International Nuclear Information System (INIS)

Martin, J.E.; Lee, C.

2000-01-01

Wastes containing radioactive materials have been produced ever since ore recovery and processing began; however, such materials did not become of public concern until the large-scale activities involving uranium and thorium ores and nuclear fission during and after World War II. Efforts to provide disposal sites for radioactive wastes, especially those associated with nuclear weapons and nuclear energy, have been largely unsuccessful for the past 40 years or so and are nearing crisis proportions as the new millenium begins - its eventual resolution is believed to require greater reliance on stewardship and a larger governmental presence. (author)

Critical management practices influencing on-site waste minimization in construction projects.

Science.gov (United States)

Ajayi, Saheed O; Oyedele, Lukumon O; Bilal, Muhammad; Akinade, Olugbenga O; Alaka, Hafiz A; Owolabi, Hakeem A

2017-01-01

As a result of increasing recognition of effective site management as the strategic approach for achieving the required performance in construction projects, this study seeks to identify the key site management practices that are requisite for construction waste minimization. A mixed methods approach, involving field study and survey research were used as means of data collection. After confirmation of construct validity and reliability of scale, data analysis was carried out through a combination of Kruskal-Wallis test, descriptive statistics and exploratory factor analysis. The study suggests that site management functions could significantly reduce waste generation through strict adherence to project drawings, and by ensuring fewer or no design changes during construction process. Provision of waste skips for specific materials and maximisation of on-site reuse of materials are also found to be among the key factors for engendering waste minimization. The result of factor analysis suggests four factors underlying on-site waste management practices with 96.093% of total variance. These measures include contractual provisions for waste minimization, waste segregation, maximisation of materials reuse and effective logistic management. Strategies through which each of the underlying measures could be achieved are further discussed in the paper. Findings of this study would assist construction site managers and other site operatives in reducing waste generated by construction activities. Copyright © 2016 Elsevier Ltd. All rights reserved.

Storage of intermediate level waste at UKAEA sites

International Nuclear Information System (INIS)

Goodill, D.R.; Tymons, B.J.

1985-08-01

This report describes the storage of wastes at UKAEA sites and accordingly contributes to the investigations conducted by the Department of the Environment into the Best Practicable Environmental Option (BPEO) for radioactive waste storage and/or disposal. This report on the storage of ILW should be read in conjunction with a similar NII funded CTS study for Licensed Sites in the UK. (author)

Ames Laboratory annual site environmental report, calendar year 1996

International Nuclear Information System (INIS)

1998-04-01

This report summarizes the environmental status of Ames Laboratory for calendar year 1996. It includes descriptions of the Laboratory site, its mission, the status of its compliance with applicable environmental regulations, its planning and activities to maintain compliance, and a comprehensive review of its environmental protection, surveillance and monitoring programs. Ames Laboratory is located on the campus of Iowa State University (ISU) and occupies twelve buildings owned by the Department of Energy (DOE). The Laboratory also leases space in ISU owned buildings. Laboratory activities involve less than ten percent of the total chemical use and approximately one percent of the radioisotope use on the ISU campus. In 1996, the Office of Assurance and Assessment merged with the Environment, Safety and Health Group forming the Environment, Safety, Health and Assurance (ESH and A) office. In 1996, the Laboratory accumulated and disposed of wastes under US Environmental Protection Agency (EPA) issued generator numbers. Ames Laboratory submitted a Proposed Site Treatment Plan to EPA in December 1995. This plan complied with the Federal Facilities Compliance Act (FFCA). It was approved by EPA in January 1996. The consent agreement/consent order was issued in February 1996. Pollution awareness, waste minimization and recycling programs, implemented in 1990 and updated in 1994, continued through 1996. Included in these efforts were a waste white paper and green computer paper recycling program. Ames Laboratory also continued to recycle salvageable metal and used oil, and it recovered freon for recycling. All of the chemical and nearly all of the radiological legacy wastes were properly disposed by the end of 1996. Additional radiological legacy waste will be properly disposed during 1997

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

Dechlorane Plus (DP) in air and plants at an electronic waste (e-waste) site in South China

Energy Technology Data Exchange (ETDEWEB)

Chen Shejun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Tian Mi; Wang Jing; Shi Tian [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Graduate School, Chinese Academy of Sciences, Beijing 100049 (China); Luo Yong [Guangdong Forestry Survey and Planning Institute, Guangzhou 510520 (China); Luo Xiaojun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Mai Bixian, E-mail: nancymai@gig.ac.cn [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

2011-05-15

Air and foliage samples (Eucalyptus spp. and Pinus massoniana Lamb.) were collected from e-waste and reference sites in South China and analyzed for Dechlorane Plus (DP) and two dechlorinated DPs. DP concentrations in the air were 13.1-1794 pg/m{sup 3} for the e-waste site and 0.47-35.7 pg/m{sup 3} for the reference site, suggesting the recycling of e-waste is an important source of DP to the environment. Plant DP, with concentrations of 0.45-51.9 ng/g dry weight at the e-waste site and 0.09-2.46 ng/g at the reference site, exhibited temporal patterns similar to the air DP except for pine needle at the reference site. The air-plant exchange of DP could be described with the two-compartment model. Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. The ratios of anti-Cl{sub 11} DP to anti-DP in the air and plants may indicate the preferential uptake of dechlorinated DP by plant compared with DP. - Highlights: > Dechlorane Plus was widely present in the air and plants in South China. > Temporal patterns of the plant DP could be described with the two-compartment model. > Plant uptake can efficiently reduce air DP concentration at the reference site. > Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. - E-waste recycling in South China results in wide occurrence of DP in the air and plant.

Non-Thermal Treatment of Hanford Site Low-Level Mixed Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

DOE proposes to transport contact-handled LLMW from the Hanford Site to the Allied Technology Group (ATG) Mixed Waste Facility (MWF) in Richland, Washington, for non-thermal treatment and to return the treated waste to the Hanford Site for eventual land disposal. Over a 3-year period the waste would be staged to the ATG MWF, and treated waste would be returned to the Hanford Site. The ATG MWF would be located on an 18 hectare (ha) (45 acre [at]) ATG Site adjacent to ATG's licensed low-level waste processing facility at 2025 Battelle Boulevard. The ATG MWF is located approximately 0.8 kilometers (km) (0.5 miles [mi]) south of Horn Rapids Road and 1.6 km (1 mi) west of Stevens Drive. The property is located within the Horn Rapids triangle in northern Richland (Figure 2.1). The ATG MWF is to be located on the existing ATG Site, near the DOE Hanford Site, in an industrial area in the City of Richland. The effects of siting, construction, and overall operation of the MWF have been evaluated in a separate State Environmental Policy Act (SEPA) EIS (City of Richland 1998). The proposed action includes transporting the LLMW from the Hanford Site to the ATG Facility, non-thermal treatment of the LLMW at the ATG MWF, and transporting the waste from ATG back to the Hanford Site. Impacts fi-om waste treatment operations would be bounded by the ATG SEPA EIS, which included an evaluation of the impacts associated with operating the non-thermal portion of the MWF at maximum design capacity (8,500 metric tons per year) (City of Richland 1998). Up to 50 employees would be required for non-thermal treatment portion of the MWF. This includes 40 employees that would perform waste treatment operations and 10 support staff. Similar numbers were projected for the thermal treatment portion of the MWF (City of Richland 1998).

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

International Nuclear Information System (INIS)

Mohamed, Yasser T.

2013-01-01

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Application of neural networks to waste site screening

International Nuclear Information System (INIS)

Dabiri, A.E.; Garrett, M.; Kraft, T.; Hilton, J.; VanHammersveld, M.

1993-02-01

Waste site screening requires knowledge of the actual concentrations of hazardous materials and rates of flow around and below the site with time. The present approach consists primarily of drilling boreholes near contaminated sites and chemically analyzing the extracted physical samples and processing the data. This is expensive and time consuming. The feasibility of using neural network techniques to reduce the cost of waste site screening was investigated. Two neural network techniques, gradient descent back propagation and fully recurrent back propagation were utilized. The networks were trained with data received from Westinghouse Hanford Corporation. The results indicate that the network trained with the fully recurrent technique shows satisfactory generalization capability. The predicted results are close to the results obtained from a mathematical flow prediction model. It is possible to develop a new tool to predict the waste plume, thus substantially reducing the number of the bore sites and samplings. There are a variety of applications for this technique in environmental site screening and remediation. One of the obvious applications would be for optimum well siting. A neural network trained from the existing sampling data could be utilized to decide where would be the best position for the next bore site. Other applications are discussed in the report

Site-Specific Seismic Site Response Model for the Waste Treatment Plant, Hanford, Washington

Energy Technology Data Exchange (ETDEWEB)

Rohay, Alan C.; Reidel, Steve P.

