Licensing plan for UMTRA project disposal sites
International Nuclear Information System (INIS)
1993-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Office developed a plan to define UMTRA Project licensing program objectives and establish a process enabling the DOE to document completion of remedial actions in compliance with 40 CFR 1 92 and the requirements of the NRC general license. This document supersedes the January 1987 Project Licensing Plan (DOE, 1987). The plan summarizes the legislative and regulatory basis for licensing, identifies participating agencies and their roles and responsibilities, defines key activities and milestones in the licensing process, and details the coordination of these activities. This plan provides an overview of the UMTRA Project from the end of remedial actions through the NRC's acceptance of a disposal site under the general license. The licensing process integrates large phases of the UMTRA Project. Other programmatic UMTRA Project documents listed in Section 6.0 provide supporting information
UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1
International Nuclear Information System (INIS)
1995-10-01
This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system's designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy
UMTRA Project: Environment, Safety, and Health Plan
International Nuclear Information System (INIS)
1995-02-01
The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations
Analysis of infiltration through a clay radon barrier at an UMTRA disposal cell
International Nuclear Information System (INIS)
1991-01-01
An infiltration study was initiated in January 1988 to assess the percent saturation in, and infiltration through, clay radon barriers of typical Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cells. Predicting infiltration through the radon barrier is necessary to evaluate whether the disposal cell will comply with the proposed US Environmental Protection Agency (EPA) groundwater protection standards (40 CFR 192). The groundwater standards require demonstrating that tailings seepage will not cause background concentrations or maximum concentration limits (MCLs) to be exceeded at the downgradient edge of the disposal facility (the point of compliance, or POC). This demonstration generally consists of incorporating the predicted seepage flux and the concentration of the specific hazardous constituents into a contaminant transport model, and predicting the resultant concentrations at the POC. The infiltration study consisted of a field investigation to evaluate moisture conditions in the radon barrier of the completed Shiprock, New Mexico, UMTRA Project disposal cell and previously completed UMTRA Project disposal cells at Clive, Utah, and Burrell, Pennsylvania. Coring was conducted to measure percent saturation profiles in the radon barriers at these disposal cells. In addition, a detailed investigation of the Shiprock radon barrier was conducted to establish the effects of meteorological stresses on moisture conditions in the filter layer and radon barrier. The Shiprock infiltration study was also intended to characterize hydraulic gradients and operational unsaturated hydraulic conductivities in the radon barrier
UMTRA -- The US Uranium Mill Tailings Remedial Action Project
International Nuclear Information System (INIS)
Lightner, R.; Cormier, C.; Bierley, D.
1995-01-01
In the late 1970s, the United States (US) established the first comprehensive regulatory structure for the management, disposal, and long-term care of wastes produced from its domestic uranium processing industry. This regulatory framework was established through the passage of the Uranium Mill Tailings Radiation Control Act of 1978, often referred to as UMTRCA. This legislation created the Uranium Mill Tailings Remedial Action (UMTRA) Project and assigned the US Department of Energy (DOE) the lead in conducting the required remedial action at 24 designated inactive uranium ore processing sites. With the majority of these 22 sites complete, the DOE's UMTRA Project has established a distinguished reputation for safely and effectively remediating these low-level waste sites in a complex regulatory and socioeconomic environment. This paper describes the past accomplishments and current status of the UMTRA Project and discusses the DOE's plans for addressing ground water contamination associated with these sites and its commitment to continuing the long-term care and management of these disposal cells
Vegetation growth patterns on six rock-covered UMTRA Project disposal cells
International Nuclear Information System (INIS)
1992-02-01
This study assessed vegetation growth patterns, the potential impacts of vegetation growth on disposal cell cover integrity, and possible measures that could be taken to monitor and/or control plant growth, where necessary, on six Uranium Mill Tailings Remedial Action (UMTRA) Project rock-covered disposal cells. A large-scale invasion of volunteer plants was observed on the Shiprock and Burrell disposal cells. Plant growth at the South Clive, Green River, and Tuba City disposal cells was sparse except for the south rock apron and south slope of the Tuba City disposal cell, where windblown sand had filled up part of the rock cover and plant growth was observed. The rock-covered topslope of the Collins Ranch disposal cell was intentionally covered with topsoil and vegetated. Plant roots growing on the disposal cells are changing the characteristics of the cover by drying out the radon barrier, encouraging the establishment of soil-building processes in the bedding and radon barrier layers, creating channels in the radon barrier, and facilitating ecological succession, which could lead to the establishment of additional deep-rooted plants on the disposal cells. If left unchecked, plant roots would reach the tailings at the Burrell and Collins Ranch disposal cells within a few years, likely resulting in the transport of contaminants out of the cells
Guidance for implementing the UMTRA Project long-term surveillance program
International Nuclear Information System (INIS)
1992-09-01
The US Nuclear Regulatory Commission (NRC) has issued a general license for the custody and long-term care of US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project permanent disposal sites. The purpose of this general license is to ensure that the UMTRA disposal sites will be cared for in such a manner as to protect the public health and safety and the environment upon completion of remedial actions. The general license will be in effect for a disposal site when NRC accepts the disposal site long-term surveillance plan (LTSP) that meets the requirements of 10 CFR 40.27. The site LTSP describes in detail the long-term surveillance program, including any monitoring, maintenance, and emergency measures necessary to fulfill the conditions of the general license. This guidance document provides (1) instructions for preparing the disposal site LTSPs and (2) instructions for carrying out the UMTRA Project long-term surveillance program, including any monitoring that may be required. The information provided in this document also is in accordance with the regulatory requirements set forth in 40 CFR 192. On January 5, 1985, the US Tenth Circuit Court of Appeals remanded the groundwater standards, 40 CFR 192.02. Proposed groundwater standards were issued for comment on September 24, 1987 (52 FR 3600). When the groundwater standards become final, this document will be revised, as appropriate. This document also will be updated in response to any changes to 10 CFR 40, or in response to changes in the manner in which the long-term care of the licensed disposal sites is carried out
Outdoor radon monitoring plan for the UMTRA Project sites
International Nuclear Information System (INIS)
1986-02-01
This document describes the monitoring schedules and methods used to measure ambient radon concentrations around Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Radon monitoring at both processing sites and disposal sites is performed primarily for two reasons. The first, and foremost, of these is to provide a means to keep the off-site radon concentrations during the construction activities As Low As Reasonably Achievable (ALARA). The second purpose is to provide a basis for comparison with the EPA standards developed for the UMTRA Project. Radon monitoring data are also used to demonstrate compliance with ambient concentration standards and for public information due to concern about potential radiation releases during construction. 1 fig., 1 tab
UMTRA Project water sampling and analysis plan, Canonsburg, Pennsylvania. Revision 1
International Nuclear Information System (INIS)
1995-09-01
Surface remedial action was completed at the US Department of Energy (DOE) Canonsburg and Burrell Uranium Mill Tailings Remedial Action (UMTRA) Project sites in southwestern Pennsylvania in 1985 and 1987, respectively. The Burrell disposal site, included in the UMTRA Project as a vicinity property, was remediated in conjunction with the remedial action at Canonsburg. On 27 May 1994, the Nuclear Regulatory Commission (NRC) accepted the DOE final Long-Term Surveillance Plan (LTSP) (DOE, 1993) for Burrell thus establishing the site under the general license in 10 CFR section 40.27 (1994). In accordance with the DOE guidance document for long-term surveillance (DOE, 1995), all NRC/DOE interaction on the Burrell site's long-term care now is conducted with the DOE Grand Junction Projects Office in Grand Junction, Colorado, and is no longer the responsibility of the DOE UMTRA Project Team in Albuquerque, New Mexico. Therefore, the planned sampling activities described in this water sampling and analysis plan (WSAP) are limited to the Canonsburg site. This WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequencies for routine monitoring at the Canonsburg site for calendar years 1995 and 1996. Currently, the analytical data further the site characterization and demonstrate that the disposal cell's initial performance is in accordance with design requirements
UMTRA Project value engineering plan
International Nuclear Information System (INIS)
1990-06-01
The objective of value engineering (VE) on the Uranium MILL Tailings Remedial Action (UMTRA) Project is to ensure that remedial action at the UMTRA Project sites is performed to meet the US Environmental Protection Agency (EPA) standards for inactive uranium mill tailings sites at the lowest cost, while maintaining a high quality of work. Through review of designs and consideration of reasonable, less expensive alternatives, VE can be an effective cost reduction tool and a means to improve the design. The UMTRA Project products are the design and construction of stabilized tailings embankments
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
UMTRA Ground Water Project management action process document
International Nuclear Information System (INIS)
1996-03-01
A critical U.S. Department of Energy (DOE) mission is to plan, implement, and complete DOE Environmental Restoration (ER) programs at facilities that were operated by or in support of the former Atomic Energy Commission (AEC). These facilities include the 24 inactive processing sites the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.) identified as Title I sites, which had operated from the late 1940s through the 1970s. In UMTRCA, Congress acknowledged the potentially harmful health effects associated with uranium mill tailings and directed the DOE to stabilize, dispose of, and control the tailings in a safe and environmentally sound manner. The UMTRA Surface Project deals with buildings, tailings, and contaminated soils at the processing sites and any associated vicinity properties (VP). Surface remediation at the processing sites will be completed in 1997 when the Naturita, Colorado, site is scheduled to be finished. The UMTRA Ground Water Project was authorized in an amendment to the UMTRCA (42 USC Section 7922(a)), when Congress directed DOE to comply with U.S. Environmental Protection Agency (EPA) ground water standards. The UMTRA Ground Water Project addresses any contamination derived from the milling operation that is determined to be present at levels above the EPA standards
Supplement to the UMTRA Project water sampling and analysis plan, Ambrosia Lake, New Mexico
International Nuclear Information System (INIS)
1995-08-01
The Ambrosia Lake Uranium Mill Tailings Remedial Action (UMTRA) Project site is in McKinley County, New Mexico. As part of UMTRA surface remediation, residual radioactive materials were consolidated on the site in a disposal cell that was completed July 1995. The need for ground water monitoring was evaluated and found not to be necessary beyond the completion of the remedial action because the ground water in the uppermost aquifer is classified as limited use
UMTRA project office federal employee occupational safety and health program plan
International Nuclear Information System (INIS)
1994-06-01
This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project
Public participation in UMTRA Project program management
International Nuclear Information System (INIS)
Majors, M.J.; Ulland, L.M.
1993-01-01
Innovative techniques for overcoming barriers to public participation on the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project have led to improved communications with stakeholders at project sites and improved communications within the project. On the UMTRA Project, it's been shown that an effective public participation program is an essential element to successful project implementation
International Nuclear Information System (INIS)
1994-02-01
This special study was conducted to prepare a guidance document for selecting in situ hydraulic conductivity (K) tests, comparing in situ testing methods, and evaluating the results of such tests. This report may be used as a practical decision-making tool by the Uranium Mill Tailings Remedial Action (UMTRA) Project staff to determine which testing method will most efficiently achieve the field-saturated K results needed for long-term planning. A detailed section on near-surface test methods discusses each method which may be applicable to characterization of UMTRA disposal cell covers, liners and foundation materials. These potentially applicable test methods include the sealed double-ring infiltrometer (SDRI), the air-entry permeameter (AEP), the guelph permeameter, the two-stage borehole technique (TSB), the pressure infiltrometer, and the disk permeameter. Analytical solutions for these methods are provided, and limitations of these solutions are discussed, and a description of testing equipment design and installation are provided
UMTRA Project-Level Cost Reduction/Productivity Improvement Program manual
International Nuclear Information System (INIS)
1995-06-01
Mission of the Uranium Mill Tailings Remedial Action (UMTRA) Project Cost Reduction/Productivity Improvement Program (CR/PIP) is to contribute to the UMTRA Project's environmental restoration mission by providing the means to achieve and recognize continuous improvements and cost savings. This manual includes program definition, description of UMTRA project organizational responsibilities and interfaces with existing project functions, guidance to contractors, and definition of project-level functions
UMTRA Project environmental, health, and safety plan
International Nuclear Information System (INIS)
1989-02-01
The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs
The effect of desiccation on UMTRA Project radon barrier materials
International Nuclear Information System (INIS)
1990-11-01
The proposed US Environmental Protection Agency (EPA) groundwater standards (40 CFR 192) require that Uranium Mill Tailings Remedial Action (UMTRA) Project remedial action designs meet low numerical limits for contaminants contained in water or vapors exiting the disposal cell embankments. To meet the standards, a cover of compacted, fine-grained soil is placed over UMTRA Project embankments. One of the functions of this cover is to limit infiltration into the disposal cell . The hydraulic conductivity of this infiltration barrier must be low in order to reduce the resultant seepage from the base of the cell to the extent necessary to comply with the proposed EPA groundwater standards. Another function of this cover is to limit the emission of radon gas. The air permeability of the cover must be low in order to reduce radon emissions to comply with EPA standards. Fine-grained soils exposed to evaporation will dry. Continued exposure will cause shrinking that, if allowed to continue, will eventually result in the development of cracks. The results of the cracking could be an increase in the hydraulic conductivity and an increase in the air permeability. This could then allow additional infiltration and increased radon emissions. Cracking of the radon barrier has been noted at one UMTRA Project location. The potential for cracking of the radon barrier during construction has been addressed by requiring moistening of previously compacted surfaces prior to placing additional lifts. The efficacy of these treatments has not been verified. The potential for cracking after construction of the cover is completed has also not been examined. The purpose of this study is to evaluate the potential for cracking of the radon barrier both during construction and after completion of the cover. The effect of shrinkage cracking on the performance of the radon barrier will also be examined
International Nuclear Information System (INIS)
1989-01-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project involves stabilizing 24 inactive uranium mill tailings piles in 10 states. Remedial work must meet standards established by the US Environmental Protection Agency (EPA). Remedial action must be designed and constructed to prevent dispersion of the tailings and other contaminated materials, and must prevent the inadvertent use of the tailings by man. This report is prepared primarily for distribution to parties involved in the UMTRA Project, including the US Nuclear Regulatory Commission (NRC), and states and tribes. It is intended to record the work done by the DOE since publication of the proposed EPA groundwater protection standards, and to show how the DOE has attempted to respond and react in a positive way to the new requirements that result from the proposed standards. This report discusses the groundwater compliance strategies now being defined and implemented by the DOE, and details the changes in disposal cell designs that result from studies to evaluate ways to facilitate compliance with the proposed EPA groundwater protection standards. This report also serves to record the technical advances, planning, and progress made on the UMTRA Project since the appearance of the proposed EPA groundwater protection standards. The report serves to establish, document, and disseminate technical approaches and engineering and groundwater information to people who may be interested or involved in similar or related projects. 24 refs., 27 figs., 8 tabs
UMTRA project water sampling and analysis plan -- Shiprock, New Mexico
International Nuclear Information System (INIS)
1994-02-01
Water sampling and analysis plan (WSAP) is required for each U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site to provide a basis for ground water and surface water sampling at disposal and former processing sites. This WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the monitoring stations at the Navaho Reservation in Shiprock, New Mexico, UMTRA Project site. The purposes of the water sampling at Shiprock for fiscal year (FY) 1994 are to (1) collect water quality data at new monitoring locations in order to build a defensible statistical data base, (2) monitor plume movement on the terrace and floodplain, and (3) monitor the impact of alluvial ground water discharge into the San Juan River. The third activity is important because the community of Shiprock withdraws water from the San Juan River directly across from the contaminated alluvial floodplain below the abandoned uranium mill tailings processing site
UMTRA project list of reportable occurrences
Energy Technology Data Exchange (ETDEWEB)
1994-04-01
This UMTRA Project List of Reportable occurrences is provided to facilitate efficient categorization of reportable occurrences. These guidelines have been established in compliance with DOE minimum reporting requirements under DOE Order 5000.3B. Occurrences are arranged into nine groups relating to US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project operations for active sites. These nine groupings are provided for reference to determined whether an occurrence meets reporting requirement criteria in accordance with the minimum reporting requirements. Event groups and significance categories that cannot or will not occur, and that do not apply to UMTRA Project operations, are omitted. Occurrence categorization shall be as follows: Group 1. Facility Condition; Group 2. Environmental; Group 3. Personnel Safety; Group 4. Personnel Radiation Protection; Group 5. Safeguards and Security; Group 6. Transportation; Group 7. Value Basis Reporting; Group 8. Facility Status; and Group 9. Cross-Category Items.
UMTRA project list of reportable occurrences
International Nuclear Information System (INIS)
1994-04-01
This UMTRA Project List of Reportable occurrences is provided to facilitate efficient categorization of reportable occurrences. These guidelines have been established in compliance with DOE minimum reporting requirements under DOE Order 5000.3B. Occurrences are arranged into nine groups relating to US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project operations for active sites. These nine groupings are provided for reference to determined whether an occurrence meets reporting requirement criteria in accordance with the minimum reporting requirements. Event groups and significance categories that cannot or will not occur, and that do not apply to UMTRA Project operations, are omitted. Occurrence categorization shall be as follows: Group 1. Facility Condition; Group 2. Environmental; Group 3. Personnel Safety; Group 4. Personnel Radiation Protection; Group 5. Safeguards and Security; Group 6. Transportation; Group 7. Value Basis Reporting; Group 8. Facility Status; and Group 9. Cross-Category Items
Environmental Audit, Rifle, Gunnison and Grand Junction UMTRA Project Sites
International Nuclear Information System (INIS)
1991-08-01
This report documents the results of the comprehensive baseline Environmental Audit completed for the Uranium Mill Tailings Remedial Action (UMTRA) sites at Grand Junction, Rifle, and Gunnison, Colorado. Included in the Audit were the actual abandoned mill sites, associated transportation and disposal cell facilities, and representative examples of the more than 4,000 known vicinity properties. Sites investigated include: Climax Mill Site, Truck/Train Haul Route, Cotter Transfer Station, Cheney Disposal Cell, Rifle Mill Sites (Old and New Rifle), Gunnison Mill Site, Vicinity Properties, and Estes Gulch and Proposed Landfill Site No. 1 Disposal Cells. The UMTRA Audit was a comprehensive baseline audit which considered all environmental programs and the activities associated with ongoing and planned remediation at the UMTRA sites listed above. Compliance with the National Environmental Policy Act (NEPA) was not considered during this investigation. The Audit Team looked at the following technical disciplines: air, surface water/drinking water, groundwater, soil/sediment/biota, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. 6 figs., 12 tabs
Environmental Audit, Rifle, Gunnison and Grand Junction UMTRA Project Sites
Energy Technology Data Exchange (ETDEWEB)
None
1991-08-01
This report documents the results of the comprehensive baseline Environmental Audit completed for the Uranium Mill Tailings Remedial Action (UMTRA) sites at Grand Junction, Rifle, and Gunnison, Colorado. Included in the Audit were the actual abandoned mill sites, associated transportation and disposal cell facilities, and representative examples of the more than 4,000 known vicinity properties. Sites investigated include: Climax Mill Site, Truck/Train Haul Route, Cotter Transfer Station, Cheney Disposal Cell, Rifle Mill Sites (Old and New Rifle), Gunnison Mill Site, Vicinity Properties, and Estes Gulch and Proposed Landfill Site No. 1 Disposal Cells. The UMTRA Audit was a comprehensive baseline audit which considered all environmental programs and the activities associated with ongoing and planned remediation at the UMTRA sites listed above. Compliance with the National Environmental Policy Act (NEPA) was not considered during this investigation. The Audit Team looked at the following technical disciplines: air, surface water/drinking water, groundwater, soil/sediment/biota, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. 6 figs., 12 tabs.
ERD UMTRA Project quality assurance program plan, Revision 7
International Nuclear Information System (INIS)
1995-09-01
This document is the revised Quality Assurance Program Plan (QAPP) dated September, 1995 for the Environmental Restoration Division (ERD) Uranium Mill Tailings Remedial Action Project (UMTRA). Quality Assurance requirements for the ERD UMTRA Project are based on the criteria outlined in DOE Order 5700.6C or applicable sections of 10 CFR 830.120. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the ERD UMTRA Project and its contractors
Project licensing plan for UMTRA [Uranium Mill Tailings Remedial Action] sites
International Nuclear Information System (INIS)
1984-07-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Licensing Plan is to establish how a disposal site will be licensed, and to provide responsibilities of participatory agencies as legislated by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604). This Plan has been developed to ensure that the objectives of licensing are met by identifying the necessary institutional controls, participatory agency responsibilities, and key milestones in the licensing process. The Plan contains the legislative basis for and a description of the licensing process (''Process'') for UMTRA sites. This is followed by a discussion of agency responsibilities, and milestones in the Process. The Plan concludes with a generic timeline of this Process. As discussed in Section 2.1, a custodial maintenance and surveillance plan will constitute the basis for a site license. The details of maintenance and surveillance are discussed in the Project Maintenance and Surveillance Plan (AL-350124.0000). 5 refs., 4 figs
Public participation in UMTRA Project Program Management
International Nuclear Information System (INIS)
Majors, M.J.; Ulland, L.M.
1993-01-01
The U.S. Department of Energy (DOE) is cleaning up radioactive soil and ore residue from 24 inactive uranium processing sites under the Uranium Mill Tailings Remedial Action (UMTRA) Project. In early 1993, the DOE adopted new guidelines strongly encouraging public participation. This guidance commits to providing the public with opportunities to participate in the decision-making process for program planning, design, and implementation. Rooted in the conviction that an effective public participation program will enable citizens to take part in policy decisions, the full adoption of the guidance by the UMTRA project can also help DOE make better decisions, provide a means to build consensus, and assist in building credibility. This transition to open communication parallels the climate of corporate America in which increases in productivity are often the result of workers and management teaming together to solve problems. While these guidelines have been embraced by public affairs staff from headquarters to the field offices, barriers still exist that inhibit substantive public involvement. The challenge for the UMTRA project is to overcome these barriers to ensure that public participation is an integral part of the way business is conducted. This paper discusses lessons learned by the UMTRA project in its efforts to address barriers to public participation and the project's plans for full compliance with the DOE guidelines
UMTRA Project Office quality assurance program plan. Revision 6
International Nuclear Information System (INIS)
1994-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites. The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. Because these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the UMTRA Project Office and its contractors
UMTRA project technical assistance contractor quality assurance implementation plan
International Nuclear Information System (INIS)
1994-03-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance contractor (TAC) Quality Assurance Implementation Plan (QAIP) outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QAIP is subordinate to the latest issue of the UMTRA Project TAC Quality Assurance Program Plan (QAPP) (DOE, 1993a), which was developed using US Department of Energy (DOE) Order 5700.6C quality assurance (QA) criteria. The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. All QA issues in the QAIP shall comply with requirements contained in the TAC QAPP (DOE, 1933a). Because industry standards for data acquisition and data control are not addressed in DOE Order 5700.6C, the QAIP has been formatted to the 14 US Environmental Protection Agency (EPA) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) QA requirements. DOE Order 5700.6C criteria that are not contained in the CERCLA requirements are added to the QAIP as additional requirements in Sections 15.0 through 18.0. Project documents that contain CERCLA requirements and 5700.6 criteria shall be referenced in this document to avoid duplication. Referenced documents are not included in this QAIP but are available through the UMTRA Project Document Control Center
UMTRA [Uranium Mill Tailings Remedial Action] Project site management manual
International Nuclear Information System (INIS)
1990-10-01
The purpose of this manual is to summarize the organizational interfaces and the technical approach used to manage the planning, design development, National Environmental Policy Act (NEPA) compliance, engineering, and remedial action required to stabilize and control the designated Uranium Mill Tailings Remedial Action (UMTRA) Project sites. This manual describes the Project's objective, participants' roles and responsibilities, technical approach for accomplishing the objective, and planning and managerial controls to be used in performing the site work. The narrative follows the flow of activities depicted in Figure 1.1, which provides the typical sequence of key Project activities. A list of acronyms used is presented at the end of the manual. The comparable manual for UMTRA Project vicinity properties is the ''Vicinity Properties Management and Implementation Manual'' (VPMIM) (UMTRA-DOE/AL-050601). Together, the two manuals cover the remedial action activities associated with UMTRA Project sites. The UMTRA Project's objective is to stabilize and control the uranium mill tailings, vicinity property materials, and other residual radioactive materials at the designated sites (Figure 1.2) in a safe and environmentally sound manner in order to minimize radiation health hazards to the public. 26 figs., 6 tabs
International Nuclear Information System (INIS)
1992-06-01
The U.S Department of Energy (DOE) administers the Uranium Mill Tailings Remedial Action (UMTRA) Project. The UMTRA Project is the result of the Uranium Mill Tailings Radiation Control Act(UMTRA) which was passed in response to the public's concern over the potential public health hazards related to uranium mill tailings and associated contaminated material at abandoned or otherwise uncontrolled inactive processing sites throughout the United States. The Gunnison, Colorado abandoned uranium mill site is one of the sites slated for cleanup by the DOE under authority of UMTRA. The contaminated material at this site will be transported to a disposal site on US Bureau of Land Management (BLM) land east of Gunnison. Remedial action activities will temporarily disturb 0.8 acre and permanently eliminate 5.1 acres of wetlands. This report describes the proposed mitigation plan for the 5.9 acres of impacted wetlands. In conjunction with the mitigation of the permanently impacted wetlands through the enhancement of wetland and adjacent riparian areas, impacts to wildlife as a result of this project will also be mitigated. However, wildlife mitigation is not the focus of this document and is covered in relevant BLM permits for this project. This plan proposes the enhancement of a 3:1 ratio of impacted wetlands in accordance with US Environmental Protection Agency guidelines, plus the enhancement of riparian areas for wildlife mitigation. Included in this mitigation plan is a monitoring plan to ensure that the proposed measures are working and being maintained
Site Observational Work Plan for the UMTRA project site at Ambrosia Lake, New Mexico
International Nuclear Information System (INIS)
1995-02-01
Ground water compliance for the Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Ambrosia Lake, New Mexico, site, is governed by the Uranium Mills Tailings Radiation Control Act (42 USC section 7901 et seq.) and the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR Part 192; 60 FR 2854). The EPA standards describe specific conditions for which the U.S. Department of Energy (DOE) may apply for supplemental standards for contaminated ground water rather than meeting background levels or numerical standards. To achieve compliance with Subpart A of the EPA standards the residual radioactive materials are currently being consolidated on the site by the DOE in a disposal cell, isolating them from direct human or ecological contact and further dispersion into the environment. Completion of the disposal cell is scheduled for early 1995. An environmental assessment and a Finding of No Significant Impact (FONSI) were completed in 1987. Concurrence with the UMTRA Surface Project Ambrosia Lake remedial action plan (RAP) was granted by the U.S. Nuclear Regulatory Commission (NRC) and state of New Mexico in 1990. The DOE deferred compliance with Subpart B of the EPA standards in the Surface Project RAP. This site observational work plan (SOWP) is the first document to address ground water compliance under Subpart B at the Ambrosia Lake site. The Ambrosia Lake UMTRA Project site is within the Grants Mineral Belt and was one of numerous uranium mills supplied by many local mines. Ground water contamination at the site occurred as a result of uranium mill operations. Contamination of ground water resulted from discharge of waste water, infiltration of water through the tailings pile, hydraulic placement of mill tailings in nearby mines, and water pumped from mine shafts
UMTRA project water sampling and analysis plan, Mexican Hat, Utah
International Nuclear Information System (INIS)
1994-04-01
The Mexican Hat, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project site is a former uranium mill that is undergoing surface remediation in the form of on-site tailings stabilization. Contaminated surface materials from the Monument Valley, Arizona, UMTRA Project site have been transported to the Mexican Hat site and are being consolidated with the Mexican Hat tailings. The scheduled completion of the tailings disposal cell is August 1995. Water is found in two geologic units at the site: the Halgaito Shale Formation and the Honaker Trail Formation. The tailings rest on the Halgaito Shale, and water contained in that unit is a result of milling activities and, to a lesser extent, water released from the tailings from compaction during remedial action construction of the disposal cell. Water in the Halgaito Shale flows through fractures and discharges at seeps along nearby arroyos. Flow from the seeps will diminish as water drains from the unit. Ground water in the lower unit, the Honaker Trail Formation, is protected from contamination by an upward hydraulic gradient. There are no nearby water supply wells because of widespread poor background ground water quality and quantity, and the San Juan River shows no impacts from the site. This water sampling and analysis plan (WSAP) recommends sampling six seeps and one upgradient monitor well compared in the Honaker Trail Formation. Samples will be taken in April 1994 (representative of high group water levels) and September 1994 (representative of low ground water levels). Analyses will be performed on filtered samples for plume indicator parameters
Accelerating transient drainage from UMTRA Project tailings piles
International Nuclear Information System (INIS)
1990-09-01
The period between the completion of construction of the tailings disposal cell and the establishment of equilibrium moisture content and seepage conditions is considered to be the period of transient drainage. Transient drainage may be due to factors such as construction water, precipitation, or residual water from the milling process. Transient seepage rates usually exceed steady state seepage rates. If the transient seepage rate causes contaminant levels to exceed groundwater compliance standards, then an alternative groundwater compliance strategy or technical approach to reduce or mitigate the effects of the drainage must be adopted. This study examines methods to accelerate the transient drainage of soils and hence to remove excess pore water from tailings in UMTRA Project disposal cells. The technical and economic feasibility of possible methods is examined. In order to perform comparative economical analyses of the various methods, an example tailings pile is postulated. This pile is considered to be 300 meters by 300 meters by 10 meters in thickness
International Nuclear Information System (INIS)
1994-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QAIP is subordinate to the latest issue of the UMTRA Project TAC Quality Assurance Program Plan (QAPP). The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. The QAIP is authorized and approved by the TAC Project Manager and QA manager. The QA program is designed to use monitoring, audit, and surveillance functions as management tools to ensure that all Project organization activities are carried out in a manner that will protect public health and safety, promote the success of the UMTRA Project and meet or exceed contract requirements
DOE`s approach to groundwater compliance on the UMTRA project
Energy Technology Data Exchange (ETDEWEB)
Metzler, D. [Dept. of Energy, Washington, DC (United States); Gibb, J.P. [Geraghty and Miller, Inc. (United States); Glover, W.A. [Roy F. Weston, Inc. (United States)
1993-03-01
Compliance with the mandate of the Uranium Mill Tailings Radiation Control Act (UMTRCA) at Uranium Mill Tailings Remedial Action (UMTRA) Project sites requires implementation of a groundwater remedial action plan that meets the requirements of Subpart B of the US Environmental Protection Agency`s proposed groundwater protection standards (40 CFR 192). The UMTRA Groundwater Project will ensure that unacceptable current risk or potential risk to the public health, safety and the environment resulting from the groundwater contamination attributable to the UMTRA sites, is mitigated in a timely and cost-efficient manner. For each UMTRA processing site and vicinity property where contamination exists, a groundwater remedial action plan must be developed that identifies hazardous constituents and establishes acceptable concentration limits for the hazardous constituents as either (a) alternate concentration limits (ACL), (b) maximum concentration limits (MCLs), (c) supplemental standards, or (d) background groundwater quality levels. Project optimization is a strategy that will aggressively work within the current regulatory framework using all available options to meet regulatory requirements. This strategy is outlined within.
Policy and procedures for classification of Class III groundwater at UMTRA Project sites
International Nuclear Information System (INIS)
1989-03-01
The US Environmental Protection Agency (EPA) has recently proposed groundwater regulations for the US Department of Energy's )DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. These regulations allow the application of supplemental standards at UMTRA Project sites in specific situations. The designation of groundwater as Class III permits the application of supplemental standards. This document discusses a final UMTRA Project policy and procedures for identifying Class III groundwater, including identification of a review area, definition of water quality, quantification of aquifer yield, and identification of methods reasonably employed for public water supply systems. These items, either individually or collectively, need to be investigated in order to determine if groundwaters at UMTRA Project sites are Class III. This document provides a framework for the DOE to determine Class III groundwaters
UMTRA project water sampling and analysis plan, Tuba City, Arizona
International Nuclear Information System (INIS)
1996-02-01
Planned, routine ground water sampling activities at the U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site in Tuba City, Arizona, are described in the following sections of this water sampling and analysis plan (WSAP). This plan identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the stations routinely monitored at the site. The ground water data are used for site characterization and risk assessment. The regulatory basis for routine ground water monitoring at UMTRA Project sites is derived from the U.S. Environmental Protection Agency (EPA) regulations in 40 CFR Part 192 (1994) and the final EPA standards of 1995 (60 FR 2854). Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), and the most effective technical approach for the site
UMTRA project water sampling and analysis plan, Naturita, Colorado
International Nuclear Information System (INIS)
1994-04-01
Surface remedial action is scheduled to begin at the Naturita UMTRA Project processing site in the spring of 1994. No water sampling was performed during 1993 at either the Naturita processing site (NAT-01) or the Dry Flats disposal site (NAT-12). Results of previous water sampling at the Naturita processing site indicate that ground water in the alluvium is contaminated as a result of uranium processing activities. Baseline ground water conditions have been established in the uppermost aquifer at the Dry Flats disposal site. Water sampling activities scheduled for April 1994 include preconstruction sampling of selected monitor wells at the processing site, surface water sampling of the San Miguel River, sampling of several springs/seeps in the vicinity of the disposal site, and sampling of two monitor wells in Coke Oven Valley. The monitor well locations provide sampling points to characterize ground water quality and flow conditions in the vicinity of the sites. The list of analytes has been updated to reflect constituents related to uranium processing activities and the parameters needed for geochemical evaluation. Water sampling will be conducted annually at minimum during the period of construction activities
International Nuclear Information System (INIS)
1995-11-01
This document contains the Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project. The QAIP outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QA program is designed to use monitoring, audit, and surveillance activities as management tools to ensure that UMTRA Project activities are carried out in amanner to protect public health and safety, promote the success of the UMTRA Project, and meet or exceed contract requirements
UMTRA Project water sampling and analysis plan, Durango, Colorado. Revision 1
International Nuclear Information System (INIS)
1995-09-01
Planned, routine ground water sampling activities at the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site in Durango, Colorado, are described in this water sampling and analysis plan. The plan identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the routine monitoring stations at the site. The ground water data are used to characterize the site ground water compliance strategies and to monitor contaminants of potential concern identified in the baseline risk assessment (DOE, 1995a). Regulatory basis for routine ground water monitoring at UMTRA Project sites is derived from the US EPA regulations in 40 CFR Part 192 (1994) and EPA standards of 1995 (60 FR 2854). Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), the Technical Approach Document (TAD) (DOE, 1989), and the most effective technical approach for the site
Long-term surveillance plan for the Lowman, Idaho, disposal site
International Nuclear Information System (INIS)
1993-09-01
The long-term surveillance plan (LTSP) for the Lowman, Idaho, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lowman disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This preliminary final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. The LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and describes, in detail, how the long-term care of the disposal site will be carried out through the UMTRA Project long-term surveillance program. The Lowman, Idaho, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program, (DOE, 1992)
Planning risk communication for UMTRA project groundwater restoration
Energy Technology Data Exchange (ETDEWEB)
Hundertmark, Charles [Jacobs Engineering Group Inc. and University of Phoenix (United States); Hoopes, Jack [Jacobs Engineering Group Inc. (United States); Flowers, Len [Roy F. Weston Company (United States); Jackson, David G [U.S. Department of Energy (United States)
1992-07-01
The U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is entering a new phase in which groundwater contamination will become a growing focus as surface remedial action draws toward completion. Planning for risk communication associated with the groundwater project will be a major factor in the successful initiation of the program. (author)
Planning risk communication for UMTRA project groundwater restoration
International Nuclear Information System (INIS)
Hundertmark, Charles; Hoopes, Jack; Flowers, Len; Jackson, David G.
1992-01-01
The U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is entering a new phase in which groundwater contamination will become a growing focus as surface remedial action draws toward completion. Planning for risk communication associated with the groundwater project will be a major factor in the successful initiation of the program. (author)
Long-term surveillance plan for the Maybell, Colorado Disposal Site
International Nuclear Information System (INIS)
1997-09-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE's determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03
Long-term surveillance plan for the Gunnison, Colorado disposal site
International Nuclear Information System (INIS)
1996-04-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03
Long-term surveillance plan for the Gunnison, Colorado, disposal site
International Nuclear Information System (INIS)
1997-04-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03
Long-term surveillance plan for the Gunnison, Colorado disposal site
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-04-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.
Long-term surveillance plan for the Gunnison, Colorado, disposal site
Energy Technology Data Exchange (ETDEWEB)
NONE
1997-04-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.
Long-term surveillance plan for the Gunnison, Colorado, disposal site
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-05-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.
Long-term surveillance plan for the Gunnison, Colorado, disposal site
International Nuclear Information System (INIS)
1996-05-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03
Long-term surveillance plan for the Gunnison, Colorado disposal site. Revision 2
International Nuclear Information System (INIS)
1997-02-01
This long-term surveillance plan (LTSP) describes the US Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Gunnison disposal site performs as designed. The program is based on two distinct activities: (1) site inspections to identify threats to disposal cell integrity, and (2) ground water monitoring to demonstrate disposal cell performance
Long-term surveillance plan for the Gunnison, Colorado, disposal site
International Nuclear Information System (INIS)
1996-05-01
This long-term surveillance plan (LTSP) describes the US Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Gunnison disposal site in Gunnison County, Colorado. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment.For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Gunnison disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Gunnison site and the NRC formally accepts this LTSP
UMTRA Project water sampling and analysis plan, Grand Junction, Colorado. Revision 1, Version 6
International Nuclear Information System (INIS)
1995-09-01
This water sampling and analysis plan describes the planned, routine ground water sampling activities at the Grand Junction US DOE Uranium Mill Tailings Remedial Action (UMTRA) Project site (GRJ-01) in Grand Junction, Colorado, and at the Cheney Disposal Site (GRJ-03) near Grand Junction. The plan identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequencies for the routine monitoring stations at the sites. Regulatory basis is in the US EPA regulations in 40 CFR Part 192 (1994) and EPA ground water quality standards of 1995 (60 FR 2854). This plan summarizes results of past water sampling activities, details water sampling activities planned for the next 2 years, and projects sampling activities for the next 5 years
Critical management issues for the Uranium Mill Tailings Remedial Action (UMTRA) Project
International Nuclear Information System (INIS)
Themelis, J.G.; Krishnan, K.R.
1985-01-01
The Uranium Mill Tailings Radiation Control Act of 1978 (PL95-604) authorized the Secretary of Energy to enter into cooperative agreements with certain states and Indian Tribes to clean up 24 inactive uranium mill tailing sites and associated vicinity properties. The Uranium Mill Tailings Remedial Action (UMTRA) Project includes the three Federal agencies (EPA, DOE, and NRC), eleven state, Indian Tribes, and at least four major contractors. The UMTRA Project extends over a period of ten years. The standards for the Project require a design life of 1000 years with a minimum performance period of 200 years. This paper discusses the critical management issues in dealing with the UMTRA Project and identifies the development of solutions for many of those issues. The highlights to date are promulgation of EPA standards, continued support from Congress and participating states and Indian Tribes, significant leadership shown at all levels, establishment of credibility with the public, and continued motivation of the team. The challenge for tomorrow is making certain NRC will license the sites and maintaining the high level of coordination exhibited to date to assure Project completion on schedule
International Nuclear Information System (INIS)
1994-04-01
Under the Uranium Mill Tailings Remedial Action (UMTRA) Project, the U.S. Department of Energy (DOE) is cleaning up contamination to protect human health and the environment at 24 inactive uranium processing sites located in 10 states. Five of the sites are either on or near Native American lands. The UMTRA Project is divided into two projects: Surface and Ground Water. On November 18, 1992, the DOE issued a notice of intent (57 FR 54374, 1992) to prepare a programmatic environmental impact statement (PEIS) for the UMTRA Ground Water Project. The PEIS will result in a record of decision that will determine how the UMTRA Ground Water Project will address ground water contamination resulting from milling operations at the UMTRA Project processing sites. DOE regulations (10 CFR section 1021.312) require that an implementation plan be prepared to provide guidance for preparing a PEIS and to record the results of the scoping process. This implementation plan describes and records the results of the PEIS scoping process; summarizes comments received and their disposition; describes the purpose of and need for agency action, the proposed action, and alternatives; lists alternatives considered and eliminated from review; identifies cooperating agencies, their roles, and responsibilities; provides a draft PEIS outline, which includes the planned PEIS scope and content (Attachment A); and provides a schedule for the PEIS process. This plan will be placed in the UMTRA Project libraries listed in Attachment B. The PEIS will identify and evaluate the potential impacts associated with alternatives for conducting the UMTRA Ground Water Project. The PEIS will not assess site-specific impacts; site-specific impacts must be analyzed in separate National Environmental Policy Act (NEPA) documents that will tier off the PEIS. This tiering process will streamline the preparation of site-specific NEPA documents
UMTRA Project water sampling and analysis plan, Belfield and Bowman, North Dakota
International Nuclear Information System (INIS)
1994-08-01
Surface remedial action is scheduled to begin at the Belfield and Bowman Uranium Mill Tailings Remedial Action (UMTRA) Project sites in the spring of 1996. Water sampling was conducted in 1993 at both the Belfield processing site and the Bowman processing/disposal site. Results of the sampling at both sites indicate that ground water conditions have remained relatively stable over time. Water sampling activities are not scheduled for 1994 because ground water conditions at the two sites are relatively stable, the 1993 sampling was comprehensive, and surface remediation activities are not scheduled to start until 1996. The next water sampling event is scheduled before the start of remedial activities and will include sampling selected monitor wells at both sites and several domestic wells in the vicinity
DECHEM: A remedial planning tool for metallic contaminants in soil at UMTRA Project sites
International Nuclear Information System (INIS)
1989-03-01
The DECHEM (DEcontamination of CHEMicals) method was developed for the Uranium Mill Tailings Remedial Action (UMTRA) Project to guide characterization and remedial planning for metals contamination in soils. This is necessary because non-radiological hazardous constituents may be more mobile than radium-226 (Ra-226), and hence may migrate more deeply into subpile soils (beneath tailings that are to be relocated) or into adjacent contaminated soils at UMTRA Project sites. The result is that remedial action to the Ra-226 excavation limit, as specified in the US Environmental Protection Agency (EPA) standards, may not adequately remove hazardous non-radiological contamination. Unmitigated, these contaminants in soil may cause health risks because of their presence in resuspended particles, their uptake by crops or fodder their seepage into aquifers used for drinking water or other possible exposure pathways. The DECHEM method was developed in response to the need for advanced planning for the remediation of chemical contaminants at UMTRA Project sites, and includes the following elements: Establishment of acceptable exposure rates for humans to chemicals, based on EPA guidelines or other toxicological literature. Modeling of chemical migration through environmental pathways from a remediated UMTRA Project site to humans. Determination of allowable residual concentrations (i.e., cleanup guidelines) for chemicals in soils that results in doses to humans that are below established acceptable exposure rates. The initial development and application of the DECHEM method has focused upon hazardous metallic contaminants such as arsenic, lead, molybdenum, and selenium, which are known to occur in elevated concentrations at some UMTRA Project sites
Public information experience in the uranium mill tailings remedial action (UMTRA) project
International Nuclear Information System (INIS)
Meyer, H.R.; Skinner, D.J.
1986-01-01
To enhance public perception of the UMTRA Project remedial actions at some 23 sites in the US, an information program has been designed to demonstrate the small risk associated with the work in each community. An unusual aspect of this information program has involved a specific effort to educate listeners concerning the Health Physics terminology being used. The information program has been successful in reducing the level of public anxiety associated with UMTRA remedial action at the first Project site, and is currently being applied at several new sites
Uranium Mill Tailings Remedial Action Project 1993 Environmental Report
Energy Technology Data Exchange (ETDEWEB)
1994-10-01
This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.
Uranium Mill Tailings Remedial Action Project 1993 Environmental Report
International Nuclear Information System (INIS)
1994-10-01
This annual report documents the Uranium Mill Tailing Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1993, surface remedial action was complete at 10 of the 24 designated UMTRA Project processing sites. In 1993 the UMTRA Project office revised the UMTRA Project Environmental Protection Implementation Plan, as required by the US DOE. Because the UMTRA Project sites are in different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments
Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado
International Nuclear Information System (INIS)
1997-04-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney disposal site. The site is in Mesa County near Grand Junction, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects public health and safety and the environment. Before each disposal site may be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Cheney disposal site. The general license becomes effective when the NRC concurs with the DOE's determination that remedial action is complete and the NRC formally accepts this plan. This document describes the long-term surveillance program the DOE will implement to ensure that the Cheney disposal site performs as designed. The program is based on site inspections to identify potential threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03
UMTRA project water sampling and analysis plan, Monument Valley, Arizona
International Nuclear Information System (INIS)
1994-04-01
The Monument Valley Uranium Mill Tailings Remedial Action (UMTRA) Project site in Cane Valley is a former uranium mill that has undergone surface remediation in the form of tailings and contaminated materials removal. Contaminated materials from the Monument Valley (Arizona) UMTRA Project site have been transported to the Mexican Hat (Utah) UMTRA Project site for consolidation with the Mexican Hat tailings. Tailings removal was completed in February 1994. Three geologic units at the site contain water: the unconsolidated eolian and alluvial deposits (alluvial aquifer), the Shinarump Conglomerate (Shinarump Member), and the De Chelly Sandstone. Water quality analyses indicate the contaminant plume has migrated north of the site and is mainly in the alluvial aquifer. An upward hydraulic gradient in the De Chelly Sandstone provides some protection to that aquifer. This water sampling and analysis plan recommends sampling domestic wells, monitor wells, and surface water in April and September 1994. The purpose of sampling is to continue periodic monitoring for the surface program, evaluate changes to water quality for site characterization, and provide data for the baseline risk assessment. Samples taken in April will be representative of high ground water levels and samples taken in September will be representative of low ground water levels. Filtered and nonfiltered samples will be analyzed for plume indicator parameters and baseline risk assessment parameters
Development of the UMTRA Project Groundwater Environmental Impact Statement
International Nuclear Information System (INIS)
Burt, C.; Ulland, L.; Metzler, D.
1993-01-01
This paper discusses the development and preparation of the Programmatic Environmental Impact Statement (PEIS) for the Uranium Mill Tailings Remedial Action (UMTRA) Groundwater Restoration Project. The initiation of the scoping process and preparation of the PEIS began when the Notice of Intent (NOI) to prepare the PEIS was published in the Federal Register on November 18, 1992. However, planning for the PEIS began well before the publication of the NOI, with various aspects of the PEIS, such as the initial formulation of the alternatives and the format of the scoping process, being developed early on. During this preliminary planning phase, it became clear that the preparation of this PEIS posed some significant challenges while at the same time provided for significant opportunities. This paper will briefly summarize the UMTRA Project, discuss the major sections in the PEIS, and describe the challenges and opportunities that developed during the preparation of the PEIS
Long-term surveillance plan for the Rifle, Colorado, Disposal site
International Nuclear Information System (INIS)
1996-09-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Estes Gulch disposal site in Garfield County, Colorado. The U.S. Environmental Protection Agency (EPA) has developed regulations for the issuance of a general license by the U.S. Nuclear Regulatory Commission (NRC) for the custody and long-term care of UMTRA Project disposal Sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites, will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Estes Gulch disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the Estes Gulch site and the NRC formally accepts this LTSP
International Nuclear Information System (INIS)
Beranich, S.J.