2005-02-24

This interim report documents the collection of site-specific geologic and geophysical data characterizing the Waste Treatment Plant site and the modeling of the site-specific structure response to earthquake ground motions.

Risk management at hazardous waste sites

International Nuclear Information System (INIS)

Travis, C.C.; Doty, C.B.

1990-01-01

The Superfund Amendments and Reauthorization Act of 1986 (SARA) provided the Environmental Protection Agency (EPA) with additional resources and direction for the identification, evaluation, and remediation of hazardous waste sites in the United States. SARA established more stringent requirements for the Superfund program, both in terms of the pace of the program and the types of remedial alternatives selected. The central requirement is that remedial alternatives be ''protective of public health and the environment'' and ''significantly and permanently'' reduce the toxicity, mobility, or volume of contaminants. The mandate also requires that potential risk be considered in the decision-making process. This document discusses risk management at hazardous waste sites. Topics include selection of sites for placement on the National Priority List, risk assessment and the decision process, risk reduction and remedial alternative selection, and aquifer restoration. 10 refs., 2 figs

Site identification presentation: Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1979-11-01

The final step in the site identification process for the Basalt Waste Isolation Project is described. The candidate sites are identified. The site identification methodology is presented. The general objectives which must be met in selecting the final site are listed. Considerations used in the screening process are also listed. Summary tables of the guidelines used are included

Contamination by trace elements at e-waste recycling sites in Bangalore, India.

Science.gov (United States)

Ha, Nguyen Ngoc; Agusa, Tetsuro; Ramu, Karri; Tu, Nguyen Phuc Cam; Murata, Satoko; Bulbule, Keshav A; Parthasaraty, Peethmbaram; Takahashi, Shin; Subramanian, Annamalai; Tanabe, Shinsuke

2009-06-01

The recycling and disposal of electronic waste (e-waste) in developing countries is causing an increasing concern due to its effects on the environment and associated human health risks. To understand the contamination status, we measured trace elements (TEs) in soil, air dust, and human hair collected from e-waste recycling sites (a recycling facility and backyard recycling units) and the reference sites in Bangalore and Chennai in India. Concentrations of Cu, Zn, Ag, Cd, In, Sn, Sb, Hg, Pb, and Bi were higher in soil from e-waste recycling sites compared to reference sites. For Cu, Sb, Hg, and Pb in some soils from e-waste sites, the levels exceeded screening values proposed by US Environmental Protection Agency (EPA). Concentrations of Cr, Mn, Co, Cu, In, Sn, Sb, Tl, Pb and Bi in air from the e-waste recycling facility were relatively higher than the levels in Chennai city. High levels of Cu, Mo, Ag, Cd, In, Sb, Tl, and Pb were observed in hair of male workers from e-waste recycling sites. Our results suggest that e-waste recycling and its disposal may lead to the environmental and human contamination by some TEs. To our knowledge, this is the first study on TE contamination at e-waste recycling sites in Bangalore, India.

Geohydrologic aspects for siting and design of low-level radioactive-waste disposal

Science.gov (United States)

Bedinger, M.S.

1989-01-01

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action.Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to

Managing wastes from the atomic age and into the future: programs, plans and challenges

International Nuclear Information System (INIS)

Miller, J.M.

2011-01-01

Various types of waste are generated at Atomic Energy of Canada Limited (AECL) nuclear sites from diversified operations, including research reactor operations, radioisotope production, hot cell operations, nuclear fuel fabrication, research and development activities, facility decommissioning, environmental restoration, etc. AECL is responsible for the safe storage and long-term management of waste generated by Chalk River Laboratories (CRL), Whiteshell Laboratories (WL) and the three partially decommissioned prototype reactors, as well as for the radioactive waste received from off-site waste generators on a fee-for-service basis. As the home for the first nuclear reactor in Canada and nuclear research facilities, CRL has been a pioneer in the management of nuclear waste. Since the dawn of the nuclear era in the 1940s, CRL's waste management facilities have evolved from storage in simple sand trenches to below-ground concrete storage, to above-ground facilities offering multiple barriers of containment. To continuously improve the waste management at AECL, a formal Waste Management Program has been introduced. An important component of this Program is a focus on waste reduction and appropriate waste characterization to ensure wastes are being handled, stored and/or disposed in the most cost-effective manner. In 2006, AECL began implementing the Government of Canada-funded Nuclear Legacy Liabilities Program (NLLP) to deal with nuclear legacy liabilities at AECL sites. Approximately 200,000 to 300,000 cubic metres of waste from earlier operations at AECL requires management through the NLLP, with a yearly increase of several thousand cubic metres. Several of the NLLP projects currently underway are focused on improving the robustness of earlier management practices, as older facilities reach the end of their design life. An important element of the NLLP is the development of an Integrated Waste Plan to ensure optimal selection of enabling facilities and their

Early Regulatory Engagement for Successful Site Remediation: the UK Experience - 13173

International Nuclear Information System (INIS)

Maitland, R.P.; Senior, D.

2013-01-01

The Office for Nuclear Regulation (ONR) is an independent safety, security and transport regulator of the UK nuclear industry. ONR regulates all civil nuclear reactor power stations, fuel manufacture, enrichment, spent fuel reprocessing, most defence sites and installations that store and process legacy spent fuel and radioactive waste. The responsibility for funding and strategic direction of decommissioning and radioactive waste management of state owned legacy sites has rested solely with the Nuclear Decommissioning Authority (NDA) since 2005. A key component of NDA's mandate was to encourage new strategic approaches and innovation to dealing with the UK's waste legacy and which deliver value-for-money to the UK taxpayer. ONR, as an agency of the Health and Safety Executive, is entirely independent of NDA and regulates all prescribed activities on NDA's sites. NDA's competition of site management and closure contracts has attracted significant international interest and the formation of consortia comprised of major British, US, French and Swedish organizations bidding for those contracts. The prominence of US organizations in each of those consortia reflects the scale and breadth of existing waste management and D and D projects in the US. This paper will articulate, in broad terms, the challenges faced by international organizations seeking to employ 'off-the-shelf' technology and D and D techniques, successfully employed elsewhere, into the UK regulatory context. The predominantly 'goal-setting' regulatory framework in the UK does not generally prescribe a minimum standard to which a licensee must adhere. The legal onus on licensees in the UK is to demonstrate, whatever technology is selected, that in its applications, risks are reduced 'So Far As Is Reasonably Practicable' or 'SFAIRP'. By the nature of its role, ONR adopts a conservative approach to regulation; however ONR also recognises that in the decommissioning (and ultimately the site closure) domain

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility

The role of geology in the evaluation of waste disposal sites

International Nuclear Information System (INIS)

Ogunsanwo, O.; Mands, E.

1999-01-01

The construction of waste disposal sites demonstrates the awareness of the need to protect the environment against pollution. The site are constructed on foundations of soils and rocks. Photo geological studies, geophysical investigations and geological field mapping are indispensable in the selection of suitable sites. Most of the construction materials (in the case of landfills) are of geologic origin and their suitability can only be ascertained after some geological assessments. Furthermore, the hydrogeological conditions within the adjoining terrains and the flow of leachates from and within the wastes must be monitored so as to prevent pollution (radiation, in the case of radioactive wastes, can be monitored with the aid of geochemistry). Several models/systems are available for the hydrogeological/geochemical evaluation of waste disposal sites. The selection of the site and the construction materials as well as the hydrogeological/ /geochemical studies are very critical as the performance of the disposal site depends solely on these aspects. These aspects are basically within the realms of geology. It is thus obvious that geology plays a leading role in the evaluation of waste disposal sites right from the site selection stage until the site is done with

Low-level radioactive waste (LLW) management at the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Becker, B.D.; Gertz, C.P.; Clayton, W.A.; Crowe, B.M.

1998-01-01

In 1978, the Department of Energy, Nevada Operations Office (DOE/NV), established a managed LLW disposal project at the Nevada Test Site (NTS). Two, sites which were already accepting limited amounts of on-site generated waste for disposal and off-site generated Transuranic Waste for interim storage, were selected to house the disposal facilities. In those early days, these sites, located about 15 miles apart, afforded the DOE/NV the opportunity to use at least two technologies to manage its waste cost effectively. The Area 5 Radioactive Waste Management Site (RWMS) uses engineered shallow-land burial cells to dispose packaged waste while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. The paper describes the technical attributes of both Area 5 and Area 3 facilities, the acceptance process, the disposal processes, and present and future capacities of both sites

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations

International Nuclear Information System (INIS)

Carilli, J.T.; Krenzien, S.K.; Geisinger, R.G.; Gordon, S.J.; Quinn, B.

2009-01-01

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams

Using Advanced Mixed Waste Treatment Technology To Meet Accelerated Cleanup Program Milestones

International Nuclear Information System (INIS)

Larsen, P.J.; Garcia, J.; Estes, C.H.; Palmer, C.R.; Meyers, G.S.

2006-01-01

Some DOE Complex facilities are entering the late stages of facility closure. As waste management operations are completed at these sites, remaining inventories of legacy mixed wastes must be finally disposed. These wastes have unique physical, chemical and radiological properties that have made their management troublesome, and hence why they have remained on site until this late stage of closure. Some of these wastes have had no approved or practical treatment alternative until just recently. Results are provided from using advanced mixed waste treatment technology to perform two treatment campaigns on these legacy wastes. Combinations of macro-encapsulation, vacuum thermal desorption (VTD), and chemical stabilization, with off-site incineration of the organic condensate, provided a complete solution to the problem wastes. One program included approximately 1,900 drums of material from the Fernald Environmental Management Project. Another included approximately 1,200 drums of material from the Accelerated Cleanup Program at the Oak Ridge Reservation. Both of these campaigns were conducted under tight time schedules and demanding specifications, and were performed in a matter of only a few months each. Coordinated rapid waste shipment, flexible permitting and waste acceptance criteria, adequate waste receiving and storage capacity, versatile feed preparation and sorting capability, robust treatment technology with a broad feed specification, and highly reliable operations were all valuable components to successful accomplishment of the project requirements. Descriptions of the waste are provided; material that was difficult or impossible to treat in earlier phases of site closure. These problem wastes included: 1) the combination of special nuclear materials mixed with high organic chemical content and/or mercury, 2) high toxic metal content mixed with high organic chemical content, and 3) very high organic chemical content mixed with debris, solids and sludge

Successful characterization of radioactive waste at the Savannah River Site

International Nuclear Information System (INIS)

Hughes, M.B.; Miles, G.M.

1995-01-01

Characterization of the low-level radioactive waste generated by forty five independent operating facilities at The Savannah River Site (SRS) experienced a slow start. However, the site effectively accelerated waste characterization based on findings of an independent assessment that recommended several changes to the existing process. The new approach included the development of a generic waste characterization protocol and methodology and the formulation of a technical board to approve waste characterization. As a result, consistent, detailed characterization of waste streams from SRS facilities was achieved in six months

Stakeholder participation for the legacy ponds and legacy silos (LP and LS) facility at Sellafield, Cumbria. UK: the nature and effectiveness of the dialogue - 16030

International Nuclear Information System (INIS)

Whitton, John

2009-01-01

The Legacy Ponds and Silos (LP and S) facilities are part of the UK nuclear legacy located at the Sellafield Site, Cumbria. There are four individual facilities containing nuclear wastes that have accumulated over a period of approximately 50 years. Waste retrieval and conditioning, in preparation for decommissioning, is currently being carried out by the site operator. LP and S have recently proposed a re-engagement with stakeholders following the initial engagement in December 2005. This paper reviews this earlier engagement in terms of the nature of dialogue that was carried out when compared against definitions of deliberation provided in the literature. The aim of this paper is to provide those planning future engagement with a better understanding of how the nature of dialogue can vary and uses participation and deliberation as indicators of effective engagement. A concern of those working towards a programme of effective stakeholder participation in 2005 was how to ensure genuine dialogue and stakeholder representation in such a strictly controlled and regulated environment with a technical complexity that challenges technical specialist and lay person alike. LP and S recognised that effective dialogue with stakeholders on the available technical options and their associated societal impacts would form a significant part of this process if options were to prove resilient. However, the challenge presented to LP and S was how to engage stakeholders on a variety of projects, whilst ensuring the output could be used by the projects as part of their technical decision making. Initial contact was made with stakeholders in December 2005, as part of a 'Baseline' Best Practicable Environmental Option (BPEO) study. A BPEO study leads to decisions on waste management based on an integrated assessment of alternative options, on the basis of factors such as the occupational and environmental risks, the environmental impacts, costs and social implications of the options

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

Energy Technology Data Exchange (ETDEWEB)

Wickline, Alfred

2005-12-01

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

Selection and cultivation of final vegetative cover for closed waste sites at the Savannah River Site, SC

International Nuclear Information System (INIS)

Cook, J.R.; Salvo, S.K.

1992-01-01

Low-level, hazardous, and mixed waste disposal sites normally require some form of plant material to prevent erosion of the final closure cap. Waste disposal sites are closed and capped in a complex scientific manner to minimize water infiltration and percolation into and through the waste material. Turf type grasses are currently being used as a vegetative cover for most sites. Consequently, the sites require periodic mowing and other expensive annual maintenance practices. The purpose of this five year study was to evaluate alternative plant material for use on wastes sites that is quickly and easily established and economically maintained, retards water infiltration, provides maximum year-round evapotranspiration, is ecologically acceptable and does not harm the closure cap. The results of the study are described in this report and suggest that two species of bamboo (Phyllostachys bissetii and P. rubromarainata) can be utilized to provide long lived, low maintenance, climax vegetation for the waste sites. These large species of bamboo will also reduce the probability of intrusion by humans, animals and deeply rooted plant species

Mixed waste management at the Hanford Site

International Nuclear Information System (INIS)

Roberts, R.J.; Jasen, W.G.

1991-01-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, special projects have been initiated for the management of RMW. This paper addresses the management of solid RMW. The management of bulk liquid RMW will not be described. 7 refs., 4 figs

Geographic factors related to site suitability of low-level waste disposal

Science.gov (United States)

Zittel, H. E.

Factors related to the site suitability of low level waste disposal sites are discussed including those which might be considered environmental and those dealing with site criteria. Possible population criteria, alternative site selection, transportation criteria, and community involvement are considered. All these factors are based on the premise that the technology exists to carry out low level waste disposal in a manner such that public health and safety can be insured. It is concluded that problems encountered in siting low level waste facilities are largely societal and political in nature.

Nuclear waste: Status of DOE's nuclear waste site characterization activities

International Nuclear Information System (INIS)

1987-01-01

Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

Nuclear Waste Management R and D - A Perspective from the UK

International Nuclear Information System (INIS)

Ian Hudson; Graham Fairhall

2006-01-01

Full text of publication follows: A radical change to the management of the nuclear legacy in the UK has been implemented following the publication of the 2002 'Managing the Nuclear Legacy: A strategy for Action'. The white paper noted that decommissioning the UK's civil public sector nuclear legacy has not always received the attention it deserves. In 2004 the Nuclear Decommissioning Authority (NDA) was established, charged with cleaning up the UK's civil public sector nuclear legacy safely, securely, cost effectively and in ways that safeguard the environment for this and future generations. The 'Managing the Nuclear Legacy' White paper and the Energy Act 2004 commits the NDA to play a role in R and D related to cleanup and decommissioning programmes. Specifically the Act defines these functions: carrying out research into matters relating to the decommissioning of nuclear installations, the cleaning- up of nuclear sites and other activities in relation to which it has functions; promoting the carrying out of research by others into these matters; distributing information about those matters; The NDA's intends to fund Research and Development (R and D) activities to support clean up and decommissioning at our sites either via direct contracts with research organisations or through the Site License Companies (SLC) in relation to their programmes of work. The NDA funded programme forms the majority of the UK civil waste management R and D programme. The NDA has entered into contracts with Nexia Solutions for R and D support and NiRex to support work on waste packaging and longer term waste management arrangements. The NDA plan to spend in the region of pounds 20 M on directly funded R and D and once SLC R and D activities are included the total is in the region of pounds 130 M i.e approximately 6% of the NDA budget. A key driver for the NDA is the support of innovative solutions to the management of current liabilities at the sites. Whilst the industry is mature

Waste treatment at the La Hague and Marcoule sites

International Nuclear Information System (INIS)

1995-04-01

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema's plants

Waste treatment at the La Hague and Marcoule sites

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

1993 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

International Nuclear Information System (INIS)

Kirkendall, J.R.; Engel, J.A.