1994-01-01
This report evaluates the impacts assessment and proposed mitigations provided in environmental documents concerning the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The projected impacts and proposed mitigations identified in UMTRA Project environmental documents were evaluated for two UMTRA Project sites. These sites are Gunnison and Durango, which are representative of currently active and inactive UMTRA Project sites, respectively. National Environmental Policy Act (NEPA) documentation was prepared for the remedial action at Durango and Gunnison as well as for the provision of an alternate water supply system at Gunnison. Additionally, environmental analysis was completed for mill site demolition Gunnison, and for a new road related to the Durango remedial action. The results in this report pertain only to the impact assessments prepared by the Regulatory Compliance staff as a part of the NEPA compliance requirements. Similarly, the mitigative measures documented are those that were identified during the NEPA process
International Nuclear Information System (INIS)
1991-01-01
The findings of the 1992 Colorado Economic Impact Study (CEIS) for the Uranium Mill Tailings Remedial Action (UMTRA) Project are outlined below. All dollar amounts used in the study are in year-of-expenditure dollars. The total funding requirement for the State of Colorado for the UMTRA Project is estimated to be $66.8 million, or 10 percent of the remedial action costs for the UMTRA Project in Colorado. The UMTRA Project will generate $487.5 million in gross labor income in Colorado between 1983 and 1996. This includes $54.4 million in state and local tax revenues and $41.2 million in federal individual income tax revenues. The net economic benefit of the UMTRA Project to Colorado is $355.1 million. For every dollar the State of Colorado invests in the UMTRA Project, it will realize $5.32 in gross labor income. The employment impact to the Western Slope region is significant. The UMTRA Project will create a total employment impact of 13,749 fulltime equivalents (FTES) spread over. a period of 13 years in seven site areas. Nearly 100 percent of the labor will be drawn from the local communities. The State of Colorado's Western Slope is anticipated to be minimally impacted by the phaseout of the UMTRA Project. Unlike industries that shut down operations without warning, the UMTRA Project workers, local government, and businesses know the schedule for completion and can consider and prepare for the impact of UMTRA Project conclusion. Further, because the majority of the work force is local, there has not been a significant investment in each community's infrastructure. Any small increases in the infrastructure will not be abandoned at the end of the UMTRA Project due to a marked increase in migration out of the local community
UMTRA project water sampling and analysis plan, Maybell, Colorado
International Nuclear Information System (INIS)
1994-06-01
This water sampling and analysis plan (WSAP) describes planned water sampling activities and provides the regulatory and technical basis for ground water sampling in 1994 at the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site in Maybell, Colorado. The WSAP identifies and justifies sampling locations, analytical parameters, and sampling frequencies at the site. The ground water data will be used for site characterization and risk assessment. The regulatory basis for the ground water and surface water monitoring activities is derived from the EPA regulations in 40 CFR Part 192 (1993) and the proposed EPA standards of 1987 (52 FR 36000). Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), the Technical Approach Document (TAD) (DOE, 1989), and the most effective technical approach for the site. This WSAP also includes a summary and the results of water sampling activities from 1989 through 1992 (no sampling was performed in 1993)
Site observational work plan for the UMTRA Project Site at Grand Junction, Colorado
International Nuclear Information System (INIS)
1996-03-01
The U.S. Department of Energy (DOE) has prepared this initial site observational work plan (SOWP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project site in Grand Junction, Colorado. This SOWP is one of the first UMTRA Ground Water Project documents developed to select a compliance strategy that meets the UMTRA ground water standards (40 CFR Part 192, as amended by 60 FR 2854) for the Grand Junction site. This SOWP applies information about the Grand Junction site to the compliance strategy selection framework developed in the UMTRA Ground Water Project draft programmatic environmental impact statement (PEIS). This risk-based, decision-making framework identifies the decision logic for selecting compliance strategies that could be used to meet the ground water standards. The DOE goal is to use the observational method to implement a cost-effective site strategy that complies with the ground water standards and protects human health and the environment. Based on an evaluation of the site characterization and risk assessment data available for the preparation of this SOWP, DOE proposes that the most likely compliance strategy for the Grand Junction site is no remediation based on the application of supplemental standards. This proposed strategy is based on a conceptual site model that indicates site-related contamination is confined to a limited-use aquifer as defined in the ground water standards
Long-term surveillance plan for the South Clive Disposal Site, Clive, Utah
International Nuclear Information System (INIS)
1996-03-01
This long-term surveillance plan (LTSP) describes the US Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project South Clive disposal site in Clive, Utah. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CRF Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the South Clive disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the South Clive site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the South Clive disposal site performs as designed. The program's primary activity is site inspections to identify threats to disposal cell integrity
Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah
International Nuclear Information System (INIS)
1997-05-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Mexican Hat, Utah, disposal site. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Mexican Hat disposal site. The general license becomes effective when the NRC concurs with the DOE's determination of completion of remedial action for the disposal site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Mexican Hat disposal site performs as designed. The program is based on two distinct types of activities: (1) site inspections to identify potential threats to disposal cell integrity, and (2) monitoring of selected seeps to observe changes in flow rates and water quality. The LTSP is based on the UMTRA Project long-term surveillance program guidance and meets the requirements of 10 CFR section 40.27(b) and 40 CFR section 192.03. 18 refs., 6 figs., 1 tab
Site observational work plan for the UMTRA project site at Shiprock, New Mexico
International Nuclear Information System (INIS)
1994-09-01
The site observational work plan (SOWP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project Site is the initial document for developing site-specific activities to achieve regulatory compliance in the UMTRA Ground Water Project. The regulatory framework used to select the proposed ground water compliance strategies is presented along with a discussion of the relationship of this SOWP to other UMTRA Ground Water Project programmatic documents. The Shiprock site consists of two, interconnected hydrogeologic systems: the terrace system and the floodplain system. Separate compliance strategies are proposed for these two systems. The compliance strategy for the terrace aquifer is no remediation with the application of supplemental standards based on classification of the terrace aquifer as having Class III (limited-use) ground water. The compliance strategy for the floodplain aquifer is active remediation using a subsurface biological barrier. These strategies were selected by applying site-specific data to the compliance framework developed in the UMTRA Ground Water programmatic environmental impact statement (PEIS) (DOE, 1994a). The site conceptual model indicates that milling-related contamination has impacted the ground water in the terrace and floodplain aquifers. Ground water occurs in both aquifers in alluvium and in fractures in the underlying Cretaceous age Mancos Shale. A mound of ground water related to fluids from the milling operations is thought to exist in the terrace aquifer below the area where settling ponds were in use during the mill operations. Most of the water occurring in the floodplain aquifer is from recharge from the San Juan River
Site observational work plan for the UMTRA Project site at Riverton, Wyoming
International Nuclear Information System (INIS)
1994-09-01
The site observational work plan (SOWP) for the Riverton, Wyoming, Uranium Mill Tailings Remedial Action (UMTRA) Project Site is the first document for the UMTRA Ground Water Project to address site-specific activities to meet compliance with the U.S. Environmental Protection Agency (EPA) proposed ground water standards (52 FR 36000 (1987)). In support of the activities the regulatory framework and drivers are presented along with a discussion of the relationship of this SOWP to other UMTRA Ground Water Project programmatic documents. A combination of the two compliance strategies that will be recommended for this site are no remediation with the application of alternate concentration levels (ACL) and natural flushing in conjunction with institutional controls. ACLs are to be applied to constituents that occur at concentrations above background levels but which are essential nutrients and occur within nutritional ranges and/or have very low toxicity and high dietary intake rates compared to the levels detected in the ground water. The essential premise of natural flushing is that ground water movement and natural attenuation processes will reduce the detected contamination to background levels within 1 00 years. These two recommended compliance strategies were evaluated by applying Riverton site-specific data to the compliance framework developed in the UMTRA Ground Water programmatic environmental impact statement. There are three aquifers beneath the site: a surficial unconfined aquifer, a middle semiconfined aquifer, and a deeper confined aquifer. The milling-related contamination at the site has affected both the surficial and semiconfined aquifers, although the leaky shale aquifers separating these units limits the downward migration of contamination into the semiconfined aquifer. A shale aquitard separates the semiconfined aquifer from the underlying confined aquifer which has not been contaminated by milling-related constituents
Economics, funding and the influence of politics on the UMTRA Project
International Nuclear Information System (INIS)
Hamp, S.
1993-01-01
This presentation discusses the factors contributing to the cost of the Uranium Mill Tailings Remediation Action Project and the political process involved in the funding. Topics covered include the following: Funding estimate and growth of estimate; Management actions during process; how the political process worked; cost of completed sites; economic benefit analysis of the project to Colorado; cost reduction program for the UMTRA project
UMTRA project water sampling and analysis plan, Falls City, Texas. Revision 1
International Nuclear Information System (INIS)
1995-09-01
Planned, routine ground water sampling activities at the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site near Falls City, Texas, are described in this water sampling and analysis plan (WSAP). The following plan identifies and justifies the sampling locations, analytical parameters, and sampling frequency for the routine monitoring stations at the site. The ground water data are used for site characterization and risk assessment. The regulatory basis for routine ground water monitoring at UMTRA Project sites is derived from the US Environmental Protection Agency (EPA) regulations in 40 CFR Part 192. Sampling procedures are guided by the UMTRA Project standard operating procedures (SOP) (JEG, n.d.), the Technical Approach Document (TAD) (DOE, 1989), and the most effective technical approach for the site. The Falls City site is in Karnes County, Texas, approximately 8 miles [13 kilometers southwest of the town of Falls City and 46 mi (74 km) southeast of San Antonio, Texas. Before surface remedial action, the tailings site consisted of two parcels. Parcel A consisted of the mill site, one mill building, five tailings piles, and one tailings pond south of Farm-to-Market (FM) Road 1344 and west of FM 791. A sixth tailings pile designated Parcel B was north of FM 791 and east of FM 1344
The UMTRA PEIS: A strategy for groundwater remediation
International Nuclear Information System (INIS)
Burt, C.; Ulland, L.; Weston, R.F.; Metzler, D.
1993-01-01
A programmatic environmental impact statement (PEIS) was initiated in 1992 for the uranium mill tailings remedial action (UMTRA) program. The PEIS kicked off the groundwater restoration phase of UMTRA, a project involving remediation of 24 sites in ten states and tribal lands contaminated with tailings from uranium mining and milling operations. The U.S. Department of Energy (DOE) agreed, in early 1992, that a PEIS was an appropriate strategy to comply with the National Environmental Policy Act (NEPA) for this second, groundwater phase of the project. This decision recognized that although a parallel effort was being undertaken in preparing a PEIS for DOE's Environmental Restoration/Waste Management (ER/WM) program, characteristics and the maturity of the UMTRA project made it more appropriate to prepare a separate PEIS. The ER/WM PEIS is intended to examine environmental restoration and waste management issues from a very broad perspective. For UMTRA, with surface remediation completed or well under way at 18 of the 24 sites, a more focused programmatic approach for groundwater restoration is more effective than including the UMTRA project within the ER/WM environmental impact statements. A separate document allows a more focused and detailed analysis necessary to efficiently tier site-specific environmental assessments for groundwater restoration at each of the 24 UMTRA former processing sites
Site Observational Work Plan for the UMTRA Project Site at Shiprock, New Mexico. Revision
International Nuclear Information System (INIS)
1995-07-01
The site observational work plan (SOWP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project Site is one of the first documents for developing an approach for achieving ground water compliance at the site. This SOWP applies Shiprock site information to a regulatory compliance framework, which identifies strategies for meeting ground water compliance at the site. The compliance framework was developed in the UMTRA ground water programmatic environmental impact statement
UMTRA project water sampling and analysis plan, Salt Lake City, Utah
International Nuclear Information System (INIS)
1994-06-01
Surface remedial action was completed at the Salt Lake City, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project site in the fall of 1987. Results of water sampling for the years 1992 to 1994 indicate that site-related ground water contamination occurs in the shallow unconfined aquifer (the uppermost aquifer). With respect to background ground water quality, contaminated ground water in the shallow, unconfined aquifer has elevated levels of chloride, sodium, sulfate, total dissolved solids, and uranium. No contamination associated with the former tailings pile occurs in levels exceeding background in ground water in the deeper confined aquifer. This document provides the water sampling and analysis plan for ground water monitoring at the former uranium processing site in Salt Lake City, Utah (otherwise known as the ''Vitro'' site, named after the Vitro Chemical Company that operated the mill). All contaminated materials removed from the processing site were relocated and stabilized in a disposal cell near Clive, Utah, some 85 miles west of the Vitro site (known as the ''Clive'' disposal site). No ground water monitoring is being performed at the Clive disposal site, since concurrence of the remedial action plan by the US Nuclear Regulatory Commission and completion of the disposal cell occurred before the US Environmental Protection Agency issued draft ground water standards in 1987 (52 FR 36000) for cleanup, stabilization, and control of residual radioactive materials at the disposal site. In addition, the likelihood of post-closure impact on the ground water is minimal to nonexistent, due to the naturally poor quality of the ground water. Water sampling activities planned for calendar year 1994 consist of sampling ground water from nine monitor wells to assess the migration of contamination within the shallow unconfined aquifer and sampling ground water from two existing monitor wells to assess ground water quality in the confined aquifer
Technical approach for the management of UMTRA ground water investigation-derived wastes
International Nuclear Information System (INIS)
1994-02-01
During characterization, remediation, or monitoring activities of the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project, ground water samples are collected to assess the extent and amount of waterborne contamination that might have come from the mill tailings. This sampling sometimes occurs in contaminated areas where ground water quality has been degraded. Ground water sampling activities may result in field-generated wastes that must be disposed of in a manner protective of human health and the environment. During ground water sampling, appropriate measures must be taken to dispose of presampling purge water and well development water that is pumped to flush out any newly constructed wells. Additionally, pumping tests may produce thousands of gallons of potentially contaminated ground water that must be properly managed. In addition to the liquid wastes, there is the potential for bringing contaminated soils to the ground surface during the drilling and installation of water wells in areas where the subsurface soils may be contaminated. These soils must be properly managed as well. This paper addresses the general technical approach that the UMTRA Project will follow in managing field-generated wastes from well drilling, development, sampling, and testing. It will provide guidance for the preparation of Technical Assistance Contractor (TAC) Standard Operating Procedures (SOP) for the management and disposal of field-generated wastes from ground water monitoring and remediation activities
International Nuclear Information System (INIS)
1993-07-01
The Uranium Mill Tailings Remedial Action (UMTRA) hydrochemistry facility is used to perform a limited but important set of services for the UMTRA Project. Routine services include support of field-based hydrological and geochemical operations and water sampling activities. Less commonly, the hydrology and geochemistry staff undertake special studies and site characterization studies at this facility. It is also used to train hydrologists, geochemists, and groundwater sampling crews. A review of this Quality Assurance Project Plan (QAPP) shall be accomplished once each calendar year. This review will be targeted to be accomplished not sooner than 6 months and not later than 18 months after the last review
Site observational work plan for the UMTRA Project site at Falls City, Texas
International Nuclear Information System (INIS)
1995-06-01
Produced by the US Department of Energy (DOE), this site observational work plan (SOWP) will be used to determine site-specific activities to comply with the US Environmental Protection Agency (EPA) ground water standards at this Uranium Mill Tailings Remedial Action (UMTRA) Project site. The purpose of the SOWP is to recommend a site-specific ground water compliance strategy at the Falls City UMTRA Project site. The Falls City SOWP presents a comprehensive summary of site hydrogeological data, delineates a conceptual model of the aquifer system, and discusses the origins of milling-related ground water contamination. It also defines the magnitude of ground water contamination, potential environmental and health risks associated with ground water contamination and data gaps, and targets a proposed compliance strategy
Long-term surveillance plan for the Shiprock Disposal site, Shiprock, New Mexico
International Nuclear Information System (INIS)
1994-09-01
The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents the land ownership interests and details how the long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Supplement to the UMTRA project water sampling and analysis plan, Slick Rock, Colorado
International Nuclear Information System (INIS)
1995-09-01
The water sampling and analysis plan (WSAP) provides the regulatory and technical basis for ground water and surface water sampling at the Uranium Mill Tailings Remedial Action (UMTRA) Project Union Carbide (UC) and North Continent (NC) processing sites and the Burro Canyon disposal site near Slick Rock, Colorado. The initial WSAP was finalized in August 1994 and will be completely revised in accordance with the WSAP guidance document (DOE, 1995) in late 1996. This version supplements the initial WSAP, reflects only minor changes in sampling that occurred in 1995, covers sampling scheduled for early 1996, and provides a preliminary projection of the next 5 years of sampling and monitoring activities. Once surface remedial action is completed at the former processing sites, additional and more detailed hydrogeologic characterization may be needed to develop the Ground Water Program conceptual ground water model and proposed compliance strategy. In addition, background ground water quality needs to be clearly defined to ensure that the baseline risk assessment accurately estimated risks from the contaminants of potential concern in contaminated ground water at the UC and NC sites
International Nuclear Information System (INIS)
1992-06-01
This report provides the basis for the US Department of Energy's (DOE) request to discontinue neutron moisture monitoring (NMM) at the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) disposal cell and decommission the neutron access holes. After 3 years of monitoring the disposal cell, the DOE has determined that the NMM method is not suitable for determining changes in moisture content in the disposal cell. Existing tailings moisture contents in the disposal cell result in a low seepage flux. The combination of a low seepage flux and geochemical retardation by foundation materials underneath the disposal cell ensures that the proposed US Environmental Protection Agency (EPA) groundwater protection standards will not be exceeded within the design life of the disposal cell. To assess the effectiveness of the NMM method for monitoring moisture contents In the disposal cell at Green River, the DOE subsequently conducted a field study and a review of historical and new literature. The literature review allowed the DOE to identify performance criteria for the NMM method. Findings of these studies suggest that: The NMM method is not sensitive to the low moisture contents found in the disposal cell.; there is an insufficient range of moisture contents in the disposal cell to develop a field calibration curve relating moisture content to neutron counts; it is not possible to collect NMM data from the disposal cell that meet data quality objectives for precision and accuracy developed from performance criteria described in the literature
UMTRA Project water sampling and analysis plan, Gunnison, Colorado: Revision 1
International Nuclear Information System (INIS)
1994-11-01
This water sampling and analysis plan summarizes the results of previous water sampling activities and the plan for future water sampling activities, in accordance with the Guidance Document for Preparing Sampling and Analysis Plans for UMTRA Sites. A buffer zone monitoring plan for the Dos Rios Subdivision is included as an appendix. The buffer zone monitoring plan was developed to ensure continued protection to the public from residual contamination. The buffer zone is beyond the area depicted as contaminated ground water due to former milling operations. Surface remedial action at the Gunnison Uranium Mill Tailings Remedial Action Project site began in 1992; completion is expected in 1995. Ground water and surface water will be sampled semiannually at the Gunnison processing site and disposal site. Results of previous water sampling at the Gunnison processing site indicate that ground water in the alluvium is contaminated by the former uranium processing activities. Background ground water conditions have been established in the uppermost aquifer at the Gunnison disposal site. The monitor well locations provide a representative distribution of sampling points to characterize ground water quality and ground water flow conditions in the vicinity of the sites. The list of analytes has been modified with time to reflect constituents that are related to uranium processing activities and the parameters needed for geochemical evaluation
International Nuclear Information System (INIS)
1990-10-01
This study is one of a number of special studies that have been conducted regarding various aspects of the Uranium Mill Tailings Remedial Action (UMTRA) Project. This special study was proposed following routine surveillance and maintenance surveys and observations reported in a special study of vegetative covers (DOE, 1988), in which plants were observed growing up through the rock erosion layer at recently completed disposal cells. Some of the plants observed were deep-rooted woody species, and questions concerning root intrusion into disposal cells and the need to control plant growth were raised. The special study discussed in this report was designed to address some of the ramifications of plant growth on disposal cells that have rock covers. The NRC has chosen rock covers over vegetative covers in the arid western United States because licenses cannot substantiate that the vegetative covers ''will be significantly greater than 30 percent and preferably 70 percent,'' which is the amount of ''vegetation required to reduce flow to a point of stability.'' The potential impacts of vegetation growing in rock covers are not addressed by the NRC (1990). The objectives, then, of this study were to determine the species of plants growing on two rock-covered disposal cells, study the rooting pattern of plants on these cells, and identify possible impacts of plant root penetration on these and other UMTRA Project rock-covered cells
Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas
International Nuclear Information System (INIS)
1995-06-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Falls City disposal site, Falls City, Texas, describes the surveillance activities for the disposal site. DOE will carry out these activities to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado
International Nuclear Information System (INIS)
1998-05-01
This long-term surveillance plan (LTSP) describes the US Department of Energy (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. The US Nuclear Regulatory Commission (NRC) developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Burro Canyon disposal cell. The general license becomes effective when the NRC concurs with the DOE's determination that remedial action is complete at the Burro Canyon disposal cell and the NRC formally accepts this LTSP. Attachment 1 contains the concurrence letters from NRC. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. Ground water monitoring will not be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low yield from the uppermost aquifer
UMTRA Surface Project management action process document: Final. Revision 2
International Nuclear Information System (INIS)
1996-06-01
Title 1 of the UMTRCA authorized the DOE to undertake remedial actions at these designed sites and associated vicinity properties (VP), which contain uranium mill tailings and other residual radioactive materials (RRM) derived from the processing sites. Title 2 of the UMTRCA addresses uranium mill sites that were licensed at the time the UMTRCA was enacted. Cleanup of these Title 2 sites is the responsibility of the licensees. The cleanup of the Title 1 sites has been split into two separate projects: the Surface Project, which deals with the mill buildings, tailings, and contaminated soils at the sites and VPs; and the Ground Water Project, which is limited to the contaminated ground water at the sites. This management action process (MAP) document discusses the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project. Since its inception through March 1996, the Surface Project (hereinafter called the Project) has cleaned up 16 of the 24 designated processing sites and approximately 5,000 VPs, reducing the risk to human health and the environment posed by the uranium mill tailings. Two of the 24 sites, Belfield and Bowman, North Dakota, will not be remediated at the request of the state, reducing the total number of sites to 22. By the start of FY1998, the remaining 6 processing sites and associated VPs will be cleaned up. The remedial action activities to be funded in FY1998 by the FY1998 budget request are remediation of the remaining Grand Junction, Colorado, VPs; closure of the Cheney disposal cell in Grand Junction, Colorado; and preparation of the completion reports for 4 completed sites
UMTRA Surface Project management action process document: Final. Revision 2
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-06-01
Title 1 of the UMTRCA authorized the DOE to undertake remedial actions at these designed sites and associated vicinity properties (VP), which contain uranium mill tailings and other residual radioactive materials (RRM) derived from the processing sites. Title 2 of the UMTRCA addresses uranium mill sites that were licensed at the time the UMTRCA was enacted. Cleanup of these Title 2 sites is the responsibility of the licensees. The cleanup of the Title 1 sites has been split into two separate projects: the Surface Project, which deals with the mill buildings, tailings, and contaminated soils at the sites and VPs; and the Ground Water Project, which is limited to the contaminated ground water at the sites. This management action process (MAP) document discusses the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project. Since its inception through March 1996, the Surface Project (hereinafter called the Project) has cleaned up 16 of the 24 designated processing sites and approximately 5,000 VPs, reducing the risk to human health and the environment posed by the uranium mill tailings. Two of the 24 sites, Belfield and Bowman, North Dakota, will not be remediated at the request of the state, reducing the total number of sites to 22. By the start of FY1998, the remaining 6 processing sites and associated VPs will be cleaned up. The remedial action activities to be funded in FY1998 by the FY1998 budget request are remediation of the remaining Grand Junction, Colorado, VPs; closure of the Cheney disposal cell in Grand Junction, Colorado; and preparation of the completion reports for 4 completed sites.
Long-term surveillance plan for the Shiprock disposal site, Shiprock, New Mexico
International Nuclear Information System (INIS)
1993-12-01
The long-term surveillance plan (LTSP) for the Shiprock, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Shiprock disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP is being submitted to the US Nuclear Regulatory Commission (NRC) as a requirement for issuance of a general license for custody and long-term care for the disposal site. The general license requires that the disposal cell be cared for in accordance with the provisions of this LTSP. This Shiprock, New Mexico, LTSP documents whether the land and interests are owned by the US or an Indian tribe and describes in detail the long-term care program through the UMTRA Project Office
Long-term surveillance plan for the Collins Ranch disposal site, Lakeview, Oregon
International Nuclear Information System (INIS)
1994-08-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Collins Ranch disposal site, Lakeview, Oregon, describes the surveillance activities for the disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado
Energy Technology Data Exchange (ETDEWEB)
1994-03-01
This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastes still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992).
Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado
International Nuclear Information System (INIS)
1994-03-01
This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastes still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992)
Site observational work plan for the UMTRA project site at Grand Junction, Colorado
International Nuclear Information System (INIS)
1996-01-01
This site observational work plan (SOWP) is one of the first Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project documents developed to select a compliance strategy that meets the UMTRA ground water standards for the Grand Junction site. This SOWP applies information about the Grand Junction site to the compliance strategy selection framework developed in the UMTRA Ground Water Project draft programmatic environmental impact statement. This risk-based, decision-making framework identifies the decision logic for selecting compliance strategies that could be used to meet the ground water standards. The US Department of Energy (DOE) goal is to implement a cost-effective site strategy that complies with the ground water standards and protects human health and the environment. Based on an evaluation of the site characterization and risk assessment data available for the preparation of this SOWP, DOE proposes that the most likely compliance strategy for the Grand Junction site is no remediation with the application of supplemental standards. This proposed strategy is based on a conceptual site model that indicates site-related contamination is confined to a limited-use aquifer as defined in the ground water standards. The conceptual model demonstrates that the uranium processing-related contamination at the site has affected the unconfined alluvial aquifer, but not the deeper confined aquifer
Long-term surveillance plan for the Mexican Hat Disposal Site, Mexican Hat, Utah
International Nuclear Information System (INIS)
1996-02-01
This plan describes the long-term surveillance activities for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Mexican Hat, Utah. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This long-term surveillance plan (LTSP) was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive material (RRM). This LTSP (based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program), documents the land ownership interests and details how the long-term care of the disposal site will be accomplished
Supplement to the UMTRA Project water sampling and analysis plan, Monument Valley, Arizona
International Nuclear Information System (INIS)
1995-09-01
This water sampling and analysis plan (WSAP) supplement supports the regulatory and technical basis for water sampling at the Riverton, Wyoming, Uranium Mill Tailings Remedial Action (UMTRA) Project site, as defined in the 1994 WSAP document for Riverton (DOE, 1994). Further, the supplement serves to confirm the Project's present understanding of the site relative to the hydrogeology and contaminant distribution as well as the intent to continue to use the sampling strategy as presented in the 1994 WSAP document for Riverton. Ground water and surface water monitoring activities are derived from the US Environmental Protection Agency regulations in 40 CFR Part 192 and 60 FR 2854. Sampling procedures are guided by the UMTRA Project standard operating procedures (JEG, n.d.), the Technical Approach Document (DOE, 1989), and the most effective technical approach for the site. Additional site-specific documents relevant to the Riverton site are the Riverton Baseline Risk Assessment (BLRA) (DOE, 1995a) and the Riverton Site Observational Work Plan (SOWP) (DOE, 1995b)
Long-term surveillance plan for the Green River, Utah, disposal site
International Nuclear Information System (INIS)
1997-06-01
The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The U.S. Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out. The Green River, Utah, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
UMTRA Surface Project management action process document. Final report: Revision 1
International Nuclear Information System (INIS)
1996-04-01
A critical mission of the US Department of Energy (DOE) is the planning, implementation, and completion of environmental restoration (ER) programs at facilities that were operated by or in support of the former Atomic Energy Commission (AEC) from the late 1940s into the 1970s. Among these facilities are the 24 former uranium mill sites designed in the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (42 USC section 7901 et seq.) Title 1 of the UMTRCA authorized the DOE to undertake remedial actions at these designated sites and associated vicinity properties (VP), which contain uranium mill tailings and other residual radioactive materials (RRM) derived from the processing sites. Title 2 of the UMTRCA addresses uranium mill sites that were licensed at the time the UMTRCA was enacted. Cleanup of these Title 2 sites is the responsibility of the licensees. The cleanup of the Title 1 sites has been split into two separate projects: the Surface Project, which deals with the mill buildings, tailings, and contaminated soils at the sites and VPs; and the Ground Water Project, which is limited to the contaminated ground water at the sites. This management action process (MAP) document discusses the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project only; a separate MAP document has been prepared for the UMTRA Ground Water Project
Uranium Mill Tailings Remedial Action Project 1994 environmental report
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-08-01
This annual report documents the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1994, surface remedial action was complete at 14 of the 24 designated UMTRA Project processing sites: Canonsburg, Pennsylvania; Durango, Colorado; Grand Junction, Colorado; Green River Utah, Lakeview, Oregon; Lowman, Idaho; Mexican Hat, Utah; Riverton, Wyoming; Salt Lake City, Utah; Falls City, Texas; Shiprock, New Mexico; Spook, Wyoming, Tuba City, Arizona; and Monument Valley, Arizona. Surface remedial action was ongoing at 5 sites: Ambrosia Lake, New Mexico; Naturita, Colorado; Gunnison, Colorado; and Rifle, Colorado (2 sites). Remedial action has not begun at the 5 remaining UMTRA Project sites that are in the planning stage. Belfield and Bowman, North Dakota; Maybell, Colorado; and Slick Rock, Colorado (2 sites). The ground water compliance phase of the UMTRA Project started in 1991. Because the UMTRA Project sites are.` different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments.
Uranium Mill Tailings Remedial Action Project 1994 environmental report
International Nuclear Information System (INIS)
1995-08-01
This annual report documents the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring and protection program. The UMTRA Project routinely monitors radiation, radioactive residual materials, and hazardous constituents at associated former uranium tailings processing sites and disposal sites. At the end of 1994, surface remedial action was complete at 14 of the 24 designated UMTRA Project processing sites: Canonsburg, Pennsylvania; Durango, Colorado; Grand Junction, Colorado; Green River Utah, Lakeview, Oregon; Lowman, Idaho; Mexican Hat, Utah; Riverton, Wyoming; Salt Lake City, Utah; Falls City, Texas; Shiprock, New Mexico; Spook, Wyoming, Tuba City, Arizona; and Monument Valley, Arizona. Surface remedial action was ongoing at 5 sites: Ambrosia Lake, New Mexico; Naturita, Colorado; Gunnison, Colorado; and Rifle, Colorado (2 sites). Remedial action has not begun at the 5 remaining UMTRA Project sites that are in the planning stage. Belfield and Bowman, North Dakota; Maybell, Colorado; and Slick Rock, Colorado (2 sites). The ground water compliance phase of the UMTRA Project started in 1991. Because the UMTRA Project sites are.' different stages of remedial action, the breadth of the UMTRA environmental protection program differs from site to site. In general, sites actively undergoing surface remedial action have the most comprehensive environmental programs for sampling media. At sites where surface remedial action is complete and at sites where remedial action has not yet begun, the environmental program consists primarily of surface water and ground water monitoring to support site characterization, baseline risk assessments, or disposal site performance assessments
Site observational work plan for the UMTRA Project site at Spook, Wyoming
International Nuclear Information System (INIS)
1995-05-01
The Spook, Wyoming, site observational work plan proposes site-specific activities to achieve compliance with Subpart B of 40 CFR Part 192 (1994) of the final US Environmental Protection Agency (EPA) ground water protection standards 60 FR 2854 (1995) at this Uranium Mill Tailing Remedial Action (UMTRA) Project site. This draft SOWP presents a comprehensive summary of existing site characterization data, a conceptual site model of the nature and extent of ground water contamination, exposure pathways, and potential impact to human health and the environment. Section 2.0 describes the requirements for meeting ground water standards at UMTRA Project sites. Section 3.0 defines past and current conditions, describes potential environmental and human health risks, and provides site-specific data that supports the selection of a proposed ground water compliance strategy. Section 4.0 provides the justification for selecting the proposed ground water compliance strategy based on the framework defined in the ground water programmatic environmental impact statement (PEIS)
Environmental management audit, Uranium Mill Tailings Remedial Action Project (UMTRA)
International Nuclear Information System (INIS)
1993-01-01
The Office of Environment, Safety and Health (EH) has established, as part of the internal oversight responsibilities within Department of Energy (DOE), a program within the Office of Environmental Audit (EH-24), to conduct environmental audits at DOE's operating facilities. This document contains the results of the Environmental Management Audit of the Uranium Mill Tailings Remedial Action (UMTRA) Project. This Environmental Management Audit was conducted by the DOE's Office of Environmental Audit from October 26 through November 6, 1992. The audit's objective is to advise the Secretary as to the adequacy of UMTRA's environmental programs, and management organization in ensuring environmental protection and compliance with Federal, state, and DOE environmental requirements. This Environmental Management Audit's scope was comprehensive and covered all areas of environmental management with the exception of environmental programs pertaining to the implementation of the requirements of the National Environmental Policy Act (NEPA), which is the responsibility of the DOE Headquarters Office of NEPA Oversight
International Nuclear Information System (INIS)
1995-09-01
A water sampling and analysis plan (WSAP) is prepared for each Uranium Mill Tailings Remedial Action (UMTRA) Project site to provide the rationale for routine ground water sampling at disposal sites and former processing sites. The WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the routine ground water monitoring stations at each site. This guidance document has been prepared by the Technical Assistance Contractor (TAC) for the US Department of Energy (DOE). Its purpose is to provide a consistent technical approach for sampling and monitoring activities performed under the WSAP and to provide a consistent format for the WSAP documents. It is designed for use by the TAC in preparing WSAPs and by the DOE, US Nuclear Regulatory Commission, state and tribal agencies, other regulatory agencies, and the public in evaluating the content of WSAPS
Recommendations for computer modeling codes to support the UMTRA groundwater restoration project
Energy Technology Data Exchange (ETDEWEB)
Tucker, M.D. [Sandia National Labs., Albuquerque, NM (United States); Khan, M.A. [IT Corp., Albuquerque, NM (United States)
1996-04-01
The Uranium Mill Tailings Remediation Action (UMTRA) Project is responsible for the assessment and remedial action at the 24 former uranium mill tailings sites located in the US. The surface restoration phase, which includes containment and stabilization of the abandoned uranium mill tailings piles, has a specific termination date and is nearing completion. Therefore, attention has now turned to the groundwater restoration phase, which began in 1991. Regulated constituents in groundwater whose concentrations or activities exceed maximum contaminant levels (MCLs) or background levels at one or more sites include, but are not limited to, uranium, selenium, arsenic, molybdenum, nitrate, gross alpha, radium-226 and radium-228. The purpose of this report is to recommend computer codes that can be used to assist the UMTRA groundwater restoration effort. The report includes a survey of applicable codes in each of the following areas: (1) groundwater flow and contaminant transport modeling codes, (2) hydrogeochemical modeling codes, (3) pump and treat optimization codes, and (4) decision support tools. Following the survey of the applicable codes, specific codes that can best meet the needs of the UMTRA groundwater restoration program in each of the four areas are recommended.
Recommendations for computer modeling codes to support the UMTRA groundwater restoration project
International Nuclear Information System (INIS)
Tucker, M.D.; Khan, M.A.
1996-04-01
The Uranium Mill Tailings Remediation Action (UMTRA) Project is responsible for the assessment and remedial action at the 24 former uranium mill tailings sites located in the US. The surface restoration phase, which includes containment and stabilization of the abandoned uranium mill tailings piles, has a specific termination date and is nearing completion. Therefore, attention has now turned to the groundwater restoration phase, which began in 1991. Regulated constituents in groundwater whose concentrations or activities exceed maximum contaminant levels (MCLs) or background levels at one or more sites include, but are not limited to, uranium, selenium, arsenic, molybdenum, nitrate, gross alpha, radium-226 and radium-228. The purpose of this report is to recommend computer codes that can be used to assist the UMTRA groundwater restoration effort. The report includes a survey of applicable codes in each of the following areas: (1) groundwater flow and contaminant transport modeling codes, (2) hydrogeochemical modeling codes, (3) pump and treat optimization codes, and (4) decision support tools. Following the survey of the applicable codes, specific codes that can best meet the needs of the UMTRA groundwater restoration program in each of the four areas are recommended
Long-term Surveillance Plan for the Falls City Disposal Site, Falls City, Texas. Revision 1
International Nuclear Information System (INIS)
1995-08-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Falls City disposal site, Falls City, Texas, describes the surveillance activities for the disposal site. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon
International Nuclear Information System (INIS)
1993-12-01
This long-term surveillance plan (LTSP) for the Lakeview, Oregon, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lakeview (Collins Ranch) disposal cell, which will be referred to as the Collins Ranch disposal cell throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and details how the long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Long-term surveillance plan for the Green River, Utah disposal site. Revision 1
International Nuclear Information System (INIS)
1994-08-01
The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out. The Green River, Utah, LTSP is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a)
Supplement to the UMTRA Project water sampling and analysis plan, Maybell, Colorado
International Nuclear Information System (INIS)
1995-09-01
This water sampling and analysis plan (WSAP) supplement supports the regulatory and technical basis for water sampling at the Maybell, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site, as defined in the 1994 WSAP document for Maybell (DOE, 1994a). Further, this supplement serves to confirm our present understanding of the site relative to the hydrogeology and contaminant distribution as well as our intention to continue to use the sampling strategy as presented in the 1994 WSAP document for Maybell. Ground water and surface water monitoring activities are derived from the US Environmental Protection Agency regulations in 40 CFR Part 192 (1994) and 60 CFR 2854 (1 995). Sampling procedures are guided by the UMTRA Project standard operating procedures (JEG, n.d.), the Technical Approach Document (DOE, 1989), and the most effective technical approach for the site. Additional site-specific documents relevant to the Maybell site are the Maybell Baseline Risk Assessment (currently in progress), the Maybell Remedial Action Plan (RAP) (DOE, 1994b), and the Maybell Environmental Assessment (DOE, 1995)
Status report groundwater: the challenge for UMTRA completion
International Nuclear Information System (INIS)
D'Antonio, J.R.
1988-01-01
UMTRA is working aggressively towards meeting the intent of the draft EPA Groundwater Protection Standards. Since September 1987, the major UMTRA thrust has been threefold: (1) perform special studies directed towards design enhancements; (2) provide design enhancements, where possible for projects under construction; and (3) evaluate the remaining sites under design for design enhancements under the proposed standards. At the time, the NRC has taken a very guarded approach towards approving proposed cover systems. UMTRA believes current cell designs will meet proposed standards. UMTRA is working closely with the NRC towards understanding the resolution of issues related to the acceptability of designs to meet the EPA groundwater standards. UMTRA met with NRC the week of October 17, 1988 to discuss results of recent special studies. Recent studies include: field moisture content validations of completed covers, soil/rock covers, rock durability, soil amendments, freeze-thaw, and erosion protection and constructability questions. When completed, UMTRA will issue final special study reports. Two of the above areas, freeze-thaw and rock durability, will be presented in the presentations which follow this one. Another of the special studies addressing design approaches to cell designs is presented in Session V
Supplement to the UMTRA Project water sampling and analysis plan, Mexican Hat, Utah
International Nuclear Information System (INIS)
1995-09-01
This water sampling and analysis plan (WSAP) supplement supports the regulatory and technical basis for water sampling at the Mexican Hat, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project site, as defined in the 1994 WSAP document for Mexican Hat (DOE, 1994). Further, the supplement serves to confirm our present understanding of the site relative to the hydrogeology and contaminant distribution as well as our intention to continue to use the sampling strategy as presented in the 1994 WSAP document for Mexican Hat. Ground water and surface water monitoring activities are derived from the US Environmental Protection Agency regulations in 40 CFR Part 192 (1991) and 60 FR 2854 (1995). Sampling procedures are guided by the UMTRA Project standard operating procedures (JEG, n.d.), the Technical Approach Document (DOE, 1989), and the most effective technical approach for the site. Additional site-specific documents relevant to the Mexican Hat site are the Mexican Hat Long-Term Surveillance Plan (currently in progress), and the Mexican Hat Site Observational Work Plan (currently in progress)
International Nuclear Information System (INIS)
1995-10-01
The final audit report for remedial action at the Mexican Hat, Utah, Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and QA remedial action close-out inspections performed by the US Department of Energy (DOE) and the Technical Assistance Contractor (TAC); on-site construction reviews (OSCR) performed by the US Nuclear Regulatory Commission (NRC); and a surveillance performed by the Navajo Nation. This report refers to remedial action activities performed at the Mexican Hat, Utah--Monument Valley, Arizona, Uranium Mill Tailings Remedial Action (UMTRA) Project sites
Long-Term Performance of Uranium Tailings Disposal Cells - 13340
International Nuclear Information System (INIS)
Bostick, Kent; Daniel, Anamary; Pill, Ken; Tachiev, Georgio; Noosai, Nantaporn; Villamizar, Viviana
2013-01-01
Recently, there has been interest in the performance and evolution of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell covers because some sites are not compliant with groundwater standards. Field observations of UMTRA disposal cells indicate that rock covers tend to become vegetated and that saturated conductivities in the upper portion of radon barriers may increase due to freeze/thaw cycles and biointrusion. This paper describes the results of modeling that addresses whether these potential changes and transient drainage of moisture in the tailings affect overall performance of the disposal cells. A numerical unsaturated/saturated 3-dimensional flow model was used to simulate whether increases in saturated conductivities in radon barriers with rock covers affect the overall performance of the disposal cells using field data from the Shiprock, NM, UMTRA site. A unique modeling approach allowed simulation with daily climatic conditions to determine changes in moisture and moisture flux from the disposal cell. Modeling results indicated that increases in the saturated conductivity at the top of radon barrier do not influence flux from the tailings with time because the tailings behave similar hydraulically to the radon barrier. The presence of a thin layer of low conductivity material anywhere in the cover or tailings restricts flux in the worst case to the saturated conductivity of that material. Where materials are unsaturated at depth within the radon barrier of tailings slimes, conductivities are typically less than 10 -8 centimeters per second. If the low conductivity layer is deep within the disposal cell, its saturated properties are less likely to change with time. The significance of this modeling is that operation and maintenance of the disposal cells can be minimized if they are allowed to progress to a natural condition with some vegetation and soil genesis. Because the covers and underlying tailings have a very low saturated
Long-Term Performance of Uranium Tailings Disposal Cells - 13340
Energy Technology Data Exchange (ETDEWEB)
Bostick, Kent; Daniel, Anamary; Pill, Ken [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States); Tachiev, Georgio; Noosai, Nantaporn; Villamizar, Viviana [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)
2013-07-01
Recently, there has been interest in the performance and evolution of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell covers because some sites are not compliant with groundwater standards. Field observations of UMTRA disposal cells indicate that rock covers tend to become vegetated and that saturated conductivities in the upper portion of radon barriers may increase due to freeze/thaw cycles and biointrusion. This paper describes the results of modeling that addresses whether these potential changes and transient drainage of moisture in the tailings affect overall performance of the disposal cells. A numerical unsaturated/saturated 3-dimensional flow model was used to simulate whether increases in saturated conductivities in radon barriers with rock covers affect the overall performance of the disposal cells using field data from the Shiprock, NM, UMTRA site. A unique modeling approach allowed simulation with daily climatic conditions to determine changes in moisture and moisture flux from the disposal cell. Modeling results indicated that increases in the saturated conductivity at the top of radon barrier do not influence flux from the tailings with time because the tailings behave similar hydraulically to the radon barrier. The presence of a thin layer of low conductivity material anywhere in the cover or tailings restricts flux in the worst case to the saturated conductivity of that material. Where materials are unsaturated at depth within the radon barrier of tailings slimes, conductivities are typically less than 10{sup -8} centimeters per second. If the low conductivity layer is deep within the disposal cell, its saturated properties are less likely to change with time. The significance of this modeling is that operation and maintenance of the disposal cells can be minimized if they are allowed to progress to a natural condition with some vegetation and soil genesis. Because the covers and underlying tailings have a very low saturated
International Nuclear Information System (INIS)
Hartmann, G.L.; Arp, S.; Hempill, H.
1993-01-01
At two uranium mill sites in Rifle, Colorado, the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is removing uranium mill tailings and contaminated subgrade soils. This remediation activity will result in the production of groundwater contaminated with uranium, heavy metals, ammonia, sulfates, and total dissolved solids (TDS). The initial remediation plan called for a wastewater treatment plant for removal of the uranium, heavy metals, and ammonia, with disposal of the treated water, which still includes the sulfates and TDSS, to the Colorado River. The National Pollutant Discharge Elimination (NPDES) permit issued by the Colorado Department of Health for the two Rifle sites contained more restrictive discharge limits than originally anticipated. During the detailed review of alternate treatment systems to meet these more restrictive limits, the proposed construction procedures were reviewed emphasizing the methods to minimize groundwater production to reduce the size of the water treatment facility, or to eliminate it entirely. It was determined that with changes to the excavation procedures and use of the contaminated groundwater for use in dust suppression at the disposal site, discharge to the river could be eliminated completely
UMTRA project water sampling and analysis plan, Old and New Rifle, Colorado
International Nuclear Information System (INIS)
1994-07-01
Surface remedial action at the Rifle, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site began in the spring of 1992. Results of water sampling at the Old and New Rifle processing sites for recent years indicate that ground water contamination occurs in the shallow unconfined alluvial aquifer (the uppermost aquifer) and less extensively in the underlying Wasatch Formation. Uranium and sulfate continue to exceed background ground water concentrations and/or maximum concentration limits at and downgradient from the former processing sites. These constituents provide the best indication of changes in contaminant distribution. Contamination in the uppermost (alluvial) aquifer at New Rifle extends a minimum of approximately 5000 feet (ft) (1,524 meters [m]) downgradient. At Old Rifle, the extent of contamination in the alluvial aquifer is much less (a minimum of approximately 1,000 ft [305 m]), partially due to differences in hydrologic regime. For example, the Old Rifle site lies in a relatively narrow alluvial floodplain; the New Rifle site lies in a broad floodplain. Data gathering for the Rifle baseline risk assessment is under way. The purpose of this effort is to determine with greater precision the background ground water quality and extent of ground water contamination at the processing sites. Historical surface water quality indicates that the Colorado River has not been affected by uranium processing activities. No compliance monitoring of the Estes Gulch disposal cell has been proposed, because ground water in the underlying Wasatch Formation is limited use (Class 111) ground water and because the disposal cell is hydrogeologically isolated from the uppermost aquifer
Energy Technology Data Exchange (ETDEWEB)
1994-12-01
The Gunnison, Colorado, abandoned uranium mill site is one site being cleaned up by the DOE under UMTRCA authority. This site`s contaminated material is being transported to a disposal site on US Bureau of Land Management (BLM) land east of Gunnison. Remedial action activities have temporarily disturbed 0.8 acre (ac) (0.3 hectares [ha]) of wetlands and permanently eliminated 4.3 ac (1.7 ha). As required by the Clean Water Act, the US Army Corps of Engineers (USACE) prepared a Section 404 Permit that addresses the loss of wetlands as a result of remedial action at the Gunnison UMTRA Project site. The 404 permit includes this report as an attachment and it describes the wetland mitigation and monitoring plan. The DOE formulated this plan in consultation with the BLM and the USACE. This report represents a revised version of the mitigation and monitoring plan (DOE, 1992b).
International Nuclear Information System (INIS)
1994-12-01
The Gunnison, Colorado, abandoned uranium mill site is one site being cleaned up by the DOE under UMTRCA authority. This site's contaminated material is being transported to a disposal site on US Bureau of Land Management (BLM) land east of Gunnison. Remedial action activities have temporarily disturbed 0.8 acre (ac) (0.3 hectares [ha]) of wetlands and permanently eliminated 4.3 ac (1.7 ha). As required by the Clean Water Act, the US Army Corps of Engineers (USACE) prepared a Section 404 Permit that addresses the loss of wetlands as a result of remedial action at the Gunnison UMTRA Project site. The 404 permit includes this report as an attachment and it describes the wetland mitigation and monitoring plan. The DOE formulated this plan in consultation with the BLM and the USACE. This report represents a revised version of the mitigation and monitoring plan (DOE, 1992b)
UMTRA Project water sampling and analysis plan: Canonsburg and Burrell, Pennsylvania
International Nuclear Information System (INIS)
1994-03-01
Surface remedial action was completed at the Canonsburg and Burrell UMTRA Project sites in southwestern Pennsylvania in 1985 and 1987, respectively. Results of 1993 water sampling indicate ground water flow conditions and ground water quality at both sites have remained relatively consistent with time. Uranium concentrations in ground water continue to exceed the maximum concentration limit (MCL) at the Canonsburg site; no MCLs are exceeded in ground water at the Burrell site. Surface water quality shows no evidence of impact from the sites
Hydrologic site characterization - the UMTRA project approach
International Nuclear Information System (INIS)
Binkman, J.E.; Hoopes, J.R.