1994-01-01

More important than waste generation numbers, the pollution prevention and waste minimization successes achieved at Hanford in 1993 have reduced waste and improved operations at the Site. Just a few of these projects are: A small research nuclear reactor, unused and destined for disposal as low level radioactive waste, was provided to a Texas University for their nuclear research program, avoiding 25 cubic meters of waste and saving $116,000. By changing the slope on a asphalt lot in front of a waste storage pad, run-off rainwater was prevented from becoming mixed low level waste water, preventing 40 cubic meters of waste and saving $750,000. Through more efficient electrostatic paint spraying equipment and a solvent recovery system, a paint shop reduced hazardous waste by 3,500 kilograms, saving $90,800. During the demolition of a large decommissioned building, more than 90% of the building's material was recycled by crushing the concrete for use on-Site and selling the steel to an off-Site recycler, avoiding a total of 12,600 metric tons of waste and saving $450,000. Additionally, several site-wide programs have avoided large quantities of waste, including the following: Through expansion of the paper and office waste recycling program which includes paper, cardboard, newspaper, and phone books, 516 metric tons of sanitary waste was reduced, saving $68,000. With the continued success of the excess chemicals program, which finds on-Site and off-Site customers for excess chemical materials, hazardous waste was reduced by 765,000 liters of liquid chemicals and 50 metric tons of solid chemicals, saving over $700,000 in disposal costs

Remaining Sites Verification Package for the 116-C-3, 105-C Chemical Waste Tanks. Attachment to Waste Site Reclassification Form 2008-002

International Nuclear Information System (INIS)

Dittmer, L.M.

2008-01-01

The 116-C-3 waste site consisted of two underground storage tanks designed to receive mixed waste from the 105-C Reactor Metals Examination Facility chemical dejacketing process. Confirmatory evaluation and subsequent characterization of the site determined that the southern tank contained approximately 34,000 L (9,000 gal) of dejacketing wastes, and that the northern tank was unused. In accordance with this evaluation, the verification sampling and modeling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrate that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also show that residual contaminant concentrations are protective of groundwater and the Columbia River

A Bayesian sampling strategy for hazardous waste site characterization

International Nuclear Information System (INIS)

Skalski, J.R.

1987-12-01

Prior knowledge based on historical records or physical evidence often suggests the existence of a hazardous waste site. Initial surveys may provide additional or even conflicting evidence of site contamination. This article presents a Bayes sampling strategy that allocates sampling at a site using this prior knowledge. This sampling strategy minimizes the environmental risks of missing chemical or radionuclide hot spots at a waste site. The environmental risk is shown to be proportional to the size of the undetected hot spot or inversely proportional to the probability of hot spot detection. 12 refs., 2 figs

Modified TCLP test for evaluating the leachability of site-specific wastes

International Nuclear Information System (INIS)

Pier, J.

1996-01-01

The Weldon Spring Site Remedial Action Project (WSSRAP) has developed a site-specific test to assess the leachability of wastes that will be placed in its on-site disposal cell. This test is modelled after the TCLP, but examines an expanded list of parameters and uses an extraction solution that is representative of conditions that are expected to exist in the disposal facility. Following the same logic that guided development of TCLP protocols, the WSSRAP developed concentration guidelines for non-TCLP parameters that were contaminants of concern in its wastes. Response actions, specific to the WSSRAP cell and wastes, were also developed to address constituents that failed to meet these guides. From 1955 to 1966, the US Atomic Energy Commission operated a uranium feed materials plant on this site. Nitroaromatic, and later, radiological wastes were disposed of in the quarry from 1945 until 1970. This paper describes testing to determine whether contaminant concentrations in leachates derived from the major waste-types that will be placed in its on-site disposal cell conform with the Department of Energy's (DOE) as low as reasonably achievable (ALARA) policy. Although the WSSRAP will continue to use the TCLP test to determine if any waste is classified RCRA-hazardous, the site-specific test described in this paper will be used to further assess whether leachate from any waste-type has the potential to adversely impact groundwater

Characterization of radionuclude behavior in low-level waste sites

International Nuclear Information System (INIS)

Toste, A.P.; Kirby, L.J.; Robertson, D.E.; Abel, K.H.; Perkins, R.W.

1982-10-01

Our laboratory is investigating the subsurface migration of radionuclides in groundwater at the Maxey Flats, Kentucky, shallow land-burial site and at a low-level aqueous waste disposal facility. At Maxey Flats, radionuclide and tracer data indicate groundwater communication between a waste trench and an adjacent experimental study area. Areal distributions of radionuclides in surface soil confirm that contamination at Maxey Flats has been largely contained on site. Of the radionuclides detected in the surface soil, only 3 H and 60 Co concentrations appear to be derived from waste. Plutonium exists in the anoxic subsurface waters at Maxey Flats as a reduced, anionic complex; some of the plutonium appears to be complexed with EDTA, whereas organic acids seem to be associated with 137 Cs and 90 Sr. At the aqueous waste disposal site, 3 H and mainly anionic species of certain radionuclides, including 60 Co, 106 Ru, 99 Tc, 131 I, and traces of 238 239 240 Pu, appear to migrate from a trench through soil adjacent to the trench. Radionuclides in the particulate and cationic forms appear to be efficiently retained by the soil. In general, observations indicate that the physicochemical form of the radionuclides mediates their subsurface migration in groundwater at both waste disposal sites

Application of neural networks to waste site screening

Energy Technology Data Exchange (ETDEWEB)

Dabiri, A.E.; Kraft, T.; Hilton, J.M. [Science Applications International Corp., San Diego, CA (United States)

1993-03-01

Waste site screening requires knowledge of the actual concentrations of hazardous materials and rates of flow around and below the site with time. The present approach to site screening consists primarily of drilling, boreholes near contaminated site and chemically analyzing the extracted physical samples and processing the data. In addition, hydraulic and geochemical soil properties are obtained so that numerical simulation models can be used to interpret and extrapolate the field data. The objective of this work is to investigate the feasibility of using neural network techniques to reduce the cost of waste site screening. A successful technique may lead to an ability to reduce the number of boreholes and the number of samples analyzed from each borehole to properly screen the waste site. The analytic tool development described here is inexpensive because it makes use of neural network techniques that can interpolate rapidly and which can learn how to analyze data rather than having to be explicitly programmed. In the following sections, data collection and data analyses will be described, followed by a section on different neural network techniques used. The results will be presented and compared with mathematical model. Finally, the last section will summarize the research work performed and make several recommendations for future work.

Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

International Nuclear Information System (INIS)

NSTec Environmental Management

2008-01-01

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells

Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2008-09-01

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

The Successful Utilization Of Commercial Treatment Capabilities To Disposition Hanford's No-Path-Forward Suspect Transuranic Wastes

International Nuclear Information System (INIS)

Blackford, L.T.; Catlow, R.L.; West, L.D.; Collins, M.S.; Romine, L.D.; Moak, D.J.

2012-01-01

The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W and FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 cubic meters (m 3 ) of legacy waste was defined as ''no-path-forward waste.'' A significant portion of this waste (7,650 m 3 ) comprised wastes with up to 50 grams of special nuclear materials (SNM) in oversized packages recovered during retrieval operations and large glove boxes removed from Hanford's Plutonium Finishing Plant (PFP). Through a collaborative effort between the DOE, CHPRC, and Perma-Fix Environmental Services, Inc. (PESI), pathways for these problematic wastes were developed and are currently being implemented.

Application for Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site - U10c Disposal Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-08-05

The NTS is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. NNSA/NSO is the federal lands management authority for the NTS and NSTec is the Management & Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The U10C Disposal Site is located in the northwest corner of Area 9 at the NTS (Figure 1) and is located in a subsidence crater created by two underground nuclear events, one in October 1962 and another in April 1964. The disposal site opened in 1971 for the disposal of rubbish, refuse, pathological waste, asbestos-containing material, and industrial solid waste. A Notice of Intent form to operate the disposal site as a Class II site was submitted to the state of Nevada on January 26, 1994, and was acknowledged in a letter to the DOE on February 8, 1994. It operated as a state of Nevada Class II Solid Waste Disposal Site (SWDS) until it closed on October 5, 1995, for retrofit as a Class III SWDS. The retrofit consisted of the installation of a minimum four-foot compacted soil layer to segregate the different waste types and function as a liner to inhibit leachate and water flow into the lower waste zone. Five neutron monitoring tubes were installed in this layer to monitor possible leachate production and water activity. Upon acceptance of the installed barrier and approval of an Operating Plan by NDEP/BFF, the site reopened in January 1996 as a Class III SWDS for the disposal of industrial solid waste and other inert waste.

Characteristics of transuranic waste at Department of Energy sites

International Nuclear Information System (INIS)

Jensen, R.T.; Wilkinson, F.J. III.

1983-05-01

This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981

GEOTECHNICAL DESIGN OF SOLID WASTE LANDFILL SITES

Directory of Open Access Journals (Sweden)

Suat AKBULUT

2003-02-01

Full Text Available Solid waste landfills are important engineering structures for protection of wastes, decrease of environmental pollution, and especially prevention of soil and water pollution. Solid wastes should conveniently be maintained in landfill areas to control environmental pollution caused by waste disposals. Until the middle of this century clay liners were used for maintenance of waste disposal, but it was observed that these liner systems were insufficient. Today thinner and less permeable liner systems are constructed by using synthetic materials. In this study, by evaluating the waste landfills, site assessment of landfills and construction of natural and synthetic liner systems were summarized respectively, and especially the design properties of these systems were examined intensively. Also, leachate collection and removal facilities, landfill gas collection unites, and final cover unites were evaluated in a detailed way.

Nevada test site waste acceptance criteria

International Nuclear Information System (INIS)

1996-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

Nevada test site waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

Issues Associated with Tritium Legacy Materials

International Nuclear Information System (INIS)

Mills, Michael

2008-01-01

term study; - Molecular sieves containing adsorbed tritiated water; - Containers used to store 3 He (containing trace quantities of tritium); - Miscellaneous containers housing 'as yet' un-identified materials. AWE has developed a plan to manage, process and dispose of legacy tritium materials applying treatment methodologies that protect the environment and minimise waste arisings. This has been accomplished through the implementation of the well established BPM process

Expected brine movement at potential nuclear waste repository salt sites

International Nuclear Information System (INIS)

McCauley, V.S.; Raines, G.E.

1987-08-01

The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m 3 brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs

Waste classification and methods applied to specific disposal sites

International Nuclear Information System (INIS)

Rogers, V.C.

1979-01-01

An adequate definition of the classes of radioactive wastes is necessary to regulating the disposal of radioactive wastes. A classification system is proposed in which wastes are classified according to characteristics relating to their disposal. Several specific sites are analyzed with the methodology in order to gain insights into the classification of radioactive wastes. Also presented is the analysis of ocean dumping as it applies to waste classification. 5 refs

Environmental analysis of closure options for waste sites at the Savannah River Plant

International Nuclear Information System (INIS)

Gordon, D.E.; King, C.M.; Looney, B.B.; Stephenson, D.E.; Johnson, W.F.

1987-01-01

Previously acceptable waste management practices (e.g., the use of unlined seepage basins) for discarding of wastes from nuclear materials production has resulted in occasional cases of groundwater contamination beneath some disposal sites, mainly in water-table aquifers. Groundwater contaminants include volatile organic compounds, heavy metals, radionuclides, and other chemicals. The closure of active and inactive waste sites that have received hazardous and/or low-level radioactive materials at the Savannah River Plant (SRP) is planned as part of an overall program to protect groundwater quality. DOE developed and submitted to Congress a groundwater protection plan for SRP. This initial plan and subsequent revisions provide the basis for closure of SRP waste sites to comply with applicable groundwater protection requirements. An environmental analysis of the closure options for the criteria waste sites that have received hazardous and/or low-level radioactive wastes was conducted to provide technical support. The several parts of this environmental analysis include description of geohydrologic conditions; determination of waste inventories; definition of closure options; modeling of environmental pathways; assessment of risk; and analysis of project costs. Each of these components of the overall analysis is described in turn in the following paragraphs. Production operations at SRP have generated a variety of solid, hazardous, and low-level radioactive waste materials. Several locations onplant have been used as waste disposal sites for solid and liquid wastes. Seventy-six individual waste sites at 45 distinct geographical locations on SRP have received hazardous, low-level radioactive, or mixed wastes. These waste sites can be categorized into 26 groupings according to the function of the waste disposed. 15 refs., 6 figs., 5 tabs

Site study plan for utilities and solid waste, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

This site plan describes utilities and solid waste studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. After utilities and solid waste information needs derived from Federal, State, and local statutes and regulations and the project specifications are briefly described, the site study plan describes the study design and rationale, the field data collection procedures and equipment, and data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs to characterize electrical power, natural gas, communication, water, wastewater sludge, nonradiological solid waste, nonradiological hazardous waste, and low-level radiological waste. These programs include details for the collection of project needs, identification of utilities and solid waste disposal contractor capabilities, and verification of the obtained data. Utilities and solid waste field activities will begin approximately at the time of site access. Utilities and solid waste characterization will be completed within the first year of activity. 29 refs., 6 figs., 2 tabs

Calcination/dissolution testing for Hanford Site tank wastes

International Nuclear Information System (INIS)

Colby, S.A.; Delegard, C.H.; McLaughlin, D.F.; Danielson, M.J.

1994-07-01

Thermal treatment by calcination offers several benefits for the treatment of Hanford Site tank wastes, including the destruction of organics and ferrocyanides and an hydroxide fusion that permits the bulk of the mostly soluble nonradioactive constituents to be easily separated from the insoluble transuranic residue. Critical design parameters were tested, including: (1) calciner equipment design, (2) hydroxide fusion chemistry, and (3) equipment corrosion. A 2 gal/minute pilot plant processed a simulated Tank 101-SY waste and produced a free flowing 700 C molten calcine with an average calciner retention time of 20 minutes and >95% organic, nitrate, and nitrite destruction. Laboratory experiments using actual radioactive tank waste and the simulated waste pilot experiments indicate that 98 wt% of the calcine produced is soluble in water, leaving an insoluble transuranic fraction. All of the Hanford Site tank wastes can benefit from calcination/dissolution processing, contingent upon blending various tank waste types to ensure a target of 70 wt% sodium hydroxide/nitrate/nitrite fluxing agent. Finally, corrosion testing indicates that a jacketed nickel liner cooled to below 400 C would corrode <2 mil/year (0.05 mm/year) from molten calcine attack

Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1987-10-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

Geographic factors related to site suitability of low-level waste disposal

International Nuclear Information System (INIS)

Zittel, H.E.

1981-01-01

A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

Savannah River Site`s Site Specific Plan. Environmental restoration and waste management, fiscal year 1992

Energy Technology Data Exchange (ETDEWEB)

1991-08-01

This Site Specific Plan (SSP) has been prepared by the Savannah River Site (SRS) in order to show the Environmental Restoration and Waste Management activities that were identified during the preparation of the Department of Energy-Headquarters (DOE-HQ) Environmental Restoration and Waste Management Five-Year Plan (FYP) for FY 1992--1996. The SSP has been prepared in accordance with guidance received from DOE-HQ. DOE-SR is accountable to DOE-HQ for the implementation of this plan. The purpose of the SSP is to develop a baseline for policy, budget, and schedules for the DOE Environmental Restoration and Waste Management activities. The plan explains accomplishments since the Fiscal Year (FY) 1990 plan, demonstrates how present and future activities are prioritized, identifies currently funded activities and activities that are planned to be funded in the upcoming fiscal year, and describes future activities that SRS is considering.

The Java Legacy Interface

DEFF Research Database (Denmark)

Korsholm, Stephan

2007-01-01

The Java Legacy Interface is designed to use Java for encapsulating native legacy code on small embedded platforms. We discuss why existing technologies for encapsulating legacy code (JNI) is not sufficient for an important range of small embedded platforms, and we show how the Java Legacy...... Interface offers this previously missing functionality. We describe an implementation of the Java Legacy Interface for a particular virtual machine, and how we have used this virtual machine to integrate Java with an existing, commercial, soft real-time, C/C++ legacy platform....

Study on detecting leachate leakage of municipal solid waste landfill site.

Science.gov (United States)

Liu, Jiangang; Cao, Xianxian; Ai, Yingbo; Zhou, Dongdong; Han, Qiting

2015-06-01

The article studies the detection of the leakage passage of leachate in a waste landfill dam. The leachate of waste landfill has its own features, like high conductivity, high chroma and an increasing temperature, also, the horizontal flow velocity of groundwater on the leakage site increases. This article proposes a comprehensive tracing method to identify the leakage site of an impermeable membrane by using these features. This method has been applied to determine two leakage sites of the Yahu municipal solid waste landfill site in Pingshan District, Shenzhen, China, which shows that there are two leachate leakage passages in the waste landfill dam A between NZK-2 and NZK-3, and between NZK-6 and NZK-7. © The Author(s) 2015.