1985-01-01
The United States Environmental Protection Agency (EPA) Standards (40 CFR 192) require site characterization of the hydrogeologic regime at and around each Uranium Mill Tailings Remedial Action (UMTRA) Project site. Also, ''judgements on the possible need for remedial or protective actions for groundwater aquifers should be guided by relevant considerations described in EPA's hazardous waste management system (47 CFR 32274).'' To address those two sets of rules and regulations, a generic approach is being developed. Fourteen primary issues were determined. These issues can be grouped into those that can be determined by documentation of available information and present conditions, those that require extensive field investigations and those that require some form of predictive modeling. To address the various issues requires an integrated effort of hydrogeologists, environmental engineers or scientists and health physicists. In this paper, the approach to the resolution of these fourteen issues is described briefly
International Nuclear Information System (INIS)
Miller, M.L.; Hylko, J.M.; Cornish, R.E.
1995-01-01
The passage of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, established the regulatory framework, under which the US EPA charged with developing standards for the cleanup and disposal of tailings at 24 designated inactive uranium processing sites located in 10 states. 40 CFR 192.12 requires that the concentration of Ra-226 in land averaged over any area of 100 square meters shall not exceed the background level by more than 5 pCi/g, averaged over the first 15 cm of soil below the surface, 15 pCi/g, averaged over 15-cm-thick layers of soils more than 15 cm below the surface. However, Th-230 is not specifically addressed by the EPA in 40 CFR 192.12, which naturally decays with a half-life of 77,000 years to form Ra-226. Consequently, the cleanup of the initial Ra-226 contamination according to the standards will not necessarily mitigate against the eventual ingrowth of residual Ra-226 with time, due to the radioactive decay of residual Th-230. Therefore, to direct the excavation of residual Th-230, four generic protocols are being used at Uranium Mill Tailings Remedial Action (UMTRA) Project sites, as follows: Determining the allowable remaining concentration of Th-230 in surface and subsurface soils; Encountering Th-230 contamination in the unsaturated subsurface soil; Encountering Th-230 contamination in the saturated zone; and Verification sampling. The four generic protocols, developed in conjunction with the supplemental standards provision, ensure protection of the general public by reducing exposures to levels that are As Low As Reasonably Achievable, while considering practical measures necessary to excavate Th-230 under conditions encountered at the UMTRA Project site
Status of the ground water flow model for the UMTRA Project, Shiprock, New Mexico, site
International Nuclear Information System (INIS)
1995-01-01
A two-dimensional numerical model was constructed for the alluvial aquifer in the area of the Uranium Mill Tailings Remedial Action (UMTRA) Project Shiprock, New Mexico, site. This model was used to investigate the effects of various hydrologic parameters on the evolution of the ground water flow field. Results of the model are useful for defining uncertainties in the site conceptual model and suggesting data collection efforts to reduce these uncertainties. The computer code MODFLOW was used to simulate the two-dimensional flow of ground water in the alluvium. The escarpment was represented as a no-flow boundary. The San Juan River was represented with the MODFLOW river package. A uniform hydraulic conductivity distribution with the value estimated by the UMTRA Project Technical Assistance Contractor (TAC) and a uniform recharge distribution was used. Infiltration from the flowing artesian well was represented using the well package. The ground water flow model was calibrated to ground water levels observed in April 1993. Inspection of hydrographs shows that these levels are representative of typical conditions at the site
International Nuclear Information System (INIS)
1996-09-01
This report summarizes the results of cultural resource activities conducted by the U.S. Department of Energy (DOE) at Uranium Mill Tailings Remedial Action (UMTRA) Project sites in Colorado for the period of October 1, 1995 through September 30, 1996. The inactive uranium mill tailings sites in Colorado are at Durango, Grand Junction, Gunnison, Maybell, Naturita, Rifle, and Slick Rock. On December 6, 1984, the DOE, the Advisory Council on Historic Preservation, and the Colorado State Historic Preservation Officer (SHPO) entered into a programmatic memorandum of understanding (PMOU). This PMOU requires the DOE to fulfillment of its obligations under various state and federal regulations for the protection and preservation of cultural resources. This report provides the state of Colorado with an annual report on the cultural resource activities performed for all UMTRA Project sites in Colorado. Due to the completion of surface activities at the UMTRA Project sites, this will be the last annual report to the state of Colorado. Cultural resources activities subsequent to this report will be reported to the state through site-specific correspondence
International Nuclear Information System (INIS)
1994-11-01
This report summarizes the results of cultural resource activities conducted by the U.S. Department of Energy (DOE) at Uranium Mill Tailings Remedial Action (UMTRA) Project sites in Colorado for the period of October 1, 1993, through September 30, 1994. The UMTRA Project is a cooperative (state and federal) program mandated by the Uranium Mill Tailings Radiation Control Act, Public Law 95-604 (42 USC section 7901 et seq.). This law requires the timely cleanup of 24 inactive uranium mill tailings sites throughout the United States. Nine of these inactive uranium mill tailings sites are in Colorado at Durango, Grand Junction, Gunnison, Maybell, Naturita, Rifle, and Slick Rock. On December 6, 1984, the DOE, Advisory Council on Historic Preservation, and Colorado State Historic Preservation Officer (SHPO) entered into a programmatic memorandum of agreement (PMOA) (DOE, 1984). This PMOA specifies requirements for the DOE's fulfillment of its obligations under various state and federal regulations for the protection and preservation of cultural resources. This report fulfills the requirement for the DOE to provide the state of Colorado with an annual report on the cultural resource activities performed for all of the UMTRA Project sites in Colorado. This report is organized by UMTRA Project site. For each site, the general remedial action activities and cultural resource activities performed during the period of record are summarized. When known, the DOE's plans for future cultural resource activities at the site are summarized
Risk assessment and reliability for low level radioactive waste disposal
International Nuclear Information System (INIS)
Gregory, P.O.; Jones, G.A.
1986-01-01
The reliability of critical design features at low-level radioactive waste disposal facilities is a major concern in the licensing of these structures. To date, no systematic methodology has been adopted to evaluate the geotechnical reliability of Uranium Mill Tailings Remedial Action (UMTRA) disposal facilities currently being designed and/or constructed. This paper discusses and critiques the deterministic methods currently used to evaluate UMTRA reliability. Because deterministic methods may not be applicable in some cases because of the unusually long design life of UMTRA facilities, it is proposed that a probabilistic risk assessment-based methodology be used as a secondary method to aid in the evaluating of geotechnical reliability of critical items. Similar methodologies have proven successful in evaluating the reliability of a variety of conventional earth structures. In this paper, an ''acceptable'' level of risk for UMTRA facilities is developed, an evaluation method is presented, and two example applications of the proposed methodology are provided for a generic UMTRA disposal facility. The proposed technique is shown to be a simple method which might be used to aid in reliability evaluations on a selective basis. Finally, other possible applications and the limitations of the proposed methodology are discussed
Site observational work plan for the UMTRA Project Site at Riverton, Wyoming. Revision 3/95
International Nuclear Information System (INIS)
1995-03-01
Ground water compliance for the Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Riverton, Wyoming, site, is governed by the Uranium Mill Tailings Radiation Control Act and the US Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. The compliance strategy proposed for this site is natural flushing in conjunction with institutional controls. The essential premise of natural flushing is that ground water movement and natural attenuation processes will reduce the detected contamination to background levels or alternate concentration limits that do not pose a risk to human health or the environment within 100 years. This document contains the following sections. Section 2.0 of this SOWP describes the requirements for meeting standards at UMTRA Project sites. Section 3.0 provides site-specific data and the related conceptual model. Section 4.0 provides the justification for the recommended ground water compliance strategy for the Riverton site. Section 5.0 provides the justification and process for collection and assessment of additional required data. Section 6.0 provides a list of the references cited. The appendixes include data on monitor wells and lithography, ground water, surface water, and sediment quality
Transient drainage summary report
International Nuclear Information System (INIS)
1996-09-01
This report summarizes the history of transient drainage issues on the Uranium Mill Tailings Remedial Action (UMTRA) Project. It defines and describes the UMTRA Project disposal cell transient drainage process and chronicles UMTRA Project treatment of the transient drainage phenomenon. Section 4.0 includes a conceptual cross section of each UMTRA Project disposal site and summarizes design and construction information, the ground water protection strategy, and the potential for transient drainage
Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado. Revision 1
International Nuclear Information System (INIS)
1995-11-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Act on (UMTRA) Project Bodo Canyon disposal site at Durango, Colorado, describes the surveillance activities for the disposal site. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal call continues to function as designed This LTSP was prepared as a requirement for DOE acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) from processing uranium ore. This LTSP documents that the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE's Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a). Following the introduction, contents of this report include the following: site final condition; site drawings and photographs; permanent site surveillance features; ground water monitoring; annual site inspections; unscheduled inspections; custodial maintenance; corrective action; record keeping and reporting requirements; emergency notification and reporting; quality assurance; personal health and safety; list of contributions; and references
Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado. Revision 1
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-11-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Act on (UMTRA) Project Bodo Canyon disposal site at Durango, Colorado, describes the surveillance activities for the disposal site. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal call continues to function as designed This LTSP was prepared as a requirement for DOE acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM) from processing uranium ore. This LTSP documents that the land and interests are owned by the United States and details how long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a). Following the introduction, contents of this report include the following: site final condition; site drawings and photographs; permanent site surveillance features; ground water monitoring; annual site inspections; unscheduled inspections; custodial maintenance; corrective action; record keeping and reporting requirements; emergency notification and reporting; quality assurance; personal health and safety; list of contributions; and references.
Site observational work plan for the UMTRA project site at Falls City, Texas
International Nuclear Information System (INIS)
1994-09-01
During surface remedial action, an estimated 7.0 million tons (6.4 million tonnes) of uranium mill tailings and other contaminated materials were consolidated and stabilized on the Falls City site. The ground water protection strategy at the Falls City disposal site for the UMTRA Surface Project (Subpart A of 40 CFR Part 192 (1994)) was an application for supplemental standards, based on Class III (limited use) ground water in the uppermost aquifer. This water is not a current or potential source of drinking water. Ground water from the uppermost aquifer (ground water from the Deweesville/Conquista Members and the Dilworth Member) contains widespread ambient contamination resulting from naturally occurring conditions and from the effects of human activity not related to uranium milling operations (uranium exploration and mining activities). The ground water cannot be effectively cleaned up for drinking or other beneficial purposes using treatment methods reasonably employed by public water supply systems. The U.S. Nuclear Regulatory Commission (NRC) and the state of Texas concurred with the ground water protection strategy for the disposal site in September 1992. Surface remedial action in accord with Subpart A was completed in April 1994. The proposed ground water compliance strategy (Subpart B of 40 CFR Part 192 (1994)) at the Falls City site is to perform no remedial action based on application for supplemental standards because the ground water in the uppermost aquifer is classified as Class III ground water. Class III ground water includes ground water that is not a current or potential source of drinking water because of widespread, ambient contamination that cannot be cleaned up using treatment methods reasonably employed by public water supply systems (40 CFR section 192.11 (e) (1994)). Although supplemental standards are being applied, the potential use of ground water in the site vicinity will be protected
Final audit report of remedial action construction at the UMTRA project site Rifle, Colorado. Rev. 1
International Nuclear Information System (INIS)
1997-01-01
This final audit report summarizes the assessments performed by the U.S. Department of Energy (DOE) Environmental Restoration Division (ERD) and its Technical Assistance Contractor (TAC) of remedial action compliance with approved plans, specifications, standards, and 40 CFR Part 192 at the Rifle, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site. Remedial action construction was directed by the Remedial Action Contractor (RAC)
Long-term surveillance plan for the Ambrosia Lake, New Mexico disposal site
International Nuclear Information System (INIS)
1995-11-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Ambrosia Lake disposal site in McKinley County, New Mexico, describes the US Department of Energy's (DOE) long-term care program for the disposal site. The DOE will carry out this program to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials
International Nuclear Information System (INIS)
1995-01-01
A standard assumption when evaluating the migration of plumes in ground water is that the impacted ground water has the same density as the native ground water. Thus density is assumed to be constant, and does not influence plume migration. This assumption is valid only for water with relatively low total dissolved solids (TDS) or a low difference in TDS between water introduced from milling processes and native ground water. Analyses in the literature suggest that relatively minor density differences can significantly affect plume migration. Density differences as small as 0.3 percent are known to cause noticeable effects on the plume migration path. The primary effect of density on plume migration is deeper migration than would be expected in the arid environments typically present at Uranium Mill Tailings Remedial Action (UMTRA) Project sites, where little or no natural recharge is available to drive the plume into the aquifer. It is also possible that at some UMTRA Project sites, a synergistic affect occurred during milling operations, where the mounding created by tailings drainage (which created a downward vertical gradient) and the density contrast between the process water and native ground water acted together, driving constituents deeper into the aquifer than either process would alone. Numerical experiments were performed with the U.S. Geological Survey saturated unsaturated transport (SUTRA) model. This is a finite-element model capable of simulating the effects of variable fluid density on ground water flow and solute transport. The simulated aquifer parameters generally are representative of the Shiprock, New Mexico, UMTRA Project site where some of the highest TDS water from processing has been observed
Long-term surveillance plan for the Ambrosia Lake, New Mexico disposal site
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-07-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Ambrosia Lake disposal site in McKinley County, New Mexico, describes the U.S. Department of Energy`s (DOE) long-term care program for the disposal site. The DOE will carry out this program to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials.
Long-term surveillance plan for the Ambrosia Lake, New Mexico disposal site
International Nuclear Information System (INIS)
1996-07-01
This long-term surveillance plan (LTSP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project Ambrosia Lake disposal site in McKinley County, New Mexico, describes the U.S. Department of Energy's (DOE) long-term care program for the disposal site. The DOE will carry out this program to ensure that the disposal cell continues to function as designed. This LTSP was prepared as a requirement for acceptance under the U.S. Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials
Effect of freezing and thawing on UMTRA covers
International Nuclear Information System (INIS)
Rager, R.; Smith, G.; Brody, R.
1988-01-01
The proposed US Environmental Protection Agency (EPA) groundwater standards (40 CFR 192) require that Uranium Mill Tailings Remedial Action (UMTRA) Project remedial action designs meet low numerical limits for contaminants contained in water or vapor exiting the embankments. To meet the standards, a cover of compacted fine-grained soil is placed over UMTRA Project embankments. One of the functions of this cover is to limit infiltration. The hydraulic conductivity of this infiltration barrier must be low in order to reduce seepage from the cell to the extent necessary to comply with the proposed EPA groundwater standards. Analyses of infiltration barriers covered with rock erosion protection show that the infiltration barriers may become saturated. Accordingly, it is necessary to assure that freezing and thawing of the infiltration barrier materials do not affect the performance of the embankment. A study has been conducted to determine if the hydraulic conductivity of fine-grained clayey soils used or proposed for use in radon/infiltration barriers is affected by repeated freezing and thawing cycles. In addition, a procedure for determining the depth of frost penetration has been developed. Laboratory freeze-thaw tests were undertaken in order to determine if the saturated hydraulic conductivity of clay soils used in UMTRA Project radon/infiltration barriers was affected. The results indicate that an increase of an order of magnitude or more in saturated hydraulic conductivity may occur during repeated freeze-thaw cycles
Site observational work plan for the UMTRA Project site at Monument Valley, Arizona
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-09-01
The site observational work plan (SOWP) for the Monument Valley, Arizona, US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site is one of the first site-specific documents developed to achieve ground water compliance at the site. This SOWP applies information about the Monument Valley site to a regulatory compliance framework that identifies strategies that could be used to meet ground water compliance. The compliance framework was developed in the UMTRA Ground Water programmatic environmental impact statement (DOE, 1995). The DOE`s goal is to implement a cost-effective site strategy that complies with the US Environmental Protection Agency (EPA) ground water standards and protects human health and the environment. The compliance strategy that emerges in the final version of the SOWP will assess potential environmental impacts and provide stakeholder a forum for review and comment. When the compliance strategy is acceptable, it will be detailed in a remedial action plan that will be subject to review by the state and/or tribe and concurrence by the US Nuclear Regulatory Commission (NRC). Information available for the preparation of this SOWP indicates active remediation is the most likely compliance strategy for the Monument Valley site. Additional data are needed to determine the most effective remediation technology.
Site observational work plan for the UMTRA Project site at Monument Valley, Arizona
International Nuclear Information System (INIS)
1995-09-01
The site observational work plan (SOWP) for the Monument Valley, Arizona, US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site is one of the first site-specific documents developed to achieve ground water compliance at the site. This SOWP applies information about the Monument Valley site to a regulatory compliance framework that identifies strategies that could be used to meet ground water compliance. The compliance framework was developed in the UMTRA Ground Water programmatic environmental impact statement (DOE, 1995). The DOE's goal is to implement a cost-effective site strategy that complies with the US Environmental Protection Agency (EPA) ground water standards and protects human health and the environment. The compliance strategy that emerges in the final version of the SOWP will assess potential environmental impacts and provide stakeholder a forum for review and comment. When the compliance strategy is acceptable, it will be detailed in a remedial action plan that will be subject to review by the state and/or tribe and concurrence by the US Nuclear Regulatory Commission (NRC). Information available for the preparation of this SOWP indicates active remediation is the most likely compliance strategy for the Monument Valley site. Additional data are needed to determine the most effective remediation technology
International Nuclear Information System (INIS)
1992-04-01
This report is a summary of the US Department of Energy's (DOE) cultural resource investigations for the Uranium Mill Tailings Remedial Action (UMTRA) Project sites in Colorado. This report is intended to fulfill the DOE's obligation for an annual report as stated in the Programmatic Memorandum of Agreement executed between the DOE, the Advisory Council on Historic Preservation, and the Colorado State Historic Preservation Officer in December 1984. Summaries of the cultural resource surveys and identified resources are provided for the UMTRA Project sites in the vicinities of Durango, Grand Junction, Gunnison, Maybell, Naturita, Rifle, and Slick Rock. This report covers all UMTRA Project cultural resource activities in Colorado from January through December 1991
Project Surveillance and Maintenance Plan
International Nuclear Information System (INIS)
1985-09-01
The Project Surveillance and Maintenance Plan (PSMP) describes the procedures that will be used by the US Department of Energy (DOE), or other agency as designated by the President to verify that inactive uranium tailings disposal facilities remain in compliance with licensing requirements and US Environmental Protection Agency (EPA) standards for remedial actions. The PSMP will be used as a guide for the development of individual Site Surveillance and Maintenance Plans (part of a license application) for each of the UMTRA Project sites. The PSMP is not intended to provide minimum requirements but rather to provide guidance in the selection of surveillance measures. For example, the plan acknowledges that ground-water monitoring may or may not be required and provides the [guidance] to make this decision. The Site Surveillance and Maintenance Plans (SSMPs) will form the basis for the licensing of the long-term surveillance and maintenance of each UMTRA Project site by the NRC. Therefore, the PSMP is a key milestone in the licensing process of all UMTRA Project sites. The Project Licensing Plan (DOE, 1984a) describes the licensing process. 11 refs., 22 figs., 8 tabs
Long-term surveillance plan for the Burro Canyon disposal cell, Slick Rock, Colorado
International Nuclear Information System (INIS)
1996-11-01
This long-term surveillance plant (LTSP) describes the US Department of energy's (DOE) long-term care program for the Uranium Mill Tailings Remediation Action (UMTRA) Project's burro Canyon disposal cell in San Miguel County, Colorado. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the Burro Canyon disposal cell performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. No ground water monitoring will be required at the Burro Canyon disposal cell because the ground water protection strategy is supplemental standards based on low-yield from the upper-most aquifer
International Nuclear Information System (INIS)
1995-06-01
Investigations conducted during preparation of the site observational work plan (SOWP) at the Uranium Mill Tailings Remedial Action (UMTRA) Project site support a proposed natural flushing ground water compliance strategy, with institutional controls. However, additional site-specific data are needed to reduce uncertainties in order to confirm the applicability and feasibility of this proposed compliance strategy option. This proposed strategy will be analyzed in the site-specific environmental assessment. The purpose of this work plan is to summarize the data collection objectives to fill those data needs, describe the data collection activities that will be undertaken to meet those objectives, and elaborate on the data quality objectives which define the procedures that will be followed to ensure that the quality of these data meet UMTRA Project needs
UMTRA consent form acquisition: a survey of nonrespondents
International Nuclear Information System (INIS)
Gonsalves, L.L.; Carpenter, D.; Borak, T.B.; Kearney, P.
1986-01-01
The Radiological Survey Activities group of the Health and Safety Research Division at Oak Ridge National Laboratory is the Inclusion Survey Contractor (ISC) for the Uranium Mill Tailings Remedial Action (UMTRA) project in Grand Junction, Colorado. The ISC is responsible for performing any required radiological surveys and data analyses for the recommendation of inclusion or exclusion of designated properties in the UMTRA project. One of the responsibilities of the ISC is to obtain consent from the property owners to conduct radiological surveys. In Grand Junction, Colorado 30-40% of the owners of designated properties have not responded to the consent-for-access requests sent by certified mail. A questionnaire was designed to identify and study this nonresponse through personal interviews with 100 randomly selected nonrespondents. A profile of the population of nonrespondents, reasons for nonresponse, as well as suggestions to encourage response were identified and analyzed
UMTRA consent form acquisition: a survey of nonrespondents
International Nuclear Information System (INIS)
Gonsalves, L.L.; Borak, T.B.; Kearney, P.; Carpenter, D.
1986-01-01
The Radiological Survey Activities group of the Health and Safety Research Division at Oak Ridge National Laboratory is the Inclusion Survey Contractor (ISC) for the Uranium Mill Tailings Remedial Action (UMTRA) project in Grand Junction, Colorado. The ISC is responsible for performing any required radiological surveys and data analyses for the recommendation of inclusion or exclusion of designated properties in the UMTRA project. One of the responsibilities of the ISC is to obtain consent from the property owners to conduct radiological surveys. In Grand Junction, Colorado 30 to 40% of the owners of designated properties have not responded to the consent-for-access requests sent by certified mail. A questionnaire was designed to identify and study this nonresponse through personal interviews with 100 randomly selected nonrespondents. A profile of the population of nonrespondents, reasons for nonresponse, as well as suggestions to encourage response were identified and analyzed
UMTRA ground water sampling techniques: Comparison of the traditional and low flow methods
International Nuclear Information System (INIS)
1995-07-01
This report describes the potential changes in water quality data that may occur with the conversion from MBV (multiple bore volume) to LF (low flow) sampling and provides two examples of how such a change might impact Project decisions. The existing scientific literature on LF sampling is reviewed and the new LF data from three UMTRA Uranium Mill Tailings Remedial Action Project sites are evaluated seeking answers to the questions posed above. Several possible approaches, that the UMTRA Project may take to address issues unanswered by the literature are presented and compared, and a recommendation is offered for the future direction of the LF conversion effort
Long-term surveillance plan for the South Clive disposal site Clive, Utah
International Nuclear Information System (INIS)
1997-09-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project South Clive disposal site in Clive, Utah. This LSTP describes the long-term surveillance program the DOE will implement to ensure the South Clive disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
Site observational work plan for the UMTRA Project site at Monument Valley, Arizona
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-03-01
The site observational work plan (SOWP) for the Monument Valley, Arizona, US Department of Energy (DOE) Uranium Mill Tailings Remedial Action(UMTRA) Project site is one of the first site-specific documents developed to achieve ground water compliance at the site. This SOWP applies information about the Monument Valley site to a regulatory compliance framework that identifies strategies that could be used to meet ground water compliance. The compliance framework was developed in the UMTRA Ground Water programmatic environmental impact statement (DOE, 1996). The DOE`s goal is to implement a cost-effective site strategy that complies with the US Environmental Protection Agency (EPA) ground water standards and protects human health and the environment. The compliance strategy that emerges in the final version of the SOWP will be evaluated in the site-specific environmental assessment to determine potential environmental impacts and provide stakeholders a forum for review and comment. When the compliance strategy is acceptable, it will be detailed in a remedial action plan that will be subject to review by the state and/or tribe and concurrence by the US Nuclear Regulatory Commission (NRC). Information for the preparation of this SOWP indicates active remediation is the most likely compliance strategy for the Monument Valley site. Additional data are needed to determine the most effective remediation technology.
Site observational work plan for the UMTRA Project site at Monument Valley, Arizona
International Nuclear Information System (INIS)
1996-03-01
The site observational work plan (SOWP) for the Monument Valley, Arizona, US Department of Energy (DOE) Uranium Mill Tailings Remedial Action(UMTRA) Project site is one of the first site-specific documents developed to achieve ground water compliance at the site. This SOWP applies information about the Monument Valley site to a regulatory compliance framework that identifies strategies that could be used to meet ground water compliance. The compliance framework was developed in the UMTRA Ground Water programmatic environmental impact statement (DOE, 1996). The DOE's goal is to implement a cost-effective site strategy that complies with the US Environmental Protection Agency (EPA) ground water standards and protects human health and the environment. The compliance strategy that emerges in the final version of the SOWP will be evaluated in the site-specific environmental assessment to determine potential environmental impacts and provide stakeholders a forum for review and comment. When the compliance strategy is acceptable, it will be detailed in a remedial action plan that will be subject to review by the state and/or tribe and concurrence by the US Nuclear Regulatory Commission (NRC). Information for the preparation of this SOWP indicates active remediation is the most likely compliance strategy for the Monument Valley site. Additional data are needed to determine the most effective remediation technology
International Nuclear Information System (INIS)
1989-06-01
This document describes the technical approach to the assessment of the performance of a full component topslope cover, three sideslope covers, and hence the way in which a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell complies with the US Environmental Protection Agency (EPA) groundwater protection standards. 4 refs
Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah
International Nuclear Information System (INIS)
1997-06-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Mexican Hat, Utah, disposal site. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Mexican Hat disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
Long-term surveillance plan for the Mexican Hat disposal site, Mexican Hat, Utah
International Nuclear Information System (INIS)
1996-01-01
This plan describes the long-term surveillance activities for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Mexican Hat, Utah. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This long-term surveillance plan (LTSP) was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive material (RRM). This LTSPC documents the land ownership interests and details how the long-term care of the disposal site will be accomplished
Long-term surveillance plan for the Estes Gulch disposal site near Rifle, Colorado
International Nuclear Information System (INIS)
1997-07-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Estes Gulch disposal site near Rifle, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Estes Gulch disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado
International Nuclear Information System (INIS)
1997-07-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney Disposal Site near Grand Junction, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Cheney Disposal Site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
Interim long-term surveillance plan for the Cheney disposal site near, Grand Junction, Colorado
International Nuclear Information System (INIS)
1997-08-01
This interim long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney Disposal Site in Mesa County near Grand Junction, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Cheney disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
International Nuclear Information System (INIS)
1995-03-01
This Comment and Response Document is a series of UMTRA document review forms regarding the UMTRA Project Vitro Processing Site Completion Report for Salt Lake City, Utah in March, 1995. The completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approved design and that all U.S. Environmental Protection Agency (EPA) standards have been satisfied. Included as appendices to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawings, the EPA standards (40 CFR Part 192); the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objective of the remedial action at Salt Lake City is to remove the tailings from the processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. Each section is evaluated in detail to check all aspects of above report, especially the inclusion of adequate verification data. Each review form contains a section entitled State of Utah Response and Action, which is an explanation or correction of DOE criticisms of the report
Long-term surveillance plan for the Green River, Utah disposal site. Revision 2
International Nuclear Information System (INIS)
1998-07-01
The long-term surveillance plan (LTSP) for the Green River, Utah, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Green River disposal cell. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). This LTSP documents whether the land and interests are owned by the United States or an Indian tribe and details how the long-term care of the disposal site will be carried out
Long-term surveillance plan for the Burro Canyon disposal cell Slick Rock, Colorado
International Nuclear Information System (INIS)
1997-08-01
This long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Burro Canyon disposal cell in San Miguel County, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Burro Canyon disposal cell performs as designed and is cared for in a manner that protects the public health and safety and the environment. The program is based on site inspections to identify threats to disposal cell integrity. Before each disposal cell is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP
International Nuclear Information System (INIS)
1993-01-01
This report summarizes the US Department of Energy's (DOE) cultural resource studies that were undertaken in support of the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project in the state of Colorado for the period of October 1, 1991, through September 30, 1992. This report fulfills the DOE's obligation to provide an annual report to the state of Colorado on the status and results of cultural resource studies conducted during the above period of record. This requirement is stated in a programmatic memorandum of agreement executed between the DOE, the Advisory Council on Historic Preservation, and the Colorado State Historic Preservation Officer in December 1984. Previous reports were based on a calendar year reporting period. However, in order to be more consistent with the programmatic memorandum of agreement, the period of record for this and subsequent annual reports has been changed to the Federal fiscal year. The current status and summaries of 1992 cultural resource surveys are provided for all UMTRA Project sites in Colorado. The sites are Durango, Grand Junction, Gunnison, Maybell, Naturita, Rifle, and Slick Rock
UMTRA project water sampling and analysis plan, Durango, Colorado
International Nuclear Information System (INIS)
1994-01-01
Surface remedial action has been completed at the Uranium Mill Tailings Remedial Action Project in Durango, Colorado. Contaminated soil and debris have been removed from the former processing site and placed in the Bodo Canyon disposal cell. Ground water at the former uranium mill/tailings site and raffinate pond area has been contaminated by the former milling operations. The ground water at the disposal site was not impacted by the former milling operations at the time of the cell's construction. Activities for fiscal 1994 involve ground water sampling and site characterization of the disposal site
UMTRA project water sampling and analysis plan, Ambrosia Lake, New Mexico
International Nuclear Information System (INIS)
1994-02-01
This water sampling and analysis plan (WSAP) provides the basis for ground water sampling at the Ambrosia Lake Uranium Mill Tailings Remedial Action (UMTRA) Project site during fiscal year 1994. It identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the monitoring locations and will be updated annually. The Ambrosia Lake site is in McKinley County, New Mexico, about 40 kilometers (km) (25 miles [mi]) north of Grants, New Mexico, and 1.6 km (1 mi) east of New Mexico Highway 509 (Figure 1.1). The town closest to the tailings pile is San Mateo, about 16 km ( 10 mi) southeast (Figure 1.2). The former mill and tailings pile are in Section 28, and two holding ponds are in Section 33, Township 14 North, Range 9 West. The site is shown on the US Geological Survey (USGS) map (USGS, 1980). The site is approximately 2100 meters (m) (7000 feet [ft]) above sea level
UMTRA water sampling and analysis plan, Green River, Utah
International Nuclear Information System (INIS)
Papusch, R.
1993-12-01
The purpose of this water sampling and analysis plan (WSAP) is to provide a basis for groundwater and surface water sampling at the Green River Uranium Mill Tailing Remedial Action (UMTRA) Project site. This WSAP identifies and justifies the sampling locations, analytical parameters, detection limits, and sampling frequency for the monitoring locations
International Nuclear Information System (INIS)
1985-03-01
This Environmental Report (ER) examines the environmental consequences of implementing a remedial action that would remove radioactive uranium mill tailings and associated contaminated materials from 394 vicinity properties near 14 inactive uranium processing sites included in the Uranium Mill Tailings Remedial Action (UMTRA) Project pursuant to Public Law 95--604, the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Vicinity properties are those properties in the vicinity of the UMTRA Project inactive mill sites, either public or private, that are believed to be contaminated by residual radioactive material originating from one of the 14 inactive uranium processing sites, and which have been designated under Section 102(a)(1) of UMTRCA. The principal hazard associated with the contaminated properties results from the production of radon, a radioactive decay product of the radium contained in the tailings. Radon, a radioactive gas, can diffuse through the contaminated material and be released into the atmosphere where it and its radioactive decay products may be inhaled by humans. A second radiation exposure pathway results from the emission of gamma radiation from uranium decay products contained in the tailings. Gamma radiation emitted from contaminated material delivers an external exposure to the whole body. If the concentration of radon and its decay products is high enough and the exposure time long enough, or if the exposure to direct gamma radiation is long enough, cancers (i.e., excess health effects) may develop in persons living and working at the vicinity properties. 3 refs., 7 tabs
International Nuclear Information System (INIS)
1996-01-01
This scope of work governs the field effort to conduct transient in situ (hereafter referred to by the trademark name HydroPunch reg-sign) investigative subsurface logging and ground water sampling, and perform well point installation services at the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project site near Salt Lake City, Utah. The HydroPunch reg-sign and well point services subcontractor (the Subcontractor) shall provide services as stated herein to be used to investigate the subsurface, collect and analyze ground water samples, and install shallow well points
Site observational work plan for the UMTRA Project site at Tuba City, Arizona
International Nuclear Information System (INIS)
1994-09-01
The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. The wet tailings remaining after processing were placed as a slurry in three piles at the site. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The site is expected to remain in this status until licensed by the U.S. Nuclear Regulatory Commission (NRC) for long-term surveillance and maintenance. The preliminary ground water compliance strategy at the Tuba City site is active remediation-specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource
Site observational work plan for the UMTRA Project Site at Tuba City, Arizona
International Nuclear Information System (INIS)
1994-09-01
The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. A total of 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. Two processes were used to refine the ore: an acid leach process and a sodium carbonate alkaline process. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The preliminary ground water compliance strategy at the Tuba City site is active remediation. The specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource
International Nuclear Information System (INIS)
Little, C.A.; Berven, B.A.; Blair, M.S.; Dickerson, K.S.; Pickering, D.A.
1988-01-01
The Ultrasonic Ranging and Data System (USRADS) was developed to allow radiation exposure data and positional information to be collected, stored and analyzed in a more efficient manner than currently employed on the (Uranium Mill Tailings Remedial Action (UMTRA) project. USRADS is a portable unit which employs ultrasonics, radio frequency transmissions, and a personal computer. Operational experience indicates that the system results in increased information about the property with decreased data analysis and transcription effort and only slightly more field effort. 5 refs., 3 figs., 2 tabs
Environmental Assessment of Ground Water Compliance at the Gunnison, Colorado, UMTRA Project Site
International Nuclear Information System (INIS)
2002-01-01
The U.S. Department of Energy (DOE) is in the process of selecting a ground water compliance strategy for the Gunnison, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project site. This Environmental Assessment (EA) discusses two alternatives and the effects associated with each. The two alternatives are (1) natural flushing coupled with institutional controls and continued monitoring and (2) no action. The compliance strategy must meet U.S. Environmental Protection Agency (EPA) ground water standards defined in Title 40 ''Code of Federal Regulations'' Part 192, Subpart B, in areas where ground water beneath and around the site is contaminated as a result of past milling operations. It has been determined that contamination in the ground water at the Gunnison site consists of soluble residual radioactive material (RRM) as defined in the Uranium Mill Tailings Radiation Control Act (UMTRCA)
International Nuclear Information System (INIS)
1996-11-01
This is the Comment and Response Document dated November 1996 for the Long-Term Surveillance Plan for the Falls City Disposal Site in Falls City, Texas. The site is part of the U.S. DOE's Uranium Mill Tailings Remedial Action Project (UMTRA). Several comments regarding the hydrology and surface erosion described in the Long-Term Surveillance Plan are addressed in this document
Site observational work plan for the UMTRA Project site at Ambrosia Lake, New Mexico
International Nuclear Information System (INIS)
1994-09-01
The Ambrosia Lake Uranium Mill Tailings Remedial Action (UMTRA) Project site is within the Grants Mineral Belt and was one of numerous uranium mills supplied by many local mines. Ground water contamination at the site occurred as a result of uranium mill operations. The potential for impacts to human health and the environment from contaminated ground water currently does not exist. No domestic or livestock wells accessing ground water from the uppermost aquifer have been identified within a 5 mile radius from the site. Therefore, no current exposure pathways to humans, livestock, or wildlife exist, nor are any foreseen. The proposed ground water compliance strategy under consideration for application at the Ambrosia Lake site is to perform no remediation, based on the application of supplemental standards because the ground water has ''limited use.''
How public issues shape environmental restoration plans - experiences with Colorado UMTRA projects
International Nuclear Information System (INIS)
Hunt, B.; Monaghan, J.
1991-01-01
Federal environmental restoration plans are being significantly impacted by open-quotes grassrootsclose quotes public pressure and by community demands, some of which have little relation to the technical standards of remediation and which go well beyond authorizing legislation. These demands often represent significant additional project costs. A review of Uranium Mill Tailings Remedial Action (UMTRA) Program experiences in Colorado suggests that the more serious open-quotes grassrootsclose quotes issues associated with remediation rarely diminish and, in fact, will intensify over time. This presents program administrators with the dilemma of attempting to adhere to program mandates and keep projects within budget, while at the same time trying to be responsive to community concerns. Such high-profiled community debates have the ability to delay remediation and even jeopardize important projects. After prolonged public debate, when it becomes clear an issue will not dissipate, project officials may be forced to meet certain community demands. Often, this results in not only increased costs, but a loss of public confidence in clean-up efforts. Evidence also suggests, however, that when critical public issues can be identified and addressed before they become overly contentious, significant problems and controversy can be avoided; but, the situation is made difficult because project officials often lack the policy guidance to determine which, if any, community demands should be addressed and to what extent they should be met. The adoption of several key public policy principles by program administrators will provide a greater ability to address community demands in a timely and successful manner
International Nuclear Information System (INIS)
McBee, J.M.
1988-01-01
The piezocone has been widely used on the Uranium Mill Tailings Remedial Action Project (UMTRA) during the characterization phase of the site remedial actions. It has proven to be a cost-effective method of acquiring detailed information about the stratigraphy of the tailings pile and in situ material properties. It has been especially in light of the extreme variability, both vertically and horizontally, of the tailings materials. At the Maybell, Colorado site, the cross-sections drawn using the piezocone logs were analyzed using a consolidation computer program (CONSOL). The CONSOL program calculates the total and time-rate of primary settlement for one-dimensional layered soil masses. Results from the CONSOL analysis showed that the preliminary calculations, which were based on the gross stratigraphy of the pile, overestimated the time of settlement of the in-place tailings after loading. This overestimate was due to the longer drainage paths determined from the gross stratigraphy. The results of the CONSOL analysis at Maybell compared well with the results from a test fill on another UMTRA site with similar conditions. Also, the analyses based on the piezocone data eliminated the need for design recommendations such as preloading soft areas of the pile or lengthening the construction schedule, thereby reducing the cost estimate for the remedial section at this site
International Nuclear Information System (INIS)
1996-01-01
The final audit report for remedial action at the Gunnison, Colorado Uranium Mill Tailings Remedial Action (UMTRA) Project site consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and QA remedial action close-out inspections performed by the U.S. Department of Energy (DOE) and the Technical Assistance Contractor (TAC); and on-site construction reviews (OSCR) performed by the U.S. Nuclear Regulatory Commission (NRC). Two radiological surveillances and four radiological audits were performed at the Gunnison site. The surveillances were performed on 16 to 19 September 1992 and 28 June to 1 July 1993. The radiological audits were performed on 4 to 7 October 1993; 13 to 16 June 1994; 19 to 22 September 1994 and 10 to 12 July 1995. The surveillances and audits resulted in 79 observations. Thirty-four of the observations raised DOE concerns that were resolved on the site or through subsequent corrective action. All outstanding issues were closed on 12 July 1995. The radiological surveillances and audits are discussed in Section 2.0 of this report. Ten QA in-process surveillances were performed at the Gunnison UMTRA Project site. The surveillances were performed on 24 to 25 September 1992, 7 to 9 July 1993, 29 October 1993, 27 to 28 June 1994, 31 October to 1 November 1994, 19 to 20 June 1 995, 20 to 21 July 1995, 17 to 18 August 1995, 20 September 1995, and 11 to 13 October 1995. The surveillances resulted in 100 observations. Six observations contained recommendations that required responses from the Remedial Action Contractor (RAC). Ninety-five observations contained a recommendation that required no response. All outstanding issues were closed on 8 January 1996. The QA in-process surveillances are discussed in Section 3.0 of this report
International Nuclear Information System (INIS)
1995-09-01
The final audit report for remedial action at the Ambrosia Lake, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project site consists of a summary of the radiological surveillances/audits, quality assurance (QA) in-process surveillances, and a QA final closeout inspection performed by the US Department of Energy (DOE) and the Technical Assistance Contractor (TAC). One radiological surveillance and three radiological audits were performed at the Ambrosia Lake site. The surveillance was performed on 12--16 April 1993 (DOE, 1993d). The audits were performed on 26--29 July 1993 (DOE, 1993b); 21--23 March 1994 (DOE, 1994d); and 1--2 August 1994 (DOE, 1994d). The surveillance and audits resulted in 47 observations. Twelve of the observations raised DOE concerns that were resolved on site or through subsequent corrective action. All outstanding issues were satisfactorily closed out on 28 December 1994. The radiological surveillance and audits are discussed in this report. A total of seven QA in-process surveillances were performed at the Ambrosia Lake UMTRA site are discussed. The DOE/TAC Ambrosia Lake final remedial action close-out inspection was conducted on 26 July 1995 (DOE, 1995a). To summarize, a total of 155 observations were noted during DOE/TAC audit and surveillance activities. Follow-up to responses required from the RAC for the DOE/TAC surveillance and audit observations indicated that all issues related to the Ambrosia Lake site were resolved and closed to the satisfaction of the DOE
Final report of the UMTRA independent technical review of TAC audit programs
International Nuclear Information System (INIS)
1994-10-01
This report details the findings of an Independent Technical Review (ITR) of practices and procedures for the Uranium Mill Tailings Remedial Action (UMTRA) Project audit program. The audit program is conducted by Jacobs Engineering Group Inc., the Technical Assistance Contractor (TAC) for the UMTRA Project. The purpose of the ITR was to ensure that the TAC audit program is effective and is conducted efficiently. The ITR was conducted from May 16-20, 1994. A review team observed audit practices in the field, reviewed the TAC audit program's documentation, and discussed the program with TAC staff and management. The format of this report has been developed around EPA guidelines; they comprise most of the major section headings. Each section begins by identifying the criteria that the TAC program is measured against, then describing the approach used by the ITR team to measure each TAC audit program against the criteria. An assessment of each type of audit is then summarized for each component in the following order: Radiological audit summary; Health and safety audit summary; Environmental audit summary; Quality assurance audit summary
International Nuclear Information System (INIS)
1996-02-01
This guidance document has two purposes: it provides guidance for writing site-specific long-term surveillance plans (LTSP) and it describes site surveillance, monitoring, and long-term care techniques for Title I disposal sites of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (42 USC Section 7901 et seq.). Long-term care includes monitoring, maintenance, and emergency measures needed to protect public health and safety and the environment after remedial action is completed. This document applies to the UMTRCA-designated Title I disposal sites. The requirements for long-term care of the Title I sites and the contents of the LTSPs are provided in U.S. Nuclear Regulatory Commission (NRC) regulations (10 CFR Section 40.27) provided in Attachment 1
Uranium Mill Tailings Remedial Action Project Vicinity Property Program
International Nuclear Information System (INIS)
Little, L.E.; Potter, R.F.; Arpke, P.W.
1988-01-01
The Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Grand Junction Project Vicinity Property Program is a $165 million program for the removal and disposal of uranium mill tailings that were used in the construction of approximately 4,000 residences, commercial buildings, and institutional facilities in the City of Grand Junction and surrounding Mesa County, Colorado. This paper discusses the UMTRA Vicinity Property Program and the economic benefits of this program for the City of Grand Junction and Mesa County, Colorado. The Bureau of Reclamation Economic Assessment Model (BREAM) was used to estimate the increases in employment and increases in personal income in Mesa County that result from the Vicinity Property Program. The effects of program-related changes in income and taxable expenditures on local and state tax revenue are also presented
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase 1) and the Ground Water Project (phase 2). For the UMTRA Project site located near Green River, Utah, the Surface Project cleanup occurred from 1988 to 1989. The tailings and radioactively contaminated soils and materials were removed from their original locations and placed into a disposal cell on the site. The disposal cell is designed to minimize radiation emissions and minimize further contamination of ground water beneath the site. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. For the Green River site, the risk assessment helps determine whether human health risks result from exposure to ground water contaminated by uranium processing. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Green River site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.
International Nuclear Information System (INIS)
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase 1) and the Ground Water Project (phase 2). For the UMTRA Project site located near Green River, Utah, the Surface Project cleanup occurred from 1988 to 1989. The tailings and radioactively contaminated soils and materials were removed from their original locations and placed into a disposal cell on the site. The disposal cell is designed to minimize radiation emissions and minimize further contamination of ground water beneath the site. The UMTRA Project's second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. For the Green River site, the risk assessment helps determine whether human health risks result from exposure to ground water contaminated by uranium processing. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Green River site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards
Risk assessment guidance document for the UMTRA project groundwater remediation phase
International Nuclear Information System (INIS)
1992-05-01
The purpose of the groundwater remedial activities at the Uranium Mill Tailings Remedial Action (UMTRA) sites is to reduce, control, or eliminate risks to human health and the environment. This is in accordance with Subpart B of 40 CFR 192. According to this regulation, the need for groundwater restoration is based upon US Environmental Protection Agency (EPA)-defined groundwater cleanup standards and must be consistent with the National Environmental Policy Act (NEPA) process. Risk assessments will be used in the UMTRA Groundwater Program to aid in the evaluation of sites. Risk assessments are conducted for four purposes: (1) Preliminary risk assessments are used to aid in prioritizing sites, scope data collection, end determine if a site presents immediate health risks. (2) Baseline risk assessments provide a comprehensive integration and interpretation of demographic, geographic, physical, chemical, and biological factors at a site to determine the extent of actual or potential harm. This information Is used to determine the need for remedial action. (3) Risk evaluation of remedial alternatives is performed to evaluate risks to humans or the environment associated with the various remedial strategies. (4) After remediation, an evaluation of residual risks is conducted. The information gathered for each of these risk evaluations is used to determine the need for subsequent evaluation. Several sites may be eliminated after a preliminary risk assessment if there is no current or future threat to humans or the environment. Likewise, much of the data from a baseline risk assessment can be used to support alternate concentration limits or supplemental standards demonstrations, or identify sensitive habitats or receptors that may be of concern in selecting a remedy
International Nuclear Information System (INIS)
1994-07-01
This report is a response to the findings and recommendations contained in the ITR report. The text of this document summarizes each ITR finding and recommendation, presents the TAC response, and concludes that implementation of many of the recommendations would benefit the UMTRA Project. Implementation of the recommendations represents ongoing improvement to the TAC well installation and development procedures and will result, in lower overall project costs. Appendix B is an implementation plan that groups similar or complementary action items, provides a schedule for implementation, identifies the group or people responsible for the changes, and estimates hours to implement the changes. The four major action items are as follows: (1) ITR Reevaluation, (2) Well Installation SOP Review and Revision, (3) Well Installation Contract Review and Revision, and (4) TAC and DOE Communications Improvement. The hours listed to implement the improvements are intended to be estimates for budgeting and planning purposes for the remainder of this fiscal year and the upcoming fiscal year
Energy Technology Data Exchange (ETDEWEB)
1994-07-01
This report is a response to the findings and recommendations contained in the ITR report. The text of this document summarizes each ITR finding and recommendation, presents the TAC response, and concludes that implementation of many of the recommendations would benefit the UMTRA Project. Implementation of the recommendations represents ongoing improvement to the TAC well installation and development procedures and will result, in lower overall project costs. Appendix B is an implementation plan that groups similar or complementary action items, provides a schedule for implementation, identifies the group or people responsible for the changes, and estimates hours to implement the changes. The four major action items are as follows: (1) ITR Reevaluation, (2) Well Installation SOP Review and Revision, (3) Well Installation Contract Review and Revision, and (4) TAC and DOE Communications Improvement. The hours listed to implement the improvements are intended to be estimates for budgeting and planning purposes for the remainder of this fiscal year and the upcoming fiscal year.