Waste certification review program at the Savannah River Site

International Nuclear Information System (INIS)

Faulk, G.W.; Kinney, J.C.; Knapp, D.C.; Burdette, T.E.

1996-01-01

After approving the waste certification programs for 45 generators of low-level radioactive and mixed waste, Westinghouse Savannah River Company (WSRC) moved forward to implement a performance-based approach for assuring that approved waste generators maintain their waste certification programs. WSRC implemented the Waste Certification Review Program, which is comprised of two sitewide programs, waste generator self-assessments and Facility Evaluation Board reviews, integrated with the WSRC Solid Waste Management Department Waste Verification Program Evaluations. The waste generator self-assessments ensure compliance with waste certification requirements, and Facility Evaluation Board reviews provide independent oversight of generators' waste certification programs. Waste verification evaluations by the TSD facilities serve as the foundation of the program by confirming that waste contents and generator performance continue to meet waste acceptance criteria (WSRC 1994) prior to shipment to treatment, storage, and disposal facilities. Construction of the Savannah River Site (SRS) was started by the US Government in 1950. The site covers approximately 300 square miles located along the Savannah River near Aiken, South Carolina. It is operated by the US Department of Energy (DOE). Operations are conducted by managing and operating contractors, including the Westinghouse Savannah River Company (WSRC). Historically, the primary purpose of the SRS was to produce special nuclear materials, primarily plutonium and tritium. In general, low-level radioactive and mixed waste is generated through activities in operations. Presently, 47 SRS facilities generate low-level radioactive and mixed waste. The policies, guidelines, and requirements for managing these wastes are determined by DOE and are reflected in DOE Order 5820.2A (US DOE 1988)

MATERNAL PERCEPTIONS OF PARENTING FOLLOWING AN EVIDENCE-BASED PARENTING PROGRAM: A QUALITATIVE STUDY OF LEGACY FOR CHILDRENTM.

Science.gov (United States)

Hartwig, Sophie A; Robinson, Lara R; Comeau, Dawn L; Claussen, Angelika H; Perou, Ruth

2017-07-01

This article presents the findings of a qualitative study of maternal perceptions of parenting following participation in Legacy for Children TM (Legacy), an evidence-based parenting program for low-income mothers of young children and infants. To further examine previous findings and better understand participant experiences, we analyzed semistructured focus-group discussions with predominantly Hispanic and Black, non-Hispanic Legacy mothers at two sites (n = 166) using thematic analysis and grounded theory techniques. The qualitative study presented here investigated how mothers view their parenting following participation in Legacy, allowing participants to describe their experience with the program in their own words, thus capturing an "insider" perspective. Mothers at both sites communicated knowledge and use of positive parenting practices targeted by the goals of Legacy; some site-specific differences emerged related to these parenting practices. These findings align with the interpretation of quantitative results from the randomized controlled trials and further demonstrate the significance of the Legacy program in promoting positive parenting for mothers living in poverty. This study emphasizes the importance of understanding real-world context regarding program efficacy and the benefit of using qualitative research to understand participant experiences. © 2017 Michigan Association for Infant Mental Health.

Los Alamos Plutonium Facility newly generated TRU waste certification

International Nuclear Information System (INIS)

Gruetzmacher, K.; Montoya, A.; Sinkule, B.; Maez, M.

1997-01-01

This paper presents an overview of the activities being planned and implemented to certify newly generated contact handled transuranic (TRU) waste produced by Los Alamos National Laboratory's (LANL's) Plutonium Facility. Certifying waste at the point of generation is the most important cost and labor saving step in the WIPP certification process. The pedigree of a waste item is best known by the originator of the waste and frees a site from expensive characterization activities such as those associated with legacy waste. Through a cooperative agreement with LANLs Waste Management Facility and under the umbrella of LANLs WIPP-related certification and quality assurance documents, the Plutonium Facility will be certifying its own newly generated waste. Some of the challenges faced by the Plutonium Facility in preparing to certify TRU waste include the modification and addition of procedures to meet WIPP requirements, standardizing packaging for TRU waste, collecting processing documentation from operations which produce TRU waste, and developing ways to modify waste streams which are not certifiable in their present form

In situ vitrification of a mixed radioactive and hazardous waste site

International Nuclear Information System (INIS)

Campbell, B.E.; Koegler, S.S.

1990-11-01

A large-scale test of the in situ vitrification (ISV) process was performed on a mixed radioactive and hazardous-chemical contaminated waste site on the Hanford Site in southeastern Washington State. A mixed-waste site was selected for this large-scale test to demonstrate the applicability of ISV to mixed wastes common to many US Department of Energy (DOE) sites. In situ vitrification is a thermal process that converts contaminated soil into a durable, leach-resistant product. Electrodes are inserted into the ground. The goals of the test are to demonstrate at least 99% retention of fission products and hazardous metals in the ISV glass during the test; demonstrate the ability of the ISV off-gas treatment system to process a waste site containing significant quantities of combustible material and demonstrate the ability of ISV to vitrify the site to a depth of 20 ft or greater. The test was completed in April 1990. 5 figs

Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

International Nuclear Information System (INIS)

2009-01-01

Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

Haiti: Feasibility of Waste-to-Energy Options at the Trutier Waste Site

Energy Technology Data Exchange (ETDEWEB)

Conrad, M. D.; Hunsberger, R.; Ness, J. E.; Harris, T.; Raibley, T.; Ursillo, P.

2014-08-01

This report provides further analysis of the feasibility of a waste-to-energy (WTE) facility in the area near Port-au-Prince, Haiti. NREL's previous analysis and reports identified anaerobic digestion (AD) as the optimal WTE technology at the facility. Building on the prior analyses, this report evaluates the conceptual financial and technical viability of implementing a combined waste management and electrical power production strategy by constructing a WTE facility at the existing Trutier waste site north of Port-au-Prince.

Hanford Site waste minimization and pollution prevention awareness program plan

International Nuclear Information System (INIS)

1994-05-01

The Hanford Site WMin/P2 program is an organized, comprehensive, and continual effort to systematically reduce the quantity and toxicity of hazardous, radioactive, mixed, and sanitary wastes; conserve resources; and prevent or minimize pollutant releases to all environmental media from all Site activities. The Hanford Site WMin/P2 program plan reflects national and DOE waste minimization and pollution prevention goals and policies, and represents an ongoing effort to make WMin/P2 part of the Site operating philosophy. In accordance with these policies, a hierarchical approach to environmental management has been adopted and is applied to all types of polluting and waste generating activities. Pollution prevention and waste minimization through source reduction are first priority in the Hanford WMin/P2 program, followed by environmentally safe recycling. Treatment to reduce the quantity, toxicity, and/or mobility will be considered only when prevention or recycling are not possible or practical. Environmentally safe disposal is the last option

Citizen participation in nuclear waste repository siting

International Nuclear Information System (INIS)

Howell, R.E.; Olsen, D.

1982-12-01

The following study presents a proposed strategy for citizen participation during the planning stages of nuclear waste repository siting. It discusses the issue from the general perspective of citizen participation in controversial issues and in community development. Second, rural institutions and attitudes toward energy development as the context for developing a citizen participation program are examined. Third, major citizen participation techniques and the advantages and disadvantages of each approach for resolving public policy issues are evaluated. Fourth, principles of successful citizen participation are presented. Finally, a proposal for stimulating and sustaining effective responsible citizen participation in nuclear waste repository siting and management is developed

Ranking system for mixed radioactive and hazardous waste sites

International Nuclear Information System (INIS)

Hawley, K.A.; Napier, B.A.

1985-01-01

The Environmental Protection Agency's Hazard Ranking System (HRS) is a simplified management decision tool that provides a common basis for evaluating a multitude of hazardous waste sites. A deficiency in the HRS for application to Department of Energy mixed radioactive and hazardous waste sites is its inability to explicitly handle radioactive material. A modification to the basic HRS to add the capability to consider radioactivity is described. The HRS considers the exposure routes of direct contact, fire/explosion, atmospheric release, surface-water release, and ground-water release. Each exposure route is further divided into release, route, containment, waste, and target characteristics. To maintain the basic HRS structure, only the waste characteristics section of each exposure route was modified. A ranking system was developed, using radiation dose pathway analysis, to group radionuclides by dose factors. For mixed waste sites, the ranking factor derived for radionuclides is compared with the ranking factor obtained for hazardous chemicals and the most restrictive is used in the overall ranking. The modified HRS has the advantages of being compatible with the original HRS, has reasonable information requirements, and provides scientifically defensible conclusions. 17 references, 2 figures, 6 tables

Stabilization and isolation of low-level liquid waste disposal sites

International Nuclear Information System (INIS)

Phillips, S.J.; Gilbert, T.W.