International Nuclear Information System (INIS)
Rael, G.J.; Cox, S.W.; Artiglia, E.W.
2000-01-01
The United States Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Surface Project has successfully completed the cleanup of 22 former uranium mill sites, more than 5400 vicinity properties, and has constructed 18 entombment cells. The Project has recently received the United States Nuclear Regulatory Commission's approval and certification for the last two disposal sites, with these sites being placed under the general license for long term custodial care of residual radioactive material. The UMTRA site located at Grand Junction, Colorado is a good example of the technical, political, economic, and public relations challenges that were overcome in achieving success. The UMTRA Team discussed, negotiated, planned, and eventually acted on this uranium mill tailings problem and brought the project to a successful conclusion for the community. From the early 1940s through the 1970s, uranium ore was mined in significant quantities under United States federal contracts for the government's national defence programmes, i.e. the Manhattan Engineering District and Atomic Energy Commission programmes. The problem started as the need for uranium decreased in the late 1960s, resulting in mills shutting down, leaving behind large quantities of process waste tailings and contaminated mill buildings. The former Climax Uranium Company mill site in Grand Junction was one of the largest of these sites. (author)
Groundwater protection management program plan
International Nuclear Information System (INIS)
1992-06-01
US Department of Energy (DOE) Order 5400.1 requires the establishment of a groundwater protection management program to ensure compliance with DOE requirements and applicable Federal, state, and local laws and regulations. The Uranium Mill Tailings Remedial Action (UMTRA) Project Office has prepared a ''Groundwater Protection Management Program Plan'' (groundwater protection plan) of sufficient scope and detail to reflect the program's significance and address the seven activities required in DOE Order 5400.1, Chapter 3, for special program planning. The groundwater protection plan highlights the methods designed to preserve, protect, and monitor groundwater resources at UMTRA Project processing and disposal sites. The plan includes an overview of the remedial action status at the 24 designated processing sites and identifies project technical guidance documents and site-specific documents for the UMTRA groundwater protection management program. In addition, the groundwater protection plan addresses the general information required to develop a water resources protection strategy at the permanent disposal sites. Finally, the plan describes ongoing activities that are in various stages of development at UMTRA sites (long-term care at disposal sites and groundwater restoration at processing sites). This plan will be reviewed annually and updated every 3 years in accordance with DOE Order 5400.1
International Nuclear Information System (INIS)
1995-02-01
This final audit report (FAR) for remedial action at the Grand Junction, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project processing site consists of a summary of the radiological surveillances/ audits, the quality assurance (QA) in-process surveillances, and the QA final close-out inspection performed by the US Department of Energy (DOE) and Technical Assistance Contractor (TAC). The FAR also summarizes other surveillances performed by the US Nuclear Regulatory Commission (NRC). To summarize, a total of one finding and 127 observations were noted during DOE/TAC audit and surveillance activities. The NRC noted general site-related observations during the OSCRs. Follow-up to responses required from MK-Ferguson for the DOE/TAC finding and observations indicated that all issues related to the Grand Junction processing site were resolved and closed out to the DOE's satisfaction. The NRC OSCRs resulted in no issues related to the Grand Junction processing site requiring a response from MK-Ferguson
International Nuclear Information System (INIS)
1993-08-01
At the request of the Office of Independent Technical Review for the U.S. Department of Energy (DOE), Uranium Mill Tailings Remedial Action (UMTRA) Project, an independent technical review (peer review) was conducted during the period of September 15-17, 1992. The review was conducted by C. Warren Ankerberg (Geraghty ampersand Miller, Inc., Tampa, Florida) and Don Messinger (Roy F. Weston, Inc., West Chester, Pennsylvania). The peer review included a review of written documentation [water sampling standard operating procedures (SOP)], an inspection of technical reports and other deliverables, a review of staff qualifications and training, and a field visit to evaluate the compliance of field procedures with SOPs. The approach of the peer reviewers was to verify that the program meets the following criteria: Reported results are traceable to and consistent with recorded data. The basic assumptions and acceptance criteria are valid. Data are traceable to their origin and to reported analytical results. The procedures employed are consistent both internally and externally with written SOPs and regulatory guidelines. Inferences and conclusions are soundly based. The procedures and/or reports generated present work that satisfies the local, state and/or Federal regulatory requirements as applicable. The approach is consistent with industry standards and/or state-of-the-art technology, as practical. The data generated by activities are legally defensible and technically sound. UMTRA staff are adequately trained and qualified for the work. This document is a response to the observations, comments, and recommendations submitted by C. Warren Ankerberg following his review. The format of this document is to present the findings and recommendations verbatim from Mr. Ankerberg's report, followed by responses from the UMTRA Project staff. Included in the responses from the UMTRA Project staff are recommended changes in SOPs and strategies for implementing the changes
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This document evaluates potential impacts to public health and the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1989 by the US DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, UMTRA Project is evaluating ground water contamination in this risk assessment.
International Nuclear Information System (INIS)
1994-09-01
This document evaluates potential impacts to public health and the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1989 by the US DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, UMTRA Project is evaluating ground water contamination in this risk assessment
Uranium Mill Tailings Remedial Action Project Environmental Protection Implementation Plan
International Nuclear Information System (INIS)
Vollmer, A.T.
1993-10-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the US Department of Energy (DOE) Order 5400.1. The UMTRA EPIP covers the time period of November 9, 1993, through November 8, 1994. It will be updated annually. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies. Contents of this report are: (1) general description of the UMTRA project environmental protection program; (2) notifications; (3) planning and reporting; (4) special programs; (5) environmental monitoring programs; (6) quality assurance and data verification; and (7) references
Uranium Mill Tailings Remedial Action Project Environmental Protection Implementation Plan
Energy Technology Data Exchange (ETDEWEB)
Vollmer, A.T.
1993-10-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the US Department of Energy (DOE) Order 5400.1. The UMTRA EPIP covers the time period of November 9, 1993, through November 8, 1994. It will be updated annually. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies. Contents of this report are: (1) general description of the UMTRA project environmental protection program; (2) notifications; (3) planning and reporting; (4) special programs; (5) environmental monitoring programs; (6) quality assurance and data verification; and (7) references.
International Nuclear Information System (INIS)
1994-09-01
This risk assessment evaluates the potential for impacts to public health or the environment from contaminated ground water at this site caused by the burning of coal containing uranium to produce uranium. Potential risk is quantified for constituents introduced from the processing activities and not for those constituents naturally occurring in background ground water in the site vicinity. Because background ground water quality has the potential to cause adverse health effects from exposure through drinking, any risks associated with contaminants attributable to site activities are incremental to these risks from background. The incremental risk from site-related contaminants is quantified in this risk assessment. The baseline risk from background water quality is incorporated only into the assessment of potential chemical interactions and the definition of the overall site condition. The US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to remedy soil and ground water contamination at the site. The UMTRA Surface Project consists of determining the extent of soil contamination and disposing of the contaminated soils in an engineered disposal cell. The UMTRA Ground Water Project consists of evaluating ground water contamination. Under the UMTRA Ground Water Project, results of this risk assessment will help determine what ground water compliance strategy may be applied at the site
Project W-049H disposal facility test report
International Nuclear Information System (INIS)
Buckles, D.I.
1995-01-01
The purpose of this Acceptance Test Report (ATR) for the Project W-049H, Treated Effluent Disposal Facility, is to verify that the equipment installed in the Disposal Facility has been installed in accordance with the design documents and function as required by the project criteria
International Nuclear Information System (INIS)
1993-12-01
The Colorado economic impact study summarizes employment and economic benefits to the state from activities associated with the Uranium Mill Tailings Remedial Action (UMTRA) Project during Colorado state fiscal year 1993 (July 1, 1992, through June 30, 1993). To capture employment benefits, a questionnaire was distributed to subcontractor employees at the active UMTRA Project sites of Grand Junction, Rifle, and Gunnison, Colorado. An estimated 52 percent of the employees working on the UMTRA Project responded to this information request. Economic data were requested from each site prime subcontractor, as well as from the Remedial Action Contractor. The most significant benefits associated with the UMTRA Project in Colorado are summarized
International Nuclear Information System (INIS)
1993-08-01
The Uranium Mill Tailing Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site, transfer site, and Cheney disposal site in Grand Junction, Colorado. Jim Hylko and Bill James of the TAC conducted this audit August 9 through 11, 1993. Bob Cornish and Frank Bosiljevec represented the US Department of Energy (DOE). This report presents one programmatic finding, eleven site-specific observations, one good practice, and four programmatic observations
International Nuclear Information System (INIS)
1993-09-01
Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing sits are summarized as follows: In accordance with EPA-promulgated land cleanup standards (40 CFR 192), in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100-m 2 grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. A bulk interpretation of these EPA standards has been accepted by the Nuclear Regulatory Commission (NRC), and while the concentration of the finer-sized soil fraction less than a No. 4 mesh sieve contains the higher concentration of radioactivity, the bulk approach in effect integrates the total sample radioactivity over the entire sample mass. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 cleanup protocol has been developed in accordance with Supplemental Standard provisions of 40 CFR 192 for NRC/Colorado Department of Health (CDH) approval for timely implementation. Detailed elements of the protocol are contained in Appendix A, Generic Protocol from Thorium-230 Cleanup/Verification at UMTRA Project Processing Sites. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR 192 relative to supplemental standards
UMTRA project water sampling and analysis plan, Gunnison, Colorado
International Nuclear Information System (INIS)
1994-06-01
This water sampling and analysis plan summarizes the results of previous water sampling activities and the plan for water sampling activities for calendar year 1994. A buffer zone monitoring plan is included as an appendix. The buffer zone monitoring plan is designed to protect the public from residual contamination that entered the ground water as a result of former milling operations. Surface remedial action at the Gunnison Uranium Mill Tailings Remedial Action Project site began in 1992; completion is expected in 1995. Ground water and surface water will be sampled semiannually in 1994 at the Gunnison processing site (GUN-01) and disposal site (GUN-08). Results of previous water sampling at the Gunnison processing site indicate that ground water in the alluvium is contaminated by the former uranium processing activities. Background ground water conditions have been established in the uppermost aquifer (Tertiary gravels) at the Gunnison disposal site. The monitor well locations provide a representative distribution of sampling points to characterize ground water quality and ground water flow conditions in the vicinity of the sites. The list of analytes has been modified with time to reflect constituents that are related to uranium processing activities and the parameters needed for geochemical evaluation. Water sampling will be conducted at least semiannually during and one year following the period of construction activities, to comply with the ground water protection strategy discussed in the remedial action plan (DOE, 1992a)
Uranium Mill Tailings Remedial Action Project environmental protection implementation plan
International Nuclear Information System (INIS)
1994-10-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the U.S. Department of Energy (DOE) Order 5400.1. The UMTRA EPIP is updated annually. This version covers the time period of 9 November 1994, through 8 November 1995. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies
Uranium Mill Tailings Remedial Action Project environmental protection implementation plan
Energy Technology Data Exchange (ETDEWEB)
1994-10-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the U.S. Department of Energy (DOE) Order 5400.1. The UMTRA EPIP is updated annually. This version covers the time period of 9 November 1994, through 8 November 1995. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies.
International Nuclear Information System (INIS)
1994-11-01
The Colorado economic impact study summarizes employment and economic benefits to the state from activities associated with the Uranium Mill Tailings Remedial Action (UMTRA) Project during Colorado state fiscal year 1994. To capture employment information, a questionnaire was distributed to subcontractor employees at the active UMTRA Project sites of Grand Junction, Naturita, Gunnison, and Rifle, Colorado. Economic data were requested from each site prime subcontractor, as well as from the Remedial Action Contractor. The most significant benefits associated with the UMTRA Project in Colorado are summarized. This study assesses benefits associated with the Grand Junction, Gunnison, Naturita, and Rifle UMTRA Projects sites for the 1-year period under study. Work at the Naturita site was initiated in April 1994 and involved demolition of buildings at the processing site. Actual start-up of remediation of Naturita is planned to begin in the spring of 1995. Work at the Slick Rock and Maybell sites is expected to begin in 1995. The only current economic benefits associated with these sites are related to UMTRA Project support work
Economic analysis of radioactive waste storage and disposal projects
International Nuclear Information System (INIS)
Kleinen, P.J.; Starnes, R.B.
1995-01-01
Radioactive waste storage and disposal efforts present challenging issues for cost and economic analyses. In particular, legal requirements for states and compact areas to develop radioactive waste disposal sites, combined with closure of some sites, have placed urgency on planning, locating, and constructing storage and disposal sites. Cost analyses of potential projects are important to the decision processes. Principal objectives for cost analyses for projects are to identify all activities, covering the entire project life cycle, and to develop costs for those activities using methods that allow direct comparisons between competing project alternatives. For radioactive waste projects, long project lives ranging from tens of years to 100 or more years must be considered. Alternative, and competing, technologies, designs, and operating plans must be evaluated. Thorough base cost estimates must be made for all project phases: planning, development, licensing/permitting, construction, operations, and maintenance, closure, and post-closure/institutional care. Economic analysis procedures need to accommodate the specific features of each project alternative and facilitate cost comparisons between differing alternatives. Economic analysis assumptions must be developed to address the unusually long project lives involved in radioactive waste projects
Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project
Energy Technology Data Exchange (ETDEWEB)
Danny Anderson
2014-07-01
As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE
International Nuclear Information System (INIS)
1994-06-01
This document evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium mill site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1990 by the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine what remedial actions are necessary for contaminated ground water at the site
International Nuclear Information System (INIS)
1995-11-01
For the UMTRA Project site located near Canonsburg, Pennsylvania (the Canonsburg site), the Surface Project cleanup occurred from 1983 to 1985, and involved removing the uranium processing mill tailings and radioactively contaminated soils and materials from their original locations and placing them in a disposal cell located on the former Canonsburg uranium mill site. This disposal cell is designed to minimize radiation emissions and further contamination of ground water beneath the site. The Ground Water Project will evaluate the nature and the extent of ground water contamination resulting from uranium processing at the former Canonsburg uranium mill site, and will determine a ground water strategy for complying with the US Environmental Protection Agency's (EPA) ground water standards established for the UMTRA Project. For the Canonsburg site, an evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people's health. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Canonsburg site. The results of this report and further site characterization of the Canonsburg site will be used to determine how to protect public health and the environment, and how to comply with the EPA standards
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-11-01
For the UMTRA Project site located near Canonsburg, Pennsylvania (the Canonsburg site), the Surface Project cleanup occurred from 1983 to 1985, and involved removing the uranium processing mill tailings and radioactively contaminated soils and materials from their original locations and placing them in a disposal cell located on the former Canonsburg uranium mill site. This disposal cell is designed to minimize radiation emissions and further contamination of ground water beneath the site. The Ground Water Project will evaluate the nature and the extent of ground water contamination resulting from uranium processing at the former Canonsburg uranium mill site, and will determine a ground water strategy for complying with the US Environmental Protection Agency`s (EPA) ground water standards established for the UMTRA Project. For the Canonsburg site, an evaluation was made to determine whether exposure to ground water contaminated by uranium processing could affect people`s health. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Canonsburg site. The results of this report and further site characterization of the Canonsburg site will be used to determine how to protect public health and the environment, and how to comply with the EPA standards.
International Nuclear Information System (INIS)
Kawanishi, M.; Komada, H.; Kitayama, K.; Akasaka, H.; Tsuchi, H.
2001-01-01
In Japan, the high-level radioactive waste (HLW) disposal project is expected to start fully after establishment of the implementing organization, which is planned around the year 2000 and to dispose the wastes in the 2030s to at latest in the middle of 2040s. Considering each step in the implementation of the HLW disposal project in Japan, this paper discusses the execution procedure for HLW disposal project, such as the selection of candidate/planned disposal sites, the construction and operation of the disposal facility, the closure and decommissioning of facilities, and the institutional control and monitoring after the closure of disposal facility, from a technical viewpoint for the rational execution of the project. Furthermore, we investigate and propose some ideas for the concept of the design of geological disposal facility, the validation and demonstration of the reliability on the disposal techniques and performance assessment methods at a candidate/planned site. Based on these investigation results, we made clear a milestone for the execution of the HLW disposal project in Japan. (author)
Uranium Mill Tailings Remedial Action Project, fiscal year 1995 annual report to stakeholders
International Nuclear Information System (INIS)
1995-01-01
In 1978, Congress authorized the DOE to assess and clean up contamination at 24 designated former uranium processing sites. The DOE is also responsible for cleaning up properties in the vicinity of the sites where wind and water erosion deposited tailings or people removed them from the site for use in construction or landscaping projects. Cleanup is being undertaken in cooperation with state governments and Indian tribes within whose boundaries the sites are located. It is being conducted in two phases: the surface project and the ground water project. This report addresses specifics about both phases of the UMTRA Project. DOE's UMTRA Project is the world's largest materials management project ever undertaken to reduce or eliminate risk to the general public from exposure to potentially hazardous and radioactive materials. With an estimated cost at completion of nearly $2 billion for both phases of the UMTRA Project, and with the responsibility for encapsulating and isolating almost one-fourth of all the uranium mill tailings generated across the entire US (more than 44 million cubic yards), the UMTRA Project and its people have achieved a long record of safely and effectively completing its mission. It continually enhances its national reputation through its diligent process and cost efficiency as well as its international recognition for its technological innovation
International Nuclear Information System (INIS)
Anderson, M.S.; Braymen, S.; McIntosh, R.
1994-01-01
This report describes an innovative technology, laser ablation-inductively couple plasma-mass spectrometry (LA-ICP-MS), operated in a mobile laboratory, to rapidly detect thorium 230 activity levels in soil samples. This technology was demonstrated on-site during November 1993 at the Gunnison, Colorado, UMTRA project site in support of their remediation effort. The LA-ICP-MS sampling and analysis technique was chosen because of the capability for rapid analysis, approximately three samples per hour, with minimal sample preparation
International Nuclear Information System (INIS)
1993-08-01
An independent technical review (peer review) was conducted during the period of September 15--17, 1992. The review was conducted by C. Warren Ankerberg (Geraghty and Miller, Inc., Tampa, Florida) and Don Messinger (Roy F. Weston, Inc., West Chester, Pennsylvania). The review was held at Jacobs Engineering in Albuquerque, New Mexico, and at the Shiprock, New Mexico, site. The peer review included a review of written documentation [water sampling standard operating procedures (SOP)], an inspection of technical reports and other deliverables, a review of staff qualifications and training, and a field visit to evaluate the compliance of field procedures with SOPS. Upon completion of the peer review, each reviewer independently prepared a report of findings from the review. The reports listed findings and recommended actions. This document responds to the observations, comments, and recommendations submitted by Don Messinger following his review. The format of this document is to present the findings and recommendations verbatim from Mr. Messinger's report, followed by responses from the UMTRA Project staff. Included in the responses from the UMTRA Project staff are recommended changes in SOPs and strategies for implementing the charges
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the Surface Project and the Ground Water Project. At the UMTRA Project site near Riverton, Wyoming, Surface Project cleanup occurred from 1988 to 1990. Tailings and radioactively contaminated soils and materials were taken from the Riverton site to a disposal cell in the Gas Hills area, about 60 road miles (100 kilometers) to the east. The surface cleanup reduces radon and other radiation emissions and minimizes further ground water contamination. The UMTRA Project`s second phase, the Ground Water Project, will evaluate the nature and extent of ground water contamination at the Riverton site that has resulted from the uranium ore processing activities. Such evaluations are used at each site to determine a strategy for complying with UMTRA ground water standards established by the US Environmental Protection Agency (EPA) and if human health risks could result from exposure to ground water contaminated by uranium ore processing. Exposure could hypothetically occur if drinking water were pumped from a well drilled in an area where ground water contamination might have occurred. Human health and environmental risks may also result if people, plants, or animals are exposed to surface water that has mixed with contaminated ground water.
UMTRA Project water sampling and analysis plan, Gunnison, Colorado. Revision 2
International Nuclear Information System (INIS)
1995-09-01
Surface remedial action at the Gunnison Uranium Mill Tailings Remedial Action Project site began in 1992; completion is expected in 1995. Ground water and surface water will be sampled semiannually at the Gunnison processing site (GUN-01) and disposal site (GUN-08). Results of previous water sampling at the Gunnison processing site indicate that ground water in the alluvium is contaminated by the former uranium processing activities. Background ground water conditions have been established in the uppermost aquifer (Tertiary gravels) at the Gunnison disposal site. Semiannual water sampling is scheduled for the spring and fall. Water quality sampling is conducted at the processing site (1) to ensure protection of human health and the environment, (2) for ground water compliance monitoring during remedial action construction, and (3) to define the extent of contamination. At the processing site, the frequency and duration of sampling will be dependent upon the nature and extent of residual contamination and the compliance strategy chosen. The monitor well locations provide a representative distribution of sampling points to characterize ground water quality and ground water flow conditions in the vicinity of the sites. The list of analytes has been modified with time to reflect constituents that are related to uranium processing activities and the parameters needed for geochemical evaluation
Energy Technology Data Exchange (ETDEWEB)
1993-09-01
Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing sits are summarized as follows: In accordance with EPA-promulgated land cleanup standards (40 CFR 192), in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100-m{sup 2} grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. A bulk interpretation of these EPA standards has been accepted by the Nuclear Regulatory Commission (NRC), and while the concentration of the finer-sized soil fraction less than a No. 4 mesh sieve contains the higher concentration of radioactivity, the bulk approach in effect integrates the total sample radioactivity over the entire sample mass. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 cleanup protocol has been developed in accordance with Supplemental Standard provisions of 40 CFR 192 for NRC/Colorado Department of Health (CDH) approval for timely implementation. Detailed elements of the protocol are contained in Appendix A, Generic Protocol from Thorium-230 Cleanup/Verification at UMTRA Project Processing Sites. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR 192 relative to supplemental standards.
International Nuclear Information System (INIS)
1995-12-01
This Colorado economic impact study summarizes employment and economic benefits to the state from activities associated with the Uranium Mill Tailings Remedial Action (UMTRA) Project during Colorado state fiscal year (FY) 1995 (1 July 1994 through 30 June 1995). To capture employment information, a questionnaire was distributed to subcontractor employees at the active UMTRA Project sites of Grand Junction, Gunnison, Maybell, Naturita, Rifle, and Slick Rock, Colorado. Economic data were requested from the Remedial Action Contractor (RAC), the Technical Assistance Contractor (TAC) and the US Department of Energy (DOE). The most significant benefits associated with the UMTRA Project in Colorado are summarized
International Nuclear Information System (INIS)
1995-11-01
The purpose of this document is to provide additional and more detailed information to supplement review of the site observational work plan (SOWP) (DOE, 1995) for the Ambrosia Lake, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project site. This document includes a discussion of the average linear velocity of the ground water in the alluvium and a discussion of the ground water quality of the alluvium, weathered Mancos Shale, and the Tres Hermanos-C Member of the Mancos Shale. The data from a 1989 aquifer test were analyzed using the curve-matching software AQTESOLV and then compared with the original results. A hydrograph of the ground water elevations in monitoring wells screened in the alluvium is presented to show how the ground water elevations change with time. Stiff and Piper diagrams were created to describe the changes in ground water geochemistry in the alluvium/weathered Mancos Sahel unit, the Tres Hermanos-C Sandstone unit, the Tres Hermanos-B Sandstone unit, and the Dakota Sandstone. Background information on other related topics such as site history, cell construction, soil characteristics, and well construction are presented in the SOWP. A geologic cross section depicts the conceptual model of the hydrostratigraphy and ground water chemistry of the Ambrosia Lake site. Hydrogeologic information of each hydrostratigraphic unit is presented
Engineering risk assessment for emergency disposal projects of sudden water pollution incidents.
Shi, Bin; Jiang, Jiping; Liu, Rentao; Khan, Afed Ullah; Wang, Peng
2017-06-01
Without an engineering risk assessment for emergency disposal in response to sudden water pollution incidents, responders are prone to be challenged during emergency decision making. To address this gap, the concept and framework of emergency disposal engineering risks are reported in this paper. The proposed risk index system covers three stages consistent with the progress of an emergency disposal project. Fuzzy fault tree analysis (FFTA), a logical and diagrammatic method, was developed to evaluate the potential failure during the process of emergency disposal. The probability of basic events and their combination, which caused the failure of an emergency disposal project, were calculated based on the case of an emergency disposal project of an aniline pollution incident in the Zhuozhang River, Changzhi, China, in 2014. The critical events that can cause the occurrence of a top event (TE) were identified according to their contribution. Finally, advices on how to take measures using limited resources to prevent the failure of a TE are given according to the quantified results of risk magnitude. The proposed approach could be a potential useful safeguard for the implementation of an emergency disposal project during the process of emergency response.
Energy Technology Data Exchange (ETDEWEB)
Tucker, M.D.
1996-01-01
The Uranium Mill Tailings Remediation Action (UMTRA) Program is responsible for the assessment and remedial action at the 24 former uranium mill tailings sites located in the United States. The surface remediation phase, which has primarily focused on containment and stabilization of the abandoned uranium mill tailings piles, is nearing completion. Attention has now turned to the groundwater restoration phase. One alternative under consideration for groundwater restoration at UMTRA sites is the use of in-situ permeable reactive subsurface barriers. In this type of a system, contaminated groundwater will be allowed to flow naturally through a barrier filled with material which will remove hazardous constituents from the water by physical, chemical or microbial processes while allowing passage of the pore water. The subject of this report is a reactive barrier which would remove uranium and other contaminants of concern from groundwater by microbial action (i.e., a microbial barrier). The purpose of this report is to assess the current state of this technology and to determine issues that must be addressed in order to use this technology at UMTRA sites. The report focuses on six contaminants of concern at UMTRA sites including uranium, arsenic, selenium, molybdenum, cadmium and chromium. In the first section of this report, the fundamental chemical and biological processes that must occur in a microbial barrier to control the migration of contaminants are described. The second section contains a literature review of research which has been conducted on the use of microorganisms to immobilize heavy metals. The third section addresses areas which need further development before a microbial barrier can be implemented at an UMTRA site.
International Nuclear Information System (INIS)
Tucker, M.D.
1996-01-01
The Uranium Mill Tailings Remediation Action (UMTRA) Program is responsible for the assessment and remedial action at the 24 former uranium mill tailings sites located in the United States. The surface remediation phase, which has primarily focused on containment and stabilization of the abandoned uranium mill tailings piles, is nearing completion. Attention has now turned to the groundwater restoration phase. One alternative under consideration for groundwater restoration at UMTRA sites is the use of in-situ permeable reactive subsurface barriers. In this type of a system, contaminated groundwater will be allowed to flow naturally through a barrier filled with material which will remove hazardous constituents from the water by physical, chemical or microbial processes while allowing passage of the pore water. The subject of this report is a reactive barrier which would remove uranium and other contaminants of concern from groundwater by microbial action (i.e., a microbial barrier). The purpose of this report is to assess the current state of this technology and to determine issues that must be addressed in order to use this technology at UMTRA sites. The report focuses on six contaminants of concern at UMTRA sites including uranium, arsenic, selenium, molybdenum, cadmium and chromium. In the first section of this report, the fundamental chemical and biological processes that must occur in a microbial barrier to control the migration of contaminants are described. The second section contains a literature review of research which has been conducted on the use of microorganisms to immobilize heavy metals. The third section addresses areas which need further development before a microbial barrier can be implemented at an UMTRA site
International Nuclear Information System (INIS)
1992-07-01
The Estes Gulch disposal site is approximately 10 kilometers (6 miles) north of the town of Rifle, off State Highway 13 on Federal land administered by the Bureau of Land Management. The Department of Energy (DOE) will transport the residual radioactive materials (RRM) by truck to the Estes Gulch disposal site via State Highway 13 and place it in a partially below-grade disposal cell. The RRM will be covered by an earthen radon barrier, frost protection layers, and a rock erosion protection layer. A toe ditch and other features will also be constructed to control erosion at the disposal site. After removal of the RRM and disposal at the Estes Gulch site, the disturbed areas at all three sites will be backfilled with clean soils, contoured to facilitate surface drainage, and revegetated. Wetlands areas destroyed at the former Rifle processing sites will be compensated for by the incorporation of now wetlands into the revegetation plan at the New Rifle site. The UMTRA Project Office, supported by the Remedial Action Contractor (RAC) and the Technical Assistance Contractor (TAC), oversees the implementation of the MAP. The RAC executes mitigation measures in the field. The TAC provides monitoring of the mitigation actions in cases where mitigation measures are associated with design features. Site closeout and inspection compliance will be documented in the site completion report
International Nuclear Information System (INIS)
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the Surface Project and the Ground Water Project. At the UMTRA Project site near Riverton, Wyoming, Surface Project cleanup occurred from 1988 to 1990. Tailings and radioactively contaminated soils and materials were taken from the Riverton site to a disposal cell in the Gas Hills area, about 60 road miles (100 kilometers) to the east. The surface cleanup reduces radon and other radiation emissions and minimizes further ground water contamination. The UMTRA Project's second phase, the Ground Water Project, will evaluate the nature and extent of ground water contamination at the Riverton site that has resulted from the uranium ore processing activities. Such evaluations are used at each site to determine a strategy for complying with UMTRA ground water standards established by the US Environmental Protection Agency (EPA) and if human health risks could result from exposure to ground water contaminated by uranium ore processing. Exposure could hypothetically occur if drinking water were pumped from a well drilled in an area where ground water contamination might have occurred. Human health and environmental risks may also result if people, plants, or animals are exposed to surface water that has mixed with contaminated ground water
Integrated Project Management System description
International Nuclear Information System (INIS)
1987-03-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project is a Department of Energy (DOE) designated Major System Acquisition (MSA). To execute and manage the Project mission successfully and to comply with the MSA requirements, the UMTRA Project Office (''Project Office'') has implemented and operates an Integrated Project Management System (IPMS). The Project Office is assisted by the Technical Assistance Contractor's (TAC) Project Integration and Control (PIC) Group in system operation. Each participant, in turn, provides critical input to system operation and reporting requirements. The IPMS provides a uniform structured approach for integrating the work of Project participants. It serves as a tool for planning and control, workload management, performance measurement, and specialized reporting within a standardized format. This system description presents the guidance for its operation. Appendices 1 and 2 contain definitions of commonly used terms and abbreviations and acronyms, respectively. 17 figs., 5 tabs
International Nuclear Information System (INIS)
Titus, F.B.
1988-01-01
Potential groundwater contamination beneath the 24 tailings piles that are to be stabilized under the UMTRA Project was intended in early project plans to be minimized by placing disposal piles over thick stratigraphic sequences of tight (minimally permeable) formations, and by designing covers that contained low permeability soil/clay infiltration barriers. The court-ordered revision of the UMTRA groundwater standards by EPA (proposed standards of September 1987) include very low Maximum Concentration Limits (MCLs), which are based mostly on Primary Drinking Water Standards. EPA also mandates that the designs should control radioactivity and hazardous constituents...for up to one thousand years, to the extends reasonably achievable, and, in any case, for at least two hundred years.... In order to accommodate this stipulation, transport modeling of water and contaminants in both the vadose and saturated zones beneath the piles is run until steady state conditions are reached. The early decision to locate stabilized piles over tight formations now exacerbates the problem of complying with the standards, since the contaminants percolate to groundwater that moves only slowly through strata having low permeabilities. Innovative solutions have been evaluated that are aimed at further minimizing long-term infiltration, geochemically fixing contaminants in place before they reach groundwater, or otherwise minimizing contaminant flux
Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-11-01
The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas.
Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2
International Nuclear Information System (INIS)
1996-11-01
The need for ground water monitoring at the Falls City disposal site was evaluated in accordance with NRC regulations and guidelines established by the DOE in Guidance for Implementing the Long-term Surveillance Program for UMTRA Project Title 1 Disposal Sites (DOE, 1996). Based on evaluation of site characterization data, it has been determined that a program to monitor ground water for demonstration of disposal cell performance based on a set of concentration limits is not appropriate because ground water in the uppermost aquifer is of limited use, and a narrative supplemental standard has been applied to the site that does not include numerical concentration limits or a point of compliance. The limited use designation is based on the fact that ground water in the uppermost aquifer is not currently or potentially a source of drinking water in the area because it contains widespread ambient contamination that cannot be cleaned up using methods reasonably employed by public water supply systems. Background ground water quality varies by orders of magnitude since the aquifer is in an area of redistribution of uranium mineralization derived from ore bodies. The DOE plans to perform post-closure ground water monitoring in the uppermost aquifer as a best management practice (BMP) as requested by the state of Texas
UMTRA Project Site Observational Work Plan, Mexican Hat, Utah
International Nuclear Information System (INIS)
1994-09-01
Surface cleanup activities at the Mexican Hat UMTRA processing site are nearing completion. Ground Water contamination at the Mexican Hat site is a result of uranium milling operations. The extent of residual process water has been identified, and it is limited to the uppermost aquifer in the vicinity of the site. Deeper aquifers are not affected because of an upward hydraulic gradient and the presence of a confining unit (the deeper aquifers are protected by hydrogeologic isolation). The uppermost unit is returning to its pre-milling, mainly unsaturated state. The unit that contains the contaminated water is not a ground water resource because it qualifies as Class III (limited use) based on limited yield. Ground water in the uppermost unit is currently not used and is not anticipated to be used as a ground water resource. The nearby San Juan River and a converted oil exploration well provide all of the water needs for the area. There are no current threats to human health or livestock; and, because the zone of contamination does not represent a ground water resource, none are anticipated in the future. There are, however, seeps where contaminated water is exposed at land surface. The seeps create potential exposure pathways for plants and wildlife. It is not known at this time if there is a risk to the environment. Additional investigations are needed and are described in this document to confirm the presence or absence of potential environmental risks. Additional hydrogeologic investigations are not required. The proposed ground water compliance strategy for the site is no remediation, because the ground water in the uppermost aquifer (which is also the zone of contamination) qualifies for supplemental standards based on Class III, limited yield, and because there are no threats to human health. Domestic and agricultural water is pumped from a deeper aquifer that is isolated from the contaminated zone
Uranium Mill Tailings Remedial Action Project. 1995 Environmental Report
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-06-01
In accordance with U.S. Department of Energy (DOE) Order 23 1. 1, Environment, Safety and Health Reporting, the DOE prepares an annual report to document the activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring program. This monitoring must comply with appropriate laws, regulations, and standards, and it must identify apparent and meaningful trends in monitoring results. The results of all monitoring activities must be communicated to the public. The UMTRA Project has prepared annual environmental reports to the public since 1989.
Uranium Mill Tailings Remedial Action Project. 1995 Environmental Report
International Nuclear Information System (INIS)
1996-06-01
In accordance with U.S. Department of Energy (DOE) Order 23 1. 1, Environment, Safety and Health Reporting, the DOE prepares an annual report to document the activities of the Uranium Mill Tailings Remedial Action (UMTRA) Project environmental monitoring program. This monitoring must comply with appropriate laws, regulations, and standards, and it must identify apparent and meaningful trends in monitoring results. The results of all monitoring activities must be communicated to the public. The UMTRA Project has prepared annual environmental reports to the public since 1989
The French geological disposal project CIGEO
Energy Technology Data Exchange (ETDEWEB)
Ouzounian, G. [ANDRA, Chatenay-Malabry cedex (France)
2015-07-01
This paper discusses the major management options for high level waste in France. Safety of the population and protection of the environment is the first priority. Reprocessing of used fuel and reuse of valuable material is considered. Reversible geological disposal (Cigéo Project) is the reference solution for the high-level waste.
Accounting for socio-economic effects in nuclear waste disposal projects
International Nuclear Information System (INIS)
Van Hove, E.
1996-01-01
The disposal of nuclear waste has become highly controversial. This paper presents the approach taken by NIRAS, the Belgian agency for the disposal of nuclear waste, to come to a decision on the establishment of a site for the permanent disposal of low level nuclear waste. A formal model is elaborated to take social effects of such a project into account, allowing for a balanced discussion of positive and negative effects at the local level. It is too early to tell it the model described in detail in this paper con solve the problems encountered by disposal agencies. The approach discussed, does however, respond to need experienced on a international scale. The paper emphasises the need for openness in the fact of assertive and articulate citizens who no longer accept the paternalistic approach. The public must not feel that there is any lack of clarity about waste projects or they will quickly voice their opinions and any opposition they feel. As far as siting is concerned, most of the controversies are fuelled ba a basic notion of 'unfairness'. Somehow the burdens seem to be imposed on parties other than those who reap the benefits. An approach to decision making through local negotiation on all aspects of a disposal projects should allow the problem of fairness to be treated in a more constructive way. (author)
U.S. Department of Energy Uranium Mill Tailings Remedial Action Ground Water Project: Project plan
International Nuclear Information System (INIS)
1994-09-01
The scope of the Project is to develop and implement a ground water compliance strategy for all 24 UMTRA Project processing sites. The compliance strategy for the processing sites must satisfy the proposed EPA ground water cleanup standards in 40 CFR Part 192, Subparts B and C (1987). This scope of work will entail the following activities on a site-specific basis: Develop a compliance strategy based on modification of the UMTRA Surface Project RAPs or develop Ground Water Project RAPs with NRC concurrence on the RAP and full participation of the affected states and tribes. Implement the RAP to include institutional controls, where appropriate, as an interim measure until compliance with the standards is achieved. Institute long-term verification monitoring for transfer to a separate long-term surveillance program on or before the Project end date. Prepare certification or confirmation reports and modify the long-term surveillance plan (LTSP), where needed, on those sites completed prior to the Project end date
Radiological survey activities: uranium mill tailings remedial action project procedures manual
International Nuclear Information System (INIS)
Little, C.A.; Berven, B.A.; Carter, T.E.
1986-07-01
The US Department of Energy (DOE) was assigned the responsibility for conducting remedial action at 24 sites, which are located in one eastern and nine western states. The DOE's responsibilities are being met through its Uranium Mill Tailings Remedial Action Project Office (UMTRA-PO) in Albuquerque, New Mexico. The purpose of this Procedures Manual is to provide a standardized set of procedures that document in an auditable manner the activities performed by the Radiological Survey Activities (RASA) group in the Dosimetry and Biophysical Transport Section (DABTS) of the Health and Safety Research Division (HASRD) at the Oak Ridge National Laboratory (ORNL), in its role as the Inclusion Survey Contractor (ISC). Members of the RASA group assigned to the UMTRA Project are headquartered in the ORNL/RASA office in Grand Junction, Colorado, and report to the ORNL/RASA Project Manager. The Procedures Manual ensures that the organizational, administrative, and technical activities of the RASA/UMTRA group conform properly to those of the ISC as described in the Vicinity Properties Management and Implementation Manual and the Summary Protocol. This manual also ensures that the techniques and procedures used by the RASA/UMTRA group and contractor personnel meet the requirements of applicable governmental, scientific, and industrial standards
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This Risk Assessment evaluated potential impacts to public health or the environment caused by ground water contamination at the former uranium mill processing site. In the first phase of the U.S. Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project, the tailing and other contaminated material at this site were placed in a disposal cell near the Gas Hills Plant in 1990. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first site-specific document to evaluate potential health and environmental risks for the Riverton site under the Ground Water Project; it will help determine whether remedial actions are needed for contaminated ground water at the site.
Energy Technology Data Exchange (ETDEWEB)
1994-08-01
This baseline risk assessment evaluates potential impact to public health or the environment from ground water contamination at the former uranium mill processing site in Cane Valley near Monument Valley, Arizona. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project has relocated and stabilized this site`s tailings and other contaminated material in a disposal cell at Mexican Hat, Utah. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project that evaluates potential health and environmental risks. It will help determine the approach required to address contaminated ground water at the site.
International Nuclear Information System (INIS)
1994-09-01
This Risk Assessment evaluated potential impacts to public health or the environment caused by ground water contamination at the former uranium mill processing site. In the first phase of the U.S. Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project, the tailing and other contaminated material at this site were placed in a disposal cell near the Gas Hills Plant in 1990. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first site-specific document to evaluate potential health and environmental risks for the Riverton site under the Ground Water Project; it will help determine whether remedial actions are needed for contaminated ground water at the site
International Nuclear Information System (INIS)
1994-08-01
This baseline risk assessment evaluates potential impact to public health or the environment from ground water contamination at the former uranium mill processing site in Cane Valley near Monument Valley, Arizona. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project has relocated and stabilized this site's tailings and other contaminated material in a disposal cell at Mexican Hat, Utah. The second phase of the UMTRA Project is to evaluate ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project that evaluates potential health and environmental risks. It will help determine the approach required to address contaminated ground water at the site
UMTRA project water sampling and analysis plan, Grand Junction, Colorado
International Nuclear Information System (INIS)
1994-07-01
Surface remedial action will be completed at the Grand Junction processing site during the summer of 1994. Results of 1993 water sampling indicate that ground water flow conditions and ground water quality at the processing site have remained relatively constant with time. Uranium concentrations in ground water continue to exceed the maximum concentration limits, providing the best indication of the extent of contaminated ground water. Evaluation of surface water quality of the Colorado River indicate no impact from uranium processing activities. No compliance monitoring at the Cheney disposal site has been proposed because ground water in the Dakota Sandstone (uppermost aquifer) is classified as limited-use (Class 111) and because the disposal cell is hydrogeologically isolated from the uppermost aquifer. The following water sampling and water level monitoring activities are planned for calendar year 1994: (i) Semiannual (early summer and late fall) sampling of six existing monitor wells at the former Grand Junction processing site. Analytical results from this sampling will be used to continue characterizing hydrogeochemical trends in background ground water quality and in the contaminated ground water area resulting from source term (tailings) removal. (ii) Water level monitoring of approximately three proposed monitor wells projected to be installed in the alluvium at the processing site in September 1994. Data loggers will be installed in these wells, and water levels will be electronically monitored six times a day. These long-term, continuous ground water level data will be collected to better understand the relationship between surface and ground water at the site. Water level and water quality data eventually will be used in future ground water modeling to establish boundary conditions in the vicinity of the Grand Junction processing site. Modeling results will be used to help demonstrate and document the potential remedial alternative of natural flushing
Remote-Handled Low-Level Waste Disposal Project Code of Record
Energy Technology Data Exchange (ETDEWEB)
S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.
2012-06-01
The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.
Remote-Handled Low-Level Waste Disposal Project Code of Record
Energy Technology Data Exchange (ETDEWEB)
S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.
2014-06-01
The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.
Remote-Handled Low-Level Waste Disposal Project Code of Record
Energy Technology Data Exchange (ETDEWEB)
Austad, S. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Guillen, L. E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKnight, C. W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ferguson, D. S. [Idaho National Lab. (INL), Idaho Falls, ID (United States)
2015-04-01
The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-03-01
The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the Monument Valley UMTRA Project site near Cane Valley, Arizona, was completed in 1994. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Adverse ecological and agricultural effects may also result from exposure to contaminated ground water. For example, livestock should not be watered with contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site investigations will be used to determine a compliance strategy to comply with the UMTRA ground water standards.
International Nuclear Information System (INIS)
1996-03-01
The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the Monument Valley UMTRA Project site near Cane Valley, Arizona, was completed in 1994. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Adverse ecological and agricultural effects may also result from exposure to contaminated ground water. For example, livestock should not be watered with contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site investigations will be used to determine a compliance strategy to comply with the UMTRA ground water standards
International Nuclear Information System (INIS)
1996-10-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project is to eliminate, reduce, or address to acceptable levels the potential health and environmental consequences of milling activities. One of the first steps in the UMTRA Ground Water Project is the preparation of the Programmatic Environmental Impact Statement (PEIS). This report contains the comments and responses received on the draft PEIS
Underground disposal of hazardous waste - state of the art and R and D projects
International Nuclear Information System (INIS)
Pitterich, H.; Brueckner, C.
1998-01-01
The project management group Entsorgung (PTE) coordinates R and D activities on deep geological disposal of hazardous waste besides other activities in the field of nuclear disposal. R and D projects aim at the improvement of tools used to predict the long-term behaviour of underground disposal facilities and the threat for man and environment associated with these facilities. The current German situation on deep geological disposal of hazardous waste is described and some results from the fields waste-anaylsis, geochemical modelling and geotechnical barriers for the sealing of waste disposal sites are presented. (orig.)
Uranium Mill Tailings Remedial Action Project surface project management plan
International Nuclear Information System (INIS)
1994-09-01
This Project Management Plan describes the planning, systems, and organization that shall be used to manage the Uranium Mill Tailings Remedial Action Project (UMTRA). US DOE is authorized to stabilize and control surface tailings and ground water contamination at 24 inactive uranium processing sites and associated vicinity properties containing uranium mill tailings and related residual radioactive materials
International Nuclear Information System (INIS)
1996-02-01
The purpose of this document is to provide additional and more detailed information to supplement review of the site observational work plan (SOWP) for the Ambrosia Lake, New Mexico, Uranium Mill Tailings Remedial Action (UMTRA) Project site. This document includes a discussion of (1) the average linear velocity of the ground water in the alluvium; (2) the ground water quality of the alluvium, weathered Mancos Shale, and the Tres Hermanos-C Member of the Mancos Shale; and (3) the fate and transport of contaminants from the uppermost aquifer to the Westwater Canyon Member of the Morrison Formation. The data from a 1989 aquifer test were analyzed using the curve-matching software AQTESOLV and then compared with the original results. A hydrograph of the ground water elevations in monitoring wells screened in the alluvium is presented to show how the ground water elevations change with time. Stiff and Piper diagrams were created to describe the changes in ground water geochemistry in the alluvium/weathered Mancos Shale unit, the Tres Hermanos-C Sandstone unit, the Tres Hermanos-B Sandstone unit, and the Dakota Sandstone. Background information on other related topics such as site history, cell construction, soil characteristics, and well construction are presented in the SOWP. Figure 1 is a geologic cross section depicting the conceptual model of the hydrostratigraphy and ground water chemistry of the Ambrosia Lake site. Table 1 presents hydrogeologic information of each hydrostratigraphic unit
International Nuclear Information System (INIS)
1995-04-01
This-assessment examines the consequences and risks that could result from the proposed construction of mitigation wetlands at the New and Old Rifle Uranium Mill Tailings Remedial Action (UMTRA) Project sites near Rifle, Colorado. Remediation of surface contamination at those sites is now under way. Preexisting wetlands at or near the Old and New Rifle sites have been cleaned up, resulting in the loss of 0.7 and 10.5 wetland acres (ac) (0.28 and 4.2 hectares [ha]) respectively. Another 9.9 ac (4.0 ha) of wetlands are in the area of windblown contamination west of the New Rifle site. The US Army Corps of Engineers (USACE) has jurisdiction over the remediated wetlands. Before remedial action began, and before any wetlands were eliminated, the USACE issued a Section 404 Permit that included a mitigation plan for the wetlands to be lost. The mitigation plan calls for 34.2 ac (1 3.8 ha) of wetlands to be constructed at the south end and to the west of the New Rifle site. The mitigation wetlands would be constructed over and in the contaminated alluvial aquifer at the New Rifle site. As a result of the hydrologic characteristics of this aquifer, contaminated ground water would be expected to enter the environment through the proposed wetlands. A preliminary assessment was therefore required to assess any potential ecological risks associated with constructing the mitigation wetlands at the proposed location
The residuals analysis project: Evaluating disposal options for treated mixed low-level waste
International Nuclear Information System (INIS)
Waters, R.D.; Gruebel, M.M.; Case, J.T.; Letourneau, M.J.
1997-01-01
For almost four years, the U.S. Department of Energy (DOE) through its Federal Facility Compliance Act Disposal Workgroup has been working with state regulators and governors' offices to develop an acceptable configuration for disposal of its mixed low-level waste (MLLW). These interactions have resulted in screening the universe of potential disposal sites from 49 to 15 and conducting ''performance evaluations'' for those fifteen sites to estimate their technical capabilities for disposal of MLLW. In the residuals analysis project, we estimated the volume of DOE's MLLW that will require disposal after treatment and the concentrations of radionuclides in the treated waste. We then compared the radionuclide concentrations with the disposal limits determined in the performance evaluation project for each of the fifteen sites. The results are a scoping-level estimate of the required volumetric capacity for MLLW disposal and the identification of waste streams that may pose problems for disposal based on current treatment plans. The analysis provides technical information for continued discussions between the DOE and affected States about disposal of MLLW and systematic input to waste treatment developers on disposal issues
Geophysical surveys at the UMTRA project Shiprock, New Mexico site
International Nuclear Information System (INIS)
Wightman, E.; Smith, B.; Newlin, B.
1996-03-01
Geophysical surveys were performed at the Uranium Mill Tailings Remedial Action (UMTRA) Shiprock site in New Mexico during February 1996. The surveys were designed to locate areas of ground water contamination, consisting largely of sulfate and nitrate salts and uranium. Electrical geophysical methods were used to locate areas of sulfate and nitrate concentrations since these products, when present in ground water, increase its electrical conductivity. These contaminants also increase the density of water, making the water with the highest concentrations of these salts sink to the bottom of the water column. At the Shiprock site, where alluvium is underlain by the impervious Mancos Shale, the saline water will tend to rest in depressions on the shale surface. Seismic refraction surveys were conducted on the floodplain. The site comprises two areas, the terrace and the floodplain, separated by a steep scarp of some 70 feet (ft) (20 meters [m]). Measurements of electrical conductivity were taken over these two areas, searching for possible pockets of saline ground water resting on top of the bedrock. Conductivity surveys were also run to identify fractures within the bedrock that may act as conduits for ground water movement. Several areas of higher than normal conductivity were found on the terrace, including halos of higher conductivities on three sides of the tailings cell. The conductivity measurements searching for fractures found only a small number of minor fracture-like anomalies. These are not considered important. On the floodplain, both conductivity and seismic refraction measurements were taken. The conductivity measurements clearly show areas of high conductivity interpreted to result from ground water contamination. The seismic refraction measurements identified bedrock depressions that may contain denser, and more saline ground water lenses. Generally, the areas of high conductivity coincide with the bedrock depressions
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This baseline risk assessment of groundwater contamination at the uranium mill tailings site near Salt Lake City, Utah, evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium ore processing site. The tailings and other contaminated material at this site were placed in a disposal cell located at Clive, Utah, in 1987 by the US Department of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate residual ground water contamination at the former uranium processing site, known as the Vitro processing site. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine the appropriate remedial action for contaminated ground water at the site.
International Nuclear Information System (INIS)
1994-09-01
This baseline risk assessment of groundwater contamination at the uranium mill tailings site near Salt Lake City, Utah, evaluates potential public health or environmental impacts resulting from ground water contamination at the former uranium ore processing site. The tailings and other contaminated material at this site were placed in a disposal cell located at Clive, Utah, in 1987 by the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project is to evaluate residual ground water contamination at the former uranium processing site, known as the Vitro processing site. This risk assessment is the first site-specific document under the Ground Water Project. It will help determine the appropriate remedial action for contaminated ground water at the site
International Nuclear Information System (INIS)
1984-06-01
The Public Information Plan is intended to be used in conjunction with the DOE-UMTRA Project ''Public Participation Plan'' to describe the Department of Energy's plan for involving the public in the decision-making process related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by Congress in the Uranium Mill Tailings Radiation Control of Act of 1978, PL95-604. The Act provides for a cooperative effort with affected states and Indian tribes for the cleanup of designated abandoned or inactive uranium mill tailings sites. The objective of the Public Information Plan of the UMTRA Project is timely and sufficient dissemination of factual information to promote understanding of the project by federal, state, and local officials, the media, special interest groups, and the general public; and thereby to encourage informed participation in the project by the public and government officials. The Uranium Mill Tailings Radiation Control Act provides for public involvement in remedial action planning, with special consideration given to landowners, Indian tribes, and the states. According to the Act, the Secretary of Energy shall hold public hearings in the states where processing sites, vicinity properties, and disposal sites are located. Public participation in the UMTRA Project will not, however, be limited to those mechanisms formally required by law. The public may also be involved informally through informational meetings, workshops, and local citizens' task forces. 12 refs., 2 figs., 1 tab
Remedial Action and Waste Disposal Project Manager's Implementing Instructions
International Nuclear Information System (INIS)
Dronen, V.R.
1998-01-01
These Project Manager's Implementing Instructions provide the performance standards required of all Environmental Restoration Contractor personnel in their work during operation and administration of the Remedial Action and Waste Disposal Project. The instructions emphasize technical competency, workplace discipline, and personal accountability to ensure a high level of safety and performance during operations activities
Project schedule and cost estimate report
International Nuclear Information System (INIS)
1988-03-01
All cost tables represent obligation dollars, at both a constant FY 1987 level and an estimated escalation level, and are based on the FY 1989 DOE Congressional Budget submittal of December 1987. The cost tables display the total UMTRA Project estimated costs, which include both Federal and state funding. The Total Estimated Cost (TEC) for the UMTRA Project is approximately $992.5 million (in 1987 escalated dollars). Project schedules have been developed that provide for Project completion by September 1994, subject to Congressional approval extending DOE's authorization under Public Law 95-604. The report contains site-specific demographic data, conceptual design assumptions, preliminary cost estimates, and site schedules. A general project overview is also presented, which includes a discussion of the basis for the schedule and cost estimates, contingency assumptions, work breakdown structure, and potential project risks. The schedules and cost estimates will be revised as necessary to reflect appropriate decisions relating to relocation of certain tailings piles, or other special design considerations or circumstances (such as revised EPA groundwater standards), and changes in the Project mission. 27 figs', 97 tabs
International Nuclear Information System (INIS)
1993-09-01
Public concern regarding the potential human health and environmental effects from uranium mill tailings led Congress to pass the Uranium Mill Tailings Radiation Control Act (UMTRCA) (Public Law 95-604) in 1978. In the UMTRCA, Congress acknowledged the potentially harmful health effects associated with uranium mill tailings at 24 abandoned uranium mill processing sites needing remedial action. Uranium processing activities at most of the 24 mill processing sites resulted in the formation of contaminated ground water beneath and, in some cases, downgradient of the sites. This contaminated ground water often has elevated levels of hazardous constituents such as uranium and nitrate. The purpose of the Ground Water Project is to protect human health and the environment by meeting EPA-proposed standards in areas where ground water has been contaminated with constituents from UMTRA Project sites. A major first step in the UMTRA Ground Water Project is the preparation of this Programmatic Environmental Impact Statement (PEIS). This document analyzes potential impacts of the alternatives, including the proposed action. These alternatives are programmatic in that they are plans for conducting the UMTRA Ground Water Project. The alternatives do not address site-specific ground water compliance. This PEIS is a planning document that will provide a framework for conducting the Ground Water Project; assess the potential programmatic and environmental impacts of conducting the UMTRA Ground Water Project; provide a method for determining the site-specific ground water compliance strategies; and provide data and information that can be used to prepare site-specific environmental impacts analyses documents more efficiently
International Nuclear Information System (INIS)
1992-01-01
This document is about the scoping session which was held at the Community Center in Falls City, Texas. The purpose was to obtain public comment on the Programmatic Environmental Impact Statement for the Uranium Mill Tailings Remedial Action Project (UMTRA), specifically on the ground water project. Presentations made by the manager for the entire UMTRA program, manager of the site and ground water program, comments made by two residents of Fall City are included in this document
Energy Technology Data Exchange (ETDEWEB)
None
1992-12-31
This document is about the scoping session which was held at the Community Center in Falls City, Texas. The purpose was to obtain public comment on the Programmatic Environmental Impact Statement for the Uranium Mill Tailings Remedial Action Project (UMTRA), specifically on the ground water project. Presentations made by the manager for the entire UMTRA program, manager of the site and ground water program, comments made by two residents of Fall City are included in this document.
Final Design Report for the RH LLW Disposal Facility (RDF) Project, Revision 3
International Nuclear Information System (INIS)
Austad, Stephanie Lee
2015-01-01
The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.
Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2011-05-01
This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.
Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project
International Nuclear Information System (INIS)
Duncan, David
2011-01-01
This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.
Swiss projects for the final disposal of radioactive wastes
International Nuclear Information System (INIS)
McCombie, C.
1987-01-01
At present, the major part of the discussion does not focus on technical assessment methodology and data, but rather on interpretation of the available geologic data for high-level waste disposal planning. Meanwhile, plans for the implementation of repositories have to be developed. Accordingly, the longer-term studies on high-level waste disposal are proceeding at a pace appropriate for their relatively far-future timescales, and intensified efforts are being put into projects for design, siting, safety assessment and construction of the more urgently required repository for low and intermediate level waste. (orig./PW) [de
A Study on Site Selecting for National Project including High Level Radioactive Waste Disposal
Energy Technology Data Exchange (ETDEWEB)
Kim, Kilyoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
2016-10-15
Many national projects are stopped since sites for the projects are not determined. The sites selections are hold by NIMBY for unpleasant facilities or by PYMFY for preferable facilities among local governments. The followings are the typical ones; NIMBY projects: high level radioactive waste disposal, THAAD, Nuclear power plant(NPP), etc. PIMFY projects: South-east new airport, KTX station, Research center for NPP decommission, etc. The site selection for high level radioactive waste disposal is more difficult problem, and thus government did not decide and postpone to a dead end street. Since it seems that there is no solution for site selection for high level radioactive waste disposal due to NIMBY among local governments, a solution method is proposed in this paper. To decide a high level radioactive waste disposal, the first step is to invite a bid by suggesting a package deal including PIMFY projects such as Research Center for NPP decommission. Maybe potential host local governments are asked to submit sealed bids indicating the minimum compensation sum that they would accept the high level radioactive waste disposal site. If there are more than one local government put in a bid, then decide an adequate site by considering both the accumulated PESS point and technical evaluation results. By considering how fairly preferable national projects and unpleasant national projects are distributed among local government, sites selection for NIMBY or PIMFY facilities is suggested. For NIMBY national projects, risk, cost benefit analysis is useful and required since it generates cost value to be used in the PESS. For many cases, the suggested method may be not adequate. However, similar one should be prepared, and be basis to decide sites for NIMBY or PIMFY national projects.
Uranium Mill Tailings Remedial Action fiscal year 1992 roadmap
International Nuclear Information System (INIS)
1993-02-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project is funded and managed as two separate projects: Surface remediation (UMTRA-S) and Groundwater compliance (UMTRA-G). Surface remediation is a Major System Acquisition and has been completed at 10 sites, 7 sites are under construction, and 7 sites are in the planning stage. The planning stages of the UMTRA-G Project, a major project, began in April 1991. A programmatic environmental impact statement (PEIS) has been started. Site characterization work and baseline risk assessment will begin FY 1993. Thus, the UMTRA-S Project is a mature and ongoing program with the roles of various organizations well defined, while the UMTRA-G Project is still being formulated and the interfaces between the DOE, states and tribes, and the EPA are being established. The Office of Environmental Restoration and Waste Management (EM) directed that all projects under its authority develop roadmaps for their activities. The UMTRA Project Roadmap was developed by the UMTRA Project Office with input from the TAC, RAC, the GJPO, and assistance from SAIC. A single roadmap has been prepared for both the UMTRA-S and UMTRA-G Projects. This was deemed appropriate due to the close relationship between the projects and to the fact that the same Government and contractor personnel are preparing the roadmaps. Roadmap development is a planning process that focuses on issue identification, root-cause analysis, and issues resolution. The methodology is divided into three phases: assessment, analysis, and issues resolution
The opalinus clay project - disposal of medium and highly-active nuclear wastes
International Nuclear Information System (INIS)
Mueller, U.
2003-01-01
This article describes the project to demonstrate the feasibility of disposing of long-living medium-active and highly-radioactive nuclear wastes in sedimentary rock in Switzerland. The disposal tasks to be carried out are reviewed and the solutions proposed are described, including short-term handling, intermediate storage and final disposal of low, medium and highly-active wastes. The present state of affairs is described and, in particular, the feasibility of implementing a final storage facility in the opalinus clay beds to be found in northern Switzerland. The project for such a facility in the wine-growing area of the canton of Zurich is described in detail, including the storage concept, the technology to be used and operational aspects as well as questions of safety
International Nuclear Information System (INIS)
Gilbert, R. O.; Meyer, H. R.; Miller, M. L.; Begley, C.
1988-06-01
This report describes a field study conducted at the Ambrosia Lake, New Mexico, UMTRA site to obtain data for calibrating the RTRAK Sodium Iodide (NaI) detectors for estimating concentrations of Ra-226 in surface soil. The statistical analyses indicate that the data are useful for estimating the calibration equations. Several statistical models are used to evaluate which model is best as a basis for the calibration equations. A procedure is provided for using the estimated calibration equations and extensive RTRAK measurements to estimate the average Ra-226 concentration on 100-m 2 land areas to determine whether additional remedial action is needed. The UMTRA Project office proposes to use the RTRAK for cleanup verification of surface Ra-226 contamination. The system enables 100% coverage of areas having undergone remedial action. The sensitivity of the system enables verification at less than 5 pCi/g averaged over 100 m 2 , as specified by the Environmental Protection Agency (EPA) standards (40 CFR Part 192). This analysis demonstrates RTRAK's ability to meet reasonable standards of statistical accuracy, using commonly accepted procedures. 5 refs., 8 figs., 1 tab
Uranium Mill Tailings Remedial Action Project fiscal year 1997 annual report to stakeholders
International Nuclear Information System (INIS)
1997-01-01
The fiscal year (FY) 1997 annual report is the 19th report on the status of the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. In 1978, Congress directed the DOE to assess and clean up contamination at 24 designated former uranium processing sites. The DOE is also responsible for cleaning up properties in the vicinity of the sites where wind and water erosion deposited tailings or people removed them from the site for use in construction or landscaping. Cleanup has been undertaken in cooperation with state governments and Indian tribes within whose boundaries the sites are located. It is being conducted in two phases: the surface project and the groundwater project. This report addresses specifics about the UMTRA surface project
Fiscal year 1996 annual report to stakeholders, Uranium Mill Tailings Remedial Action Project
International Nuclear Information System (INIS)
1996-01-01
This is the Fiscal Year (FY) 1996 annual report on the status of the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. In 1978, Congress directed the DOE to assess and clean up contamination at 24 designated former uranium processing sites. The DOE is also responsible for cleaning up properties in the vicinity of the sites where wind and water erosion deposited tailings or people removed them from the site for use in construction of landscaping. Cleanup is being undertaken in cooperation with state governments and Indian tribes within whose boundaries the sites are located. It is being conducted in two phases: the surface project and the ground water project. This report addresses specifics about the surface phase of the UMTRA Project
International Nuclear Information System (INIS)
1988-01-01
The mission of the Uranium Mill Tailings Remedial Action (UMTRA) Project is explicitly stated and directed in the Uranium Mill Tailings Radiation Control Act of 1978, Public Law 95-604, 42 USC 7901 (hereinafter referred to as the ''Act''). Title I of the Act authorizes the Department of Energy (DOE) to undertake remedial actions at 24 designated inactive uranium processing sites and associated vicinity properties containing uranium mill tailings and other residual radioactive materials derived from the processing sites. The Act, amended in January 1983, by Public Law 97-415, also authorizes DOE to perform remedial actions at vicinity properties in Edgemont, South Dakota. Cleanup of the Edgemont processing site is the responsibility of the Tennessee Valley Authority. This document describes the plan, organization, system, and methodologies used to manage the design, construction, and other activities required to clean up the designated sites and associated vicinity properties in accordance with the Act. The plan describes the objectives of the UMTRA Project, defines participants' roles and responsibilities, outlines the technical approach for accomplishing the objectives, and describes the planning and managerial controls to be used in integrating and performing the Project mission. 21 figs., 21 tabs
Quality control of radioactive waste disposal container for borehole project
International Nuclear Information System (INIS)
Mohamad Pauzi Ismail; Suhairy Sani; Azhar Azmi; Ilham Mukhriz Zainal Abidin
2014-01-01
This paper explained quality control of radioactive disposal container for the borehole project. Non-destructive Testing (NDT) is one of the quality tool used for evaluating the product. The disposal container is made of 316L stainless steel. The suitable NDT method for this object is radiography, ultrasonic, penetrant and eddy current testing. This container will be filled with radioactive capsules and cement mortar is grouted to fill the gap. The results of NDT measurements are explained and discussed. (author)
Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2011-05-01
This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.
Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project
Energy Technology Data Exchange (ETDEWEB)
Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham
2011-03-01
This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-03-01
The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, contaminated soil, equipment, and materials associated with the former uranium ore processing at UMTRA Project sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to minimize further contamination of ground water. Surface cleanup at the UMTRA Project site near Lakeview, Oregon, was completed in 1989. The mill operated from February 1958 to November 1960. The Ground Water Project evaluates the nature and extent of ground water contamination that resulted from the uranium ore processing activities. The Ground Water Project is in its beginning stages. Human health may be at risk from exposure to ground water contaminated by uranium ore processing. Exposure could occur by drinking water pumped out of a hypothetical well drilled in the contaminated areas. Ecological risks to plants or animals may result from exposure to surface water and sediment that have received contaminated ground water. A risk assessment describes a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the ecological environment may be exposed, and the health or ecological effects that could result from that exposure. This risk assessment is a site-specific document that will be used to evaluate current and potential future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will determine whether any action is needed to protect human health or the ecological environment.
International Nuclear Information System (INIS)
Filbert, Wolfgang; Herold, Philipp
2015-01-01
The paper summarizes the lessons learned in demonstration projects regarding operational safety during the final disposal of vitrified waste and spent fuel. The three demonstration projects for the direct disposal of vitrified waste and spent fuel are described. The first two demonstration projects concern the shaft transport of heavy payloads of up to 85 t and the emplacement operations in the mine. The third demonstration project concerns the borehole emplacement operation. Finally, open issues for the next steps up to licensing of the emplacement and disposal systems are summarized.
Energy Technology Data Exchange (ETDEWEB)
None
1996-10-01
This programmatic environmental impact statement (PElS) was prepared for the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project to comply with the National Environmental Policy Act (NEPA). This PElS provides an analysis of the potential impacts of the alternatives and ground water compliance strategies as well as potential cumulative impacts. On November 8, 1978, Congress enacted the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law, codified at 42 USC §7901 et seq. Congress found that uranium mill tailings " ... may pose a potential and significant radiation health hazard to the public, and that every reasonable effort should be made to provide for stabilization, disposal, and control in a safe, and environmentally sound manner of such tailings in order to prevent or minimize other environmental hazards from such tailings." Congress authorized the Secretary of Energy to designate inactive uranium processing sites for remedial action by the U.S. Department of Energy (DOE). Congress also directed the U.S. Environmental Protection Agency (EPA) to set the standards to be followed by the DOE for this process of stabilization, disposal, and control. On January 5, 1983, EPA published standards (40 CFR Part 192) for the disposal and cleanup of residual radioactive materials. On September 3, 1985, the U.S. Court of Appeals for the Tenth Circuit set aside and remanded to EPA the ground water provisions of the standards. The EPA proposed new standards to replace remanded sections and changed other sections of 40 CFR Part 192. These proposed standards were published in the Federal Register on September 24, 1987 (52 FR 36000). Section 108 of the UMTRCA requires that DOE comply with EPA's proposed standards in the absence of final standards. The Ground Water Project was planned under the proposed standards. On January 11, 1995, EPA published the final rule, with which the DOE must now comply. The PElS and the Ground Water Project are
International Nuclear Information System (INIS)
1996-01-01
This programmatic environmental impact statement (PElS) was prepared for the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project to comply with the National Environmental Policy Act (NEPA). This PElS provides an analysis of the potential impacts of the alternatives and ground water compliance strategies as well as potential cumulative impacts. On November 8, 1978, Congress enacted the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law, codified at 42 USC §7901 et seq. Congress found that uranium mill tailings ' ... may pose a potential and significant radiation health hazard to the public, and that every reasonable effort should be made to provide for stabilization, disposal, and control in a safe, and environmentally sound manner of such tailings in order to prevent or minimize other environmental hazards from such tailings.' Congress authorized the Secretary of Energy to designate inactive uranium processing sites for remedial action by the U.S. Department of Energy (DOE). Congress also directed the U.S. Environmental Protection Agency (EPA) to set the standards to be followed by the DOE for this process of stabilization, disposal, and control. On January 5, 1983, EPA published standards (40 CFR Part 192) for the disposal and cleanup of residual radioactive materials. On September 3, 1985, the U.S. Court of Appeals for the Tenth Circuit set aside and remanded to EPA the ground water provisions of the standards. The EPA proposed new standards to replace remanded sections and changed other sections of 40 CFR Part 192. These proposed standards were published in the Federal Register on September 24, 1987 (52 FR 36000). Section 108 of the UMTRCA requires that DOE comply with EPA's proposed standards in the absence of final standards. The Ground Water Project was planned under the proposed standards. On January 11, 1995, EPA published the final rule, with which the DOE must now comply. The PElS and the Ground Water Project are in
Determination of aerosol size distributions at uranium mill tailings remedial action project sites
International Nuclear Information System (INIS)
Newton, G.J.; Reif, R.H.; Hoover, M.D.
1994-01-01
The U.S. Department of Energy (DOE) has an ongoing program, the Uranium Mill Tailings Remedial Action (UMTRA) Project, to stabilize piles of uranium mill tailings in order to reduce the potential radiological hazards to the public. Protection of workers and the general public against airborne radioactivity during remedial action is a top priority at the UMTRA Project. The primary occupational radionuclides of concern are 230 Th, 226 Ra, 210 Pb, 210 Po, and the short-lived decay products of 222 Rn with 230 Th causing the majority of the committed effective dose equivalent (CEDE) from inhaling uranium mill tailings. Prior to this study, a default particle size of 1.0 μm activity median aerodynamic diameter (AMAD) was assumed for airborne radioactive tailings dust. Because of recent changes in DOE requirements, all DOE operations are now required to use the CEDE methodology, instead of the annual effective dose equivalent (AEDE) methodology, to evaluate internal radiation exposures. Under the transition from AEDE to CEDE, with a 1.0 μm AMAD particle size, lower bioassay action levels would be required for the UMTRA Project. This translates into an expanded internal dosimetry program where significantly more bioassay monitoring would be required at the UMTRA Project sites. However, for situations where the particle size distribution is known to differ significantly from 1.0 μm AMAD, the DOE allows for corrections to be made to both the estimated dose to workers and the derived air concentration (DAC) values. For particle sizes larger than 1.0 μm AMAD, the calculated CEDE from inhaling tailings would be relatively lower
Integrated Project Management System description
International Nuclear Information System (INIS)
1994-09-01
The Integrated Program Management System (IPMS) Description is a ''working'' document that describes the work processes of the Uranium Mill Tailings Remedial Action Project Office (UMTRA) and IPMS Group. This document has undergone many revisions since the UMTRA Project began; this revision not only updates the work processes but more clearly explains the relationships between the Project Office, contractors, and other participants. The work process flow style has been revised to better describe Project work and the relationships of participants. For each work process, more background and guidance on ''why'' and ''what is expected'' is given. For example, a description of activity data sheets has been added in the work organization and the Project performance and reporting processes, as well as additional detail about the federal budget process and funding management and improved flow charts and explanations of cost and schedule management. A chapter has been added describing the Cost Reduction/Productivity Improvement Program. The Change Control Board (CCB) procedures (Appendix A) have been updated. Project critical issues meeting (PCIM) procedures have been added as Appendix B. Budget risk assessment meeting procedures have been added as Appendix C. These appendices are written to act as stand-alone documentation for each process. As the procedures are improved and updated, the documentation can be updated separately
International Nuclear Information System (INIS)
MCLELLAN, G.W.
2007-01-01
CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal issues as well as challenges with
International Nuclear Information System (INIS)
1983-03-01
The International Stripa Project is a joint undertaking by a number of countries, carried out under the sponsorship of the OECD Nuclear Energy Agency. It concerns research into the feasibility and safety of disposal of highly radioactive wastes from nuclear power generation, deep underground in crystalline rock. The Project is managed by the Division KBS of the Swedish Nuclear Fuel Supply Company (SKBF), under the direction of representatives from each participating country. This report summarizes the objectives and preliminary results of experimental work performed within the framework of the Stripa Project and that undertaken prior to the establishment of the Project at the Stripa Mine in Sweden. It also describes the part played by the Project in the development of national policies for the safe disposal of radioactive wastes
International Nuclear Information System (INIS)
1995-08-01
The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase 1) and the Ground Water Project (Phase 2). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-08-01
The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase 1) and the Ground Water Project (Phase 2). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment.
Project report for the commercial disposal of mixed low-level waste debris
Energy Technology Data Exchange (ETDEWEB)
Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.
1994-05-01
This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.
Design requirements document for project W-520, immobilized low-activity waste disposal
International Nuclear Information System (INIS)
Ashworth, S.C.
1998-01-01
This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity
Project report for the commercial disposal of mixed low-level waste debris
International Nuclear Information System (INIS)
Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.
1994-05-01
This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project
Design requirements document for project W-520, immobilized low-activity waste disposal
Energy Technology Data Exchange (ETDEWEB)
Ashworth, S.C.
1998-08-06
This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.
Environment, safety, and health regulatory implementation plan
International Nuclear Information System (INIS)
1993-01-01
To identify, document, and maintain the Uranium Mill Tailings Remedial Action (UMTRA) Project's environment, safety, and health (ES ampersand H) regulatory requirements, the US Department of Energy (DOE) UMTRA Project Office tasked the Technical Assistance Contractor (TAC) to develop a regulatory operating envelope for the UMTRA Project. The system selected for managing the UMTRA regulatory operating envelope data bass is based on the Integrated Project Control/Regulatory Compliance System (IPC/RCS) developed by WASTREN, Inc. (WASTREN, 1993). The IPC/RCS is a tool used for identifying regulatory and institutional requirements and indexing them to hardware, personnel, and program systems on a project. The IPC/RCS will be customized for the UMTRA Project surface remedial action and groundwater restoration programs. The purpose of this plan is to establish the process for implementing and maintaining the UMTRA Project's regulatory operating envelope, which involves identifying all applicable regulatory and institutional requirements and determining compliance status. The plan describes how the Project will identify ES ampersand H regulatory requirements, analyze applicability to the UMTRA Project, and evaluate UMTRA Project compliance status
US Department of Energy Uranium Mill Tailings Remedial Action ground water Project
International Nuclear Information System (INIS)
1993-01-01
The scope of the Project is to develop and implement a ground water compliance strategy for all 24 UMTRA processing sites. The compliance strategy for the processing sites must satisfy requirements of the proposed EPA ground water cleanup standards in 40 CFR Part 192, Subparts B and C (1988). This scope of work will entail the following activities, on a site-specific basis: Development of a compliance strategy based upon modification of the UMTRA Surface Project remedial action plans (RAP) or development of Ground Water Project RAPs with NRC and state or tribal concurrence on the RAP; implementation of the RAP to include establishment of institutional controls, where appropriate; institution of long-term verification monitoring for transfer to a separate DOE program on or before the Project end date; and preparation of completion reports and final licensing on those sites that will be completed prior to the Project end date
Engineering feasibility analysis for in-situ stabilization of Canonsburg residues. [UMTRA project
Energy Technology Data Exchange (ETDEWEB)
1982-01-01
The US Department of Energy is considering several methods for carrying out remedial actions in Canonsburg, Pennsylvania, at the site of an inactive uranium-processing mill. The main objective of this study is to determine the feasibility of in-situ stabilization as the remedial action. In-situ stabilization is an alternative to site decontamination and offsite disposal. The problems associated with offsite hauling of large quantities of contaminated material and with the location and development of a new disposal site could be avoided by the implementation of an in-situ stabilization concept. In addition, the in-situ approach would be more cost-effective than offsite disposal. This study will establish that a technically feasible and implementable in-situ stabilization concept can be developed that meets regulatory requirements and is cost effective. This study in no way commits the DOE to implement any specific actions described herein. 11 refs., 30 figs., 24 tabs.
Offsite source recovery project - ten years of sealed source recovery and disposal
Energy Technology Data Exchange (ETDEWEB)
Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA
2010-01-01
The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources
Tumulus Disposal Demonstration Project assessment plan for potential worker exposure: Revision 1
International Nuclear Information System (INIS)
Styers, D.R.
1989-03-01
The purpose of the ''Assessment Plan for Potential Worker Exposure'' is to determine the potential radiological exposures to the workers as they dispose of low-level radioactive wastes (LLW) on the Tumulus Disposal Demonstration Project (TDDP). An evaluation of the work procedures and precautions will be made so as to maintain the exposure levels As Low As Reasonably Achievable (ALARA). 10 refs., 10 figs
Energy Technology Data Exchange (ETDEWEB)
MCLELLAN, G.W.
2007-02-07
CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal
Lessons Learned from the On-Site Disposal Facility at Fernald Closure Project
International Nuclear Information System (INIS)
Kumthekar, U.A.; Chiou, J.D.
2006-01-01
The On-Site Disposal Facility (OSDF) at the U.S. Department of Energy's (DOE) Fernald Closure Project near Cincinnati, Ohio is an engineered above-grade waste disposal facility being constructed to permanently store low level radioactive waste (LLRW) and treated mixed LLRW generated during Decommissioning and Demolition (D and D) and soil remediation performed in order to achieve the final land use goal at the site. The OSDF is engineered to store 2.93 million cubic yards of waste derived from the remediation activities. The OSDF is intended to isolate its LLRW from the environment for at least 200 years and for up to 1,000 years to the extent practicable and achievable. Construction of the OSDF started in 1997 and waste placement activities will complete by the middle of April 2006 with the final cover (cap) placement over the last open cell by the end of Spring 2006. An on-site disposal alternative is considered critical to the success of many large-scale DOE remediation projects throughout the United States. However, for various reasons this cost effective alternative is not readily available in many cases. Over the last ten years Fluor Fernald Inc. has cumulated many valuable lessons learned through the complex engineering, construction, operation, and closure processes of the OSDF. Also in the last several years representatives from other DOE sites, State agencies, as well as foreign government agencies have visited the Fernald site to look for proven experiences and practices, which may be adapted for their sites. This paper present a summary of the major issues and lessons leaned at the Fernald site related to engineering, construction, operation, and closure processes for the disposal of remediation waste. The purpose of this paper is to share lessons learned and to benefit other projects considering or operating similar on-site disposal facilities from our successful experiences. (authors)
International Nuclear Information System (INIS)
1995-09-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Public Affairs Plan is to establish goals for the fiscal year (FY) 1996 UMTRA Project public affairs program and to identify specific activities to be conducted during the year. It describes the roles of various agencies involved in the public affairs program and defines the functions of the UMTRA Project Technical Assistance Contractor (TAC) Public Affairs Department. It replaces the FY 1995 Public Affairs Plan (DOE/AL/62350-154). The plan also describes the US Department of Energy's (DOE) plans to keep stakeholders and other members of the public informed about UMTRA Project policies, plans, and activities, and provide opportunities for stakeholders and interested segments of the public to participate in UMTRA Project decision-making processes. The plan applies to the UMTRA Project Team; the DOE Grand Junction Projects Office (GJPO); the DOE Albuquerque Operations Office, Office of Public Affairs (OPA); the TAC; the UMTRA Project Remedial Action Contractor (RAC); and other cooperating agencies
Mine subsidence control projects associated with solid waste disposal facilities
International Nuclear Information System (INIS)
Wood, R.M.
1994-01-01
Pennsylvania environmental regulations require applicant's for solid waste disposal permits to provide information regarding the extent of deep mining under the proposed site, evaluations of the maximum subsidence potential, and designs of measures to mitigate potential subsidence impact on the facility. This paper presents three case histories of deep mine subsidence control projects at solid waste disposal facilities. Each case history presents site specific mine grouting project data summaries which include evaluations of the subsurface conditions from drilling, mine void volume calculations, grout mix designs, grouting procedures and techniques, as well as grout coverage and extent of mine void filling evaluations. The case studies described utilized basic gravity grouting techniques to fill the mine voids and fractured strata over the collapsed portions of the deep mines. Grout mixtures were designed to achieve compressive strengths suitable for preventing future mine subsidence while maintaining high flow characteristics to penetrate fractured strata. Verification drilling and coring was performed in the grouted areas to determine the extent of grout coverage and obtain samples of the in-place grout for compression testing. The case histories presented in this report demonstrate an efficient and cost effective technique for mine subsidence control projects
Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2011-04-01
This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.
Remote-Handled Low Level Waste Disposal Project Alternatives Analysis
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2010-10-01
This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.
Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2011-03-01
This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.
Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis
Energy Technology Data Exchange (ETDEWEB)
David Duncan
2010-06-01
This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.
International Nuclear Information System (INIS)
1993-01-01
The goal of the Uranium Mill Tailings Remedial Action (UMTRA) Project in North Dakota is to improve the environment and reduce the negative health effects associated with residual radioactive material (RRM) from the inactive processing sites at Belfield and Bowman, North Dakota. A secondary benefit of the UMTRA Project is economic gain. The 1992 North Dakota Economic Impact Study (NDEIS) analyzes the impact of the remedial actions at the inactive Belfield and Bowman processing sites and their associated vicinity properties. This analysis is based on the assumption that the state of North Dakota will provide 10 percent of the funding required for remediation. For every dollar the state of North Dakota invests in the Belfield and Bowman onsite portion of the UMTRA Project, it will realize $5.04 in gross labor income (i.e., gross labor income divided by the state's total funding requirement). For every dollar the state of North Dakota invests, it will realize a net return of $3.04 (i.e., net benefit divided by the state's total funding requirement). This reflects only labor expenditure and employment impact. ff state and local non-labor tax benefits were considered in the net economic benefit, North Dakota could receive significantly more than $3.04 for each dollar it invests. The UMTRA Project work at Belfield and Bowman will benefit the state of North Dakota. Benefits include a reduction in the negative health effects caused by low-level RRM, an improvement in the environment, and increased economic growth
Remedial action and waste disposal project - ERDF readiness evaluation plan
International Nuclear Information System (INIS)
Casbon, M.A.
1996-06-01
This Readiness Evaluation Report presents the results of the project readiness evaluation to assess the readiness of the Environmental Restoration and Disposal Facility. The evaluation was conducted at the conclusion of a series of readiness activities that began in January 1996. These activities included completion of the physical plant; preparation, review, and approval of operating procedures; definition and assembly of the necessary project and operational organizations; and activities leading to regulatory approval of the plant and operating plans
International Nuclear Information System (INIS)
Texier, D.; Degnan, P.; Loutre, M.F.; Lemaitre, G.; Paillard, D.; Thorne, M.
2000-01-01
The BIOCLIM project (Modelling Sequential Biosphere systems under Climate change for Radioactive Waste Disposal) is part of the EURATOM fifth European framework programme. The project was launched in October 2000 for a three-year period. It is coordinated by ANDRA, the French national radioactive waste management agency. The project brings together a number of European radioactive waste management organisations that have national responsibilities for the safe disposal of radioactive wastes, and several highly experienced climate research teams. Waste management organisations involved are: NIREX (UK), GRS (Germany), ENRESA (Spain), NRI (Czech Republic) and ANDRA (France). Climate research teams involved are: LSCE (CEA/CNRS, France), CIEMAT (Spain), UPMETSIMM (Spain), UCL/ASTR (Belgium) and CRU (UEA, UK). The Environmental Agency for England and Wales provides a regulatory perspective. The consulting company Enviros Consulting (UK) assists ANDRA by contributing to both the administrative and scientific aspects of the project. This paper describes the project and progress to date. (authors)
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This risk assessment evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site.
International Nuclear Information System (INIS)
1994-09-01
This risk assessment evaluates potential impacts to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an off-site disposal cell by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial activities at the site were conducted from 1989 to 1993. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment evaluates the most contaminated ground water that flows beneath the processing site toward the Colorado River. The monitor wells that have consistently shown the highest concentrations of most contaminants are used to assess risk. This risk assessment will be used in conjunction with additional activities and documents to determine what remedial action may be needed for contaminated ground water at the site
Energy Technology Data Exchange (ETDEWEB)
1994-11-01
This baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota, evaluates the potential impacts to public health or the environment from contaminated ground water at this site. This contamination is a result of the uraniferous lignite ashing process, when coal containing uranium was burned to produce uranium. Potential risk is quantified only for constituents introduced by the processing activities and not for the constituents naturally occurring in background ground water in the site vicinity. Background ground water, separate from any site-related contamination, imposes a percentage of the overall risk from ground water ingestion in the Bowman site vicinity. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to address soil and ground water contamination at the site. The UMTRA Surface Project involves the determination of the extent of soil contamination and design of an engineered disposal cell for long-term storage of contaminated materials. The UMTRA Ground Water Project evaluates ground water contamination. Based on results from future site monitoring activities as defined in the site observational work plan and results from this risk assessment, the DOE will propose an approach for managing contaminated ground water at the Bowman site.
International Nuclear Information System (INIS)
1994-11-01
This baseline risk assessment of ground water contamination at the inactive uraniferous lignite ashing site near Bowman, North Dakota, evaluates the potential impacts to public health or the environment from contaminated ground water at this site. This contamination is a result of the uraniferous lignite ashing process, when coal containing uranium was burned to produce uranium. Potential risk is quantified only for constituents introduced by the processing activities and not for the constituents naturally occurring in background ground water in the site vicinity. Background ground water, separate from any site-related contamination, imposes a percentage of the overall risk from ground water ingestion in the Bowman site vicinity. The US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project is developing plans to address soil and ground water contamination at the site. The UMTRA Surface Project involves the determination of the extent of soil contamination and design of an engineered disposal cell for long-term storage of contaminated materials. The UMTRA Ground Water Project evaluates ground water contamination. Based on results from future site monitoring activities as defined in the site observational work plan and results from this risk assessment, the DOE will propose an approach for managing contaminated ground water at the Bowman site
International Nuclear Information System (INIS)
1994-09-01
This baseline risk assessment evaluates potential impacts to public health and the environment resulting from ground water contamination from past activities at the former uranium processing site in Canonsburg, Pennsylvania. The US Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Project has placed contaminated material from this site in an on-site disposal cell. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the UMTRA Ground Water Project. Currently, no domestic or drinking water well tap into contaminated ground water of the two distinct ground water units: the unconsolidated materials and the bedrock. Because there is no access, no current health or environmental risks are associated with the direct use of the contaminated ground water. However, humans and ecological organisms could be exposed to contaminated ground water if a domestic well were to be installed in the unconsolidated materials in that part of the site being considered for public use (Area C). The first step is evaluating ground water data collected from monitor wells at the site. For the Canonsburg site, this evaluation showed the contaminants in ground water exceeding background in the unconsolidated materials in Area C are ammonia, boron, calcium, manganese, molybdenum, potassium, strontium, and uranium
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This baseline risk assessment evaluates potential impacts to public health and the environment resulting from ground water contamination from past activities at the former uranium processing site in Canonsburg, Pennsylvania. The US Department of Energy Uranium Mill Tailings Remedial Action (UMTRA) Project has placed contaminated material from this site in an on-site disposal cell. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the UMTRA Ground Water Project. Currently, no domestic or drinking water well tap into contaminated ground water of the two distinct ground water units: the unconsolidated materials and the bedrock. Because there is no access, no current health or environmental risks are associated with the direct use of the contaminated ground water. However, humans and ecological organisms could be exposed to contaminated ground water if a domestic well were to be installed in the unconsolidated materials in that part of the site being considered for public use (Area C). The first step is evaluating ground water data collected from monitor wells at the site. For the Canonsburg site, this evaluation showed the contaminants in ground water exceeding background in the unconsolidated materials in Area C are ammonia, boron, calcium, manganese, molybdenum, potassium, strontium, and uranium.
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)
International Nuclear Information System (INIS)
Baudoin, P.; Gay, D.; Certes, C.; Serres, C.
2000-01-01
The SPA project (Spent fuel disposal Performance Assessment) is the latest of four integrated performance assessment exercises on nuclear waste disposal in geological formations, carried out in the framework of the European Community 'Nuclear Fission' Research Programmes. The SPA project, which was undertaken by ENRESA, GRS, IPSN, NRG, SCK.CEN and VTT between May 1996 and April 1999, was devoted to the study of disposal of spent fuel in various host rock formations (clay, crystalline rocks and salt formation). This project is a direct continuation of the efforts made by the European Community since 1982 to build a common understanding of the methods applicable to deep disposal performance assessment. (authors)
International Nuclear Information System (INIS)
1994-11-01
This baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado, evaluates potential public health and environmental impacts resulting from ground water contamination at the former North Continent (NC) and Union Carbide (UC) uranium mill processing sites. The tailings at these sites will be placed in a disposal cell at the proposed Burro Canyon, Colorado, site. The US Department of Energy (DOE) anticipates the start of the first phase remedial action by the spring of 1995 under the direction of the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project will evaluate ground water contamination. This baseline risk assessment is the first site-specific document for these sites under the Ground Water Project. It will help determine the compliance strategy for contaminated ground water at the site. In addition, surface water and sediment are qualitatively evaluated in this report
Energy Technology Data Exchange (ETDEWEB)
1994-11-01
This baseline risk assessment of ground water contamination at the uranium mill tailings sites near Slick Rock, Colorado, evaluates potential public health and environmental impacts resulting from ground water contamination at the former North Continent (NC) and Union Carbide (UC) uranium mill processing sites. The tailings at these sites will be placed in a disposal cell at the proposed Burro Canyon, Colorado, site. The US Department of Energy (DOE) anticipates the start of the first phase remedial action by the spring of 1995 under the direction of the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The second phase of the UMTRA Project will evaluate ground water contamination. This baseline risk assessment is the first site-specific document for these sites under the Ground Water Project. It will help determine the compliance strategy for contaminated ground water at the site. In addition, surface water and sediment are qualitatively evaluated in this report.
Household Hazardous Waste Disposal Project. Summary Report. Metro Toxicant Program Report No. 1A.
Ridgley, Susan M.; Galvin, David V.
The Household Hazardous Waste Disposal Project was established as an interagency effort to reduce the level of toxicants entering the environment by developing a control plan for the safe disposal of small quantities of household chemicals. This summary report provides an overview of the aspects of this problem that were examined, and the steps…
International Nuclear Information System (INIS)
Seitz, R.
2011-01-01
It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.
Final disposal of radioactive wastes in Switzerland: concept and overview of Project Guarantee 1985
International Nuclear Information System (INIS)
Anon.
1985-01-01
The validity of the operational licences of the existing Swiss nuclear power plants (NPP) Beznau I and II, Muehleberg, Goesgen and Leibstadt after 31st. December 1985 is, because of official requirements, dependent on the demonstration of permanent, safe management and final disposal of radioactive waste. For this purpose, the NPP companies have to prepare a so-called guarantee project and present this to the Bundesrat for review. The appropriate investigations and research have been carried out by Nagra (National Cooperative for the Storage of Radioactive Waste). The 1985 Project Gewaehr (Guarantee) is described in an eight volume report NGB 85-01 to 85-08 and individual research projects are reported on in separate NTB-series reference reports. The present volume NGB 85-01 takes the form of a self-contained project overview in which the concepts for nuclear waste management are described, the contents of the remaining volumes NGB 85-02 to 85-08 are summarized and Project conclusions are drawn from Project Gewaehr 1985. Project Gewaehr 1985 covers two repository types: Type C repository for high-level and certain alpha-containing intermediate-level waste, and Type B repository for all remaining intermediate- and low-level waste. The Project shows in detail that technical feasibility of final disposal can be assumed given presently available methods, that the technical safety barriers show a high level of efficiency and that suitable geological options are available to ensure long-term safety in Switzerland as the concept is defined by official requirements. The Project safety analyses show that the chosen disposal concepts assure the protection of mankind and the environment under all realistically anticipated conditions
International Nuclear Information System (INIS)
Masuda, Sumio; Sakuma, Hideki; Umeki, Hiroyuki
2015-01-01
Important standards and concept about geological disposal have been arranged as an international common base and are being generalized. The authors overview the concept of geological disposal, and would like this paper to help arouse broad discussions for promoting the implementation plan of geological disposal projects in the future. In recent years, the scientific and technological rationality of geological disposal has been recognized internationally. With the addition of discussions from social viewpoints such as ethics, economy, etc., geological disposal projects are in the stage of starting after establishment of social consensus. As an international common base, the following consolidated and systematized items have been presented as indispensable elements in promoting business projects: (1) step-by-step approach, (2) safety case, (3) reversibility and recovery potential, and (4) trust building and communications. This paper outlines the contents of the following cases, where international common base was reflected on the geological disposal projects in Japan: (1) final disposal method and safety regulations, and (2) impact of the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident on geological disposal plan. (A.O.)
Considerations for alternative low-level radioactive disposal sites
International Nuclear Information System (INIS)
Beck, J.M.
1986-01-01
In the immediate future, there is a need for low-level radioactive disposal sites to accommodate wastes that would otherwise be placed at a later date in permanent, government sanctioned ''compact'' sites. Until these ''compact'' sites become operational, a potential, relatively low-cost alternative exists in the numerous inactive uranium processing sites that are likewise proposed for remedial action removal or stabilization operations. This paper addressed disposal from the aspects of engineering design, economics and liability of participating parties. Many uranium (and by-product) processing facilities in the western states now stand idle due to current economic conditions within the industry. Many more were previously deactivated for various reasons. All must be dealt with under the UMTRA Program Guidelines with regard to removal, reclamation or other remedial action activities. With cooperative efforts, some of these sites would appear to be suitable for disposal of small volume, low-level radioactive wastes that presently render urban properties valueless in terms of real estate and aesthetic values. Likely sites would appear to be those slated for in-place stabilization and reclamation, particularly where the urban property material has a lower level of radioactivity than the disposal site material. The resultant impacts for site stabilization and reclamation would be solely in the areas of increased material volumes (generally requiring a minimal increase in engineering design complexity) and liability. Clearly, liability will be the overriding factor in such an approach. With the complex hierarchy of regulatory agencies involved and the private sector, what appears to be a relative simple and economic approach may have extreme difficulty in achieving reality
International Nuclear Information System (INIS)
1995-12-01
As required by the Romer-Twining Agreement of 1990, the US Department of Energy (DOE) has prepared this annual economic impact study for the state of Colorado. This report assesses the economic impacts related to the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project in Colorado during the state fiscal year (FY) between 1 July 1994 and 30 June 1995. To estimate net economic benefit, employment, salaries and wages, and other related economic benefits are discussed, quantified, and then compared to the state's 10 percent share of the remedial action costs. Actual data obtained from sites currently undergoing remedial action were used as the basis for analyses. If data were not available, estimates were used to derive economic indicators. This study describes the types of employment associated with the UMTRA Project and estimates of the numbers of people employed by UMTRA Project subcontractors in Colorado during state FY 1995. Employment totals are reported in estimated average annual jobs; however, the actual number of workers at the site fluctuates depending on weather and on the status of remedial action activities. In addition, the actual number of people employed on the Project during the year may be higher than the average annual employment reported due to the temporary nature of some of the jobs
River Protection Project (RPP) Immobilized Low- Ativity Waste (ILAW) Disposal Plan
International Nuclear Information System (INIS)
BRIGGS, M.G.