1987-01-01

Rockwell Hanford Operations is developing and testing equipment for stabilization and isolation of low-level radioactive liquid waste disposal sites. Stabilization and isolation are accomplished by a dynamic consolidation and particulate grout injection system. System equipment components include: a mobile grout plant for transport, mixing, and pumping of particulate grout; a vibratory hammer/extractor for consolidation of waste, backfill, and for emplacement of the injector; dynamic consolidation/injector probe for introducing grout into fill material; and an open-void surface injector that uses surface or subsurface mechanical or pneumatic packers and displacement gas filtration for introducing grout into disposal structure access piping. Treatment of a liquid-waste disposal site yields a physically stable, cementitious monolith. Additional testing and modification of this equipment for other applications to liquid waste disposal sites is in progress

Turning nuclear waste into glass

Energy Technology Data Exchange (ETDEWEB)

Pegg, Ian L.

2015-02-15

Vitrification has emerged as the treatment option of choice for the most dangerous radioactive waste. But dealing with the nuclear waste legacy of the Cold War will require state-of-the-art facilities and advanced glass formulations.

Siting a low-level radioactive waste disposal facility in California

International Nuclear Information System (INIS)

Romano, S.A.; Gaynor, R.K.

1991-01-01

US Ecology is the State of California's designee to site, develop and operate a low-level radioactive waste disposal facility. In March 1988, a site in the Ward Valley of California's Mojave Desert was chosen for development. Strong local community support has been expressed for the site. US Ecology anticipates licensing and constructing a facility to receive waste by early 1991. This schedule places California well ahead of the siting milestones identified in Federal law. (author) 1 fig., 2 refs

The Savannah River Site Waste Inventory Management Program

International Nuclear Information System (INIS)

Griffith, J.M.; Holmes, B.R.

1995-01-01

Each hazardous and radioactive waste generator that delivers waste to Savannah River Site (SRS) treatment, storage and disposal (TSD) facilities is required to implement a waste certification plan. The waste certification process ensures that waste has been properly identified, characterized, segregated, packaged, and shipped according to the receiving facilities waste acceptance criteria. In order to comply with the rigid acceptance criteria, the Reactor Division developed and implemented the Waste Inventory Management Program (WIMP) to track the generation and disposal of low level radioactive waste. The WIMP system is a relational database with integrated barcode technology designed to track the inventory radioactive waste. During the development of the WIMP several waste minimization tools were incorporated into the design of the program. The inclusion of waste minimization tools as part of the WIMP has resulted in a 40% increase in the amount of waste designated as compactible and an overall volume reduction of 5,000 cu-ft

Nevada Test Site 2008 Waste Management Monitoring Report Area 3 and Area 5 Radioactive Waste Management Sites

International Nuclear Information System (INIS)

2009-01-01

Environmental monitoring data were collected at and around the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site. These data are associated with radiation exposure, air, groundwater, meteorology, vadose zone, subsidence, and biota. This report summarizes the 2008 environmental data to provide an overall evaluation of RWMS performance and to support environmental compliance and performance assessment (PA) activities

Solution speciation of plutonium and Americium at an Australian legacy radioactive waste disposal site.

Science.gov (United States)

Ikeda-Ohno, Atsushi; Harrison, Jennifer J; Thiruvoth, Sangeeth; Wilsher, Kerry; Wong, Henri K Y; Johansen, Mathew P; Waite, T David; Payne, Timothy E

2014-09-02

During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. Because of periodic saturation and overflowing of the former disposal trenches, Pu and Am have been transferred from the buried wastes into the surrounding surface soils. The presence of readily detected amounts of Pu and Am in the trench waters provides a unique opportunity to study their aqueous speciation under environmentally relevant conditions. This study aims to comprehensively investigate the chemical speciation of Pu and Am in the trench water by combining fluoride coprecipitation, solvent extraction, particle size fractionation, and thermochemical modeling. The predominant oxidation states of dissolved Pu and Am species were found to be Pu(IV) and Am(III), and large proportions of both actinides (Pu, 97.7%; Am, 86.8%) were associated with mobile colloids in the submicron size range. On the basis of this information, possible management options are assessed.

Early Regulatory Engagement for Successful Site Remediation: the UK Experience - 13173

Energy Technology Data Exchange (ETDEWEB)

Maitland, R.P.; Senior, D. [Office for Nuclear Regulation, Redgrave Court, Liverpool L20 7HS (United Kingdom)

2013-07-01

The Office for Nuclear Regulation (ONR) is an independent safety, security and transport regulator of the UK nuclear industry. ONR regulates all civil nuclear reactor power stations, fuel manufacture, enrichment, spent fuel reprocessing, most defence sites and installations that store and process legacy spent fuel and radioactive waste. The responsibility for funding and strategic direction of decommissioning and radioactive waste management of state owned legacy sites has rested solely with the Nuclear Decommissioning Authority (NDA) since 2005. A key component of NDA's mandate was to encourage new strategic approaches and innovation to dealing with the UK's waste legacy and which deliver value-for-money to the UK taxpayer. ONR, as an agency of the Health and Safety Executive, is entirely independent of NDA and regulates all prescribed activities on NDA's sites. NDA's competition of site management and closure contracts has attracted significant international interest and the formation of consortia comprised of major British, US, French and Swedish organizations bidding for those contracts. The prominence of US organizations in each of those consortia reflects the scale and breadth of existing waste management and D and D projects in the US. This paper will articulate, in broad terms, the challenges faced by international organizations seeking to employ 'off-the-shelf' technology and D and D techniques, successfully employed elsewhere, into the UK regulatory context. The predominantly 'goal-setting' regulatory framework in the UK does not generally prescribe a minimum standard to which a licensee must adhere. The legal onus on licensees in the UK is to demonstrate, whatever technology is selected, that in its applications, risks are reduced 'So Far As Is Reasonably Practicable' or 'SFAIRP'. By the nature of its role, ONR adopts a conservative approach to regulation; however ONR also recognises that in the

Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

Energy Technology Data Exchange (ETDEWEB)

Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

2013-07-01

The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

NRC Waste Incidental to Reprocessing Program: Overview of Consultation and Monitoring Activities at the Idaho National Laboratory and the Savannah River Site - What We Have Learned - 12470

Energy Technology Data Exchange (ETDEWEB)

Suber, Gregory [Nuclear Regulatory Commission (United States)

2012-07-01

In 2005 the U.S. Nuclear Regulatory Commission (NRC) began to implement a new set of responsibilities under the Ronald W. Reagan National Defense Authorization Act (NDAA) of Fiscal Year 2005. Section 3116 of the NDAA requires the U.S. Department of Energy (DOE) to consult with the NRC for certain non-high level waste determinations and also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2005, the NRC staff began consulting with DOE and completed reviews of draft waste determinations for salt waste at the Savannah River Site. In 2006, a second review was completed on tank waste residuals including sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center Tank Farm at the Idaho National Laboratory. Monitoring Plans were developed for these activities and the NRC is actively monitoring disposal actions at both sites. NRC is currently in consultation with DOE on the F-Area Tank Farm closure and anticipates entering consultation on the H-Area Tank Farm at the Savannah River Site. This paper presents, from the NRC perspective, an overview of how the consultation and monitoring process has evolved since its conception in 2005. It addresses changes in methods and procedures used to collect and develop information used by the NRC in developing the technical evaluation report and monitoring plan under consultation and the implementation the plan under monitoring. It will address lessons learned and best practices developed throughout the process. The NDAA has presented significant challenges for the NRC and DOE. Past and current successes demonstrate that the NDAA can achieve its intended goal of facilitating tank closure at DOE legacy defense waste sites. The NRC believes many of the challenges in performing the WD reviews have been identified and addressed. Lessons learned have been collected and documented throughout the review process. Future success will be contingent on each agencies commitment to

Conflict resolution in low-level waste facility siting

International Nuclear Information System (INIS)

English, M.R.