2000-01-01
This document replaces HNF-1517, Rev 2 which is deleted. It incorporates updates to reflect changes in programmatic direction associated with the vitrification plant contract change and associated DOE/ORP guidance. In addition it incorporates the cancellation of Project W-465, Grout Facility, and the associated modifications to Project W-520, Immobilized High-Level Waste Disposal Facility. It also includes document format changes and section number modifications consistent with CH2M HILL Hanford Group, Inc. procedures
Energy Technology Data Exchange (ETDEWEB)
Choi, Heui Joo; Choi, Jong Won; Lee, Jong Youl; Jung, Jong Tae; Kim, Sung Ki; Lee, Min Soo; Cho, Dong Keun; Kook, Dong Hak
2008-11-15
High level radioactive waste disposal system project for advanced nuclear fuel cycle produced this report which are dealing with the repository status of proceding countries as of 2008. This report has brief review on disposal facilities which are operating and will be operating and on future plan of those nations. The other report 'Development of the Geological Disposal System for High Level Waste' which was produced like this report time and this report would help the readers grasp the current repository status. Because our country is a latecomer in the HLW disposal world, it is strongly recommended to catch up with advanced disposal system and concepts of developed nations and this report is expected to make it possible. There are several nations which were the main survey target; Finland, USA, Sweden, Germany, France, Switzerland, and Japan. Recent information was applied to this report and our project team will produce annual state-of-the-art report with continuous updates.
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-11-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project, and the Ground Water Project. For the UMTRA Project site located near Naturita, Colorado, phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado. The surface cleanup will reduce radon and other radiation emissions from the former uranium processing site and prevent further site-related contamination of ground water. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health and the environment, and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water or surface water that has mixed with contaminated ground water. Therefore, a risk assessment was conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.
International Nuclear Information System (INIS)
1995-11-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project, and the Ground Water Project. For the UMTRA Project site located near Naturita, Colorado, phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation's Upper Burbank Repository at Uravan, Colorado. The surface cleanup will reduce radon and other radiation emissions from the former uranium processing site and prevent further site-related contamination of ground water. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health and the environment, and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water or surface water that has mixed with contaminated ground water. Therefore, a risk assessment was conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment
Overview of uranium mill tailings remedial action project of the United States of America 1995-1996
International Nuclear Information System (INIS)
Edge, R.
1997-01-01
From the early 1940's through the 1960's the United States federal government contracted for processed uranium ore for national defense research, weapons development and commercial nuclear energy. When these contracts were terminated, the mills ceased operation leaving large uranium tailings on the former mill sites. The purpose of the Uranium Remedial Action Project (UMTRA) is to minimize or eliminate potential health hazards resulting from exposure of the public to the tailings at these abandons sites. There are 24 inactive uranium mill tailings sites, in 10 states and an Indian reservation lands, included for clean up under the auspices of UMTRA. Presently the last 2 sites are under remediation. This paper addresses the progress of the project over the last two years. (author)
International Nuclear Information System (INIS)
1995-04-01
The US Department of Energy (DOE) is responsible for performing remedial action to bring surface and ground water contaminant levels at 24 inactive uranium processing sites into compliance with the US Environmental Protection Agency (EPA) standards. DOE is accomplishing this through the Uranium Mill Tailings Remedial Action (UMTRA) Surface and Ground Water Projects. Remedial action will be conducted with the concurrence of the US Nuclear Regulatory Commission (NRC) and the full participation of affected states and Indian tribes. Uranium processing activities at most of 24 the inactive mill sites resulted in the contamination of ground water beneath and, in some cases, downgradient of the sites. This contaminated ground water often has elevated levels of constituents such as uranium and nitrate. The purpose of the UMTRA Ground Water Project is to eliminate, or reduce to acceptable levels, the potential health and the environmental consequences of milling activities by meeting the EPA standards in areas where ground water has been contaminated. The first step in the UMTRA Ground Water Project is the preparation of this programmatic environmental impact statement (PEIS). This document analyzes potential impacts of four programmatic alternatives, including the proposed action. The alternatives do not address site-specific ground water compliance strategies. Rather, the PEIS is a planning document that provides a framework for conducting the Ground Water Project; assesses the potential programmatic impacts of conducting the Ground Water Project; provides a method for determining the site-specific ground water compliance strategies; and provides data and information that can be used to prepare site-specific environmental impacts analyses more efficiently
The AGP-Project conceptual design for a Spanish HLW final disposal facility
International Nuclear Information System (INIS)
Biurrun, E.; Engelmann, H.-J.; Huertas, F.; Ulibarri, A.
1992-01-01
Within the framework of the AGP Project a Conceptual Design for a HLW Final Disposal Facility to be eventually built in an underground salt formation in Spain has been developed. The AGP Project has the character of a system analysis. In the current project phase I several alternatives has been considered for different subsystems and/or components of the repository. The system variants, developed to such extent as to allow a comparison of their advantages and disadvantages, will allow the selection of a reference concept, which will be further developed to technical maturity in subsequent project phases. (author)
International Nuclear Information System (INIS)
Batandjieva, B.; Metcalf, P.
2003-01-01
Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years
International Nuclear Information System (INIS)
Bryan, W.E.; Oakley, L.B.
1993-04-01
This document summarizes the systems engineering assessment that was performed for the Mixed Waste Disposal Initiative (MWDI) Project to determine what types of documentation are required for the success of the project. The report also identifies the documents that will make up the MWDI Project Record and describes the Configuration Management Plan describes the responsibilities and process for making changes to project documentation
Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment plan
International Nuclear Information System (INIS)
April, J.G.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Plastino, J.C.; Roeck, F.V.; Tuttle, B.G.
1997-04-01
This Readiness Assessment Plan presents the methodology used to assess the readiness of the 300-FF-1 Remedial Action Project. Remediation involves the excavation, treatment if applicable, and final disposal of contaminated soil and debris associated with the waste sites in the 300-FF-1 Operable Unit. The scope of the 300-FF-1 remediation is to excavate, transport, and dispose of contaminated solid from sites identified in the 300-FF-1 Operable Unit
International Nuclear Information System (INIS)
1994-04-01
This baseline risk assessment at the former uranium mill tailings site near Shiprock, New Mexico, evaluates the potential impact to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an on-site disposal cell in 1986 through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. There are no domestic or drinking water wells in the contaminated ground water of the two distinct ground water units: the contaminated ground water in the San Juan River floodplain alluvium below the site and the contaminated ground water in the terrace alluvium area where the disposal cell is located. Because no one is drinking the affected ground water, there are currently no health or environmental risks directly associated with the contaminated ground water. However, there is a potential for humans, domestic animals, and wildlife to the exposed to surface expressions of ground water in the seeps and pools in the area of the San Juan River floodplain below the site. For these reasons, this risk assessment evaluates potential exposure to contaminated surface water and seeps as well as potential future use of contaminated ground water
Energy Technology Data Exchange (ETDEWEB)
1994-04-01
This baseline risk assessment at the former uranium mill tailings site near Shiprock, New Mexico, evaluates the potential impact to public health or the environment resulting from ground water contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in an on-site disposal cell in 1986 through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating ground water contamination. This risk assessment is the first document specific to this site for the Ground Water Project. There are no domestic or drinking water wells in the contaminated ground water of the two distinct ground water units: the contaminated ground water in the San Juan River floodplain alluvium below the site and the contaminated ground water in the terrace alluvium area where the disposal cell is located. Because no one is drinking the affected ground water, there are currently no health or environmental risks directly associated with the contaminated ground water. However, there is a potential for humans, domestic animals, and wildlife to the exposed to surface expressions of ground water in the seeps and pools in the area of the San Juan River floodplain below the site. For these reasons, this risk assessment evaluates potential exposure to contaminated surface water and seeps as well as potential future use of contaminated ground water.
International Nuclear Information System (INIS)
Kawanishi, Motoi; Komada, Hiroya; Tsuchino, Susumu; Shiozaki, Isao; Kitayama, Kazumi; Akasaka, Hidenari; Inagaki, Yusuke; Kawamura, Hideki
1999-01-01
The making high activity of the high-level radioactive waste disposal business shall be fully started after establishing of the implementing organization which is planned around 2000. Considering each step of disposal business, in this study, the implementation procedure for a series of disposal business such as the selection of the disposal site, the construction and operation of the disposal facility, the closure and decommissioning of the disposal facility and the management after closure, which are carried forward by the implementation body is discussed in detail from the technical viewpoint and an example of the master schedule is proposed. Furthermore, we investigate and propose the concept of the geological disposal which becomes important in carrying forward to making of the business of the disposal, such as the present site selection smoothly, the fundamental idea of the safe securing for disposal, the basic idea to get trust to the disposal technique and the geological environmental condition which is the basic condition of this whole study for the disposal business making. (author)
West Hackberry Brine Disposal Project pre-discharge characterization. Final report
Energy Technology Data Exchange (ETDEWEB)
DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C. (eds.)
1982-01-01
The physical, chemical and biological attributes are described for: (1) a coastal marine environment centered about a Department of Energy Strategic Petroleum Reserve (SPR) brine disposal site 11.4 km off the southwest coast of Louisiana; and (2) the lower Calcasieu and Sabine estuarine systems that provide leach waters for the SPR project. A three month sampling effort, February through April 1981, and previous investigations from the study area are integrated to establish baseline information for evaluation of impacts from brine disposal in the nearshore marine waters and from freshwater withdrawal from the coastal marsh of the Chenier Plain. January data are included for some tasks that sampled while testing and mobilizing their instruments prior to the February field effort. The study addresses the areas of physical oceanography, estuarine hydrology and hydrography, water and sediment quality, benthos, nekton, phytoplankton, zooplankton, and data management.
Buffer zone monitoring plan for the Dos Rios subdivision, Gunnison, Colorado
International Nuclear Information System (INIS)
1996-02-01
This report presents a plan for water quality monitoring at the Dos Rios subdivision (Units 2, 3, and the Island Unit) that is intended to satisfy the informational needs of residents who live southwest (downgradient) of the former Gunnison processing site. Water quality monitoring activities described in this report are designed to protect the public from residual contamination that entered the ground water as a result of previous uranium milling operations. Requirements presented in this monitoring plan are also included in the water sampling and analysis plan (WSAP) for the Gunnison Uranium Mill Tailings Remedial Action (UMTRA) Project site. The Gunnison WSAP is a site-specific document prepared by the U.S. Department of Energy (DOE) that provides background, guidance, and justification for future ground water sampling and analysis activities for the UMTRA Project Gunnison processing and disposal sites. The WSAP will be updated annually, as additional water quality data are collected and interpreted, to provide ongoing protection for public health and the environment
International Nuclear Information System (INIS)
1992-10-01
To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards the US Department of Energy (DOE) proposes to meet background concentrations or the EPA maximum concentration limits (MCLS) for hazardous constituents in groundwater in the uppermost aquifer at the point of compliance (POC) at the Gunnison Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site near Gunnison, Colorado. The proposed remedial action will ensure protection of human health and the environment. A summary of the principal features of the water resources protection strategy for the Gunnison disposal site is included in this report
International Nuclear Information System (INIS)
1991-12-01
To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards (Subpart A of 40 CFR 192), the US Department of Energy (DOE) proposes to meet background concentrations or the EPA maximum concentration limits (MCLS) for hazardous constituents in groundwater in the uppermost aquifer (Cliff House/Menefee aquifer) at the point of compliance (POC) at the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site in Bodo Canyon near Durango, Colorado (DOE, 1989). Details of hydrologic site characterization at the disposal site are provided in Attachment 3, Groundwater Hydrology Report. The principal features of the water resources protection strategy for the Bodo Canyon disposal site are presented in this document
International Nuclear Information System (INIS)
Fujita, Tomoo; Taniguchi, Naoki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Ota, Kunio; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Hama, Katsuhiro; Kunimaru, Takanori; Takeuchi, Ryuji; Tanai, Kenji; Kurikami, Hiroshi; Wakasugi, Keiichiro; Ishii, Eiichi
2011-03-01
This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project, of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the project as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)
Uranium mill tailings remedial action project real estate management plan
International Nuclear Information System (INIS)
1994-09-01
This plan summarizes the real estate requirements of the US Department of Energy's (DOE) Uranium Mill Tailings Action (UMTRA) Project, identifies the roles and responsibilities of project participants involved in real estate activities, and describes the approaches used for completing these requirements. This document is intended to serve as a practical guide for all project participants. It is intended to be consistent with all formal agreements, but if a conflict is identified, the formal agreements will take precedence
Uranium mill tailings remedial action project real estate management plan
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
This plan summarizes the real estate requirements of the US Department of Energy`s (DOE) Uranium Mill Tailings Action (UMTRA) Project, identifies the roles and responsibilities of project participants involved in real estate activities, and describes the approaches used for completing these requirements. This document is intended to serve as a practical guide for all project participants. It is intended to be consistent with all formal agreements, but if a conflict is identified, the formal agreements will take precedence.
International Nuclear Information System (INIS)
1993-07-01
This Action Plan contains responses, planned actions, and estimated costs for addressing the findings discovered in the Environmental Management Audit conducted for the U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action Project (UMTRA), October 26 through November 6, 1992. This document should be read in conjunction with the Audit Report to ensure the findings addressed in this document are fully understood. The scope of the UMTRA Environmental Management Audit was comprehensive and encompassed all areas of environmental management except environmental programs pertaining to the National Environmental Policy Act (NEPA) compliance. The Audit Report listed 18 findings: 11 were identified as compliance findings, and the remaining 7 were best management practice findings. Root cause analysis was performed on all the findings. The results of the analysis as well as planned corrective actions are summarized in Section 5.0. All planned actions were prioritized using the Tiger Team Assessment Corrective Action Plan system. Based on assigned priorities, all planned actions were costed by fiscal year. This Action Plan contains a description of the organizational and management structures to be used to implement the Action Plan, a brief discussion of root cause analysis and funding, followed by the responses and planned actions for each finding. A member of the UMTRA Project Office (PO) has been assigned responsibility for tracking the progress on each of the findings. The UMTRA PO staff wrote and/or approved all of the corrective actions recorded in this Action Plan
International Nuclear Information System (INIS)
1996-02-01
The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment. Human health risk may result from exposure to ground water contaminated from uranium ore processing. Exposure could occur from drinking water obtained from a well placed in the areas of contamination. Furthermore, environmental risk may result from plant or animal exposure to surface water and sediment that have received contaminated ground water
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-08-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase I), and the Ground Water Project (phase II). For the UMTRA Project site located near Naturita, Colorado (the Naturita site), phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation`s Upper Burbank Repository at Uravan, Colorado, about 13 road miles (mi) (21 kilometers [km]) to the northwest. No uranium mill tailings are involved because the tailings were removed from the Naturita site and placed at Coke Oven, Colorado, during 1977 to 1979. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health or the environment; and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has received contaminated ground water. Therefore, a risk assessment is conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment.
Energy Technology Data Exchange (ETDEWEB)
NONE
1996-02-01
The U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (Phase I) and the Ground Water Project (Phase II). Under the UMTRA Surface Project, tailings, radioactive contaminated soil, equipment, and materials associated with the former uranium ore processing sites are placed into disposal cells. The cells are designed to reduce radon and other radiation emissions and to prevent further ground water contamination. The Ground Water Project evaluates the nature and extent of ground water contamination resulting from the uranium ore processing activities. Two UMTRA Project sites are near Rifle, Colorado: the Old Rifle site and the New Rifle site. Surface cleanup at the two sites is under way and is scheduled for completion in 1996. The Ground Water Project is in its beginning stages. A risk assessment identifies a source of contamination, how that contamination reaches people and the environment, the amount of contamination to which people or the environment may be exposed, and the health or environmental effects that could result from that exposure. This report is a site-specific document that will be used to evaluate current and future impacts to the public and the environment from exposure to contaminated ground water. This evaluation and further site characterization will be used to determine if action is needed to protect human health or the environment. Human health risk may result from exposure to ground water contaminated from uranium ore processing. Exposure could occur from drinking water obtained from a well placed in the areas of contamination. Furthermore, environmental risk may result from plant or animal exposure to surface water and sediment that have received contaminated ground water.
International Nuclear Information System (INIS)
1995-08-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of the Surface Project (phase I), and the Ground Water Project (phase II). For the UMTRA Project site located near Naturita, Colorado (the Naturita site), phase I involves the removal of radioactively contaminated soils and materials and their transportation to a disposal site at Union Carbide Corporation's Upper Burbank Repository at Uravan, Colorado, about 13 road miles (mi) (21 kilometers [km]) to the northwest. No uranium mill tailings are involved because the tailings were removed from the Naturita site and placed at Coke Oven, Colorado, during 1977 to 1979. Phase II of the project will evaluate the nature and extent of ground water contamination resulting from uranium processing and its effect on human health or the environment; and will determine site-specific ground water compliance strategies in accordance with the US Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. Human health risks could occur from drinking water pumped from a hypothetical well drilled in the contaminated ground water area. Environmental risks may result if plants or animals are exposed to contaminated ground water, or surface water that has received contaminated ground water. Therefore, a risk assessment is conducted for the Naturita site. This risk assessment report is the first site-specific document prepared for the Ground Water Project at the Naturita site. What follows is an evaluation of current and possible future impacts to the public and the environment from exposure to contaminated ground water. The results of this evaluation and further site characterization will be used to determine whether any action is needed to protect human health or the environment
Study on quality assurance for high-level radioactive waste disposal project
International Nuclear Information System (INIS)
Takada, Susumu
2005-01-01
The U.S. Department of Energy (DOE) has developed comparatively detailed quality assurance requirements for the high-level radioactive waste disposal systems. Quality assurance is recognized as a key issue for confidence building and smooth implementation of the HLW program in Japan, and Japan is at an initial phase of repository development. Then the quality assurance requirements at site research and site selection, site characterization, and site suitability analysis used in the Yucca Mountain project were examined in detail and comprehensive descriptions were developed using flow charts. Additionally, the applicability to the Japan high-level radioactive waste disposal project was studied. The examination and study were performed for the following QA requirements: The requirements that have the relative importance at site research and site selection, site characterization, and site suitability analysis (such as planning and performing scientific investigations, sample control, data control, model development and use, technical report review, software control, and control of the electric management of data). The requirements that have the relative importance at the whole repository phases (such as quality assurance program, document control, and control of quality assurance records). (author)
International Nuclear Information System (INIS)
1994-12-01
The Colorado economic impact study summarizes employment and economic benefits to the state from activities associated with the Uranium Mill Tailings Remedial Action (UMTRA) Project during Colorado state fiscal year 1994 (1 July 1993 through 30 June 1994). To capture employment information, a questionnaire was distributed to subcontractor employees at the active UMTRA Project sites of Grand Junction, Naturita, Gunnison, and Rifle, Colorado. Economic data were requested from each site prime subcontractor, as well as from the Remedial Action Contractor. Information on wages, taxes, and subcontract expenditures in combination with estimates and economic multipliers is used to estimate the dollar economic benefits to Colorado during the state fiscal year. Finally, the fiscal year 1994 estimates are compared to fiscal year 1993 employment and economic information
The Dutch geologic radioactive waste disposal project
International Nuclear Information System (INIS)
Hamstra, J.; Verkerk, B.
1981-01-01
The Final Report reviews the work on geologic disposal of radioactive waste performed in the Netherlands over the period 1 January 1978 to 31 December 1979. The attached four topical reports cover detailed subjects of this work. The radionuclide release consequences of an accidental flooding of the underground excavations during the operational period was studied by the institute for Atomic Sciences in Agriculture (Italy). The results of the quantitative examples made for different effective cross-sections of the permeable layer connecting the mine excavations with the boundary of the salt dome, are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multi-layer disposal configurations were analysed and compared. A more detailed description is given of specific design and construction details of a waste repository such as the shaft sinking and construction, the disposal mine development, the mine ventilation and the different plugging and sealing procedures for both the disposal boreholes and the shafts. Thanks to the hospitality of the Gesellschaft fuer Strahlenforschung, an underground working area in the Asse mine became available for performing a dry drilling experiment, which resulted successfully in the drilling of a 300 m deep disposal borehole from a mine room at the -750 m level
International Nuclear Information System (INIS)
Labalette, Th.
2011-01-01
The French Act of 28 June 2006 identifies reversible disposal in deep geological facilities as the benchmark solution for long-term management of high-level waste (HLW) and for intermediate-level long-lived waste (ILW-LL). The Act tasks ANDRA (national agency for the management of radioactive wastes) with the pursuit of studies and research on the choice of a site and the design of the repository, with a view to examining the licence application in 2015 and, provided that the licence is granted, to make the facility operational by 2025. At the end of 2009, ANDRA submitted to the Government its proposals regarding the site and the design of the Industrial Centre for Geological Disposal, known as CIGEO. With the definition of a possible area for the construction of underground disposal facilities, one of the key stages in the project has been achieved. The choice of a surface site will be validated following the public consultation scheduled for the end of 2012. The project is now on the point of entering the definition stage (preliminary design). CIGEO will be a nuclear facility unlike any other. It will be built and operated for a period of over 100 years. For it to be successful, the project must meet certain requirements related to its integration in the local area, industrial planning, safety and reversibility, while also controlling costs. Reversibility is a very important concept that will be defined by law. It is ANDRA's responsibility to ensure that a reasonable balance is found between these different concerns. (author)
Wildlife mitigation and monitoring report Gunnison, Colorado, site
International Nuclear Information System (INIS)
1997-04-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project is administered by the U.S. Department of Energy (DOE); its purpose is to cleanup uranium mill tailings and other contaminated material at 24 UMTRA Project sites in 10 states. This report summarizes the wildlife mitigation and monitoring program under way at the Gunnison UMTRA Project, Gunnison, Colorado. Remedial action at the Gunnison site was completed in December 1995 and is described in detail in the Gunnison completion report. The impacts of this activity were analyzed in the Gunnison environmental assessment (EA). These impacts included two important game species: the pronghorn antelope (Antilocapra americans) and sage grouse (Wentrocerus urophasianus). Haul truck traffic was predicted to limit antelope access to water sources north of the Tenderfoot Mountain haul road and that truck traffic along this and other haul roads could result in antelope road kills. Clearing land at the disposal cell, haul road and borrow site activities, and the associated human activities also were predicted to negatively impact (directly and indirectly) sage grouse breeding, nesting, loafing, and wintering habitat. As a result, an extensive mitigation and monitoring plan began in 1992. Most of the monitoring studies are complete and the results of these studies, written by different authors, appear in numerous reports. This report will: (1) Analyze existing impacts and compare them to predicted impacts. (2) Summarize mitigation measures. (3) Summarize all existing monitoring data in one report. (4) Analyze the effectiveness of the mitigation measures
Energy Technology Data Exchange (ETDEWEB)
Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)
2015-07-01
International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory
International Nuclear Information System (INIS)
1995-11-01
This report contains the comment and response document for the Draft Long-Term Surveillance Plan of the Bodo Canyon Site in Durango, California. This is a part of the Uranium Mill Tailings Remedial Action (UMTRA) Project. Questions and comments regarding specific sections or statements in the report are described and then a response to each review comment or question is provided
International Nuclear Information System (INIS)
Dupuis, Marie-Claude; Gonnot, Francois-Michel
2013-07-01
Andra is exploring several options for the disposal of low-level long-lived waste (LLW-LL). With the French Government's approval, in June 2008 Andra began looking around France for a site to build an LLW-LL repository. In late 2008 it provided the Government with a report analysing the geological, environmental and socio-economic aspects of the forty odd municipalities that expressed an interest in the project. After the withdrawal of the two municipalities chosen in 2009 to conduct geological investigations, the government asked Andra to re-explore the various management options for graphite and radium-bearing waste, focusing in particular on ways to manage these types of waste separately. The High Committee for Transparency and Information on Nuclear Safety (HCTISN) created a working group to provide feedback on the search for a site for LLW-LL. Andra submitted a report to the Government in late 2012. This report contains proposals for continuing the search and draw in particular on the HCTISN's recommendations. Contents: 1 - Radioactive waste (Sources, Types, Management, Waste to be disposed of at Cigeo, Cigeo's estimated disposal capacities, Where IS HLW and ILW-LL being stored until Cigeo is commissioned? 2 - Why deep geological disposal? (A 15-year research programme, Presentation and assessment of the research results, The public debate of 2005-2006, Deep geological disposal ratified by the 2006 Planning Act, The 2006 Planning Act: other areas of research complementary to deep geological disposal, The situation in other countries); 3 - Why the Meuse/Haute-Marne site? (Selection of the Meuse and Haute-Marne site to host an underground research laboratory, The geological formation in the Meuse and Haute-Marne site, Callovo-Oxfordian clay, Siting of Cigeo's installations); 4 - How will Cigeo operate? (The installations at Cigeo, Construction of Cigeo, Transport of waste packages, Operation of Cigeo, Closure of Cigeo); 5 - Safety at Cigeo
Bure CLIS: role, operation, disposal project
International Nuclear Information System (INIS)
Jaquet, B.
2011-01-01
The Local Information and Oversight Committee (CLIS) is an independent body tasked by law to monitor studies carried out by the French National Radioactive Waste Management Agency (ANDRA) at the Bure laboratory and in the area surrounding Bure, within the framework of research on radioactive waste management and, in particular, on final disposal of such waste in deep geological formations. The role of the CLIS, whose members include representatives of the State, Parliament, local authorities, unions, associations and the medical profession, is to provide all population groups, beginning with the inhabitants of La Meuse and La Haute-Marne departments, with information regarding these studies and their results, as well as the underground repository project and the stakes involved: it is thus the chief contact for the inhabitants of the area. It also encourages discussion of a project that is subject to a long decision-making process, during which the CLIS is called upon to give its opinion at different stages. The objectives of the CLIS' actions are to provide information to as wide a public as possible (through public meetings, a regular newsletter and a web site) using its own data (appraisals and independent assessments), so that the public can effectively contribute to the debates held throughout the process, and also to be an independent player in the process, whenever its involvement is required and even when this is not specifically planned. (author)
Iraq nuclear facility dismantlement and disposal project
Energy Technology Data Exchange (ETDEWEB)
Cochran, J R; Danneels, J [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W D [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C J; Chesser, R K [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)
2007-07-01
The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)
Spent fuel waste disposal: analyses of model uncertainty in the MICADO project
International Nuclear Information System (INIS)
Grambow, B.; Ferry, C.; Casas, I.; Bruno, J.; Quinones, J.; Johnson, L.
2010-01-01
The objective was to find out whether international research has now provided sufficiently reliable models to assess the corrosion behavior of spent fuel in groundwater and by this to contribute to answering the question whether the highly radioactive used fuel from nuclear reactors can be disposed of safely in a geological repository. Principal project results are described in the paper
Slope and bank erosional stability of the Canonsburg, Pennsylvania, UMTRA disposal site
International Nuclear Information System (INIS)
1994-12-01
This report was prepared in response to US Nuclear Regulatory Commission (NRC) comments received in a letter of 8 March 1994. This letter included discussions of the US Department of Energy (DOE) 21 May 1993 geomorphic report for the Canonsburg, Pennsylvania, site. To clarify the NRC's position, a DOE/NRC conference call was held on 12 April 1994. The NRC clarified that it did not require a preliminary erosion protection design for the Canonsburg site, but directed the DOE to address a ''one-bad-year'' scenario. The NRC wants confirmation that one bad year of stream flooding and landsliding will not release residual radioactive material (RRM) from the Canonsburg site into the creek. The NRC is concerned that a bad year theoretically could occur between postcell-closure inspections. These annual inspections are conducted in September or October. The NRC suggested that the following procedures should be conducted in this analysis: a flooding analysis, including the maximum saturation levels (flood water elevations) anticipated during a 100-year flood; a stream bank erosion analysis to determine how much of the bank adjacent to the site may be removed in a bad year; a slope stability analysis to determine how far back the site would be disturbed by slope instability that could be triggered by a bad year of stream bank erosion; and a ''critical cross section'' study to show the relationship of the RRM located outside the disposal cell to the maximum computer estimated erosion/landslide activity
International Nuclear Information System (INIS)
2016-05-01
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants
International Nuclear Information System (INIS)
Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica
2008-01-01
Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of
Bentonite-amended soil special study
International Nuclear Information System (INIS)
1989-12-01
This special study was conducted to assess the viability of soil with a high percentage of bentonite added as an infiltration barrier in the cover of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cells. To achieve maximum concentration limits (MCLs) at several UMTRA Project sites, covers with a very low permeability are needed. If alternate concentration limits (ACLs) are the appropriate site groundwater compliance strategy, the US Department of Energy (DOE) is required to demonstrate, among other things, that the infiltration to the disposal cell is as low as reasonably achievable, and hence that the cover has a very low permeability. When the study discussed here was begun, the lowest permeability element available was CLAYMAX R , a manufactured liner material constructed of natural material (bentonite clay) between two geosynthetics.The strength of soil-bentonite mixes was measured to see if they could be placed on sideslopes and not pose stability problems. Also evaluated were the hydraulic conductivities of soil-bentonite mixes. If the strengths and permeabilities of soils with a high percentage of bentonite are favorable, the soils may be used as infiltration barriers in current cover designs without changing pile geometries. The scope of work for this study called for a literature review and a two-phased laboratory testing program. This report presents the results of the literature review and the first phase of the testing program
International Nuclear Information System (INIS)
Jantzen, C.M.
2000-01-01
A vitrification process was developed and successfully implemented by the US Department of Energy's (DOE) Savannah River Site (SRS) and at the West Valley Nuclear Services (WVNS) to convert high-level liquid nuclear wastes (HLLW) to a solid borosilicate glass for safe long term geologic disposal. Over the last decade, SRS has successfully completed two additional vitrification projects to safely dispose of mixed low level wastes (MLLW) (radioactive and hazardous) at the SRS and at the Oak Ridge Reservation (ORR). The SRS, in conjunction with other laboratories, has also demonstrated that vitrification can be used to dispose of a wide variety of MLLW and low-level wastes (LLW) at the SRS, at ORR, at the Los Alamos National Laboratory (LANL), at Rocky Flats (RF), at the Fernald Environmental Management Project (FEMP), and at the Hanford Waste Vitrification Project (HWVP). The SRS, in conjunction with the Electric Power Research Institute and the National Atomic Energy Commission of Argentina (CNEA), have demonstrated that vitrification can also be used to safely dispose of ion-exchange (IEX) resins and sludges from commercial nuclear reactors. In addition, the SRS has successfully demonstrated that numerous wastes declared hazardous by the US Environmental Protection Agency (EPA) can be vitrified, e.g. mining industry wastes, contaminated harbor sludges, asbestos containing material (ACM), Pb-paint on army tanks and bridges. Once these EPA hazardous wastes are vitrified, the waste glass is rendered non-hazardous allowing these materials to be recycled as glassphalt (glass impregnated asphalt for roads and runways), roofing shingles, glasscrete (glass used as aggregate in concrete), or other uses. Glass is also being used as a medium to transport SRS americium (Am) and curium (Cm) to the Oak Ridge Reservation (ORR) for recycle in the ORR medical source program and use in smoke detectors at an estimated value of $1.5 billion to the general public
25 CFR 171.420 - Can I dispose of sewage, trash, or other refuse on a BIA irrigation project?
2010-04-01
... 25 Indians 1 2010-04-01 2010-04-01 false Can I dispose of sewage, trash, or other refuse on a BIA... AND WATER IRRIGATION OPERATION AND MAINTENANCE Irrigation Facilities § 171.420 Can I dispose of sewage, trash, or other refuse on a BIA irrigation project? No. Sewage, trash, or other refuse are considered...
International Nuclear Information System (INIS)
1995-02-01
This risk assessment evaluates the possibility of health and environmental risks from contaminated ground water at the uranium mill tailings site near Durango, Colorado. The former uranium processing site's contaminated soil and material were removed and placed at a disposal site located in Body Canyon, Colorado, during 1986--1991 by the US Departments of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating the nature and extent of ground water contamination at the site. This risk assessment follows an approach similar to that used by the US Environmental Protection Agency. The first step is to determine what site-related contaminants are found in ground water samples. The next step in the risk assessment is to determine how much of these contaminants people might ingest if they got their drinking water from a well on the site. In accordance with standard practice for this type of risk assessment, the highest contaminant concentrations from the most contaminated wells are used. The risk assessment then explains the possible health problems that could result from this amount of contamination
Energy Technology Data Exchange (ETDEWEB)
1995-02-01
This risk assessment evaluates the possibility of health and environmental risks from contaminated ground water at the uranium mill tailings site near Durango, Colorado. The former uranium processing site`s contaminated soil and material were removed and placed at a disposal site located in Body Canyon, Colorado, during 1986--1991 by the US Departments of Energy`s Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating the nature and extent of ground water contamination at the site. This risk assessment follows an approach similar to that used by the US Environmental Protection Agency. The first step is to determine what site-related contaminants are found in ground water samples. The next step in the risk assessment is to determine how much of these contaminants people might ingest if they got their drinking water from a well on the site. In accordance with standard practice for this type of risk assessment, the highest contaminant concentrations from the most contaminated wells are used. The risk assessment then explains the possible health problems that could result from this amount of contamination.
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Public Affairs Plan is to establish goals for the Fiscal Year 1995 UMTRA public affairs program and identify specific activities to be conducted during the year. It also describes the roles of various agencies involved in the conduct of the public affairs program and defines the functions of the Technical Assistance Contractor (TAC) Public Affairs Department. It integrates and replaces the Public Participation Plan (DOE/AL/62350-47D) and Public Information Plan (DOE/AL/623590-71). The plan describes the US Department of Energy`s (DOE) plans to keep stakeholders and other members of the public informed about project policies, plans, and activities, and provide opportunities for stakeholders and interested segments of the public to participate in project decision-making processes. The plan applies to the UMTRA Project Office; the DOE Albuquerque Operations Office, Office of Intergovernmental and External Affairs (OIEA); the UMTRA TAC; the UMTRA Remedial Action Contractor (RAC); and other cooperating agencies.
International Nuclear Information System (INIS)
1994-09-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Public Affairs Plan is to establish goals for the Fiscal Year 1995 UMTRA public affairs program and identify specific activities to be conducted during the year. It also describes the roles of various agencies involved in the conduct of the public affairs program and defines the functions of the Technical Assistance Contractor (TAC) Public Affairs Department. It integrates and replaces the Public Participation Plan (DOE/AL/62350-47D) and Public Information Plan (DOE/AL/623590-71). The plan describes the US Department of Energy's (DOE) plans to keep stakeholders and other members of the public informed about project policies, plans, and activities, and provide opportunities for stakeholders and interested segments of the public to participate in project decision-making processes. The plan applies to the UMTRA Project Office; the DOE Albuquerque Operations Office, Office of Intergovernmental and External Affairs (OIEA); the UMTRA TAC; the UMTRA Remedial Action Contractor (RAC); and other cooperating agencies
Disposal of tritium-exposed metal hydrides
International Nuclear Information System (INIS)
Nobile, A.; Motyka, T.
1991-01-01
A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R ampersand D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed
Technical database and management system (DBMS) for the UMTRA project processing sites
International Nuclear Information System (INIS)
Hillman, R.L.; Mohr, D.E.
1985-01-01
The technical DBMS is a structured and organized method for collecting, storing, retrieving, and analyzing technical data based upon standard operating procedures and quality control measures. The automated environment created by this design exists both as a repository for processing site technical data and the analysis techniques used against this data for site characterization, evaluation, and design. The system is composed of diverse technical subjects that are collectively used to address remedial action problems associated with mill tailings disposal. These technical subjects include hydrology, geology, geochemistry, radiology, and engineering
Technical assistance contractor Management Plan. Final [report
Energy Technology Data Exchange (ETDEWEB)
1993-09-01
The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) and its major teaming partners [Roy F. Weston, Inc. (RFW), Sergent, Hauskins & Beckwith Agra, Inc. (SHB Agra), and Geraghty & Miller, Inc. (G&M)]. The first three companies have worked together effectively on the UMTRA Project for more than 10 years. With the initiation of the UMTRA Groundwater Project in April 1991, a need arose to increase the TAC`s groundwater technical breadth and depth, so G&M was brought in to augment the team`s capabilities. The TAC contract`s scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both surface and groundwater projects. The TAC team continues to support the DOE in completing surface remedial actions and initiating groundwater remediation work for start-up, characterization, design, construction oversight, and remedial operations. A key feature of the TAC`s management approach is the extensive set of communication systems implemented for the UMTRA Project. These systems assist all functional disciplines in performing UMTRA Project tasks associated with management, technical support, administrative support, and financial/project controls.
Technical assistance contractor Management Plan
International Nuclear Information System (INIS)
1993-09-01
The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) and its major teaming partners [Roy F. Weston, Inc. (RFW), Sergent, Hauskins ampersand Beckwith Agra, Inc. (SHB Agra), and Geraghty ampersand Miller, Inc. (G ampersand M)]. The first three companies have worked together effectively on the UMTRA Project for more than 10 years. With the initiation of the UMTRA Groundwater Project in April 1991, a need arose to increase the TAC's groundwater technical breadth and depth, so G ampersand M was brought in to augment the team's capabilities. The TAC contract's scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both surface and groundwater projects. The TAC team continues to support the DOE in completing surface remedial actions and initiating groundwater remediation work for start-up, characterization, design, construction oversight, and remedial operations. A key feature of the TAC's management approach is the extensive set of communication systems implemented for the UMTRA Project. These systems assist all functional disciplines in performing UMTRA Project tasks associated with management, technical support, administrative support, and financial/project controls
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the first is the Surface Project, and the second is the Ground Water Project. For the UMTRA Project site known as the Vitro site, near Salt Lake City, Utah, Surface Project cleanup occurred from 1985 to 1987. The UMTRA Project`s second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. A risk assessment is the process of describing a source of contamination and showing how that contamination may reach people and the environment. The amount of contamination people or the environment may be exposed to is calculated and used to characterize the possible health or environmental effects that may result from this exposure. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Vitro site. The results of this report and further site characterization of the Vitro site will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards.
International Nuclear Information System (INIS)
Harvego, Lisa
2009-01-01
The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory's recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy's ability to meet obligations with the State of Idaho
The disposal of orphan wastes using the greater confinement disposal concept
International Nuclear Information System (INIS)
Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.
1991-01-01
In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs
Low-level radioactive waste in the northeast: disposal volume projections
International Nuclear Information System (INIS)
1982-10-01
The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m 3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%
Nordic nuclear safety research 1994-1997. Project on disposal of radioactive waste
International Nuclear Information System (INIS)
Broden, Karin
1999-01-01
This presentation describes the Nordic Nuclear Safety Research (NKS) programme, which is a scientific co-operation programme in nuclear safety, radiation protection and emergence preparedness. The purpose of the programme is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, manuals, recommendations, and other types of background material. This material is to serve decision-makers and other concerned staff members at authorities, research establishments and enterprises in the nuclear field. Three waste disposal projects under NKS are briefly described: (1) Waste characterisation, (2) Performance analysis of the engineered barrier system of the repositories for low- and intermediate-level waste, (3) Environmental impact assessment
International Nuclear Information System (INIS)
Ramos, S.J.; Berven, B.A.; Little, C.A.
1986-08-01
The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups
International Nuclear Information System (INIS)
Ramos, S.J.; Berven, B.A.; Little, C.A.
1986-01-01
The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups
Environmental Restoration Disposal Facility (Project W-296) Safety Assessment
International Nuclear Information System (INIS)
Armstrong, D.L.
1994-08-01
This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment
Environmental Restoration Disposal Facility (Project W-296) Safety Assessment
Energy Technology Data Exchange (ETDEWEB)
Armstrong, D.L.
1994-08-01
This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.
International Nuclear Information System (INIS)
1995-09-01
The Uranium Mill Tailings Remedial Action (UMTRA) Project consists of two phases: the first is the Surface Project, and the second is the Ground Water Project. For the UMTRA Project site known as the Vitro site, near Salt Lake City, Utah, Surface Project cleanup occurred from 1985 to 1987. The UMTRA Project's second phase, the Ground Water Project, evaluates the nature and extent of ground water contamination resulting from uranium processing and determines a strategy for ground water compliance with the Environmental Protection Agency (EPA) ground water standards established for the UMTRA Project. A risk assessment is the process of describing a source of contamination and showing how that contamination may reach people and the environment. The amount of contamination people or the environment may be exposed to is calculated and used to characterize the possible health or environmental effects that may result from this exposure. This risk assessment report is the first site-specific document prepared for the UMTRA Ground Water Project at the Vitro site. The results of this report and further site characterization of the Vitro site will be used to determine what is necessary, if anything, to protect human health and the environment while complying with EPA standards
Red-impact project: First results of the evaluations of the impact of P and T on geological disposal
International Nuclear Information System (INIS)
Marivoet, Jan; Vokal, Antonin; Gudowski, Waclaw
2006-01-01
The Red-Impact project (Impact of partitioning, transmutation and waste reduction technologies on the final nuclear waste disposal) is a research project in the 6. Framework Programme of the European Commission. The main objective of the project is to assess the impact of partitioning and transmutation (P and T) on geological disposal and waste management. The project started with the identification of a number of representative fuel cycle scenarios. Five basis scenarios are considered for the evaluations: 2 industrial scenarios and 3 innovative scenarios. Mass flow schemes have been prepared for each basis fuel cycle scenario and the corresponding neutronic calculations have been made. A first list of performance indicators that will be calculated or estimated in the project has been prepared. As a first step the impact of 2 fuel cycle scenarios, the reference 'open cycle' scenario and of the innovative 'fast neutron Gen IV' scenario, on geological repositories in granite and clay formations have been evaluated. The results obtained show that the introduction of innovative fuel cycle scenarios can result in a considerable reduction of the needed size of the geological repository. However, the impact on the radiological consequences is rather limited. Indeed, the maximum dose, which is expected to occur a few tens of thousands year after the disposal of the waste, is essentially due to fission products and their amount is about proportional to the heat generated by nuclear fissions. (authors)
Rebecca Zagozewski; Ian Judd-Henrey; Suzie Nilson; Lalita Bharadwaj
2011-01-01
The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatche...
Rebecca Zagozewski; Ian Judd-Henrey; Suzie Nilson; Lalita Bharadwaj
2011-01-01
The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatche...
Energy Technology Data Exchange (ETDEWEB)
Lisa Harvego
2009-06-01
The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratory’s recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energy’s ability to meet obligations with the State of Idaho.
International Nuclear Information System (INIS)
Metcalf, P.
2003-01-01
The scope of ASAM project covers near surface disposal facilities for all types of low and intermediate level wastes with emphasis of the post-closure safety assessment.The objectives are to explore practical application to a range of disposal facilities for a number of purposes e.g. development of design concepts, safety re-assessment, upgrading safety and to develop practical approaches to assist regulators, operators and other experts in review of safety assessment. The task of the Co-ordination Group are: reassessment of existing facilities - use of safety assessment in decision making on selection of options (volunteer site Hungary); disused sealed sources - evaluation of disposability of disused sealed sources in near surface facilities (volunteer site Saratov, Russia); mining and minerals processing waste - evaluation of long-term safety (volunteer site pmc S. Africa). An agreement on the scope and objectives of the project are reached and the further consideration, such as human intrusion/institutional control/security; waste from oil/gas industry; very low level waste; categorization of sealed sources coordinated with other IAEA activities are outlined
Compas project stress analysis of HLW containers: behaviour under realistic disposal conditions
International Nuclear Information System (INIS)
Ove Arup and Partners, London
1990-01-01
The Compas project is concerned with the structural performance of metal overpacks which may be used to encapsulate vitrified high-level waste (HLW) forms before disposal in deep geological repositories. In this final stage of the project, analysis of an HLW overpack of realistic design is performed to predict its behaviour when subjected to likely repository loads. This analysis work is undertaken with the benefit of experience gained in previous phases of the project in which the ability to accurately predict overpack behaviour, when subjected to a uniform external pressure, was demonstrated. Burial in clay, granite and salt environments has been considered and two distinct loading arrangements identified, in an attempt to represent the worst conditions that could be imposed by such media. The analysis successfully demonstrates the ability of the containers to withstand extreme, yet credible, repository loads
Remedial action and waste disposal project: 100-DR-1 remedial action readiness evaluation plan
International Nuclear Information System (INIS)
April, J.G.; Bryant, D.L.; Calverley, C.
1996-08-01
This plan presents the method used to assess the readiness of the 100- DR-1 Remedial Action Project. Remediation of the 100-D sites (located on the Hanford Site) involves the excavation (treatment if applicable) and final disposal of contaminated soil and debris associated with the high-priority waste sites in the 100 Areas
Site characterization quality assurance for the California LLRW Disposal Site Project
International Nuclear Information System (INIS)
Hanrahan, T.P.; Ench, J.E.; Serlin, C.L.; Bennett, C.B.
1988-01-01
In December of 1985 US Ecology was chosen as the license designee for the State of California's low-level radioactive waste disposal facility. In early 1987, three candidate sites were selected for characterization studies in preparation for identifying the preferred site. The geotechnical characterization activities along with studies of the ecological and archaeological attributes, as well as assessments of the socio-economic impacts and cultural resources all provide input towards selection of the proposed site. These technical studies in conjunction with comments from local citizen committees and other interested parties are used as a basis for determining the proposed site for which full site characterization as required by California licensing requirements are undertaken. The purpose of this paper is to present an overview of the program for Quality Assurance and Quality Control for the site characterization activities on the California LLRW Disposal Site Project. The focus is on three major perspectives: The composite QA Program and two of the primary characterization activities, the geotechnical and the meteorological investigations
International Nuclear Information System (INIS)
1994-04-01
The purpose of the UMTRA Ground Water Project is to protect human health and the environment by meeting the proposed EPA standards in areas where ground water has been contaminated. The first step in the UMTRA Ground Water Project is the preparation of this programmatic environmental impact statement (PEIS). This document analyzes potential impacts of four programmatic alternatives, including the proposed action. The alternatives do not address site-specific ground water compliance. Rather, the PEIS is a planning document that provides a framework for conducting the Ground Water Project; assesses the potential programmatic impacts of conducting the Ground Water Project; provides a method for determining the site-specific ground water compliance strategies; and provides data and information that can be used to prepare site-specific environmental impacts analyses more efficiently. This PEIS differs substantially from a site-specific environmental impact statement because multiple ground water compliance strategies, each with its own unique set of potential impacts, could be used to implement all the alternatives except the no action alternative. Implementing a PEIS alternative means applying a ground water compliance strategy or strategies at a specific site. It is the use of a strategy or a combination of strategies that would result in site-specific impacts
International Nuclear Information System (INIS)
Ueda, Hiroyoshi; Suzuki, Satoru; Ishiguro, Katsuhiko; Oyamada, Kiyoshi; Yashio, Shoko; White, Matt; Wilmot, Roger
2009-01-01
NUMO (Nuclear Waste Management Organization of Japan) has the responsibility for implementing deep geological disposal of high-level (HLW) and transuranic (TRU) radioactive waste from the Japanese nuclear programme. A formal Requirements Management System (RMS) is planned to efficiently and effectively support the computerised implementation of the management strategy and the methodology required to drive the step-wise siting processes, and the following repository operational phase,. The RMS will help in the comprehensive management of the decision-making processes in the geological disposal project, in change management as the disposal system is optimised, in driving projects such as the R and D programme efficiently, and in maintaining structured records regarding past decisions, all of which lead to soundness of the project in terms of long-term continuity. The system is planned to have information handling and management functions using a database that includes the decisions/requirements in the programme under consideration, the way in which these are structured in terms of the decision-making process and other associated information. A two-year development programme is underway to develop and enhance an existing trial RMS to a practical system. Functions for change management, history management and association with the external timeline management system are being implemented in the system development work. The database format is being improved to accommodate the requirements management data relating to the facility design and to safety assessment of the deep geological repository. This paper will present an outline of the development work with examples to demonstrate the system's practicality. In parallel with the system/database developments, a case research of the use of requirements management in radioactive waste disposal projects was undertaken to identify key issues in the development of an RMS for radioactive waste disposal and specify a number of
Environmental Assessment of Ground Water Compliance at the Naturita, Colorado, UMTRA Project Site
Energy Technology Data Exchange (ETDEWEB)
None
2003-04-23
This Environmental Assessment addresses the environmental effects of a proposed action and the no action alternative to comply with U.S. Environmental Protection Agency (EPA) ground water standards at the Naturita, Colorado, Uranium Mill Tailings Remedial Action Project site. In 1998, the U.S. Department of Energy (DOE) completed surface cleanup at the site and encapsulated the tailings in a disposal cell 15 miles northwest near the former town of Uravan, Colorado. Ground water contaminants of potential concern at the Naturita site are uranium and vanadium. Uranium concentrations exceed the maximum concentration limit (MCL) of 0.044 milligram per liter (mg/L). Vanadium has no MCL; however, vanadium concentrations exceed the EPA Region III residential risk-based concentration of 0.33 mg/L (EPA 2002). The proposed compliance strategy for uranium and vanadium at the Naturita site is no further remediation in conjunction with the application of alternate concentration limits. Institutional controls with ground water and surface water monitoring will be implemented for these constituents as part of the compliance strategy. This compliance strategy will be protective of human health and the environment. The proposed monitoring program will begin upon regulatory concurrence with the Ground Water Compliance Action Plan (DOE 2002a). Monitoring will consist of verifying that institutional controls remain in place, collecting ground water samples to verify that concentrations of uranium and vanadium are decreasing, and collecting surface water samples to verify that contaminant concentrations do not exceed a regulatory limit or risk-based concentration. If these criteria are not met, DOE would reevaluate the proposed action and determine the need for further National Environmental Policy Act documentation. No comments were received from the public during the public comment period. Two public meetings were held during this period. Minutes of these meetings are included as
Environmental Assessment of Ground Water Compliance at the Naturita, Colorado, UMTRA Project Site
International Nuclear Information System (INIS)
2003-01-01
This Environmental Assessment addresses the environmental effects of a proposed action and the no action alternative to comply with U.S. Environmental Protection Agency (EPA) ground water standards at the Naturita, Colorado, Uranium Mill Tailings Remedial Action Project site. In 1998, the U.S. Department of Energy (DOE) completed surface cleanup at the site and encapsulated the tailings in a disposal cell 15 miles northwest near the former town of Uravan, Colorado. Ground water contaminants of potential concern at the Naturita site are uranium and vanadium. Uranium concentrations exceed the maximum concentration limit (MCL) of 0.044 milligram per liter (mg/L). Vanadium has no MCL; however, vanadium concentrations exceed the EPA Region III residential risk-based concentration of 0.33 mg/L (EPA 2002). The proposed compliance strategy for uranium and vanadium at the Naturita site is no further remediation in conjunction with the application of alternate concentration limits. Institutional controls with ground water and surface water monitoring will be implemented for these constituents as part of the compliance strategy. This compliance strategy will be protective of human health and the environment. The proposed monitoring program will begin upon regulatory concurrence with the Ground Water Compliance Action Plan (DOE 2002a). Monitoring will consist of verifying that institutional controls remain in place, collecting ground water samples to verify that concentrations of uranium and vanadium are decreasing, and collecting surface water samples to verify that contaminant concentrations do not exceed a regulatory limit or risk-based concentration. If these criteria are not met, DOE would reevaluate the proposed action and determine the need for further National Environmental Policy Act documentation. No comments were received from the public during the public comment period. Two public meetings were held during this period. Minutes of these meetings are included as
Publications desktop survival guide
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-06-01
Purpose of this guide is to document and simplify the writing, reviewing, and production process for the Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor (TAC) staff and to provide specific answers concerning the content, style, and format of UMTRA Project documents. Goal of the UMTRA Project document preparation process is to deliver to the US DOE high-quality documents that meet requirements (meets expressed client needs; accurate and consistent technical content; clear writing; well organized document; consistent style). A document review process has been established to ensure that TAC documents are accurate, consistent, and well organized. The editing process applies standard rules for style and format, spelling, grammar, punctuation, and sentence structure to make the document consistent and easier to read. This guide sets forth the rules to be applied to UMTRA Project documents.
International Nuclear Information System (INIS)
Torres-Vidal, C.; Graham, D.; Batandjieva, B.
2002-01-01
The International Atomic Energy Agency (IAEA) Research Coordinated Project on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM) was launched in November 1997 and it has been underway for three years. The ISAM project was developed to provide a critical evaluation of the approaches and tools used in long-term safety assessment of near surface repositories. It resulted in the development of a harmonised approach and illustrated its application by way of three test cases - vault, borehole and Radon (a particular range of repository designs developed within the former Soviet Union) type repositories. As a consequence, the ISAM project had over 70 active participants and attracted considerable interest involving around 700 experts from 72 Member States. The methodology developed, the test cases, the main lessons learnt and the conclusions have been documented and will be published in the form of an IAEA TECDOC. This paper presents the work of the IAEA on improvement of safety assessment methodologies for near surface waste disposal facilities and the application of these methodologies for different purposes in the individual stages of the repository development. The paper introduces the main objectives, activities and outcome of the ISAM project and summarizes the work performed by the six working groups within the ISAM programme, i.e. Scenario Generation and Justification, Modelling, Confidence Building, Vault, Radon Type Facility and Borehole test cases. (author)
Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment report
International Nuclear Information System (INIS)
Carson, J.W.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Remsen, W.E.; Tuttle, B.G.; Wilson, R.C.
1997-09-01
This report documents the readiness assessment for initial startup of the 300-FF-1 Remedial Action Task. A readiness assessment verifies and documents that field activities are ready to start (or restart) safely. The 300-FF-1 assessment was initiated in April 1997. Readiness assessment activities included confirming the completion of project-specific procedures and permits, training staff, obtaining support equipment, receipt and approval of subcontractor submittals, and mobilization and construction of site support systems. The scope of the 300-FF-1 Remedial Action Task includes excavation and disposal of contaminated soils at liquid waste disposal facilities and of waste in the 618-4 Burial Ground and the 300-FF-1 landfills. The scope also includes excavation of test pits and test trenches
Energy Technology Data Exchange (ETDEWEB)
Breen, B.J. [NDA, Herdus House, Westlakes Science and Technology Park, Moor Row, Cumbria, CA24 3HU (United Kingdom); Garcia-Sineriz, J.L. [AITEMIN, c/Margarita Salas 14-Parque Leganes Tecnologico-Leganes, ES-28918, Madrid (Spain); Maurer, H. [ETH Zurich, ETH Honggerberg, CH-8093, Zurich (Switzerland); Mayer, S. [ANDRA, 1-7 rue Jean-Monnet, F-92298 Chatenay-Malabry cedex (France); Schroeder, T.J. [NRG, P.O. Box 25, NL-1755 ZG Petten (Netherlands); Verstricht, J. [EURIDICE EIG, c/o SCK.CEN, Boeretang 200, BE-2400 Mol (Belgium)
2012-07-01
Monitoring to provide information on the evolution of geological disposal presents several challenges. The 4-year, euros M 5, EC MoDeRn Project (http://www.modern-fp7.eu/), which commenced in 2009, addresses monitoring processes, state-of-the-art technology and innovative research and development of monitoring techniques. This paper discusses some of the key drivers for the development of innovative monitoring techniques and provides outlines of the demonstration programmes being conducted within MoDeRn. The aim is to develop these innovative monitoring techniques and to demonstrate them under realistic conditions present in underground laboratories. These demonstration projects, applying a range of different monitoring techniques, are being carried out at underground research facilities in different geological environments at HADES URL in Belgium (plastic clay), Bure in France (indurated clay) and at Grimsel Test Site (granite) in Switzerland. These are either built upon existing infrastructure (EC ESDRED Low pH shotcrete and TEM experiments at Grimsel; and PRACLAY experiment and underground galleries in HADES) or will be attached to infrastructure that is being developed and financed by resources outside of this project (mock-up disposal cell in Bure). At Grimsel Test Site, cross-hole and hole-to-tunnel seismic methods are being employed as a means to monitor induced changes in an artificially saturated bentonite wall confined behind a shotcrete plug. Recognising the limitations for travel-time tomography for monitoring a disposal cell, full waveform inversion techniques are being employed to enhance the capacity to monitor remote from the excavation. At the same Grimsel location, an investigation will be conducted of the potential for using a high frequency wireless (HFW) sensor network embedded within the barrier system; this will include the possibility of providing energy remotely to isolated sensors. At the HADES URL, the monitoring programme will utilise
International Nuclear Information System (INIS)
Fujita, Tomoo; Taniguchi, Naoki; Tanai, Kenji; Nishimura, Mayuka; Kobayashi, Yasushi; Hiramoto, Masayuki; Maekawa, Keisuke; Sawada, Atsushi; Makino, Hitoshi; Sasamoto, Hiroshi; Yoshikawa, Hideki; Shibata, Masahiro; Wakasugi, Keiichiro; Nakano, Katsushi; Seo, Toshihiro; Miyahara, Kaname; Naito, Morimasa; Yui, Mikazu; Matsui, Hiroya; Kurikami, Hiroshi; Kunimaru, Takanori; Ishii, Eiichi; Ota, Kunio; Hama, Katsuhiro; Takeuchi, Ryuji
2007-03-01
This report summarizes the progress of research and development on geological disposal during the surface-based investigation phase (2001-2005) in the Horonobe Underground Research Laboratory project (HOR), of which aims are to apply the design methods of geological disposal and mass transport analysis to actual geological conditions obtained from the surface-based investigations in HOR as an example of actual geological environment. For the first aim, the design methods for the geological disposal facility proposed in 'H12 report (the second progress report)' was reviewed and then improved based on the recent knowledge. The applicability of design for engineered barrier system, backfill of disposal tunnel, underground facility was illustrated. For the second aim, the conceptual structure from site investigation and evaluation to mass transport analysis was developed as a work flow at first. Then following this work flow a series of procedures for mass transport analysis was applied to the actual geological conditions to illustrate the practical workability of the work flow and the applicability of this methodology. Consequently, based on the results, future subjects were derived. (author)
International Nuclear Information System (INIS)
1991-11-01
The purpose of the Cost Reduction/Productivity Improvement Program Plan is to formalize and improve upon existing efforts to control costs which have been underway since project inception. This program plan has been coordinated with the Department of Energy (DOE) Office of Environmental Management (EM) and the DOE Field Office, Albuquerque (AL). It incorporates prior Uranium Mill Tallings Remedial Action (UMTRA) Project Office guidance issued on the subject. The opportunities for reducing cosh and improving productivity are endless. The CR/PIP has these primary objectives: Improve productivity and quality; heighten the general cost consciousness of project participants, at all levels of their organizations; identify and implement specific innovative employee ideas that extend beyond what is required through existing processes and procedures; emphasize efforts that create additional value for the money spent by maintaining the project Total Estimated Cost (TEC) at the lowest possible level
International Nuclear Information System (INIS)
1996-10-01
The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project is to eliminate, reduce, or address to acceptable levels the potential health and environmental consequences of milling activities by meeting Environmental Protection Agency (EPA) ground water standards. One of the first steps in the UMTRA Ground Water Project is the preparation of this Programmatic Environmental Impact Statement (PEIS). The EPA standards allow the use of different strategies for achieving compliance with the standards. This document analyzes the potential impacts of four alternatives for conducting the Ground Water Project. Each of the four alternatives evaluated in the PEIS is based on a different mix of strategies to meet EPA ground water standards. The PEIS is intended to serve as a programmatic planning document that provides an objective basis for determining site-specific ground water compliance strategies and data and information that can be used to prepare site-specific environmental impact analyses more efficiently. DOE will prepare appropriate further National Environmental Policy Act documentation before making site-specific decisions to implement the Ground Water Project. Affected States, Tribes, local government agencies, and members of the public have been involved in the process of preparing this PEIS; DOE encourages their continued participation in the site-specific decision making process
International Nuclear Information System (INIS)
2016-05-01
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants
Energy Technology Data Exchange (ETDEWEB)
1993-12-01
This Baseline Risk Assessment of Groundwater Contamination at the Uranium Mill Tailings Site Near Gunnison, Colorado evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells. This risk assessment evaluates the most contaminated monitor wells at the processing site. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium.
International Nuclear Information System (INIS)
1993-12-01
This Baseline Risk Assessment of Groundwater Contamination at the Uranium Mill Tailings Site Near Gunnison, Colorado evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells. This risk assessment evaluates the most contaminated monitor wells at the processing site. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium
Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal
Energy Technology Data Exchange (ETDEWEB)
Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
2016-10-15
In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.
Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal
International Nuclear Information System (INIS)
Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu
2016-01-01
In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea
International Nuclear Information System (INIS)
XiangLing, L.
2009-01-01
The management of spent nuclear fuel and other long-lived radio active waste is an important environmental issue today. Disposal in deep clay geological formations is one of the promising options to dispose of these wastes. In this context, the related research activities in the Euratom Framework Programme of European Commission are continually taking on an enhanced significance. The TIMODAZ is one of the STREP projects (Specific Targeted Research Project) in the Sixth EURATOM Framework Programme and contributes to the research related to the geological disposal of radioactive waste. The consortium is composed of a strong multidisciplinary team involving both European radioactive waste management organizations and nuclear research institutes, universities, industrial partners as well as consultancy companies (SME's). Totally, 15 partners coming from 8 countries are involved with a total budget of about 4000k EURO. Being the coordinator (through the EURIDICE expertise group), SCK-CEN plays the leading role in the project. Meanwhile, SCK-CEN participates the research in different work packages covering the laboratory tests, in-situ tests as well as the integration of TIMODAZ results within the safety case. An important item for the long-term safety of underground disposal is the proper evaluation of the DZ (damaged zone) in the clay host rock. The DZ is defined here as the zone of host rock that experiences THMC (Thermo-Hydro-Mechanical-Chemical) modifications induced by the repository, with potential major changes in the transport properties for radionuclides. The DZ is first initiated during the repository construction. Its behaviour is dynamic, dependent on changing conditions that vary from the open-drift period, to initial closure period and to the entire heating-cooling cycle of the decaying waste. The early THMC disturbances created by the excavation, the operational phase and the thermal load might be the most severe transient that the repository will undergo
The U.S. regulatory framework for long-term management of uranium mill tailings
International Nuclear Information System (INIS)
Smythe, C.; Bierley, D.; Bradshaw, M.
1995-01-01
The US established the regulatory structure for the management, disposal, and long-term care of uranium mill tailings in 1978 with the passage of the Uranium Mill Tailings Radiation Control Act (UMTRCA) (Pub. L. 95-604). This legislation has governed the cleanup and disposal of uranium tailings at both inactive and active sites. The passage of the UMTRCA established a federal regulatory program for the cleanup and disposal of uranium mill tailings in the US. This program involves the DOE, the NRC, the EPA, various states and tribal governments, private licensees, and the general public. The DOE has completed surface remediation at 14 sites, with the remaining sites either under construction or in planning. The DOE's UMTRA Project has been very successful in dealing with public and agency demands, particularly regarding disposal site selection and transportation issues. The active sites are also being cleaned up, but at a slower pace than the inactive sites, with the first site tentatively scheduled for completion in 1996
Uranium Mill Tailings Remedial Action Project, Surface Project Management Plan. Revision 1
International Nuclear Information System (INIS)
1994-12-01
Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) authorizes the US Department of Energy (DOE) to undertake remedial action at 24 designated inactive uranium processing sites and associated vicinity properties (VP) containing uranium mill tailings and related residual radioactive materials. The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project is to minimize or eliminate radiation health hazards to the public and the environment at the 24 sites and related VPs. This document describes the management organization, system, and methods used to manage the design, construction, and other activities required to clean up the designated sites and associated VPs, in accordance with the UMTRCA
Uranium Mill Tailings Remedial Action Project, Surface Project Management Plan. Revision 1
Energy Technology Data Exchange (ETDEWEB)
1994-12-01
Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) authorizes the US Department of Energy (DOE) to undertake remedial action at 24 designated inactive uranium processing sites and associated vicinity properties (VP) containing uranium mill tailings and related residual radioactive materials. The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Surface Project is to minimize or eliminate radiation health hazards to the public and the environment at the 24 sites and related VPs. This document describes the management organization, system, and methods used to manage the design, construction, and other activities required to clean up the designated sites and associated VPs, in accordance with the UMTRCA.
Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program
Energy Technology Data Exchange (ETDEWEB)
1994-02-01
In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE`s overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program.
Uranium Mill Tailings Remedial Action Project Safety Advancement Field Effort (SAFE) Program
International Nuclear Information System (INIS)
1994-02-01
In 1992, the Uranium Mill Tailings Remedial Action (UMTRA) Project experienced several health and safety related incidents at active remediation project sites. As a result, the U.S. Department of Energy (DOE) directed the Technical Assistance Contractor (TAC) to establish a program increasing the DOE's overall presence at operational remediation sites to identify and minimize risks in operations to the fullest extent possible (Attachments A and B). In response, the TAC, in cooperation with the DOE and the Remedial Action Contractor (RAC), developed the Safety Advancement Field Effort (SAFE) Program
Special study for the statistical evaluation of groundwater data trends. Final report
International Nuclear Information System (INIS)
1993-05-01
Analysis of trends over time in the concentrations of chemicals in groundwater at Uranium Mill Tailings Remedial Action (UMTRA) Project sites can provide valuable information for monitoring the performance of disposal cells and the effectiveness of groundwater restoration activities. Random variation in data may obscure real trends or may produce the illusion of a trend where none exists, so statistical methods are needed to reliably detect and estimate trends. Trend analysis includes both trend detection and estimation. Trend detection uses statistical hypothesis testing and provides a yes or no answer regarding the existence of a trend. Hypothesis tests try to reach a balance between false negative and false positive conclusions. To quantify the magnitude of a trend, estimation is required. This report presents the statistical concepts that are necessary for understanding trend analysis. The types of patterns most likely to occur in UMTRA data sets are emphasized. Two general approaches to analyzing data for trends are proposed and recommendations are given to assist UMTRA Project staff in selecting an appropriate method for their site data. Trend analysis is much more difficult when data contain values less than the reported laboratory detection limit. The complications that arise are explained. This report also discusses the impact of data collection procedures on statistical trend methods and offers recommendations to improve the efficiency of the methods and reduce sampling costs. Guidance for determining how many sampling rounds might be needed by statistical methods to detect trends of various magnitudes is presented. This information could be useful in planning site monitoring activities
International Nuclear Information System (INIS)
Shobu, Nobuhiro; Amazawa, Hiroya; Koibuchi, Hiroto; Nakata, Hisakazu; Kato, Masatoshi; Takao, Tomoe; Terashima, Daisuke; Tanaka, Yoshie; Shirasu, Hisanori
2013-12-01
Japan Atomic Energy Agency (hereafter abbreviated as “JAEA”) has promoted near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities after receiving project approval from the government in November 2009. JAEA has carried out public information about low-level radioactive wastes disposal project on the web site. When some town meetings are held toward mutual understanding with the public, more detailed and clear explanations for safety management of near surface disposal are needed especially. Therefore, the information provision method to make the public understand should be reviewed. Moreover, a web-based survey should be carried out in order to get a sense of what the public knows, what it values and where it stands on nuclear energy and radiation issues, because the social environment surrounding nuclear energy and radiation issues has drastically changed as a result of the accident at the Fukushima Daiichi Nuclear Power Station on March 11, 2011. This review clarified the points to keep in mind about public information on near surface disposal project for low-level radioactive wastes generated from research, industrial and medical facilities, and that public awareness and understanding toward nuclear energy and radiation was changed before and after the accident at Fukushima Daiichi Nuclear Power Plant. (author)
The HAW project: demonstration facility for the disposal of high-level waste in salt
International Nuclear Information System (INIS)
Rothfuchs, T.
1991-01-01
This publication is the interim report 1988-89 of the international HAW project performed in the 800 m level of the Asse salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radiactivos S.A. (ENRESA) and the Netherlands Energy Research Foundation (ECN). After some delays in the licensing procedure the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 20 refs.; 92 figs.; 14 tabs
Special study on vegetative covers
International Nuclear Information System (INIS)
1988-11-01
This report describes the findings of a special study on the use of vegetative covers to stabilize tailings piles for the Uranium Mill Tailings Remedial Action (UMTRA) Project. The principal rationale for using plants would be to establish a dynamic system for controlling water balance. Specifically, vegetation would be used to intercept and transpire precipitation to the atmosphere, rather than allowing water to drain into the tailings and mobilize contaminants. This would facilitate compliance with groundwater standards proposed for the UMTRA Project by the Environmental Protection Agency. The goals of the study were to evaluate the feasibility of using vegetative covers on UMTRA Project piles, define the advantages and disadvantages of vegetative covers, and develop general guidelines for their use when such use seems reasonable. The principal method for the study was to analyze and apply to the UMTRA Project the results of research programs on vegetative covers at other US Department of Energy (DOE) waste management facilities. The study also relied upon observations made of existing stabilized piles at UMTRA Project sites where natural vegetation is growing on the rock-covered surfaces. Water balance and erosion models were also used to quantify the long-term performance of vegetative covers planned for the topslopes of stabilized piles at Grand Junction and Durango, Colorado, two UMTRA Project sites where the decision was made during the course of this special study to use vegetative covers. Elements in the design and construction of the vegetative covers at these two sites are discussed in the report, with explanations of the differing features that reflect differing environmental conditions. 28 refs., 18 figs., 9 tabs
International Nuclear Information System (INIS)
1994-07-01
The purpose of this plan is to establish a waste minimization and pollution prevention awareness (WM/PPA) program for the U.S. Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The program satisfies DOE requirements mandated by DOE Order 5400.1. This plan establishes planning objectives and strategies for conserving resources and reducing the quantity and toxicity of wastes and other environmental releases
Energy Technology Data Exchange (ETDEWEB)
Pinza, M.R.; Gardiner, W.W.; Barrows, E.S.; Borde, A.B.
1996-11-01
The objective of the Westchester Creek project was to evaluate proposed dredged material from this area to determine its suitability for unconfined ocean disposal at the Mud Dump Site. Westchester Creek was one of five waterways that the US Army Corps of Engineers- New York District (USACE-NYD) requested the Battelle/Marine Sciences Laboratory (MSL) to sample and evaluate for dredging and disposal in May 1995. The evaluation of proposed dredged material from the Westchester Creek project area consisted of bulk sediment chemical analyses, chemical analyses of dredging site water and elutriate, benthic acute and water-column toxicity tests, and bioaccumulation studies. Thirteen individual sediment core samples were collected from this area and analyzed for grain size, moisture content, and total organic carbon (TOC). One composite sediment sample representing the Westchester Creek area to be dredged, was analyzed for bulk density, specific gravity, metals, chlorinated pesticides, polychlorinated biphenyl (PCB) congeners, polynuclear aromatic hydrocarbons (PAHs), and 1,4-dichlorobenzene. Dredging site water and elutriate water, which is prepared from the suspended- particulate phase (SPP) of the Westchester Creek sediment composite, was analyzed for metals, pesticides, and PCBS.
International Nuclear Information System (INIS)
Yamashita, Yuji; Tanaka, Satoru
2012-01-01
We made a descriptive inference about the role of the U.S. National Academies in the U.S. radioactive waste disposal projects on the basis of literature-based information and compared the U.S. National Academies with the Science Council of Japan to determine their implications on the progress of social acceptability of radioactive waste disposal projects in Japan. The descriptive inference was made as follows. We described the organizational characteristics of the U.S. National Academies and the U.S. federal governments related to the projects. We outlined the related bills and demonstrated chronologically the activities related to the projects by the U.S. National Academies and the U.S. Government. As a consequence, we identified some specific roles that the U.S. National Academies played in the U.S. radioactive waste disposal projects. The U.S. National Academies have acted not only as a scientific and engineering adviser for the governments but also as an anchor for some political decision making or judicial actions. Furthermore, we analyzed the credibility of the Science Council of Japan and the U.S. National Academies from the viewpoint that a reliable third party must exhibit fairness, expertise and continuity. From the results of the comparison, it was found that the Science Council of Japan has the possibility to become a reliable third party that can help the radioactive waste disposal projects in Japan. (author)
The Hazardous Waste/Mixed Waste Disposal Facility
International Nuclear Information System (INIS)
Bailey, L.L.
1991-01-01
The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996
The EVEREST project: sensitivity analysis of geological disposal systems
International Nuclear Information System (INIS)
Marivoet, Jan; Wemaere, Isabelle; Escalier des Orres, Pierre; Baudoin, Patrick; Certes, Catherine; Levassor, Andre; Prij, Jan; Martens, Karl-Heinz; Roehlig, Klaus
1997-01-01
The main objective of the EVEREST project is the evaluation of the sensitivity of the radiological consequences associated with the geological disposal of radioactive waste to the different elements in the performance assessment. Three types of geological host formations are considered: clay, granite and salt. The sensitivity studies that have been carried out can be partitioned into three categories according to the type of uncertainty taken into account: uncertainty in the model parameters, uncertainty in the conceptual models and uncertainty in the considered scenarios. Deterministic as well as stochastic calculational approaches have been applied for the sensitivity analyses. For the analysis of the sensitivity to parameter values, the reference technique, which has been applied in many evaluations, is stochastic and consists of a Monte Carlo simulation followed by a linear regression. For the analysis of conceptual model uncertainty, deterministic and stochastic approaches have been used. For the analysis of uncertainty in the considered scenarios, mainly deterministic approaches have been applied
Energy Technology Data Exchange (ETDEWEB)
Durham, Robin E.; Sackschewsky, Michael R.
2007-09-01
This report summarizes the first year survival of sagebrush seedlings planted as compensatory mitigation for the Integrated Disposal Facility Project. Approximately 42,600 bare root seedlings and 26,000 pluglings were planted at a mitigation site along Army Loop Road in February 2007. Initial baseline monitoring occurred in March 2007, and first summer survival was assessed in September 2007. Overall survival was 19%, with bare root survival being marginally better than pluglings (21% versus 14%). Likely major factors contributing to low survival were late season planting and insufficient soil moisture during seedling establishment.
Waste and Disposal: Research and Development
International Nuclear Information System (INIS)
Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.
2002-01-01
This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to
Waste and Disposal: Research and Development
Energy Technology Data Exchange (ETDEWEB)
Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P
2002-04-01
This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to
International Nuclear Information System (INIS)
Reith, C.C.; Meyer, H.R.; Till, J.E.; Matthews, M.L.; Richey, R.H.
1989-01-01
This paper reports on the DECHEM method, developed on the Uranium Mill Tailings Remedial Action (UMTRA) Project to guide characterization and remedial planning for heavy metals contamination in soils. This is necessary because metals and metalloids such as arsenic, lead, molybdenum, selenium, uranium, and vanadium that are sometimes associated with the mill tailings may be more mobile than radium-226 (Ra-226), hence may migrate more deeply into subpile soils (beneath tailings that are to be relocated) or into adjacent contaminated materials at UMTRA Project sites. The result is that remedial action to the Ra-226 excavation limit, as specified in the UMTRA Project's authorizing legislation, may not remove all hazardous non-radiological contamination
Zagozewski, Rebecca; Judd-Henrey, Ian; Nilson, Suzie; Bharadwaj, Lalita
2011-04-28
The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR) was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.
Siting Study for the Remote-Handled Low-Level Waste Disposal Project
Energy Technology Data Exchange (ETDEWEB)
Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr
2010-10-01
The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.
International Nuclear Information System (INIS)
Alexandrov, A.; Boyanov, S.; Christoskova, M.; Ivanov, A.
2006-01-01
The State Enterprise Radioactive Waste is the responsible organisation in Bulgaria for the radioactive waste management and, in particular, for the establishment of the national disposal facility (NDF) for low and intermediate level short-lived radioactive waste (LIL RAW SL). According to the national strategy for the safe management of spent fuel and radioactive waste the NDF should be commissioned in 2015. NDF will accept two main waste streams - for disposal and for storage if the waste is not disposable. The major part of disposable waste is generated by Kozloduy NPP. The disposal facility will be a near surface module type engineered facility. Consecutive erection of new modules will be available in order to increase the capacity of the facility. The corrective measures are previewed to be applied if needed - upgrading of engineered barriers and/or retrieval of the waste. The active control after the facility is closed should be not more than 300 years. The safety of the facility is supposed to be based on the passive measures based on defense in deep consisting of physical barriers and administrative measures. A multi barrier approach will be applied. Presently the NDF project is at the first stage of the facility life cycle - the site selection. The siting process itself consists of four stages - elaboration of a concept for waste disposal and site selection planning, data collection and region analyses, characterization of the preferred sites-candidates and site confirmation. Up till now the work on the first two stages of the siting process had been done by the SE RAW. Geological site investigations have been carried out for more than two decades all over the territory of the country. The results of the investigations have been summarized and analysed thoroughly. More than 40 potential sites have been considered, after the preselection 12 sites have been selected as favourable and among them 5 are pointed out as acceptable. The ultimate decision for a site
The HAW project: demonstration facility for the disposal of high-level waste in salt
International Nuclear Information System (INIS)
Rothfuchs, T.
1991-01-01
This report is the so-called Synthesis report 1985-1989 of the international HAW project performed in the 800 m level of the ASSE salt mine in the Federal Republic of Germany. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste in geological salt-deposits. The HAW-project is carried out by the GSF-Institut fuer Tieflagerung (IFT) in cooperation with the French Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA); the Spanish Empresa Nacional de Residuos Radioactivos S.A (ENRESA) and the Netherlands Energy Research Foundation (ECN). During the years 1985 to 1989 the underground test field was excavated and after some delays in the licensing procedure, the emplacement of 30 vitrified highly radioactive canisters (containers) is now envisaged for early 1991. 32 refs; 76 figs., 11 tabs
Alternative geochemical barrier materials
International Nuclear Information System (INIS)
1991-07-01
Previous investigations of the effects of neutralization and reduction on uranium mill tailings pore fluids by the Technical Support Contractor indicated that arsenic, selenium, and molybdenum continue to remain in solution in all but reducing conditions. These hazardous constituents are present in groundwaters as oxyanions and, therefore, are not expected to be removed by adsorption into clays and most other soil constituents. It was decided to investigate the attenuation capacity of two commonly available crystalline iron oxides, taconite and scoria, and a zeolite, a network aluminosilicate with a cage structure. Columns of the candidate materials were exposed to solutions of individual constituents, including arsenic, molybdenum, selenium, and, uranium, and to the spiked tailings pore fluid from the Bodo Canyon disposal cell near Durango, Colorado. In addition to the single material columns, a homogeneous blend of the three materials and layers of the materials were exposed to spiked tailings pore fluids. The results of these experiments indicate that with the exception of molybdenum, the constituents of concern are attenuated by the taconite; however, they are not sufficiently attenuated to meet the groundwater protection standards applicable to the UMTRA Project. Therefore, the candidate barrier materials did not prove to be useful to the UMTRA Project for the cleanup of groundwaters
International Nuclear Information System (INIS)
Winters, K.H.; Jackson, C.P.; Clark, C.M.
1990-06-01
This document describes a study of groundwater flow and radionuclide migration in the far field of a hypothetical repository located in the clay beneath Harwell Laboratory. The work forms part of the assessment of the radiological impact of disposal in a clay formation, carried out as the UK contribution to the CEC PACOMA project. (Author)
Directory of Open Access Journals (Sweden)
Rebecca Zagozewski
2011-01-01
Full Text Available The impact of current and historical waste disposal practices on the environment and human health of Indigenous people in First Nations communities has yet to be adequately addressed. Solid waste disposal has been identified as a major environmental threat to First Nations Communities. A community-based participatory research project (CBPR was initiated by the Saskatoon Tribal Council Health and Family Services Incorporated to investigate concerns related to waste disposal in three Saskatchewan First Nations Communities. Utilizing a qualitative approach, we aimed to gain an understanding of past and present waste disposal practices and to identify any human and environmental health concerns related to these practices. One to one interviews and sharing circles were conducted with Elders. Elders were asked to share their perspectives on past and present waste disposal practices and to comment on the possible impacts these practices may have on the environment and community health. Historically waste disposal practices were similar among communities. The homeowner generated small volumes of waste, was exclusively responsible for disposal and utilized a backyard pit. Overtime waste disposal evolved to weekly pick-up of un-segregated garbage with waste disposal and open trash burning in a community dump site. Dump site locations and open trash burning were identified as significant health issues related to waste disposal practices in these communities. This research raises issues of inequity in the management of waste in First Nations Communities. It highlights the need for long-term sustainable funding to support community-based waste disposal and management strategies and the development of First Nations centered and delivered educational programs to encourage the adoption and implementation of waste reduction, reutilization and recycling activities in these communities.
International Nuclear Information System (INIS)
2005-01-01
Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects
International Nuclear Information System (INIS)
Levich, R.A.; Ferrigan, P.M.; Wilkey, P.L.
1990-01-01
The Nuclear Energy Agency of the organization for Economic Cooperation and Development (OECD/NEA) sponsors the International Stripa Project. The objectives of the Stripa Project are to develop techniques for characterizing sites located deep in rock formations that are potentially suitable for the geologic disposal of high-level radioactive wastes and to evaluate particular engineering design considerations that could enhance the long-term safety of a high-level radioactive waste repository in a geologic medium. The purpose of this paper is to briefly summarize the research conducted at Stripa and discuss the ways in which the technology developed for the Stripa Project has been and will be transfered to the United States Civilian Radioactive Waste Management Program's Yucca Mountain Project. 3 refs., 2 figs
International Nuclear Information System (INIS)
1990-01-01
The international co-operation project HYDROCOIN for studying groundwater flow modelling in the context of radioactive waste disposal was initiated in 1984. Thirteen organizations from ten countries and two international organizations have participated in the project which has been managed by the Swedish Nuclear Power Inspectorate, SKI. This report summarizes the results from the second phase of HYDROCOIN, Level 2, which has addressed the issue of validation by testing the capabilities of groundwater flow models to describe five field and laboratory experiments: . Thermal convection and conduction around a field heat transfer experiment in a quarry, . A laboratory experiment with thermal convection as a model for variable density flow, . A small groundwater flow system in fractured monzonitic gneiss, . Three-dimensional regional groundwater flow in low permeability rocks, and . Soil water redistribution near the surface at a field site. The five test cases cover various media of interest for final disposal such as low permeability saturated rock, unsaturated rock, and salt formations. They also represent a variety of spatial and temporal scales. From model simulations on the five test cases conclusions are drawn regarding the applicability of the models to the experimental and field situations and the usefulness of the available data bases. The results are evaluated with regard to the steps in an ideal validation process. The data bases showed certain limitations for validation purposes with respect to independent data sets for calibration and validation. In spite of this, the HYDROCOIN Level 2 efforts have significantly contributed to an increased confidence in the applicability of groundwater flow models to different situations relevant to final disposal. Furthermore, the work has given much insight into the validation process and specific recommendations for further validation efforts are made
Subseabed Disposal Project chemical response studies. Annual report, October 1982-September 1983
International Nuclear Information System (INIS)
Brush, L.H.
1985-10-01
Studies of the chemical response of deep-sea sediments to a subseabed repository for high-level radioactive waste continued during Fiscal Year 1983. Chemical Response Studies comprise Waste Package, Near-Field, and Far-Field Studies. This year, as in the past, investigators in the US Subseabed Disposal Project (SDP) carried out most of these chemical response experiments with red clay from the MPG 1 study location 1500 km north of Hawaii. The results of all studies carried out to date imply that oxidized red clay would form a highly effective barrier to radionuclides that form cationic species, but that anionic radionuclides would begin to escape from the sediment to the overlying water column on the order of thousands of years after emplacement. In Fiscal Year 1984, investigators in the US SDP will initiate chemical response studies with mildly reduced Atlantic clay- and carbonate-rich sediments in cooperation with the Sediment Barrier Task Group of the Organization for Economic Cooperation and Development - Nuclear Energy Agency Coordinated Program on the Assessment of the Subseabed Disposal of Radioactive Waste (Seabed Working Group). The objective of these US studies will be to quantify the chemical response of Atlantic sediments to a subseabed repository with a level of confidence similar to that for Pacific red clay
Environmental monitoring annual report for the Tumulus Disposal Demonstration Project
International Nuclear Information System (INIS)
Yager, R.E.; Craig, P.M.
1989-01-01
The Fiscal Year 1988 Annual Report is the third in a series of semi-annual Tumulus Development Disposal Project data summary reports. The reporting schedule has been modified to correspond to the fiscal years and the subcontractor contract periods. This data summary spans the time from start of operations in June 1987 through the end of September 1988. The environmental data collected include run-off water quality and quantity, groundwater quality and levels, soil sampling and hydrometeorological data. This data is being used and analyzed here to demonstrate the environmental performance objectives for the TDDP as part of the overall performance assessment for the TDDP. Approximately one year of pre-operational data were collected prior to operations beginning on April 11, 1988. Comparisons are made between pre- and post-operational data. No significant environmental impacts have been found since operations have begun. 10 refs., 21 figs., 22 tabs
The HAW-project: Demonstration facility for the disposal of high-level waste in salt
International Nuclear Information System (INIS)
Rothfuchs, T.; Duijves, K.A.
1990-04-01
The HAW-project plants the testwise emplacement of 30 vitrified highly radioactive canisters containing Cs-137 and Sr-90 at the 800 m level of the Asse salt mine for a testing period of approximately five years. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste (HAW) in geological salt formations. During the years 1985 to 1989 the underground test field was excavated, the measuring equipment installed, and two preceedings inactive electrical tests taken into operation. Furthermore, the components of a system for transportation and emplacement of highly radioactive canisters was fabricated, installed, and preliminarily tested. After some delays in the licensing procedure the emplacement of the 30 radioactive canisters is now envisaged for early 1991. For handling of the radioactive canisters and their emplacement into the boreholes a system consisting of a transport cask, a transport vehicle, a disposal machine, and of a borehole slider has been developed and will be tested. The actual scientific investigation programme is based on the estimation and observation of the interaction between the radioactive canisters and the rock salt. This programme includes measurement of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. Also the thermally induced stress and deformation fields in the surrounding rock mass will be investigated carefully. (orig./HP)
Energy Technology Data Exchange (ETDEWEB)
1993-09-01
This baseline risk assessment evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site near Monument Valley, Arizona. The tailings and other contaminated material at this site are being relocated and stabilized in a disposal cell at Mexican Hat, Utah, through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The tailings removal is planned for completion by spring 1994. After the tailings are removed, groundwater contamination at the site will continue to be evaluated. This risk assessment is the first document specific to this site for the Groundwater Project. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site.
International Nuclear Information System (INIS)
1993-09-01
This baseline risk assessment evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site near Monument Valley, Arizona. The tailings and other contaminated material at this site are being relocated and stabilized in a disposal cell at Mexican Hat, Utah, through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The tailings removal is planned for completion by spring 1994. After the tailings are removed, groundwater contamination at the site will continue to be evaluated. This risk assessment is the first document specific to this site for the Groundwater Project. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site
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
Land disposal alternatives for low-level waste
International Nuclear Information System (INIS)
Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.
1982-01-01
The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables
HAW project. Demonstrative disposal of high-level radioactive wastes in the Asse salt mine
International Nuclear Information System (INIS)
Rothfuchs, T.; Duijves, K.; Stippler, R.
1988-01-01
Since 1968 the GSF has been carrying out research and development programs for the final disposal of high-level radioactive waste (HAW) in salt formations. The heat producing waste has been simulated so far by means of electrical heaters and also cobalt-60-sources. In order to improve the final concept for HAW disposal in salt formations the complete technical system of an underground repository is to be tested in an one-to-one scale test facility. To satisfy the test objectives thirty high radioactive canisters containing the radionuclides Cs-137 and Sr-90 will be emplaced in six boreholes located in two test galleries at the 800 m-level in the Asse salt mine. The duration of testing will be approximately five years. For the handling of the radioactive canisters and their emplacement into the boreholes a system consisting of transportation casks, transportation vehicle, disposal machine, and borehole slider will be developed and tested. The actual scientific investigation program is based on the estimation and observation of the interaction between the radioactive canisters and the rock salt. This program includes measurement of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. Also the thermally induced stress and deformation fields in the surrounding rock mass will be investigated carefully. The project is funded by the BMFT and the CEC and carrier out in close co-operation with the Netherlands Energy Research Foundation (ECN)
HLW disposal in Germany - R and D achievements and outlook
International Nuclear Information System (INIS)
Steininger, W.
2006-01-01
The paper gives a brief overview of the status of R and D on HLW disposal. Shortly addressed is the current nuclear policy. After describing the responsibilities regarding R and D for disposing of heat-generating high-level (HLW) waste (vitrified waste and spent fuel), selected projects are mentioned to illustrate the state of knowledge in disposing of waste in rock salt. Participation in international projects and programs is described to illustrate the value for the German concepts and ideas for HLW disposal in different rock types. Finally, a condensed outlook on future activities is given. (author)
International Nuclear Information System (INIS)
Kowe, R.; Mobbs, S.; Proehl, G.; Bergstrom, U.; Kanyar, B.; Olyslaegers, G.; Zeevaert, T.; Simon, I.
2004-01-01
The BIOMOSA (Biosphere Models for Safety Assessment of Radioactive Waste Disposal) project is a part of the EC fifth framework research programme. The main goal of this project is the improvement of the scientific basis for the application of biosphere models in the framework of long-term safety studies of radioactive waste disposal facilities. Furthermore, the outcome of the project will provide operators and regulatory bodies with guidelines for performance assessments of repository systems. The study focuses on the development and application of site-specific models and a generic biosphere tool BIOGEM (Biosphere Generic Model), using the experience from the national programmes and the IAEA BIOMASS reference biosphere methodology. The models were applied to 5 typical locations in the EU, resulting in estimates of the annual individual doses to the critical groups and the ranking of the importance of the pathways for each of the sites. The results of the site-specific and generic models were then compared. In all cases the doses calculated by the generic model were less than the doses obtained from the site-specific models. Uncertainty in the results was estimated by means of stochastic calculations which allow a comparison of the overall model uncertainty with the variability across the different sites considered. (author)
Dyckman, Claire; And Others
This teaching unit is part of the final report of the Household Hazardous Waste Disposal Project. It consists of activities presented in an introduction and three sections. The introduction contains an activity for students in grades 4-12 which defines terms and concepts for understanding household hazardous wastes. Section I provides activities…
Energy Technology Data Exchange (ETDEWEB)
Bergmans, Anne; Schroeder, Jantine [University of Antwerp, Faculty of Political and Social Sciences, 2000 Antwerp (Belgium); Simmons, Peter [University of East Anglia, School of Environmental Sciences, NR4 7TJ Norwich (United Kingdom); Barthe, Yannick; Meyer, Morgan [CNRS, Ecole des Mines, 75272 Paris (France); Sundqvist, Goeran [Universitetet i Oslo, Centre for Studies of Technology, Innovation and Culture, 0851 Oslo (Norway); Martell, Merixell [MERIENCE Strategic Thinking, 08734 Olerdola (Spain); Kallenbach-Herbert, Beate [Oeko Institut, 64295 Darmstadt (Germany)
2012-07-01
InSOTEC is a social sciences research project which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. It currently investigates and analyses the most striking socio-technical challenges to implementing geological disposal of radioactive waste in 14 national programs. A focus is put on situations and issues where the relationship between the technical and social components is still unstable, ambiguous and controversial, and where negotiations are taking place in terms of problem definitions and preferred solutions. Such negotiations can vary from relatively minor contestation, over mild commotion, to strong and open conflicts. Concrete examples of socio-technical challenges are: the question of siting, introducing the notion of reversibility / retrievability into the concept of geological disposal, or monitoring for confidence building. In a second stage the InSOTEC partners aim to develop a fine-grained understanding of how the technical and the social influence, shape, build upon each other in the case of radioactive waste management and the design and implementation of geological disposal. How are socio-technical combinations in this field translated and materialized into the solutions finally adopted? With what kinds of tools and instruments are they being integrated? Complementary to providing better theoretical insight into these socio-technical challenges/combinations, InSOTEC aims to provide concrete suggestions on how to address these within national and international contexts. To this end, InSOTEC will deliver insights into how mechanisms for interaction between the technical community and a broad range of socio-political actors could be developed. (authors)
Engineering geology of waste disposal
International Nuclear Information System (INIS)
Bentley, S.P.
1996-01-01
This volume covers a wide spectrum of activities in the field of waste disposal. These activities range from design of new landfills and containment properties of natural clays to investigation, hazard assessment and remediation of existing landfills. Consideration is given to design criteria for hard rock quarries when used for waste disposal. In addition, an entire section concerns the geotechnics of underground repositories. This covers such topics as deep drilling, in situ stress measurement, rock mass characterization, groundwater flows and barrier design. Engineering Geology of Waste Disposal examines, in detail, the active role of engineering geologists in the design of waste disposal facilities on UK and international projects. The book provides an authoritative mix of overviews and detailed case histories. The extensive spectrum of papers will be of practical value to those geologists, engineers and environmental scientists who are directly involved with waste disposal. (UK)
Modeling flood events for long-term stability
International Nuclear Information System (INIS)
Schruben, T.; Portillo, R.
1985-01-01
The primary objective for the disposal of uranium mill tailings in the Uranium Mill Tailings Remedial Action (UMTRA) Project is isolation and stabilization to prevent their misuse by man and dispersal by natural forces such as wind, rain, and flood waters (40 CFR-192). Stabilization of sites that are located in or near flood plains presents unique problems in design for long-term performance. This paper discusses the process involved with the selection and hydrologic modeling of the design flood event; and hydraulic modeling with geomorphic considerations of the design flood event. The Gunnison, Colorado, and Riverton, Wyoming, sites will be used as examples in describing the process
The diversity of waste disposal planning in Switzerland
International Nuclear Information System (INIS)
McCombie, C.
1989-01-01
In this overview of radioactive waste disposal planning in Switzerland, emphasis is placed upon describing the diversity of the planning and explaining the strategic thinking which has resulted in this diversity. Although Switzerland is a small country and has only a modest nuclear programme in absolute terms, planning and preparation for final disposal projects has been progressing for the last 10 or more years on a very broad front. The reasons for this breadth of approach are partly technical and partly determined by political and public pressures. Following a summary of the requirements for disposal and of the relevant boundary conditions, the resulting concepts are described and the controversial issue of repository siting is discussed. The current status of projects for disposal of low and intermediate-level wastes (L/ILW) and of high-level wastes (HLW) is noted; we conclude with some remarks on the advantages and disadvantages from the side of the organization responsible for implementation of repository projects of proceeding on such a broad technical front. (aughor). 2 figs.; 1 tab
Environmental monitoring six month report for the Tumulus Disposal Demonstration Project
International Nuclear Information System (INIS)
Yager, R.E.; Furnari, J.A.; Craig, P.M.
1989-05-01
The Fiscal Year 1989 Six Month Report is the fourth in a series of semi-annual Tumulus Disposal Demonstration Project (TDDP) data summary reports. This data summary spans the time from start of operations in June 1987 through the end of March 1989 with particular emphasis on the last six months: October 1988 through March 1989. The environmental data collected include run-off water quality and quantity, groundwater quality and levels, soil sampling and hydrometeorological data. These data are being used and analyzed here to demonstrate the environmental performance objectives for the TDDP as part of the overall performance assessment. Comparisons are made between pre- and post-operational data and data collected during size month period ending March 31, 1989. No significant environmental impacts have been found since operations have begun. 13 refs., 28 figs., 12 tabs
40 CFR 35.6345 - Equipment disposal options.
2010-07-01
... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Equipment disposal options. 35.6345 Section 35.6345 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY GRANTS AND OTHER FEDERAL... options. The following disposal options are available: (a) Use the equipment on another CERCLA project and...
International Nuclear Information System (INIS)
1990-01-01
INTRAVAL is an international project concerned with the use of mathematical models for predicting the potential transport of radioactive substances in the geosphere. Such models are used to help assess the longterm safety of radioactive waste disposal systems. The INTRAVAL project was established to evaluate the validity of these models. Results from a set of selected laboratory and field experiments as well as studies of occurrences of radioactive substances in nature (natural analogues) are compared in a systematic way with model predictions. Discrepancies between observations and predictions are discussed and analyzed
Cleanup protocol for 226Ra-contaminated cobbly soil at UMTRA Project sites
International Nuclear Information System (INIS)
Gonzales, D.E.; Millard, J.B.; Miller, M.L.; Metzler, D.
1994-01-01
The nonuniform distribution of 226Ra and other radiological contamination of cobbly soil encountered on several Uranium Mill Tailings Remedial Action Project sites is presented and discussed, and the concomitant challenges to the intent and implementation of the U.S. Environmental Protection Agency's soil cleanup standards are noted. In response to technical assessments and information presented to the U.S. Nuclear Regulatory Commission by the U.S. Department of Energy, the Nuclear Regulatory Commission has recently resolved the dilemma by concluding that compliance with Environmental Protection Agency soil cleanup standards for cobby soil at Uranium Mill Tailings Remedial Action Project sites would be adequately attained using bulk radionuclide concentrations, instead of requiring that the radionuclide concentration of the finer soil fraction passing a No. 4 mesh sieve met the standards. A Nuclear Regulatory Commission-approved procedure developed for cobbly soil remediation is outlined and discussed. The site-specific implementation of this procedure at Uranium Mill Tailings Remedial Action Project sites containing cobbly soil is estimated to save millions of dollars
Financing of radioactive waste disposal
International Nuclear Information System (INIS)
Reich, J.
1989-01-01
Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de
International Nuclear Information System (INIS)
Baudoin, P.; Serres, C.; Certes, C.; Gay, D.
2001-01-01
This paper presents a summary of the results obtained in the framework of the SPA (spent fuel disposal performance assessment) project. The project was undertaken by ENRESA, E; GRS, D; IPSN, F; NRG, NL; SCK.CEN, B and VTT, FIN between May 1996 and April 1999. Devoted to the study of spent fuel disposal in various host rock formations (clay, crystalline rocks and salt formation), it notably had the objective to evaluate the long-term performance of different repository systems and to identify the most influential elements. The variety of concepts, sites and scenarios considered in the framework of this project provides a wide range of information from which some general conclusions can be drawn. Focusing on the work done in the case of granite host rock formations, this paper describes the various approaches adopted and states the main sources of differences. It particularly stresses the differences related to the geosphere and biosphere modelling. For the geosphere modelling, ENRESA, GRS and VTT use one dimensional discrete approaches to model the migration of contaminants through the geosphere taking into account for matrix diffusion, whereas IPSN uses a three dimensional continuum approach based on a single porosity model. The comparison of the biosphere conversion factors shows the high influence on the calculated radionuclide dose contributions that can results from biosphere modelling assumptions. It notably points out the differences existing between a simplified ''water drinking'' approach as implemented by VTT and a more classical one in which a wider range of exposure pathways are taken into account. (orig.)
International Nuclear Information System (INIS)
Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van
2002-01-01
A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)
International Nuclear Information System (INIS)
Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.
2008-01-01
The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)
7 CFR 3015.168 - Disposal of equipment.
2010-01-01
..., DEPARTMENT OF AGRICULTURE UNIFORM FEDERAL ASSISTANCE REGULATIONS Property § 3015.168 Disposal of equipment. When original or replacement equipment is no longer to be used in projects or programs currently or... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposal of equipment. 3015.168 Section 3015.168...
Medications at School: Disposing of Pharmaceutical Waste
Taras, Howard; Haste, Nina M.; Berry, Angela T.; Tran, Jennifer; Singh, Renu F.
2014-01-01
Background: This project quantified and categorized medications left unclaimed by students at the end of the school year. It determined the feasibility of a model medication disposal program and assessed school nurses' perceptions of environmentally responsible medication disposal. Methods: At a large urban school district all unclaimed…
International Nuclear Information System (INIS)
Rothfuchs, T.; Cuevas, C. de las; Donker, H.; Feddersen, H.K.; Garcia-Celma, A.; Gies, H.; Goreychi, M.; Graefe, V.; Heijdra, J.; Hente, B.; Jockwer, N.; LeMeur, R.; Moenig, J.; Mueller, K.; Prij, J.; Regulla, D.; Smailos, E.; Staupendahl, G.; Till, E.; Zankl, M.
1995-01-01
In order to improve the final concept for the disposal of high-level radioactive waste (HAW) in boreholes drilled into salt formation plans were developed a couple of years ago for a full scale testing of the complete technical system of an underground repository. To satisfy the test objectives, thirty highly radioactive radiation sources were planned to be emplaced in six boreholes located in two test galleries at the 800-m-level in the Asse salt mine. A duration of testing of approximately five years was envisaged. Because of licensing uncertainties the German Federal Government decided on December 3rd, 1992 to stop all activities for the preparation of the test disposal immediately. In the course of the preparation of the test disposal, however, a system, necessary for handling of the radiation sources was developed and installed in the Asse salt mine and two non-radioactive reference tests with electrical heaters were started in November 1988. These tests served for the investigation of thermal effects in comparison to the planned radioactive tests. An accompanying scientific investigation programme performed in situ and in the laboratory comprises the estimation and observation of the thermal, radiation-induced, and mechanical interaction between the rock salt and the electrical heaters and the radiation sources, respectively. The laboratory investigations are carried out at Braunschweig (FRG), Petten (NL), Saclay (F) and Barcelona (E). As a consequence of the premature termination of the project the working programme was revised. The new programme agreed to by the project partners included a controlled shutdown of the heater tests in 1993 and a continuation of the laboratory activities until the end of 1994. (orig.)
FUNDING ALTERNATIVES FOR LOW-LEVEL WASTE DISPOSAL
International Nuclear Information System (INIS)
Becker, Bruce D.; Carilli, Jhon
2003-01-01
For 13 years, low-level waste (LLW) generator fees and disposal volumes for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Radioactive Waste Management Sites (RWMSs) had been on a veritable roller coaster ride. As forecast volumes and disposal volumes fluctuated wildly, generator fees were difficult to determine and implement. Fiscal Year (FY) 2000 forecast projections were so low, the very existence of disposal operations at the Nevada Test Site (NTS) were threatened. Providing the DOE Complex with a viable, cost-effective disposal option, while assuring the disposal site a stable source of funding, became the driving force behind the development of the Waste Generator Access Fee at the NTS. On September 26, 2000, NNSA/NV (after seeking input from DOE/Headquarters [HQ]), granted permission to Bechtel Nevada (BN) to implement the Access Fee for FY 2001 as a two-year Pilot Program. In FY 2001 (the first year the Access Fee was implemented), the NTS Disposal Operations experienced a 90 percent increase in waste receipts from the previous year and a 33 percent reduction in disposal fee charged to the waste generators. Waste receipts for FY 2002 were projected to be 63 percent higher than FY 2001 and 15 percent lower in cost. Forecast data for the outyears are just as promising. This paper describes the development, implementation, and ultimate success of this fee strategy
International Nuclear Information System (INIS)
Knott, R.R.; Little, C.A.
1991-08-01
The Pollutant Assessments Group (PAG) at the Grand Junction Office (GJO), Colorado, of Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude these sites from UMTRAP based on whether the on-site residual radioactive material (if any) originated from the former mill sites, and radiation levels on-site are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the Quality Assurance Plan (QAP) for the PAG in conducting all activities related to UMTRAP. All quality assurance provisions given by the DOE, DOE/UMTRA and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the PAG/UMTRA QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups. 11 refs., 6 figs., 3 tabs
Disposal Site Information Management System
International Nuclear Information System (INIS)
Larson, R.A.; Jouse, C.A.; Esparza, V.
1986-01-01
An information management system for low-level waste shipped for disposal has been developed for the Nuclear Regulatory Commission (NRC). The Disposal Site Information Management System (DSIMS) was developed to provide a user friendly computerized system, accessible through NRC on a nationwide network, for persons needing information to facilitate management decisions. This system has been developed on NOMAD VP/CSS, and the data obtained from the operators of commercial disposal sites are transferred to DSIMS semiannually. Capabilities are provided in DSIMS to allow the user to select and sort data for use in analysis and reporting low-level waste. The system also provides means for describing sources and quantities of low-level waste exceeding the limits of NRC 10 CFR Part 61 Class C. Information contained in DSIMS is intended to aid in future waste projections and economic analysis for new disposal sites
International Nuclear Information System (INIS)
2001-11-01
The primary objectives of the CRP were to: promote the sharing of experiences of the Member States in their application of engineered barrier materials for near surface disposal facilities; help enhance their use of engineered barriers by improving techniques and methods for selecting, planning and testing performance of various types of barrier materials for near surface disposal facilities. The objective of this publication is to provide and overview of technical issues related to the engineered barrier systems and a summary of the major findings of each individual research project that was carried out within the framework of the CRP. This publication deals with a general overview of engineered barriers in near surface disposal facilities, key technical information obtained within the CRP and overall conclusions and recommendations for future research and development activities. Appendices presenting individual research accomplishments are also provided. Each of the 13 appendices was indexed separately
International Nuclear Information System (INIS)
DEFFENBAUGH, M.L.
2000-01-01
The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational
UMTRA project: Canonsburg final design
International Nuclear Information System (INIS)
Thiers, G.R.; Guros, F.B.; Smith, E.S.
1984-01-01
Final design for on-site stabilization of over 300,000 cubic yards of abandoned mill tailings in Canonsburg, Pennsylvania, is being completed this Fall. This paper describes design criteria, design procedures, and difficulties encountered for the following required elements: 1. Encapsulation cell; 2. Durability of erosion protection material; 3. Flood control berm; 4. Sedimentation pond; 5. Wastewater treatment plant. The 70,000 cubic yards of the tailings for which radiation levels exceed 100 picocuries per gram will be placed on a 2-ft-thick compacted clay liner and encased by a 3-ft-thick compacted clay cover. The remaining tailings will be covered with at least two feet of clay to prevent radon escape and to reduce rainfall infiltration. Erosion protection will be provided for the encapsulation cell, the drainage swales, and from potential meandering of nearby Chartiers Creek
Energy Technology Data Exchange (ETDEWEB)
1994-04-01
This report evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells to determine the potential for immediate human health and environmental impacts. This risk assessment evaluates the most contaminated groundwater that flows beneath the processing site towards the Gunnison River. The monitor wells that have consistently shown the highest concentration of most contaminants are used in this risk assessment. This risk assessment will be used in conjunction with additional activities and documents to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium.
International Nuclear Information System (INIS)
1988-01-01
The Title I groundwater standards for inactive uranium mill tailings sites, which were promulgated on January 5, 1983, by the US Environmental Protection Agency (EPA) for the Uranium Mill Tailings Remedial Action (UMTRA) Project, were remanded to the EPA on September 3, 1985, by the US Tenth Circuit Court of Appeals. The Court instructed the EPA to compile general groundwater standards for all Title I sites. On September 24, 1987, the EPA published proposed standards (52FR36000-36008) in response to the remand. This report includes an evaluation of the potential effects of the proposed EPA groundwater standards on the UMTRA Project, as well as a discussion of the DOE's position on the proposed standards. The report also contains and appendix which provides supporting information and cost analyses. In order to assess the impacts of the proposed EPA standards, this report summarizes the proposed EPA standards in Section 2.0. The next three sections assess the impacts of the three parts of the EPA standards: Subpart A considers disposal sites; Subpart B is concerned with restoration at processing sites; and Subpart C addresses supplemental standards. Section 6.0 integrates previous sections into a recommendations section. Section 7.0 contains the DOE response to questions posed by the EPA in the preamble to the proposed standards. 6 refs., 5 figs., 3 tabs
International Nuclear Information System (INIS)
1994-04-01
This report evaluates potential impacts to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site are being placed in an off-site disposal cell by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This is the second risk assessment of groundwater contamination at this site. The first risk assessment was performed primarily to evaluate existing domestic wells to determine the potential for immediate human health and environmental impacts. This risk assessment evaluates the most contaminated groundwater that flows beneath the processing site towards the Gunnison River. The monitor wells that have consistently shown the highest concentration of most contaminants are used in this risk assessment. This risk assessment will be used in conjunction with additional activities and documents to assist in determining what remedial action is needed for contaminated groundwater at the site after the tailings are relocated. This risk assessment follows an approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the groundwater are cadmium, cobalt, iron, manganese, sulfate, uranium, and some of the products of radioactive decay of uranium
Energy Technology Data Exchange (ETDEWEB)
1993-12-31
Scientists, engineers, elected officials, and industry regulators from the United, States and Germany met in Albuquerque, New Mexico, August 16--20, 1993, in the first joint international workshop to discuss uranium tailings remediation. Entitled ``Workshop on Uranium Production Environmental Restoration: An Exchange between the US and Germany,`` the meeting was hosted by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The goal of the workshop was to further understanding and communication on the uranium tailings cleanup projects in the US and Germany. Many communities around the world are faced with an environmental legacy -- enormous quantities of hazardous and low-level radioactive materials from the production of uranium used for energy and nuclear weapons. In 1978, the US Congress passed the Uranium Mill Tailings Radiation Control Act. Title I of the law established a program to assess the tailings at inactive uranium processing sites and provide a means for joint federal and state funding of the cleanup efforts at sites where all or substantially all of the uranium was produced for sale to a federal agency. The UMTRA Project is responsible for the cleanup of 24 sites in 10 states. Germany is facing nearly identical uranium cleanup problems and has established a cleanup project. At the workshop, participants had an opportunity to interact with a broad cross section of the environmental restoration and waste disposal community, discuss common concerns and problems, and develop a broader understanding of the issues. Abstracts are catalogued individually for the data base.
International Nuclear Information System (INIS)
1993-01-01
Scientists, engineers, elected officials, and industry regulators from the United, States and Germany met in Albuquerque, New Mexico, August 16--20, 1993, in the first joint international workshop to discuss uranium tailings remediation. Entitled ''Workshop on Uranium Production Environmental Restoration: An Exchange between the US and Germany,'' the meeting was hosted by the US Department of Energy's (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The goal of the workshop was to further understanding and communication on the uranium tailings cleanup projects in the US and Germany. Many communities around the world are faced with an environmental legacy -- enormous quantities of hazardous and low-level radioactive materials from the production of uranium used for energy and nuclear weapons. In 1978, the US Congress passed the Uranium Mill Tailings Radiation Control Act. Title I of the law established a program to assess the tailings at inactive uranium processing sites and provide a means for joint federal and state funding of the cleanup efforts at sites where all or substantially all of the uranium was produced for sale to a federal agency. The UMTRA Project is responsible for the cleanup of 24 sites in 10 states. Germany is facing nearly identical uranium cleanup problems and has established a cleanup project. At the workshop, participants had an opportunity to interact with a broad cross section of the environmental restoration and waste disposal community, discuss common concerns and problems, and develop a broader understanding of the issues. Abstracts are catalogued individually for the data base
Energy Technology Data Exchange (ETDEWEB)
DEFFENBAUGH, M.L.
2000-08-01
The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement
International Nuclear Information System (INIS)
Mobbs, S.F.; Harvey, M.P.; Martin, J.S.; Mayall, A.; Jones, M.E.
1991-01-01
A joint project involving contractors from France, Germany and the UK was set up by the Commission of the European Communities to assess the implications of two waste management options: the direct disposal of spent fuel and reprocessing of that fuel. This report describes the calculation of the radiological impact on the public of the management and disposal of the wastes associated with these two options. Six waste streams were considered: discharge of liquid reprocessing effluents, discharge of gaseous reprocessing effluents, disposal of low-level solid wastes arising from reprocessing, disposal of intermediate-level solid wastes arising from reprocessing, disposal of vitrified high-level reprocessing wastes, and direct disposal of spent fuel. The results of the calculations are in the form of maximum annual doses and risks to individual members of the public, and collective doses to four population groups, integrated over six time periods. These results were designed for input into a computer model developed by another contractor, Yard Ltd, which combines costs and impacts in a multi-attribute hierarchy to give an overall measure of the impact of a given option
Waste disposal into the ground
Energy Technology Data Exchange (ETDEWEB)
Mawson, C A
1955-07-01
The establishment of an atomic energy project is soon followed by the production of a variety of radioactive wastes which must be disposed of safely, quickly and cheaply. Experience has shown that much more thought has been devoted to the design of plant and laboratories than to the apparently dull problem of what to do with the wastes, but the nature of the wastes which will arise from nuclear power production calls for a change in this situation. We shall not be concerned here with power pile wastes, but disposal problems which have occurred in operation of experimental reactors have been serious enough to show that waste disposal should be considered during the early planning stages. (author)
Subproject L-045H 300 Area Treated Effluent Disposal Facility
International Nuclear Information System (INIS)
1991-06-01
The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The ''300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations
Technical Assistance Contractor management plan. Revision 1
International Nuclear Information System (INIS)
1995-08-01
The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) as the prime contractor and three teaming partner subcontractors: Roy F. Weston, Inc. (RFW), AGRA Earth and Environmental, Inc. (AGRA), and Geraghty and Miller, Inc. (G and M). The TAC contract's scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both Surface and Ground Water Projects. The TAC team supports the DOE in completing surface remedial action and initiating ground water remediation work for start-up, characterization, compliance planning, design, construction oversight, and remedial operations. The TAC provides the DOE UMTRA Project Team with a dedicated management, scientific, and technical resource base in Albuquerque, New Mexico, which is supplemented by corporate resources. A carefully developed and maintained staff of technical experts is available to assess, analyze, develop, and execute cost-effective solutions to the demanding technical and institutional problems presented by the UMTRA Project
Public Perspectives in the Japanese HLW Disposal Program
International Nuclear Information System (INIS)
Inatsugu, Shigefumi; Takeuchi, Mitsuo; Kato, Toshiaki
2006-01-01
Following legislation entitled the 'Specified Radioactive Waste Final Disposal Act', the Nuclear Waste Management Organization of Japan (NUMO) was established in October 2000 as the implementing organization for geological disposal of vitrified high-level waste (HLW). Implementation of NUMO's disposal project will be based on three principles: 1) respecting public initiative and opinion, 2) adopting a stepwise approach and 3) ensuring transparency in information disclosure. NUMO has decided to adopt an open solicitation approach to finding volunteer municipalities for Preliminary Investigation Areas (PIAs). The official announcement of the start of the open solicitation program was made in 2002. Although no official applications had been received from volunteer municipalities by the end of 2005, NUMO has been continuing to carry out various activities aimed specifically at public communication and encouraging dialogue about the deep geological disposal project This paper summarizes the results obtained and lessons learned so far and identifies the issues that NUMO must tackle immediately in the areas of communication and dialogue
Public Perspectives in the Japanese HLW Disposal Program
Energy Technology Data Exchange (ETDEWEB)
Inatsugu, Shigefumi; Takeuchi, Mitsuo; Kato, Toshiaki [Nuclear Waste Management Organization of Japan (NUNIO), Tokyo (Japan)
2006-09-15
Following legislation entitled the 'Specified Radioactive Waste Final Disposal Act', the Nuclear Waste Management Organization of Japan (NUMO) was established in October 2000 as the implementing organization for geological disposal of vitrified high-level waste (HLW). Implementation of NUMO's disposal project will be based on three principles: 1) respecting public initiative and opinion, 2) adopting a stepwise approach and 3) ensuring transparency in information disclosure. NUMO has decided to adopt an open solicitation approach to finding volunteer municipalities for Preliminary Investigation Areas (PIAs). The official announcement of the start of the open solicitation program was made in 2002. Although no official applications had been received from volunteer municipalities by the end of 2005, NUMO has been continuing to carry out various activities aimed specifically at public communication and encouraging dialogue about the deep geological disposal project This paper summarizes the results obtained and lessons learned so far and identifies the issues that NUMO must tackle immediately in the areas of communication and dialogue.
Site observational work plan for the UMTRA Project site at Spook, Wyoming
International Nuclear Information System (INIS)
1994-09-01
Ground water in the uppermost aquifer beneath and downgradient from the Spook site was contaminated by uranium-processing activities that occurred from 1962 until 1966. Contamination from the tailings pile and the acid pond (including uranium, selenium, nitrate, and radium-226 and -228) leached into the subsurface by infiltration and migrated into ground water, forming a plume extending approximately 2,500 feet (ft) (760 meters [m]) downgradient from the site. The surface remedial action at the Spook site under Subpart A of 40 CFR Part 192 consisted of stabilizing the uranium mill tailings and other residual radioactive materials in a disposal cell in the bottom of the Spook open-pit mine and covering the cell with overburden material. The ground water protection strategy was supplemental standards based on Class 3 ground water in the uppermost aquifer because of widespread ambient contamination. The proposed ground water protection strategy to comply with Subpart B of 40 CFR Part 192 at the Spook site is to perform no remediation. This strategy is based on ground water in the uppermost aquifer (also the zone of contamination) being classified as Class 3, which allows the application of supplemental standards. Class 3 ground water beneath the Spook site is neither a current nor a potential source of drinking water because of widespread, ambient contamination that cannot be cleaned up using treatment methods reasonably employed in public water supply systems
Annual status report on the Uranium Mill Tailings Remedial Action Program
International Nuclear Information System (INIS)
1992-12-01
This fourteenth annual status report for the Uranium Mill Tailings Remedial Action (UMTRA) Project Office summarizes activities of the Uranium Mill Tailings Remedial Action Surface (UMTRA-Surface) and Uranium Mill Tailings Remedial Action Groundwater (UMTRA-Groundwater) Projects undertaken during fiscal year (FY) 1992 by the US Department of Energy (DOE) and other agencies. Project goals for FY 1993 are also presented. An annual report of this type was a statutory requirement through January 1, 1986, pursuant to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604. The DOE will continue to submit annual reports to DOE-Headquarters, the states, tribes, and local representatives through Project completion in order to inform the public of the yearly Project status. The purpose of the remedial action is to stabilize and control the tailings and other residual radioactive material (RRM) located on the inactive uranium processing sites in a safe and environmentally sound manner, and to minimize or eliminate potential health hazards. Commercial and residential properties near designated processing sites that are contaminated with material from the sites, herein referred to as ''vicinity properties (VP),'' are also eligible for remedial action. Included in the UMTRA Project are 24 inactive uranium processing sites and associated VPs located in 10 states, and the VPs associated with the Edgemont, South Dakota, uranium mill currently owned by the Tennessee Valley Authority (TVA) (Figure A.1, Appendix A)
Energy Technology Data Exchange (ETDEWEB)
Bush, Richard [USDOE Office of Legacy Management, Washington, DC (United States); Lemke, Peter [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)
2015-11-01
The groundwater compliance strategy for the Tuba City, Arizona, Disposal Site is defined in the 1999 Phase I Ground Water Compliance Action Plan for the Tuba City, Arizona, UMTRA Site. Samples are collected and analyzed on a semiannual basis to evaluate the performance of the Phase I remediation system. Sampling and analyses were conducted as specified in Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated). U.S. Environmental Protection Agency (EPA) groundwater standards were exceeded in samples collected from monitoring wells and extraction wells as listed in Table 1. The data from this sampling event are generally consistent with previously obtained values and are acceptable for general use as qualified. Data anomalies are not significant with respect to the known nature and extent of contamination and progress of remedial action at the site. The data from this sampling event will be incorporated into the annual performance evaluation report that will present a comprehensive hydrologic summary and evaluation of groundwater remedial action performance at the Tuba City site through March 2016.
Energy Technology Data Exchange (ETDEWEB)
Bush, Richard [USDOE Office of Legacy Management, Washington, DC (United States); Lemke, Peter [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)
2016-04-01
The groundwater compliance strategy for the Tuba City, Arizona, Disposal Site is defined in the 1999 Phase I Ground Water Compliance Action Plan for the Tuba City, Arizona, UMTRA Site. Samples are collected and analyzed on a semiannual basis to evaluate the performance of the Phase I remediation system. Sampling and analyses were conducted as specified in Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated). U.S. Environmental Protection Agency (EPA) groundwater standards were exceeded in samples collected from monitoring wells as listed in Table 1. The data from this sampling event are generally consistent with previously obtained values and are acceptable for general use as qualified. Data anomalies are not significant with respect to the known nature and extent of contamination and progress of remedial action at the site. The data from this sampling event will be incorporated into the annual performance evaluation report that will present a comprehensive hydrologic summary and evaluation of groundwater remedial action performance at the Tuba City site through March 2016.
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
UK surplus source disposal programme - 16097
International Nuclear Information System (INIS)
John, Gordon H.; Reeves, Nigel; Nisbet, Amy C.; Garnett, Andrew; Williams, Clive R.
2009-01-01
The UK Surplus Source Disposal Programme (SSDP), managed by the Environment Agency, was designed to remove redundant radioactive sources from the public domain. The UK Government Department for Environment, Food and Rural Affairs (Defra) was concerned that disused sources were being retained by hospitals, universities and businesses, posing a risk to public health and the environment. AMEC provided a range of technical and administrative services to support the SSDP. A questionnaire was issued to registered source holders and the submitted returns compiled to assess the scale of the project. A member of AMEC staff was seconded to the Environment Agency to provide technical support and liaise directly with source holders during funding applications, which would cover disposal costs. Funding for disposal of different sources was partially based on a sliding scale of risk as determined by the IAEA hazard categorisation system. This funding was also sector dependent. The SSDP was subsequently expanded to include the disposal of luminised aircraft instruments from aviation museums across the UK. These museums often hold significant radiological inventories, with many items being unused and in a poor state of repair. These instruments were fully characterised on site by assessing surface dose rate, dimensions, source integrity and potential contamination issues. Calculations using the Microshield computer code allowed gamma radiation measurements to be converted into total activity estimates for each source. More than 11,000 sources were disposed of under the programme from across the medical, industrial, museum and academic sectors. The total activity disposed of was more than 8.5 E+14 Bq, and the project was delivered under budget. (authors)
Research on the disposal of radioactive wastes; Forschung zur Entsorgung radioaktiver Abfaelle
Energy Technology Data Exchange (ETDEWEB)
NONE
2015-02-15
The report covers the following issues: Challenges of the nuclear disposal; actual state of knowledge: research and development on final disposal in salt rocks, clays, granite, general topics; research and development strategy: goals of the governmental project funding, strategic research objectives, research and development needs; research and development projects.
Design concept of a knowledge management system of geological disposal technology
International Nuclear Information System (INIS)
Osawa, Hideaki; Umeki, Hiroyuki; Makino, Hitoshi; Takase, H.; Mckinley, I.G.; Okubo, H.
2008-01-01
JAEA is developing a 'Knowledge Management System' for vast quantities of data or information arising from various sources relevant to the geological disposal programs in Japan. The geological disposal project is taking a stepwise approach to selecting a disposal site and, to the approval and licensing, construction, operation and closure of a repository. It is a long-term project required approximately 100 years. In this paper, in order to structuralize, as knowledge, the results of R and D on geological disposal technologies of high-level radioactive wastes, the knowledge management approach was first reviewed. The paper is followed by descriptions of the technical characteristics, procedure to carry out a plan, and education of geological disposal technologies such as knowledge management etc. The structuring of the knowledge base and the knowledge management system including the construction of safety case were described. (S. Ohno)
Energy Technology Data Exchange (ETDEWEB)
Labalette, Th. [Agence Nationale pour la Gestion des Dechets Radioactifs - ANDRA, Dir. des Projets, 92 - Chatenay Malabry (France)
2011-02-15
The French Act of 28 June 2006 identifies reversible disposal in deep geological facilities as the benchmark solution for long-term management of high-level waste (HLW) and for intermediate-level long-lived waste (ILW-LL). The Act tasks ANDRA (national agency for the management of radioactive wastes) with the pursuit of studies and research on the choice of a site and the design of the repository, with a view to examining the licence application in 2015 and, provided that the licence is granted, to make the facility operational by 2025. At the end of 2009, ANDRA submitted to the Government its proposals regarding the site and the design of the Industrial Centre for Geological Disposal, known as CIGEO. With the definition of a possible area for the construction of underground disposal facilities, one of the key stages in the project has been achieved. The choice of a surface site will be validated following the public consultation scheduled for the end of 2012. The project is now on the point of entering the definition stage (preliminary design). CIGEO will be a nuclear facility unlike any other. It will be built and operated for a period of over 100 years. For it to be successful, the project must meet certain requirements related to its integration in the local area, industrial planning, safety and reversibility, while also controlling costs. Reversibility is a very important concept that will be defined by law. It is ANDRA's responsibility to ensure that a reasonable balance is found between these different concerns. (author)
International Nuclear Information System (INIS)
Brunnengraeber, Achim
2015-01-01
The nuclear power production that was productive for two generations produces radioactive wastes that will be a hazardous and financial burden for many future generations. Science, politics, industry and the society are responsible to find a successful solution for the project of final disposal of radioactive wastes. With the fast development of renewable energies with the perspectives of sustainability and other advantages nuclear power will not have a remarkable future. The search for a final repository site is a tremendous governmental, economic and public challenge but can also be seen as a social chance. Democracy could be enforced by this process, public commitment, transparency, co-determination, confidence in political processes are indispensible premises.
Estimating the cost of disposal for Canada's nuclear fuel waste
International Nuclear Information System (INIS)
Ates, Y.
1996-07-01
Atomic Energy of Canada Ltd (AECL) prepared an Environmental Impact Statement and nine supporting Primary Reference Documents on the concept for disposal of Canada's nuclear fuel waste. This report summarizes the basis of the cost estimate which is provided in the primary reference document on engineering for a disposal facility. The scope of the cost estimate is explained by describing the key features of the disposal facility design, by noting the major assumptions made in preparing the estimates, and by listing the included and excluded cost components. An activity-based project planning and control method is explained whereby the project schedule, costs, and personnel requirements are interlinked; forming an integrated perspective on the total project life cycle. The summary and distribution of costs in each project stage by major facility or activity are presented. The results of studies which reviewed the overall cost estimate are also described. These studies indicate that, within the scope, the estimate is reasonable and compares well with similar international studies. (author)
International Nuclear Information System (INIS)
1978-01-01
This report has been prepared by the Swedish Energy Commission's working group for Safety and Environment. The main contributions are by profs. Jan Rydberg of Chalmers University of Technology, Sweden and John W Winchester of Florida State University, USA. The aim of the report is to discuss weather the KBS-project fullfills the Swedish ''Stipulations Act'', that a absolutely safe way of disposing of the nuclear waste must have been demonstrated before any new reactors are allowed to be taken inot use. Rydberg and Winchester do not arrive at similar conclusions. (L.E.)
International Nuclear Information System (INIS)
Mokka, J.
2016-01-01
Full text: Posiva Oy is an expert organization established in 1995 and responsible for the final disposal of the spent nuclear fuel of its owners. Posiva currently employs around 100 people and has a turnover of some 63 million (2015). The company headquarters are located in Olkiluoto in the municipality of Eurajoki, Finland. Posiva is owned by two Finnish NPP operators Teollisuuden Voima Oyj (60%) (TVO) and Fortum Power & Heat Oy (40%), both of which are responsible for their costs of nuclear waste management. The Finnish final disposal programme has a long history. When NPP unit Olkiluoto 1 renewed its operating licence for the first time in 1983, TVO presented a programme showing final disposal to commence in the 2020s. In the 1980s and 1990s, the programme concentrated on concept development and site selection activities. After 2003, when Posiva received the decision in principle from the Finnish Government, a new phase began in the programme. Since 2004, Posiva Oy has constructed an underground rock characterization facility on the repository site in Olkiluoto, in western Finland. This facility, called ONKALO, has provided an opportunity to carry out further site investigations, develop construction techniques, and test and demonstrate the engineered barrier system in an actual repository environment. As a result of these investigations and development efforts, the application for a licence to construct the encapsulation plant and the geological repository was submitted in 2012. The Radiation and Nuclear Safety Authority in Finland (STUK) first gave a positive review on the safety of the facility, and consequently the Finnish Government granted the construction licence in November 2015. After receiving the construction licence as the first disposal programme in the world, the next phase in the program will be the construction project of the final disposal facilities required for the disposal operations. A significant first-of-a-kind construction project like
Economics of low-level radioactive waste disposal
International Nuclear Information System (INIS)
Schafer, J.; Jennrich, E.
1983-01-01
Regardless of who develops new low-level radioactive waste disposal sites or when, economics will play a role. To assist in this area the Department of Energy's Low-Level Radioactive Waste Management Program has developed a computer program, LLWECON, and data base for projecting disposal site costs. This program and its non-site specific data base can currently be used to compare the costs associated with various disposal site development, financing, and operating scenarios. As site specific costs and requirements are refined LLWECON will be able to calculate exact life cycle costs for each facility. While designed around shallow land burial, as practiced today, LLWECON is flexible and the input parameters discrete enough to be applicable to other disposal options. What the program can do is illustrated
International Nuclear Information System (INIS)
Takada, Susumu
2006-01-01
The objective of this report is to assist related organizations in the development of quality assurance systems for a high-level radioactive waste disposal system. This report presents detail information with which related organizations can begin the development of quality assurance systems at an initial phase of repository development for a high-level radioactive waste disposal program, including data qualification, model validation, systems and facilities for quality assurance (e.g., technical data management system, sample management facility, etc.), and QA program applicability (items and activities). These descriptions are based on information in QA program for the Yucca Mountain Project (YMP), such as the U.S. Department of Energy (DOE) Quality Assurance Requirements and Description (QARD), DOE/RW-0333P, quality implementing procedures, and reports implemented by the procedures. Additionally, this report includes some brief recommendations for developing of quality assurance systems, such as establishment of quality assurance requirements, measures for establishment of QA system. (author)
International Nuclear Information System (INIS)
Hunt, R.D.; McGinnis, C.P.; Cruse, J.M.
1994-01-01
The US Department of Energy (DOE) Office of Environmental Restoration and Waste Remediation has created the Office of Technology Development (OTD) to provide new and improved remediation technologies for the 1 x 10 8 gal of radioactive waste in the underground storage tanks (USTs) at five DOE sites. The OTD established and the Underground Storage Tank-Integrated Demonstration (UST-ID) to perform demonstrations, tests, and evaluations on these new technologies before these processes are transferred to the tank sites for use in full-scale remediation of the USTs. The UST-ID projects are performed by the Characterization and Waste Retrieval Program or the Waste Processing and Disposal Program (WPDP). During FY 1994, the WPDP is funding 12 projects in the areas of supernate processing, sludge processing, nitrate destruction, and final waste forms. The supernate projects are primarily concerned with cesium removal. A mobile evaporator and concentrator for cesium-free supernate is also being demonstrated. The sludge projects are emphasizing sludge dissolution and the evaluation of the TRUEX and diamide solvent extraction processes for transuranic waste streams. One WPDP project is examining both supernate and sludge processes in an effort to develop a system-level plan for handling all UST waste. The other WPDP studies are concerned with nitrate and organic destruction as well as subsequent waste forms. The current status of these WPDP projects is presented
Bettington, Emilie; Spinks, Jean; Kelly, Fiona; Gallardo-Godoy, Alejandra; Nghiem, Son; Wheeler, Amanda J
2017-12-19
Objective The aim of the present study was to explore disposal practices of unwanted medicines in a representative sample of Australian adults, compare this with previous household waste surveys and explore awareness of the National Return and Disposal of Unwanted Medicines (RUM) Project. Methods A 10-min online survey was developed, piloted and conducted with an existing research panel of adult individuals. Survey questions recorded demographics, the presence of unwanted medicines in the home, medicine disposal practices and concerns about unwanted medicines. Descriptive statistical analyses and rank-ordered logit regression were conducted. Results Sixty per cent of 4302 respondents reported having unwanted medicines in their household. Medicines were primarily kept just in case they were needed again and one-third of these medicines were expired. Two-thirds of respondents disposed of medicines with the household garbage and approximately one-quarter poured medicines down the drain. Only 17.6% of respondents had heard of the RUM Project, although, once informed, 91.7% stated that they would use it. Respondents ranked the risk of unintended ingestion as the most important public health message for future social marketing campaigns. Conclusions Respondents were largely unaware of the RUM Project, yet were willing to use it once informed. Limited awareness could lead to environmental or public health risks, and targeted information campaigns are needed. What is known about the topic? There is a growing international evidence base on how people dispose of unwanted medicines and the negative consequences, particularly the environmental effects of inappropriate disposal. Although insight into variation in disposal methods is increasing, knowledge of how people perceive risks and awareness of inappropriate disposal methods is more limited. What does this paper add? This study provides evidence of inappropriate medicines disposal and potential stockpiling of medicines in
Waste and Disposal: Demonstration
International Nuclear Information System (INIS)
Neerdael, B.; Buyens, M.; De Bruyn, D.; Volckaert, G.
2002-01-01
Within the Belgian R and D programme on geological disposal, demonstration experiments have become increasingly important. In this contribution to the scientific report 2001, an overview is given of SCK-CEN's activities and achievements in the field of large-scale demonstration experiments. In 2001, main emphasis was on the PRACLAY project, which is a large-scale experiment to demonstrate the construction and the operation of a gallery for the disposal of HLW in a clay formation. The PRACLAY experiment will contribute to enhance understanding of water flow and mass transport in dense clay-based materials as well as to improve the design of the reference disposal concept. In the context of PRACLAY, a surface experiment (OPHELIE) has been developed to prepare and to complement PRACLAY-related experimental work in the HADES Underground Research Laboratory. In 2001, efforts were focussed on the operation of the OPHELIE mock-up. SCK-CEN also contributed to the SELFRAC roject which studies the self-healing of fractures in a clay formation
On-site disposal as a decommissioning strategy
International Nuclear Information System (INIS)
1999-11-01
On-site disposal is not a novel decommissioning strategy in the history of the nuclear industry. Several projects based on this strategy have been implemented. Moreover, a number of studies and proposals have explored variations within the strategy, ranging from in situ disposal of entire facilities or portions thereof to disposal within the site boundary of major components such as the reactor pressure vessel or steam generators. Regardless of these initiatives, and despite a significant potential for dose, radioactive waste and cost reduction, on-site disposal has often been disregarded as a viable decommissioning strategy, generally as the result of environmental and other public concerns. Little attention has been given to on-site disposal in previous IAEA publications in the field of decommissioning. The objective of this report is to establish an awareness of technical factors that may or may not favour the adoption of on-site disposal as a decommissioning strategy. In addition, this report presents an overview of relevant national experiences, studies and proposals. The expected end result is to show that, subject to safety and environmental protection assessment, on-site disposal can be a viable decommissioning option and should be taken into consideration in decision making
Energy Technology Data Exchange (ETDEWEB)
Barrows, E.S.; Antrim, L.D.; Pinza, M.R.; Gardiner, W.W.; Kohn, N.P.; Gruendell, B.D.; Mayhew, H.L.; Word, J.Q.; Rosman, L.B. [Battelle Marine Sciences Laboratory, Sequim, Washington (United States)
1996-08-01
The U.S. Army Corps of Engineers (USACE) is authorized by Section 103 of the Marine Protection, Research, and Sanctuaries Act of 1972 (MPRSA), Public Law 92-532, and by the Clean Water Act of 1972 (CWA) and Amendments of 1977 to permit, evaluate, and regulate the disposal of dredged material in ocean waters to minimize adverse environmental effects. Compliance with the regulations of the MPRSA calls for physical and biological testing of sediment proposed for dredging prior to its disposal in ocean waters. The testing required by the MPRSA criteria is conducted under a testing manual developed by the USACE and the U.S. Environmental Protection Agency (EPA), Evaluation of Dredged Material Proposed for Ocean Disposal (Testing Manual), commonly referred to as the `Green Book.` Testing protocols in the Green Book include bulk sediment analysis, grain size analysis, elutriate testing, and biological testing. The biological testing includes bioassays for acute toxicity as well as analysis to determine bioaccumulation of certain contaminants by marine organisms. The objective of the USACE-NYD Federal Projects Program was to evaluate sediment proposed for dredging and unconfined ocean disposal at the Mud Dump Site. The results of analytical measurements and bioassays performed on the test sediments were compared with analyses of sediment from the Mud Dump Reference Site to determine whether the test sediments were acutely toxic to marine organisms or resulted in statistically significantly greater bioaccumulation of contaminants in marine organisms, relative to the reference sediment. Testing for the federal project areas was performed according to the requirements.
Technical Assistance Contractor management plan. Revision 1
Energy Technology Data Exchange (ETDEWEB)
NONE
1995-08-01
The Technical Assistance Contractor (TAC) for the Uranium Mill Tailings Remedial Action (UMTRA) Project comprises Jacobs Engineering Group Inc. (JEG) as the prime contractor and three teaming partner subcontractors: Roy F. Weston, Inc. (RFW), AGRA Earth and Environmental, Inc. (AGRA), and Geraghty and Miller, Inc. (G and M). The TAC contract`s scope is to provide technical, analytical, environmental, engineering, design, inspection, and management support services to the US Department of Energy (DOE) for both Surface and Ground Water Projects. The TAC team supports the DOE in completing surface remedial action and initiating ground water remediation work for start-up, characterization, compliance planning, design, construction oversight, and remedial operations. The TAC provides the DOE UMTRA Project Team with a dedicated management, scientific, and technical resource base in Albuquerque, New Mexico, which is supplemented by corporate resources. A carefully developed and maintained staff of technical experts is available to assess, analyze, develop, and execute cost-effective solutions to the demanding technical and institutional problems presented by the UMTRA Project.
Argentine project for the final disposal of high-level radioactive wastes
International Nuclear Information System (INIS)
Palacios, E.; Ciallella, N.R.; Petraitis, E.J.
1989-01-01
From 1980 Argentina is carrying out a research program on the final disposal of high level radioactive wastes. The quantity of wastes produced will be significant in next century. However, it was decided to start with the studies well in advance in order to demonstrate that the high level wastes could be disposed in a safety way. The option of the direct disposal of irradiated fuel elements was discarded, not only by the energetic value of the plutonium, but also for ecological reasons. In fact, the presence of a total inventory of actinides in the non-processed fuel would imply a more important radiological impact than that caused if the plutonium is recycled to produce energy. The decision to solve the technological aspects connected with the elimination of high-level radioactive wastes well in advance, was made to avoid transfering the problem to future generations. This decision is based not only on technical evaluations but also on ethic premises. (Author)
International Nuclear Information System (INIS)
1993-12-01
Intraval is an international project that addresses the validation of models of transport of radionuclides through groundwater in the geosphere. Such models are used in assessment of the long-term safety of nuclear waste disposal systems. The present report summarises the results for the test cases and presents some additional remarks
International Nuclear Information System (INIS)
1991-01-01
The international cooperation project HYDROCOIN for studying groundwater flow modelling in the context of radioactive waste disposal was initiated in 1984. Thirteen organisations from ten countries and two international organisations have participated in the project which has been managed by the Swedish Nuclear Power Inspectorate, SKI. This report summarises the results from the third phase of HYDROCOIN, Level 3, which has addressed the issues of uncertainty and sensitivity analysis of groundwater flow problems and how uncertainties affect the modelling results. Seven test cases were selected for the project, representing a variety of flow situations in different media, as well as variety of temporal and spatial scales. These test cases were tackled by the participating organisations (Project Teams) using a number of different codes. An overview of the methodologies used in uncertainty and sensitivity analysis is given. Results from the various Teams attempting the Test Cases are presented and conclusions are drawn as to the applicability of the results obtained to the test cases being analysed as well as the general applicability of the results. The importance of making uncertainty and sensitivity analysis as part of a performance analysis of the safety of a nuclear waste repository is stressed. The conclusion is drawn that the HYDROCOIN Level 3 study has greatly contributed to the understanding of these issues. 42 refs., 159 figs., 61 tabs
Technical responsibilities in low-level waste disposal
International Nuclear Information System (INIS)
Murray, R.L.; Walker, C.K.
1989-01-01
North Carolina will be the host state for a low-level radioactive waste (LLRW) disposal facility serving the Southeast Compact for 20 yr beginning in 1993. Primary responsibility for the project rests with the North Carolina Low-Level Radioactive Waste Management Authority, a citizen board. The North Carolina project embodies a unique combination of factors that places the authority in a position to exercise technical leadership in the LLRW disposal field. First, the Southeast Compact is the largest in the United States in terms of area, population, and waste generation. second, it is in a humid rather than an arid region. Third, the citizens of the state are intensely interested in preserving life style, environment, and attractiveness of the region to tourists and are especially sensitive to the presence of waste facilities of any kind. Finally, disposal rules set by the Radiation Protection Commission and enforced by the Radiation Protection Section are stricter than the U.S. Nuclear Regulatory Commission's 10CFR61. These four factors support the authority's belief that development of the facility cannot be based solely on engineering and economics, but that social factors, including perceptions of human risk, concerns for the environment, and opinions about the desirability of hosting a facility, should be integral to the project. This philosophy guides the project's many technical aspects, including site selection, site characterization, technology selection and facility design, performance assessment modeling, and waste reduction policies. Each aspect presents its own unique problems
Evaluation of salt and mine rock disposal. Project No. 76-283
International Nuclear Information System (INIS)
1976-11-01
Studies are being performed on the isolation of nuclear waste in geological formations; this would entail constructing an underground mine in selected rock strata for waste storage. Rocks removed from the mine during construction must be either disposed of permanently or temporarily stored for later backfill into the mine. Several methods of storing or disposing of the mined rock are discussed in this report. The technical feasibility, cost, advantages and disadvantages of each method are presented and the ranking of methods based on currently available data is discussed. Salt, shale, granite, and limestone are covered
Planning for a space infrastructure for disposal of nuclear space power systems
International Nuclear Information System (INIS)
Angelo, J. Jr.; Albert, T.E.; Lee, J.
1989-01-01
The development of safe, reliable, and compact power systems is vital to humanity's exploration, development, and, ultimately, civilization of space. Nuclear power systems appear to present to offer the only practical option of compact high-power systems. From the very beginning of US space nuclear power activities, safety has been a paramount requirement. Assurance of nuclear safety has included prelaunch ground handling operations, launch, and space operations of nuclear power sources, and more recently serious attention has been given to postoperational disposal of spent or errant nuclear reactor systems. The purpose of this paper is to describe the progress of a project to utilize the capabilities of an evolving space infrastructure for planning for disposal of space nuclear systems. Project SIREN (Search, Intercept, Retrieve, Expulsion - Nuclear) is a project that has been initiated to consider post-operational disposal options for nuclear space power systems. The key finding of Project SIREN was that although no system currently exists to affect the disposal of a nuclear space power system, the requisite technologies for such a system either exist or are planned for part of the evolving space infrastructure
Overview of low level waste disposal facility costs
International Nuclear Information System (INIS)
Saverot, P.M.
1995-01-01
Economics and uncertainty go hand-in-hand and it is too soon to have conclusive data on the life cycle costs of a disposal facility. While LLW volumes from are decreasing year after year, the effect of the projected LLW volumes from decommissioning may have a significant impact on the final unit costs. This overview recognizes that countries see LLW disposal costs differently depending on the scale of their programs and on the geographical, political and economic frameworks within which they operate. The reasons for the cost differences arise from a number of factors: differences in designs and in technologies (near surface engineered vault, enhanced shallow land burial, silo type caverns,...), disposal capacities, programmatic and regulatory requirements, organizational, managerial and institutional frameworks, contractual arrangements, etc. Comparison of actual project costs, if done incorrectly, can lead to invalid conclusions and little purpose would be served by so doing since cost variations reflect the reality faced by each country