1989-01-01

Siting a low-level waste facility is only one part of the low-level waste management process. But it is a crucial part, a prism that focuses many of the other issues in low-level waste management. And, as the 1990 and 1992 milestones approach, siting has a urgency that makes the use of alternative dispute resolution (ADR) techniques especially appropriate, to avoid protracted and expensive litigation and to reach creative and durable solutions. Drawing upon literature in the ADR field, this paper discusses ADR techniques as they apply to low-level waste management and the groundwork that must be laid before they can be applied. It also discusses questions that can arise concerning the terms under which negotiations are carried out. The paper then give suggestions for achieving win/win negotiations. Potential objections to negotiated agreements and potential answers to those objections are reviewed, and some requisites for negotiation are given

Delegated Democracy. The Siting of Swedish Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Johansson, Hanna Sofia (Stockholm Univ., SCORE, SE-106 91 Stockholm (Sweden))

2009-12-15

This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

Delegated Democracy. The Siting of Swedish Nuclear Waste

International Nuclear Information System (INIS)

Johansson, Hanna Sofia

2009-12-01

This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

Waste repository planned for Bruce Site

International Nuclear Information System (INIS)

King, F.

2004-01-01

Ontario Power Generation (OPG) and Kincardine, the municipality nearest the Bruce site, have agreed in principal to the construction of a deep geologic repository for low and medium level radioactive waste on the site. The two parties signed the 'Kincardine Hosting Agreement' on October 13, 2004 to proceed with planning, seek regulatory approval and further public consultation of the proposed project. A construction Licence is not expected before 2013. (author)

On site clean up with a hazardous waste incinerator

International Nuclear Information System (INIS)

Cross, F.L. Jr.; Tessitore, J.L.

1987-01-01

The Army Corps of Engineers and the EPA have determined that on-site incineration for the detoxification of soils, sediments, and sludges is a viable, safe, and economic alternative. This paper discusses an approach to on-site incineration as a method of detoxification of soils/sediments contaminated with organic hazardous wastes. Specifically, this paper describes the procedures used to evaluate on-site incineration at a large Superfund site with extensive PCB contaminated soils and sediments. The paper includes the following: (1) a discussion of site waste quantities and properties, (2) a selection of an incineration technology with a resulting concept and design, (3) a discussion of incinerator permitting requirements, (4) discussion and rationale for an incinerator sub-scale testing approach, and (5) analysis of on-site incineration cost

Status of siting studies for a near surface repository site for radioactive wastes in the Philippines

International Nuclear Information System (INIS)

Valdezco, E.M.; Palattao, M.V.B.; Marcelo, E.A.; Caseria, E.S.; Venida, L.L.; Cruz, J.M. dela

2002-01-01

The Philippines, through the Philippine Nuclear Research Institute (PNRI), decided to conduct a study on siting a low level radioactive waste disposal facility. The infrastructure set up for this purpose, the radioactive waste disposal concept, the overall siting process, the methodology applied and preliminary results obtained are described in this paper. (author)

Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

International Nuclear Information System (INIS)

McAulay, I.R.

1996-01-01

Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials

Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

Energy Technology Data Exchange (ETDEWEB)

McAulay, I R [Trinity Coll., Dublin (Ireland). Physical Lab.

1996-10-01

Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials.

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1991-07-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

Keller, J.F.; Stewart, T.L.

1993-01-01

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

Managing the nuclear legacy n the UK: Progress towards the establishment of the Nuclear Decommissioning Authority

International Nuclear Information System (INIS)

Sellers, R.M.

2003-01-01

In November 2001, the British Government announced its intention to undertake a radical revision of the arrangements for managing public sector civil nuclear liabilities in the UK. Its proposals for this transformation were published in a White Paper 'Managing the Nuclear Legacy - A Strategy for Action' published on 4 July 2002. This calls for the formation of a new organisation, originally referred to as the Liabilities Management Authority, but since renamed the Nuclear Decommissioning Authority (NDA), responsible to Government and with a remit to ensure that the UK's nuclear legacy is cleaned up safely, securely, cost effectively and in ways which protect the environment. The NDA will be responsible for some twenty-one UK nuclear sites comprising about 85% of the UK's civil nuclear liabilities. These sites are those currently operated by the United Kingdom Atomic Energy Authority (UKAEA) and British Nuclear Fuels plc (BNFL), and amongst other things include many facilities from the early years of nuclear power etc in the UK, liabilities associated with the Joint European Torus (JET) fusion research project at UKAEA's Culham site, the Magnox nuclear power stations, and the associated facilities at Sellafield for reprocessing as well as those associated with the UK's fast reactor programme based at Dounreay. The challenge is to decommission and dismantle these facilities, package the radioactive wastes ready for disposal and remedy the sites, taking into account the uncertainties associated with many of the older facilities and the potential technical novelty of the processes that will have to be deployed to achieve this. This paper is concerned with the work of the Liabilities Management Unit (LMU) in preparing the way for the NDA and what it has achieved in its first eighteen months. The following issues are addressed: The Liabilities Management Unit and its remit (which presents the LMU Functional Groups and their responsibilities); Acquiring a detailed

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

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2012-07-17

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as

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

International Nuclear Information System (INIS)

2012-01-01

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 547, Miscellaneous Contaminated Waste Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 547 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended). CAU 547 consists of the following three Corrective Action Sites (CASs), located in Areas 2, 3, and 9 of the Nevada National Security Site: (1) CAS 02-37-02, Gas Sampling Assembly; (2) CAS 03-99-19, Gas Sampling Assembly; AND (3) CAS 09-99-06, Gas Sampling Assembly Closure activities began in August 2011 and were completed in June 2012. Activities were conducted according to the Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for CAU 547 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2011). The recommended corrective action for the three CASs in CAU 547 was closure in place with administrative controls. The following closure activities were performed: (1) Open holes were filled with concrete; (2) Steel casings were placed over vertical expansion joints and filled with cement; (3) Engineered soil covers were constructed over piping and exposed sections of the gas sampling system components; (4) Fencing, monuments, Jersey barriers, radiological postings, and use restriction (UR) warning signs were installed around the perimeters of the sites; (5) Housekeeping debris was picked up from around the sites and disposed; and (6) Radiological surveys were performed to confirm final radiological postings. UR documentation is included in Appendix D. The post-closure plan was presented in detail in the CADD/CAP for CAU 547 and is included as

Streamlined approach to waste management at CRL

International Nuclear Information System (INIS)

Adams, L.; Campbell, B.

2011-01-01

Radioactive, mixed, hazardous and non-hazardous wastes have been and continue to be generated at Chalk River Laboratories (CRL) as a result of research and development activities and operations since the 1940s. Over the years, the wastes produced as a byproduct of activities delivering the core missions of the CRL site have been of many types, and today, over thirty distinct waste streams have been identified, all requiring efficient management. With the commencement of decommissioning of the legacy created as part of the development of the Canadian nuclear industry, the volumes and range of wastes to be managed have been increasing in the near term, and this trend will continue into the future. The development of a streamlined approach to waste management is a key to successful waste management at CRL. Waste management guidelines that address all of the requirements have become complex, and so have the various waste management groups receiving waste, with their many different processes and capabilities. This has led to difficulties for waste generators in understanding all of the requirements to be satisfied for the various CRL waste receivers, whose primary concerns are to be safe and in compliance with their acceptance criteria and license conditions. As a result, waste movement on site can often be very slow, especially for non-routine waste types. Recognizing an opportunity for improvement, the Waste Management organization at CRL has implemented a more streamlined approach with emphasis on early identification of waste type and possible disposition path. This paper presents a streamlined approach to waste identification and waste management at CRL, the implementation methodology applied and the early results achieved from this process improvement. (author)

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Restoration

2007-07-01

Corrective Action Unit (CAU) 139, Waste Disposal Sites, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 139 consists of seven Corrective Action Sites (CASs) located in Areas 3, 4, 6, and 9 of the Nevada Test Site (NTS), which is located approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1). CAU 139 consists of the following CASs: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Details of the site history and site characterization results for CAU 139 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007). The purpose of this Corrective Action Plan (CAP) is to present the detailed scope of work required to implement the recommended corrective actions as specified in Section 4.0 of the approved CADD (NNSA/NSO, 2007). The approved closure activities for CAU 139 include removal of soil and debris contaminated with plutonium (Pu)-239, excavation of geophysical anomalies, removal of surface debris, construction of an engineered soil cover, and implementation of use restrictions (URs). Table 1 presents a summary of CAS-specific closure activities and contaminants of concern (COCs). Specific details of the corrective actions to be performed at each CAS are presented in Section 2.0 of this report.

Corrective Action Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada