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1

Long-term surveillance plan for the Shiprock disposal site, Shiprock, New Mexico  

SciTech Connect

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.

Not Available

1993-12-01

2

Long-term surveillance plan for the Shiprock Disposal site, Shiprock, New Mexico  

SciTech Connect

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).

Not Available

1994-09-01

3

Engineering assessment of inactive uranium mill tailings, Shiprock site, Shiprock, New Mexico  

SciTech Connect

Ford, Bacon and Davis Utah Inc. has reevaluated the Shiprock site in order to revise the March 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Shiprock, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 1.5 million dry tons of tailings at the Shiprock site constitutes the most significant environental impact, although windblown tailings and external gamma radiation also are factors. The eight alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material (Option I), to removal of the tailings to remote disposal sites and decontamination of the tailings site (Options II through VIII). Cost estimates for the eight options range from about $13,400,000 for stabilization in place to about $37,900,000 for disposal at a distance of about 16 miles. Three principal alternatives for the reprocessing of the Shiprock tailings were examined: (a) heap leaching; (b) treatment at an existing mill; and (c) reprocessing at a new conventional mill constructed for tailings reprocessing. The cost of the uranium recovered would be about $230/lb by heap leach and $250/lb by conventional plant processes. The spot market price for uranium was $25/lb early in 1981. Therefore, reprocessing the tailings for uranium recovery is not economically attractive.

Not Available

1981-07-01

4

Site observational work plan for the UMTRA project site at Shiprock, New Mexico  

SciTech Connect

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.

Not Available

1994-09-01

5

Baseline risk assessment of ground water contamination at the Uranium Mill Tailings Site near Shiprock, New Mexico. Revision 1  

SciTech Connect

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.

Not Available

1994-04-01

6

UMTRA project water sampling and analysis plan -- Shiprock, New Mexico  

SciTech Connect

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.

Not Available

1994-02-01

7

NRC disposed to site  

NASA Astrophysics Data System (ADS)

A committee of the National Research Council (NRC) has found the risk of human exposure to radiation from nuclear waste to be minimal at a proposed underground disposal site. In a report on the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico, the NRC committee asserted that the danger of radioactive exposure at the site is unlikely to exceed U.S. and international standards for protection from radiation. Unless the site is breached by humansmost likely those drilling for gas or oilthere is no credible or probable chance of the release of the radioactive waste, the committee said.

Carlowicz, Michael

8

Hanford Site Mixed Waste Disposal  

Microsoft Academic Search

Significant volumes of mixed low-level waste (MLLW) will be generated as part of the management and remediation of the Hanford Site. The MLLW that is generated as part of the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA) process will largely be managed as part of that remediation effort, with disposal likely in the centralized Environmental Restoration Disposal

2001-01-01

9

Baseline risk assessment of groundwater contamination at the uranium mill tailings site near Shiprock, New Mexico. Draft  

SciTech Connect

This report evaluates potential impact 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 were placed in a disposal cell on the site in 1986 by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This risk assessment is the first document specific to this site for the Groundwater Project. This risk assessment follows the 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 floodplain groundwater are arsenic, magnesium, manganese, nitrate, sodium, sulfate, and uranium. The complete list of contaminants associated with the terrace groundwater could not be determined due to the lack of the background groundwater quality data. However, uranium, nitrate, and sulfate are evaluated since these chemicals are clearly associated with uranium processing and are highly elevated compared to regional waters. It also could not be determined if the groundwater occurring in the terrace is a usable water resource, since it appears to have originated largely from past milling operations. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if a drinking well were installed in the contaminated groundwater or if there were exposure to surface expressions of contaminated water. Potential exposures to surface water include incidental contact with contaminated water or sediments by children playing on the floodplain and consumption of meat and milk from domestic animals grazed and watered on the floodplain.

Not Available

1993-09-01

10

40 CFR 228.3 - Disposal site management responsibilities.  

Code of Federal Regulations, 2010 CFR

...2010-07-01 false Disposal site management responsibilities. 228...Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED...DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN...228.3 Disposal site management responsibilities....

2010-07-01

11

40 CFR 228.7 - Regulation of disposal site use.  

Code of Federal Regulations, 2013 CFR

... 2013-07-01 false Regulation of disposal site use. 228...PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING 228.7 Regulation of disposal site use....

2013-07-01

12

40 CFR 228.7 - Regulation of disposal site use.  

Code of Federal Regulations, 2014 CFR

... 2014-07-01 false Regulation of disposal site use. 228...PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING 228.7 Regulation of disposal site use....

2014-07-01

13

40 CFR 228.7 - Regulation of disposal site use.  

Code of Federal Regulations, 2012 CFR

...2012-07-01 2011-07-01 true Regulation of disposal site use. 228...PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING 228.7 Regulation of disposal site use....

2012-07-01

14

40 CFR 228.7 - Regulation of disposal site use.  

Code of Federal Regulations, 2011 CFR

... 2011-07-01 false Regulation of disposal site use. 228...PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING 228.7 Regulation of disposal site use....

2011-07-01

15

Chemical Evidence for Uranium Bioreduction at Shiprock, New Mexico  

NASA Astrophysics Data System (ADS)

The Department of Energy Uranium Mill Tailings (UMTRA) site at Shiprock, New Mexico includes a mill tailings disposal cell on a mesa overlooking the floodplain of the San Juan River. A plume of contaminated groundwater extends across the floodplain to the river. Although organisms that can reduce uranyl have been identified at the site, the extent of intrinsic reduction is difficult to assess. Uranyl concentrations vary due to mixing between three components: the contaminant plume, river water, and water from a flowing well of deep origin. Chloride and 3H were used to construct a three-component mixing model for floodplain groundwaters. The fraction of each component at each sampling point was used to estimate the uranyl concentration expected from dilution of the plume source by the other components. A much lower concentration than expected was taken to indicate bioreduction. Experimentation indicated that uranyl would only be bioreduced where nitrate was first completely removed; the model results showed evidence for uranyl reduction only where nitrate had been markedly and significantly removed, also by bioreduction. Low nitrate concentrations in these zones may have resulted from post-reduction mixing with nitrate-bearing water.

McKinley, J. P.; Long, P. E.; Elias, D.; Krumholz, L. R.

2001-12-01

16

Nebraska files suit to block disposal site  

SciTech Connect

Just when the Central Interstate Low-Level Radioactive Waste Compact thought things might be starting to go its way, the state of Nebraska, following instructions from Gov. Ben Nelson, has filed a new lawsuit to block development of an LLW disposal site within its borders. The suit maintains that the recently reconfigured proposed site (in which an area of wetlands was excluded) has not received [open quotes]community consent,[close quotes] as required by state law; says that site developer, US Ecology, has not obtained county consent; and asks that the court permanently prevent development of any LLW site in Nebraska until community consent is demonstrated.

Not Available

1993-12-01

17

40 CFR 228.7 - Regulation of disposal site use.  

Code of Federal Regulations, 2010 CFR

...PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING 228.7 Regulation of disposal site...regulated by setting limitations on times of dumping and rates of discharge, and...

2010-07-01

18

Regulatory Requirements for Land Disposal of Coal Gasification Waste and Their Implications for Disposal Site Design  

Microsoft Academic Search

The regulatory requirements applicable to the land disposal of solid wastes from coal gasification plants are reviewed from the standpoint of disposal site design and design performance evaluation. After consideration of the design flexibility allowed under existing regulations, three approaches to disposal site design are analyzed, and the state-of-the-art approach is determined to be the preferred one. This approach utilizes

Masood Ghassemi; George Richard

1984-01-01

19

A CEFAS Multidisciplinary Project Team The Rame Head Disposal Site Environmental impacts resulting from disposal of  

E-print Network

modelling 63 5.1.6. Sediment budget for the disposal site. 64 5.2. Is Disposal Having an Impact on DivingA CEFAS Multidisciplinary Project Team ­ The Rame Head Disposal Site 1 Environmental impacts Recreational diving 19 Fishing and shellfishery activities 20 Sewage outfalls and overflows 20 2.2.6. Public

20

Escarpment seeps at Shiprock, New Mexico. [Risk posed by seep water to human health and the environment  

SciTech Connect

The purpose of this report is to characterize the seeps identified at the Shiprock UMTRA Project site during the prelicensing custodial care inspection conducted in December of 1990, to evaluate the relationship between the seeps and uranium processing activities or tailings disposal, and to evaluate the risk posed by the seep water to human health and the environment. The report provides a brief description of the geology, groundwater hydrology, and surface water hydrology. The locations of the seeps and monitor wells are identified, and the water quality of the seeps and groundwater is discussed in the context of past activities at the site. The water quality records for the site are presented in tables and appendices; this information was used in the risk assessment of seep water.

Not Available

1991-10-01

21

43 CFR 2743.3 - Leased disposal sites.  

Code of Federal Regulations, 2011 CFR

...2011-10-01 false Leased disposal sites. 2743.3 Section 2743...2743.3 Leased disposal sites. (a) Upon request...determine whether they are contaminated with hazardous substances...of the landfill concerning site management and a review...

2011-10-01

22

Specialized Disposal Sites for Different Reprocessing Plant Wastes  

SciTech Connect

Once-through fuel cycles have one waste form: spent nuclear fuel (SNF). In contrast, the reprocessed SNF yields multiple wastes with different chemical, physical, and radionuclide characteristics. The different characteristics of each waste imply that there are potential cost and performance benefits to developing different disposal sites that match the disposal requirements of different waste. Disposal sites as defined herein may be located in different geologies or in a single repository containing multiple sections, each with different characteristics. The paper describes disposal options for specific wastes and the potential for a waste management system that better couples various reprocessing plant wastes with disposal facilities. (authors)

Forsberg, Charles W. [Nuclear Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831 (United States); Driscoll, Michael J. [Department of Nuclear Science and Technology, Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, MA, 02139 (United States)

2007-07-01

23

Pyramiding tumuli waste disposal site and method of construction thereof  

Microsoft Academic Search

This patent describes an improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a

Golden

1989-01-01

24

Pyramiding tumuli waste disposal site and method of construction thereof  

Microsoft Academic Search

An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus

Golden; Martin P

1989-01-01

25

METHODOLOGY TO INVENTORY, CLASSIFY, AND PRIORITIZE UNCONTROLLED WASTE DISPOSAL SITES  

EPA Science Inventory

A comprehensive method to inventory uncontrolled waste disposal sites integrates all available historic, engineering, geologic, land use, water supply, and public agency or private company records in order to develop a complete and accurate site profile. Detailed information on s...

26

WASTE DISPOSAL SITES: A NECESSARY EVIL?  

Microsoft Academic Search

Hazardous waste disposal ranges from discarding a burning cigarette butt from the car window to getting rid of highly toxic waste products. Managing waste disposal in all its various forms to mitigate the impact on the environment remains the ultimate challenge. However, the environment is very forgiving up to a certain point and one needs to understand exactly where this

Gideon Tredoux

27

Uranium waste disposal at the Savannah River Site  

SciTech Connect

The Savannah River Site generates waste containing depleted, natural, and enriched uranium residue. The past and current practice for disposal of this waste at the Savannah River Site have been assessed using radionuclide pathway analysis to estimate environmental impact of closure alternatives for existing disposal sites, and to assist in the development of improved disposal facilities in the near future. This paper outlines the status of uranium waste management technology as currently practiced to maintain the environmental impact within an acceptable limit at the Savannah River Site, and indicates those steps being taken to improve future operations.

Cook, J.R.; McDonell, W.R.; Wilhite, E.L.

1990-01-01

28

Uranium waste disposal at the Savannah River Site  

SciTech Connect

The Savannah River Site generates waste containing depleted, natural, and enriched uranium residue. The past and current practice for disposal of this waste at the Savannah River Site have been assessed using radionuclide pathway analysis to estimate environmental impact of closure alternatives for existing disposal sites, and to assist in the development of improved disposal facilities in the near future. This paper outlines the status of uranium waste management technology as currently practiced to maintain the environmental impact within an acceptable limit at the Savannah River Site, and indicates those steps being taken to improve future operations.

Cook, J.R.; McDonell, W.R.; Wilhite, E.L.

1990-12-31

29

Site Selection for the Disposal of LLW in Taiwan  

SciTech Connect

This paper presents the implementation status of the low-level radioactive waste (LLW) disposal program in Taiwan, including the disposal facility regulations, status of waste management, final disposal program, licensing procedures, waste acceptance criteria, site selection criteria and processes and preliminary disposal concepts. The first phase of site selection for low-level radioactive waste final disposal in Taiwan was implemented between 1992 and 2002. The site selection process adopted a Geographic Information System (GIS), Hierarchical Analysis System, Expert Evaluation System, and site reconnaissance. An incentive program for voluntary sites was also initiated. After a series of evaluations and discussion of 30 potential candidate sites, including 8 recommended sites, 5 qualified voluntary townships, and several remote uninhabited small islets, Hsiao-chiou islet was selected as the first priority candidate site in February 1998. The geological investigation work in Hsiao-chiou was conducted from March 1999 through October 2000. An Environmental Impact Statement Report (EIS) and the Investment Feasibility Study Report (IFS) were submitted to the Environmental Protection Agency (EPA) in November 2000 and to the Ministry of Economic Affairs (MOEA) in June 2001, respectively. Unfortunately, the site investigation was discontinued in 2002 due to political and public acceptance consideration. After years of planning, the second phase of the site selection process was launched in August 2004 and will be conducted through 2008. It is planned that a repository will be constructed in early 2009 and start to operate in 2014. The site selection process for the second phase is based on the earlier work and four potential candidate sites were selected for evaluation until 2005. A near surface disposal concept is proposed for a site located in the Taiwan strait, and cavern disposal concepts are proposed for three other sites located on the main island. This paper presents the implementation status of the LLW disposal program in Taiwan, including the disposal facility regulations, status of waste management, final disposal program, licensing procedures, waste acceptance criteria, site selection criteria and processes, and preliminary disposal concepts 'NIMBY' (Not in my backyard) is a critical problem for implementation of the final disposal project. Resistance from local communities has been continuously received during site characterization. To overcome this, an incentive program to encourage community acceptance has been approved by the Government. Programs for community promotion are being proposed and negotiations are also underway. (authors)

Chuang, W.S.; Chi, L.M.; Tien, N.C.; Chang, F.L. [Institute of Nuclear Energy Research, P.O. Box 3-7, Lung-Tan 32500, Taiwan (China)

2006-07-01

30

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site  

SciTech Connect

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE`s Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS.

Price, L. [Science Applications International Corp., Albuquerque, NM (United States)

1994-09-01

31

CONVECTIVE-DISPERSIVE TRANSPORT MODEL FOR WASTES DISPOSED AT THE 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

A two-dimensional, convective-dispersive transport model was used to predict bounds on the expected long-term time-averaged dilutions for wastes disposed of at the 106-Mile Ocean Disposal Site (between 38 degrees 40' and 39 degrees 00'N, and 72 degrees 00' and 72 degrees 30'W). o...

32

STOCHASTIC CONVECTIVE-DISPERSIVE TRANSPORT MODEL FOR WASTES DISPOSED AT THE 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

A two-dimensional, stochastic, convective-dispersive transport model was developed to predict expected dilutions for wastes disposed at the 106-Mile Ocean Disposal Site. The major model assumptions were: (1) wastes were completely mixed vertically and remained in the upper mixed ...

33

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2010 CFR

...The primary emphasis in disposal site suitability is given to isolation of wastes, a matter having long-term impacts, and to...avoided where tectonic processes such as faulting, folding, seismic activity, or vulcanism may occur with such frequency...

2010-01-01

34

Physical factors at the Rame Head disposal site anthropogenic aspects  

E-print Network

for some. At the disposal site, the main issue regarding litter is an aesthetic one. On the Whitsand Bay beaches, litter is likely to derive from regional tourism and fishing activity as well as from

35

EVALUATION OF ON-SITE WASTEWATER TREATMENT AND DISPOSAL OPTIONS  

EPA Science Inventory

A literature review of published and unpublished data was conducted to identify all conceivable alternative on-site systems, including wastewater manipulation, treatment and disposal options. Wastewater manipulation options included flow reduction, wasteload reduction and waste s...

36

10 CFR 61.62 - Funding for disposal site closure and stabilization.  

Code of Federal Regulations, 2010 CFR

...2010-01-01 false Funding for disposal site closure and stabilization... LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Financial Assurances 61.62 Funding for disposal site closure and...

2010-01-01

37

10 CFR 61.44 - Stability of the disposal site after closure.  

Code of Federal Regulations, 2010 CFR

...2010-01-01 false Stability of the disposal site after closure. 61.44... LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Performance Objectives 61.44 Stability of the disposal site after closure. The...

2010-01-01

38

Preparations for Mixed Waste Disposal at the Nevada Test Site  

SciTech Connect

The Radioactive Waste Management Complex (RWMC) at the Nevada Test Site (NTS) is preparing for the receipt and disposal of low-level mixed waste (MV) generated within the U.S. Department of Energy (DOE) complex. The NTS maintains and develops disposal locations to accommodate various waste forms, and is engaged in developing verification and handling processes to ensure proper acceptance and disposal. Operations at the RWMC are focused on ensuring future disposal needs can be accommodated with a maximum benefit to risk ratio. This paper addresses the programmatic developments implemented at the NTS to accommodate the receipt, verification, and disposal of MW. The Radioactive Waste Acceptance Program (RWAP) has incorporated aspects of the Waste Analysis Plan (WAP) into the Nevada Test Site Waste Acceptance Criteria (NTSWAC). The verification program includes statistical sampling components that take into account waste form, program reliability, and other factors. The WAP allows for a conglomerate of verification techniques including visual examination, non-destructive examination, and chemical screening ensuring compliance with the NTSWAC. The WAP also provides for the acceptance of MW with most U.S. Environmental Protection Agency waste codes. The MW sent to the NTS for disposal must meet Land-Disposal Restriction standards. To support the verification processes outlined in the WAP, a Real-Time-Radiography (RTR) facility was constructed. Using a 450 keV, 5-mA tube-head system with a bridge and manipulator assembly, MW packages can undergo non-destructive examination (x-ray) at the RWMC. Prior to the NTS accepting the waste shipment, standard waste boxes, drums, and nominally sized bulk items can be manipulated on a cart and examined directly or skewed in real-time to ensure compliance with NTSWAC requirement s An existing MW disposal cell at the RWMC has been tailored to meet the requirements of a Category 2 non-reactor Nuclear Facility. In retrofitting an existing facility to meet new requirements, several considerations were analyzed and incorporated into the final design. For Example, seismic loading considerations for disposal location performance during a postulated event resulted in several calculations and physical modifications to the existing facility. In addition to instituting changes required for MW disposal, the NTS continues to overcome unique challenges associated with handling and disposing low-level radioactive waste (LLW). As a Nuclear Facility, the RWMC has the capabilities required to manage all types of LLW/MW, meeting the disposal needs integral to clean up the DOE complex. With the advent of the accelerated cleanup schedule, the increase in waste generation has required a facility that can handle unique disposal requirements in a safe manner for the public, the workers, and the environment. (authors)

Clark, D.K.; Perez, P.A.; Doyle, G. [Bechtel Nevada, P. O. Box 98521, Las Vegas, Nevada 89193-8521 (United States)

2006-07-01

39

SITE MANAGEMENT AND MONITORING PLAN IMPLEMENTATION MANUAL - SAN FRANCISCO DEEP OCEAN DISPOSAL SITE (SF-DODS)  

EPA Science Inventory

EPA published in 1994 a Final Rule formally designating the San Francisco Deep Ocean Disposal Site (SF-DODS) for the disposal of suitable dredged material removed from the San Francisco Bay region and other nearby harbors or dredging sites. This Final Rule contained an extensive ...

40

Disposal of Hanford site tank wastes  

Microsoft Academic Search

Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West

Kupfer

1993-01-01

41

The Monitoring of UK Sewage Sludge Disposal Sites  

Microsoft Academic Search

In recent years there has been an increase in the intensity and frequency of environmental monitoring surveys at UK sewage sludge disposal sites. These have been carried out by the regulatory authorities and by the licensees. in order to ensure maximum efficiency, a coordinated and harmonised programme of monitoring has been developed. the programme concentrates on sediment chemical and biological

S. M. Rowlatt; H. L. Rees; C. M. G. Vivian; M. M. Parker

1991-01-01

42

TRACE METALS MONITORING AT TWO OCEAN DISPOSAL SITES  

EPA Science Inventory

The areal distributions of the concentration of cadmium, copper, nickel, and vanadium in sea scallop and ocean quahog tissue were examined in the vicinity of two ocean disposal sites located off the U.S. mid-Atlantic coast on four cruises conducted in 1974 and 1975. Incidental co...

43

Chemical pretreatment of Savannah River Site nuclear waste for disposal  

SciTech Connect

This work describes two processes, Extended Sludge Processing and In-Tank Precipitation, which have been developed and demonstrated at full-scale to pretreat the Savannah River Site High-Level Waste for permanent disposal. These processes will be carried out in waste storage tanks which have been modified for chemical processing. These processes will concentrate the radioactivity into a small volume for vitrification. The bulk of the waste will be sufficiently decontaminated such that it can be disposed of as a low-level waste. The decontaminated waste will be incorporated into a cement wasteform in the Saltstone Facility.

Hobbs, D.T.; Walker, D.D.

1992-12-31

44

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

SciTech Connect

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

NSTec Environmental Restoration

2009-07-31

45

Voluntary cleanup of the Ames chemical disposal site.  

SciTech Connect

The U.S. Department of Energy completed a voluntary removal action at the Ames chemical disposal site, a site associated with the early days of the Manhattan Project. It contained chemical and low-level radioactive wastes from development of the technology to extract uranium from uranium oxide. The process included the preparation of a Remedial Investigation, Feasibility Study, Baseline Risk Assessment, and, ultimately, issuance of a Record of Decision. Various stakeholder groups were involved, including members of the regulatory community, the general public, and the landowner, Iowa State University. The site was restored and returned to the landowner for unrestricted use.

Taboas, A. L.; Freeman, R.; Peterson, J.; Environmental Assessment; USDOE

2003-01-01

46

Health effects of a thorium waste disposal site.  

PubMed Central

A case-control study of 112 households residing in the vicinity of a thorium waste disposal site found a higher prevalence of birth defects (RR 2.1) and liver diseases (RR 2.3) among exposed than the unexposed group. The numbers were quite small and the confidence intervals wide, however, so that no definite conclusions can be drawn from these data. PMID:2316775

Najem, G R; Voyce, L K

1990-01-01

47

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs  

SciTech Connect

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS Waste Acceptance Criteria. The disposal operations previously mentioned take place at the NTS in two disposal facilities. The isolation protection and overall performance of the two LLW disposal facilities at the NTS transcend those of any federal radioactive waste disposal site in the United States. The first of the two disposal sites is the Area 5 Radioactive Waste Management Site (RWMS) which is situated on alluvial fan deposits in the Frenchman Flat basin, approximately 770 feet (235 meters) above the water table. The Area 5 RWMS utilizes a combination of engineered shallow land disposal cells and deep augured shafts for the disposal of a variety of waste streams. Fifteen miles (24 kilometers) north of the Area 5 RWMS is the Area 3 RWMS located approximately 1,600 feet (488 meters) above the water table in Yucca Flat. Disposal activities at the Area 3 RWMS center around the placement of bulk LLW in subsidence craters formed from underground testing of nuclear weapons. Native alluvium soil is used to cover waste placed in the disposal cells at both facilities. In addition, information on the technical attributes, facility performance, updates on waste disposal volumes and capabilities, and current and future disposal site requirements will also be described. (authors)

Di Sanza, E.F.; Carilli, J.T. [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)

2006-07-01

48

Pyramiding tumuli waste disposal site and method of construction thereof  

DOEpatents

An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

Golden, Martin P. (Hamburg, NY)

1989-01-01

49

Application of studies on the overboard placement of dredged sediments to the management of disposal sites  

USGS Publications Warehouse

From the mid 1960's until 1991, dredging and disposal occurred in the northern Chesapeake Bay without guidelines to maximize the capacity and to minimize the spread of the deposits beyond the disposal sites, particularly toward the navigation channel. Planning for future dredging projects is dependant upon the remaining site capacity and the behavior of the disposed sediment. Recent studies have shown that the fate of the deposited sediments is determined primarily by the water depth and bathymetry in the vicinity of the disposal site, and the method of dredging and disposal utilized. Currently used open-water disposal sites in the northern Chesapeake Bay are reaching their maximum capacity. This makes the application of the information from these studies critical, both for the optimal use of current sites and for the evaluation of new sites. Management scenarios utilizing these studies are applied to a disposal site in the northern Chesapeake Bay.

Panageotou, William; Halka, Jeffrey

1994-01-01

50

36 CFR 6.5 - Solid waste disposal sites in operation on September 1, 1984.  

Code of Federal Regulations, 2012 CFR

...continued use of a solid waste disposal site only if the operator has...for the storage, handling or disposal of a solid waste containing...septic system waste or domestic sewage; (vii) Petroleum, including...operator of the solid waste disposal site must cease...

2012-07-01

51

36 CFR 6.5 - Solid waste disposal sites in operation on September 1, 1984.  

Code of Federal Regulations, 2014 CFR

...continued use of a solid waste disposal site only if the operator has...for the storage, handling or disposal of a solid waste containing...septic system waste or domestic sewage; (vii) Petroleum, including...operator of the solid waste disposal site must cease...

2014-07-01

52

36 CFR 6.5 - Solid waste disposal sites in operation on September 1, 1984.  

Code of Federal Regulations, 2011 CFR

...continued use of a solid waste disposal site only if the operator has...for the storage, handling or disposal of a solid waste containing...septic system waste or domestic sewage; (vii) Petroleum, including...operator of the solid waste disposal site must cease...

2011-07-01

53

36 CFR 6.5 - Solid waste disposal sites in operation on September 1, 1984.  

Code of Federal Regulations, 2013 CFR

...continued use of a solid waste disposal site only if the operator has...for the storage, handling or disposal of a solid waste containing...septic system waste or domestic sewage; (vii) Petroleum, including...operator of the solid waste disposal site must cease...

2013-07-01

54

Modeling Groundwater Flow and Infiltration at Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

Microsoft Academic Search

Taiwan is evaluating representative sites for the potential disposal of low-level radioactive waste (LLW), including consideration of shallow land burial and cavern disposal concepts. A representative site for shallow land burial is on a small island in the Taiwan Strait with basalt bedrock. The shallow land burial concept includes an engineered cover to limit infiltration into the waste disposal cell.

B. W. Arnold; C. Lee; C. Ma; R. G. Knowlton

2006-01-01

55

Sorption of strontium and fractal scaling of the heterogeneous media in a candidate VLLW disposal site  

E-print Network

for a candidate very low level waste (VLLW) disposal site, with the grain size ranging from tens of microns to 75 in the modeling of radionuclide migration in the heterogeneous disposal site. A total of three deep pits and five between Kd and D was approximately linear. Keywords Heterogeneous media Á Waste disposal Á Fractal

Hu, Qinhong "Max"

56

Overview of Low-Level Waste Disposal Operations at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future.

DOE /Navarro

2007-02-01

57

Studies of Current Circulation at Ocean Waste Disposal Sites  

NASA Technical Reports Server (NTRS)

The author has identified the following significant results. Acid waste plume was observed in LANDSAT imagery fourteen times ranging from during dump up to 54 hours after dump. Circulation processes at the waste disposal site are highly storm-dominated, with the majority of the water transport occurring during strong northeasterlies. There is a mean flow to the south along shore. This appears to be due to the fact that northeasterly winds produce stronger currents than those driven by southeasterly winds and by the thermohaline circulation. During the warm months (May through October), the ocean at the dump site stratifies with a distinct thermocline observed during all summer cruising at depths ranging from 10 to 21 m. During stratified conditions, the near-bottom currents were small. Surface currents responded to wind conditions resulting in rapid movement of surface drogues on windy days. Mid-depth drogues showed an intermediate behavior, moving more rapidly as wind velocities increased.

Klemas, V. (principal investigator); Davis, G.; Henry, R.

1976-01-01

58

Selection of low-level radioactive waste disposal sites using screening models versus more complex methodologies  

Microsoft Academic Search

The task of choosing a waste-disposal site from a set of candidate sites requires an approach capable of objectively handling many environmental variables for each site. Several computer methodologies have been developed to assist in the process of choosing a site for the disposal of low-level radioactive waste; however, most of these models are costly to apply, in terms of

I. Uslu; D. E. Fields

1993-01-01

59

75 FR 22524 - Ocean Dumping; Designation of Ocean Dredged Material Disposal Sites Offshore of the Siuslaw River...  

Federal Register 2010, 2011, 2012, 2013, 2014

...Disposal Sites Offshore of the Siuslaw River, Oregon AGENCY: Environmental Protection...finalizes the designation of the Siuslaw River ocean dredged material disposal sites pursuant...dispose of material dredged from the Siuslaw River navigation channel, and to provide a...

2010-04-29

60

Source term development for tritium at the Sheffield disposal site  

SciTech Connect

The Sheffield low-level radioactive waste disposal site, which ceased operation in 1978, has been the focus of modeling efforts by the NRC for the purpose of predicting long-term site behavior. To provide the NRC with the information required for its modeling effort, a study to define the source term for tritium in eight trenches at the Sheffield site has been undertaken. Tritium is of special interest since significant concentrations of the isotope have been found in groundwater samples taken at the site and at locations outside the site boundary. Previous estimates of tritium site inventory at Sheffield are in wide disagreement. In this study, the tritium inventory in the eight trenches was estimated by reviewing the radioactive shipping records (RSRs) for waste buried in these trenches. It has been found that the tritium shipped for burial at the site was probably higher than previously estimated. In the eight trenches surveyed, which amount to roughly one half the total volume and activity buried at Sheffield, approximately 2350 Ci of tritium from non-fuel cycle sources were identified. The review of RSRs also formed the basis for obtaining waste package descriptions and for contacting large waste generators to obtain more detailed information regarding these waste packages. As a result of this review and the selected generator contacts, the non-fuel cycle tritium waste was categorized. The tritium releases from each of these waste categories were modeled. The results of this modeling effort are presented for each of the eight trenches selected. 3 references, 2 figures.

MacKenzie, D.R.; Barletta, R.E.; Smalley, J.F.; Kempf, C.R.; Davis, R.E.

1984-01-01

61

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

SciTech Connect

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325

NSTec Environmental Programs

2010-09-14

62

10 CFR 61.52 - Land disposal facility operation and disposal site closure.  

Code of Federal Regulations, 2013 CFR

...REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements...covered. (10) Active waste disposal operations must...measures. (11) Only wastes containing or contaminated with radioactive materials shall be...

2013-01-01

63

10 CFR 61.52 - Land disposal facility operation and disposal site closure.  

Code of Federal Regulations, 2014 CFR

...REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements...covered. (10) Active waste disposal operations must...measures. (11) Only wastes containing or contaminated with radioactive materials shall be...

2014-01-01

64

10 CFR 61.52 - Land disposal facility operation and disposal site closure.  

Code of Federal Regulations, 2012 CFR

...REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements...covered. (10) Active waste disposal operations must...measures. (11) Only wastes containing or contaminated with radioactive materials shall be...

2012-01-01

65

10 CFR 61.52 - Land disposal facility operation and disposal site closure.  

Code of Federal Regulations, 2010 CFR

...REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements...covered. (10) Active waste disposal operations must...measures. (11) Only wastes containing or contaminated with radioactive materials shall be...

2010-01-01

66

10 CFR 61.52 - Land disposal facility operation and disposal site closure.  

Code of Federal Regulations, 2011 CFR

...REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements...covered. (10) Active waste disposal operations must...measures. (11) Only wastes containing or contaminated with radioactive materials shall be...

2011-01-01

67

10 CFR 61.51 - Disposal site design for land disposal.  

Code of Federal Regulations, 2011 CFR

10 Energy 2 2011-01-01 2011-01-01...61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...water away from the disposed waste, and to resist...

2011-01-01

68

10 CFR 61.51 - Disposal site design for land disposal.  

Code of Federal Regulations, 2014 CFR

10 Energy 2 2014-01-01 2014-01-01...61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...water away from the disposed waste, and to resist...

2014-01-01

69

10 CFR 61.51 - Disposal site design for land disposal.  

Code of Federal Regulations, 2012 CFR

10 Energy 2 2012-01-01 2012-01-01...61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...water away from the disposed waste, and to resist...

2012-01-01

70

10 CFR 61.51 - Disposal site design for land disposal.  

Code of Federal Regulations, 2013 CFR

10 Energy 2 2013-01-01 2013-01-01...61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...water away from the disposed waste, and to resist...

2013-01-01

71

10 CFR 61.51 - Disposal site design for land disposal.  

Code of Federal Regulations, 2010 CFR

10 Energy 2 2010-01-01 2010-01-01...61.51 Section 61.51 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...water away from the disposed waste, and to resist...

2010-01-01

72

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

SciTech Connect

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

NSTec Environmental Restoration

2007-07-01

73

Neptunium Disposal to the Savannah River Site Tank Farm  

SciTech Connect

Researchers investigated the neutralization of an acidic neptunium solution from a Savannah River Site (SRS) processing canyon and the properties of the resulting slurry to determine the feasibility of disposal in the SRS tank farm. The acidic solution displayed no properties that precluded the proposed disposal route. Neutralization of the acidic neptunium forms a 4 wt per cent slurry of precipitated metal hydroxides. The insoluble solids consist largely of iron (92 per cent) and neptunium hydroxides (2 per cent). The concentration of soluble neptunium remaining after neutralization equaled much less than previous solubility measurements predicted. Researchers used an apparatus similar to an Ostwald-type viscometer to estimate the consistency of the neptunium slurry with the solids present. The yield stress and consistency of the 4 wt per cent slurry will allow transfer through the tank farm, although concentration of the insoluble solids above 4 wt per cent may cause significant problems due to increased consistency and yield stress. The consistency of the 4 wt per cent slurry is 7.6 centipoise (cP) with a yield stress less than 1 Pascal (Pa). The neptunium slurry, when combined with actual washed radioactive sludge, slightly reduces the yield stress and consistency of the sludge and produces a combined slurry with acceptable rheological properties for vitrification.

Walker, D.D.

2004-02-26

74

Studies of Current Circulation at Ocean Waste Disposal Sites. [Delaware  

NASA Technical Reports Server (NTRS)

The author has identified the following significant results. Circulation processes at the acid waste disposal site are highly event-dominated, with the majority of the water transport occurring during strong northeasters. There is a mean flow to the south alongshore. This appears to be due to the fact that northeasterly winds produce stronger currents than those driven by southeasterly winds and by the thermohaline circulation. During the warm months, the ocean stratifies with warm water over cold water. A distinct thermocline was observed with expendable bathythermographs during all summer cruises at depths ranging from 10 to 21 meters. During stratified conditions, the near-bottom drogues showed very little movements. The duPont waste plume was observed in LANDSAT satellite imagery during dump up to 54 hours after dump.

Klemas, V. (principal investigator); Davis, G.; Henry, R.

1975-01-01

75

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

Arnold, P.

2012-10-31

76

Waste inventory and preliminary source term model for the Greater Confinement Disposal site at the Nevada Test Site  

SciTech Connect

Currently, there are several Greater Confinement Disposal (GCD) boreholes at the Radioactive Waste Management Site (RWMS) for the Nevada Test Site. These are intermediate-depth boreholes used for the disposal of special case wastes, that is, radioactive waste within the Department of Energy complex that do not meet the criteria established for disposal of high-level waste, transuranic waste, or low-level waste. A performance assessment is needed to evaluate the safety of the GCD site, and to examine the feasibility of the GCD disposal concept as a disposal solution for special case wastes in general. This report documents the effort in defining all the waste inventory presently disposed of at the GCD site, and the inventory and release model to be used in a performance assessment for compliance with the Environmental Protection Agency`s 40 CFR 191.

Chu, M.S.Y.; Bernard, E.A.

1991-12-01

77

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.  

Code of Federal Regulations, 2011 CFR

...for waste shipment from waste generator sites for disposal at the...waste shipment from waste generator sites for disposal at the...Assurance Programs at Waste Generator Sites. The Agency will...establishes the applicable Nuclear Quality Assurance...

2011-07-01

78

40 CFR 194.8 - Approval process for waste shipment from waste generator sites for disposal at the WIPP.  

Code of Federal Regulations, 2010 CFR

...for waste shipment from waste generator sites for disposal at the...waste shipment from waste generator sites for disposal at the...Assurance Programs at Waste Generator Sites. The Agency will...establishes the applicable Nuclear Quality Assurance...

2010-07-01

79

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect

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.

NONE

1997-04-01

80

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect

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.

NONE

1996-02-01

81

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect

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.

NONE

1996-05-01

82

Probabilistic Performance Assessment of a Low-Level Radioactive Waste Disposal Site on the Nevada Test Site  

Microsoft Academic Search

The Area 5 Radioactive Waste Management Site on the Nevada Test Site has been disposing of low-level, mixed low-level, and transuranic radioactive waste since 1961. In 1988, the U.S. Department of Energy implemented performance objectives for low-level radioactive waste disposal site performance and required all site operators to prepare a performance assessment. Since then, an iterative performance assessment process has

G. J. Shott; V. Yucel; L. T. Desotell

2008-01-01

83

Groundwater hydrology study of the Ames Chemical Disposal Site  

SciTech Connect

The Ames Laboratory Chemical Disposal Site is located in northwestern Ames, Iowa west of Squaw Creek. From 1957 to 1966, Ames Laboratory conducted research to develop processes to separate uranium and thorium from nuclear power fuel and to separate yttrium from neutron shielding sources. The wastes from these processes, which contained both hazardous and radiological components, were placed into nine burial pits. Metal drums, plywood boxes, and steel pails were used to store the wastes. Uranium was also burned on the ground surface of the site. Monitoring wells were placed around the waste burial pits. Groundwater testing in 1993 revealed elevated levels of Uranium 234, Uranium 238, beta and alpha radiation. The north side of the burial pit had elevated levels of volatile organic compounds. Samples in the East Ravine showed no volatile organics; however, they did contain elevated levels of radionuclides. These analytical results seem to indicate that the groundwater from the burial pit is flowing down hill and causing contamination in the East Ravine. Although there are many avenues for the contamination to spread, the focus of this project is to understand the hydrogeology of the East Ravine and to determine the path of groundwater flow down the East Ravine. The groundwater flow data along with other existing information will be used to assess the threat of chemical migration down the East Ravine and eventually off-site. The primary objectives of the project were as follows: define the geology of the East Ravine; conduct slug tests to determine the hydraulic conductivity of both oxidized and unoxidized till; develop a three-dimensional mathematical model using ModIME and MODFLOW to simulate groundwater flow in the East Ravine.

Stickel, T.

1996-05-09

84

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

SciTech Connect

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

Wickline, Alfred

2005-12-01

85

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

SciTech Connect

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

Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01

86

LOCAL ARRANGEMENTS FOR WASTE DISPOSAL (BEGBROKE SITE) Landfill (England & Wales) Regulations 2002  

E-print Network

1 LOCAL ARRANGEMENTS FOR WASTE DISPOSAL (BEGBROKE SITE) Landfill (England & Wales) Regulations 2002 Under the Landfill (England & Wales) Regulations 2002, the University is no longer permitted to dispose of its hazardous waste other than at a registered hazardous waste site. New, amended, regulations came

Paxton, Anthony T.

87

LOCAL ARRANGEMENTS FOR WASTE DISPOSAL (MAIN SITE) Landfill (England & Wales) Regulations 2002  

E-print Network

1 LOCAL ARRANGEMENTS FOR WASTE DISPOSAL (MAIN SITE) Landfill (England & Wales) Regulations 2002 Under the Landfill (England & Wales) Regulations 2002, the University is no longer permitted to dispose of its hazardous waste other than at a registered hazardous waste site. Amended, regulations came

Paxton, Anthony T.

88

Dungeness crab survey for the Southwest Ocean Disposal Site and addtiional sites off Grays Harbor, Washington, June 1991  

SciTech Connect

As part of the Grays Harbor Navigation Improvement Project, the US Army Corps of Engineers, Seattle District (USACE), has made active use of the Southwest Ocean Disposal Site off Grays Harbor, Washington. Disposal site boundaries were established to avoid an area where high densities of Young-of-the-Year (YOY) Dungeness crab, Cancer magister, were observed during the site selection surveys. To monitor possible impacts of disposal operations on Dungeness crab at the site, USACE recommended a crab distribution survey prior to disposal operations in the February 1989 environmental impact statement supplement (EISS) as part of a tiered monitoring strategy for the site. According to the tiered monitoring strategy, a preliminary survey is conducted to determine if the disposal site contains an exceptionally high density of YOY Dungeness crab. The trigger for moving to a more intensive sampling effort is a YOY crab density within the disposal site that is 100 times higher than the density in the reference area to the north. This report concerns a 1991 survey that was designed to verify that the density of YOY Dungeness crab present at the disposal site was not exceptionally high. Another objective of the survey was to estimate Dungeness crab densities at nearshore areas that are being considered as sediment berm sites by USACE.

Antrim, L.D.; Cullinan, V.I.; Pearson, W.H. [Battelle Marine Research Lab., Sequim, WA (United States)

1992-01-01

89

Greater Confinement Disposal Test at the Nevada Test Site. [At 30 meters  

SciTech Connect

The Greater Confinement disposal Test (GCDT) at the Nevada Test Site will be a full scale demonstration of intermediate depth burial for disposal of defense low-level radioactive wastes considered unsuitable for shallow land burial. The GCDT project will demonstrate that these wastes can be efficaciously disposed at a depth of approximately 30 meters where the probability of future inadvertent human intrusion and of potential waste migration are negligible. The GCDT will be instrumented to collect data on properties of the disposal madium (alluvial sediments). Tracers will be injected to assess the transport potential of wastes through the medium. Tracer data will be analyzed to determine the effectiveness of the disposal method.

Dickman, P.T.; Boland, J.R.

1983-02-01

90

Selection of a ground disposal site by sensitivity analysis  

Microsoft Academic Search

Disposal of radioactive wastes in the ground is not allowed in Japan at ; present mainly because of the difficulties in estimating the ground migration of ; radionuclides and in evaluating the internal dose caused by these wastes. The ; desirable conditions for the ground disposal of radioactive wastes and the ; approximate method for estimating the internal dose are

S. Morisawa; Y. Inoue

1974-01-01

91

Long-term surveillance plan for the Cheney disposal site near Grand Junction, Colorado  

SciTech Connect

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.

NONE

1997-04-01

92

STRATEGY FOR MONITORING OF CONTAMINANT DISTRIBUTIONS RESULTING FROM PROPOSED SEWAGE SLUDGE DISPOSAL AT THE 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

It has been proposed that future ocean disposal of sewage sludge from the US east coast be done at a site beyond the edge of the continental shelf. In anticipation of that, a monitoring strategy has been developed to determine the average spatial distribution of contamination. Th...

93

Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods  

SciTech Connect

According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

Veil, J.A.

1997-09-01

94

Long-term surveillance plan for the Estes Gulch disposal site near Rifle, Colorado  

SciTech Connect

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.

NONE

1997-07-01

95

Interim long-term surveillance plan for the Cheney disposal site near, Grand Junction, Colorado  

SciTech Connect

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.

NONE

1997-08-01

96

Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah  

SciTech Connect

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.

NONE

1997-06-01

97

Dungeness crab survey for the Southwest Ocean Disposal Site off Grays Harbor, Washington, June 1990  

SciTech Connect

As part of the Grays Harbor Navigation Improvement Project, the Seattle District of the US Army Corps of Engineers has begun active use of the Southwest Ocean Disposal Site off Grays Harbor, Washington. This survey was to verify that the location of the area of high crab density observed during site selection surveys has not shifted into the Southeast Ocean Disposal Site. In June 1990, mean densities of juvenile Dungeness crab were 146 crab/ha within the disposal site and 609 crab/ha outside ad north of the disposal site. At nearshore locations outside the disposal site, juvenile crab density was 3275 crab/ha. Despite the low overall abundance, the spatial distribution of crab was such that the high crab densities in 1990 have remained outside the Southwest Ocean Disposal Site. The survey data have confirmed the appropriateness of the initial selection of the disposal site boundaries and indicated no need to move to the second monitoring tier. 8 refs., 9 figs., 2 tabs.

Higgins, B.J.; Pearson, W.H. (Battelle/Marine Sciences Lab., Sequim, WA (United States))

1991-09-01

98

Long-term surveillance plan for the Gunnison, Colorado disposal site. Revision 2  

SciTech Connect

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.

NONE

1997-02-01

99

Framework for DOE mixed low-level waste disposal: Site fact sheets  

SciTech Connect

The Department of Energy (DOE) is required to prepare and submit Site Treatment Plans (STPS) pursuant to the Federal Facility Compliance Act (FFCAct). Although the FFCAct does not require that disposal be addressed in the STPS, the DOE and the States recognize that treatment of mixed low-level waste will result in residues that will require disposal in either low-level waste or mixed low-level waste disposal facilities. As a result, the DOE is working with the States to define and develop a process for evaluating disposal-site suitability in concert with the FFCAct and development of the STPS. Forty-nine potential disposal sites were screened; preliminary screening criteria reduced the number of sites for consideration to twenty-six. The DOE then prepared fact sheets for the remaining sites. These fact sheets provided additional site-specific information for understanding the strengths and weaknesses of the twenty-six sites as potential disposal sites. The information also provided the basis for discussion among affected States and the DOE in recommending sites for more detailed evaluation.

Gruebel, M.M.; Waters, R.D.; Hospelhorn, M.B.; Chu, M.S.Y. [eds.

1994-11-01

100

Geoenvironmental site investigation using different techniques in a municipal solid waste disposal site in Brazil  

NASA Astrophysics Data System (ADS)

Different geoenvironmental site investigation techniques to assess contamination from a municipal solid waste disposal site in Brazil are presented here. Superficial geophysical investigation (geoelectrical survey), resistivity piezocone penetration tests (RCPTU), soil samples collected with direct-push samplers and water samples collected from monitoring wells were applied in this study. The application of the geoelectrical method was indispensable to identify the presence and flow direction of contamination plumes (leachate) as well as to indicate the most suitable locations for RCPTU tests and soil and water sampling. Chemical analyses of groundwater samples contributed to a better understanding of the flow of the contaminated plume. The piezocone presented some limitations for tropical soils, since the groundwater level is sometimes deeper than the layer which is impenetrable to the cone, and the soil genesis and unsaturated conditions affect soil behavior. The combined interpretation of geoelectrical measurements and soil and water samplings underpinned the interpretation of RCPTU tests. The interpretation of all the test results indicates that the contamination plume has already overreached the landfills west-northwest borders. Geoenvironmental laboratory test results suggest that contamination from the solid waste disposal site has been developing gradually, indicating the need for continuous monitoring of the groundwater.

Mondelli, Giulliana; Giacheti, Heraldo Luiz; Boscov, Maria Eugnia Gimenez; Elis, Vagner Roberto; Hamada, Jorge

2007-05-01

101

Long-term surveillance plan for the Mexican Hat disposal site, Mexican Hat, Utah  

SciTech Connect

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.

NONE

1996-01-01

102

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado  

SciTech Connect

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).

Not Available

1994-03-01

103

Geohydrologic descriptions of selected solid waste disposal sites in Puerto Rico  

USGS Publications Warehouse

Fifty solid-waste disposal sites in Puerto Rico were examined in 1977 and ranked according to their potential for degradation of the water resources. Twenty-five of the sites show significant leachate pollution potential. The cover material at 21 sites is relatively permeable and offers insignificant attenuation to leachates. Thirty-six sites are adjacent to streams and nine of these are located in headwater areas. Rainfall is abundant and at 40 of the sites exceeds 1,500 millimeters per years. General descriptions of the 50 disposal sites are given with their geohydrologic setting. Baseline data consisting of specific conductance, pH, temperature, dissolved oxygen, and common ions were obtained at many of the sites. Such information provides a technical basis for assessing future effects of those solid-waste disposal sites on the quality of water resources. (USGS)

Torres-Gonzalez, Arturo; Gmez-Gmez, Fernando

1982-01-01

104

REFERENCE AREA DATABASE FOR THE SAN FRANCISCO DEEP OCEAN DISPOSAL SITE (SF-DODS)  

EPA Science Inventory

In order for a dredging project to be authorized to dispose of dredged material at the San Francisco Deep Ocean Disposal Site (SF-DODS), sediment evaluations (including, as appropriate, physical, chemical, and biological testing) must first be conducted. EPA determines the suita...

105

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2013 CFR

10 Energy 2 2013-01-01 2013-01-01...61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...suitability is given to isolation of wastes, a matter having...

2013-01-01

106

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2012 CFR

10 Energy 2 2012-01-01 2012-01-01...61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...suitability is given to isolation of wastes, a matter having...

2012-01-01

107

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2014 CFR

10 Energy 2 2014-01-01 2014-01-01...61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...suitability is given to isolation of wastes, a matter having...

2014-01-01

108

10 CFR 61.50 - Disposal site suitability requirements for land disposal.  

Code of Federal Regulations, 2011 CFR

10 Energy 2 2011-01-01 2011-01-01...61.50 Section 61.50 Energy NUCLEAR REGULATORY COMMISSION...LAND DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for...suitability is given to isolation of wastes, a matter having...

2011-01-01

109

Mitigation action plan for remedial action at the Uranium Mill Tailing Sites and Disposal Site, Rifle, Colorado  

SciTech Connect

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.

Not Available

1992-07-01

110

Long-term surveillance plan for the Mexican Hat disposal site Mexican Hat, Utah  

SciTech Connect

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.

NONE

1997-05-01

111

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

SciTech Connect

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).

NSTec Environmental Management

2009-01-31

112

Long-term surveillance plan for the Lowman, Idaho, Disposal site. Revision 1  

SciTech Connect

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 site, which will be referred to as the Lowman site 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. The radioactive sands at the Lowman site were stabilized on the site. 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. The LTSP documents whether the land and interests are owned by the United States or a state, 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).

Not Available

1994-04-01

113

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

SciTech Connect

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

Zittel, H.E.

1981-01-01

114

76 FR 32360 - Casmalia Disposal Site; Notice of Proposed CERCLA Administrative De Minimis Settlement  

Federal Register 2010, 2011, 2012, 2013, 2014

...2011, a published notice of a proposed administrative de minimis settlement concerning the Casmalia Disposal Site in Santa Barbara County, California listed the name of one of the parties to the settlement as ``EADS North America'' rather than...

2011-06-06

115

DREDGED MATERIAL RECLAMATION AT THE JONES ISLAND CONFINED DISPOSAL FACILITY SITE CAPSULE  

EPA Science Inventory

In this SITE demonstration, phytoremediation technology was applied to contaminated dredged materials from the Jones Island Confined Disposal Facility (CDF) located in Milwaukee Harbor, Wisconsin. The Jones Island CDF receives dredged materials from normal maintenance of Milwauke...

116

78 FR 37759 - Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation  

Federal Register 2010, 2011, 2012, 2013, 2014

...ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 228 [EPA-R06-OW-2013-0221; FRL-9826-6] Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation AGENCY: Environmental Protection Agency (EPA)....

2013-06-24

117

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations  

SciTech Connect

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

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

2009-03-01

118

LINERS FOR SANITARY LANDFILLS AND CHEMICAL AND HAZARDOUS WASTE DISPOSAL SITES  

EPA Science Inventory

This report lists addresses of sanitary landfills and chemical and hazardous waste disposal sites and holding ponds with some form of impermeable lining. Liners included are polyethylene, polyvinyl chloride, Hypalon R, ethylene propylene diene monomer, butyl rubber, conventional ...

119

Long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon. Revision 2  

SciTech Connect

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).

Not Available

1993-12-01

120

DREDGED MATERIAL TRANSPORT AT DEEP-OCEAN DISPOSAL SITES  

EPA Science Inventory

Assessment of environmental impact of dredged material disposal in deep ocean water calls for predictions of water column concentration, exposure time as well as the impacted area of the bottom (footprint). redictions based on vertical willing and horizontal advection of single p...

121

A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

Microsoft Academic Search

For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to

R. G. Knowlton; B. W. Arnold; P. D. Mattie; M. Kuo; N. Tien

2006-01-01

122

Long-term surveillance plan for the Ambrosia Lake, New Mexico disposal site  

SciTech Connect

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.

NONE

1996-07-01

123

2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites  

SciTech Connect

This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

None

2013-11-01

124

Geographic information system (G.I.S.) research project at Navajo Community College - Shiprock Campus  

SciTech Connect

The Navajo and Hopi GIS Project was established to assess the feasibility and impact of implementing GIS techology at Tribal institutions. Los Alamos and Lawrence Livermore National Laboratories funded the Navajo and Hopi Geographic Information System (G.I.S.) Project and assigned a mentor from LANL to help guide the project for three summer months of 1995. The six organizations involved were: LANL, LLNL, Navajo Community College, Navajo Nation Land Office, Northern Arizona University and San Juan College. The Navajo Land Office provided the system software, hardware and training. Northern Arizona University selected two students to work at Hopi Water Resource Department. Navajo Community College provided two students and two faculty members. San Juan College provided one student to work with the N.C.C. group. This made up two project teams which led to two project sites. The project sites are the Water Resource Department on the Hopi reservation and Navajo Community College in Shiprock, New Mexico.

Yazzie, R.; Peter, C.; Aaspas, B.; Isely, D.; Grey, R.

1995-12-31

125

Addressing epistemic uncertainty in a radioactive waste disposal facility siting: examples of applications  

Microsoft Academic Search

The siting of a radioactive waste disposal facility involves site survey, site selection and site confirmation. Throughout\\u000a the siting process a series of calculations and data analyses are performed with increasing complexity as increasing amounts\\u000a and more detailed data becomes available. Each one of these stages requires a multidisciplinary approach to evaluate the most\\u000a important aspects that affect the performance

Francisco Luiz de LemosTerrence; Terrence M. Sullivan

2011-01-01

126

Long-term Surveillance Plan for the Falls City Disposal Site, Falls City, Texas. Revision 1  

SciTech Connect

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).

NONE

1995-08-01

127

Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas  

SciTech Connect

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).

NONE

1995-06-01

128

75 FR 5708 - Ocean Dumping; Designation of Ocean Dredged Material Disposal Sites Offshore of the Siuslaw River...  

Federal Register 2010, 2011, 2012, 2013, 2014

...Disposal Sites Offshore of the Siuslaw River, OR AGENCY: Environmental Protection...disposal sites near the mouth of the Siuslaw River, Oregon, pursuant to the Marine Protection...dispose of material dredged from the Siuslaw River navigation channel, and to provide a...

2010-02-04

129

Long-term surveillance plan for the Rifle, Colorado, Disposal site  

SciTech Connect

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.

NONE

1996-09-01

130

Long-term surveillance plan for the Gunnison, Colorado, disposal site  

SciTech Connect

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.

NONE

1996-05-01

131

43 CFR 2743.3 - Leased disposal sites.  

Code of Federal Regulations, 2013 CFR

...with the lessee and users of the landfill concerning site management and a review of all...of solid waste deposited at the landfill; (iii) A visual inspection of the leased site; and (iv) An appropriate...

2013-10-01

132

43 CFR 2743.3 - Leased disposal sites.  

Code of Federal Regulations, 2012 CFR

...with the lessee and users of the landfill concerning site management and a review of all...of solid waste deposited at the landfill; (iii) A visual inspection of the leased site; and (iv) An appropriate...

2012-10-01

133

43 CFR 2743.3 - Leased disposal sites.  

Code of Federal Regulations, 2014 CFR

...with the lessee and users of the landfill concerning site management and a review of all...of solid waste deposited at the landfill; (iii) A visual inspection of the leased site; and (iv) An appropriate...

2014-10-01

134

2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites  

SciTech Connect

This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

none,

2014-03-01

135

Hydrogeologic setting east of a low-level radioactive-waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

Core samples from 45 test wells and 4 borings were used to describe the glacial geology of the area east of the low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois. Previous work has shown that shallow ground water beneath the disposal site flows east through a pebbly-sand unit of the Toulon Member of the Glasford Formation. The pebbly sand was found in core samples from wells in an area extending northeast from the waste-disposal site to a strip-mine lake and east along the south side of the lake. Other stratigraphic units identified in the study area are correlated with units found on the disposal site. The pebbly-sand unit of the Toulon Member grades from a pebbly sand on site into a coarse gravel with sand and pebbles towards the lake. The Hulick Till Member, a key bed, underlies the Toulon Member throughout most of the study area. A narrow channel-like depression in the Hulick Till is filled with coarse gravelly sand of the Toulon Member. The filled depression extends eastward from near the northeast corner of the waste-disposal site to the strip-mine lake. (USGS)

Foster, J.B.; Garklavs, George; Mackey, G.W.

1984-01-01

136

Surface-water hydrology at three coal-refuse disposal sites in southern Illinois: Staunton 1, New Kathleen, and Superior  

Microsoft Academic Search

Hydrologic data were collected and analyzed for three coal refuse disposal sites in southern Illinois. The disposal sites were associated with underground mines and consisted of piles of coarse waste (gob) and slurry areas where fine waste rejected from coal washing was deposited. Prereclamation data were available for the Superior washer site in Macoupin County and the New Kathleen site

L. M. Mele; P. F. Prodan

1983-01-01

137

Long-term surveillance plan for the Collins Ranch disposal site, Lakeview, Oregon  

SciTech Connect

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).

Not Available

1994-08-01

138

Long-term surveillance plan for the Green River, Utah disposal site. Revision 1  

SciTech Connect

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).

Not Available

1994-08-01

139

Long-term surveillance plan for the Green River, Utah, disposal site  

SciTech Connect

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).

NONE

1997-06-01

140

Ground-water quality beneath solid-waste disposal sites at anchorage, Alaska  

USGS Publications Warehouse

Studies at three solid-waste disposal sites in the Anchorage area suggest that differences in local geohydrologic conditions influence ground-water quality. A leachate was detected in ground water within and beneath two sites where the water table is very near land surface and refuse is deposited either at or below the water table in some parts of the filled areas. No leachate was detected in ground water beneath a third site where waste disposal is well above the local water table.

Zenone, Chester; Donaldson, D.E.; Grunwaldt, J.J.

1975-01-01

141

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site  

Microsoft Academic Search

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment,

THERESA J. BROWN; SHARON WIRTH

1999-01-01

142

Modeling transport of disposed dredged material from placement sites in Grays Harbor, WA  

E-print Network

Modeling transport of disposed dredged material from placement sites in Grays Harbor, WA E- to mid- term dredge material management strategies for the Federal Navigation Project at Grays Harbor dredging quantities. However, the most heavily used dredged material placement sites lie in proximity

US Army Corps of Engineers

143

FERNANDINA BEACH OCEAN DREDGED MATERIAL DISPOSAL SITE STATUS AND TRENDS, AUGUST 2005.  

EPA Science Inventory

This EPA Region 4 study documents the current status (2005) of the Fernandina Ocean Dredged Material Disposal Site. It includes an assessment of the benthic sediment quality, water quality and benthic bilogical communities. The report is located at the following web site: http...

144

MICROBIAL DEGRADATIVE ACTIVITY IN GROUND WATER AT A CHEMICAL WASTE DISPOSAL SITE  

EPA Science Inventory

The microbial fate and effects of toxic organic chemicals at the ambient concentration in leachates derived from a waste disposal landfill site are examined. roundwater downslope from the burial site contains high levels of dissolved organic chemicals such as toluene, xylene, ben...

145

Multiattribute utility analysis of alternative sites for the disposal of nuclear waste  

Microsoft Academic Search

Five potential sites nominated for the Nation`s first geologic repository for disposing of nuclear waste are evaluated using multiattribute utility analysis. The analysis was designed to aid the Department of Energy in its selection of 3 sites for characterization, a detailed data-gathering process that will involve the construction of exploratory shafts for underground testing and that may cost as much

Miley W. Merkhofer; Ralph L. Keeney

1987-01-01

146

Long-term surveillance plan for the Lowman, Idaho, disposal site  

SciTech Connect

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).

Not Available

1993-09-01

147

A data base for low-level radioactive waste disposal sites  

SciTech Connect

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

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

1989-07-01

148

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado. Revision 1  

SciTech Connect

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.

NONE

1995-11-01

149

NWTS program criteria for mined geologic disposal of nuclear wasite: site performance criteria  

SciTech Connect

This report states ten criteria governing the suitability of sites for mined geologic disposal of high-level radioactive waste. The Department of Energy will use these criteria in its search for sites and will reevaluate their use when the Nuclear Regulatory Commission issues radioactive waste repository rules. These criteria encompass site geometry, geohydrology, geochemistry, geologic characteristics, tectonic environment, human intrusion, surface characteristics, environment, and potential socioeconomic impacts. The contents of this document include background discussion, site performance criteria, and appendices. The background section describes the waste disposal system, the application of the site criteria, and applicable criteria from NWTS-33(1) - Program Objectives, Functional Requirements and System Performance Criteria. Appendix A, entitled Comparison with Other Siting Criteria compares the NWTS criteria with those recommended by other agencies. Appendix B contains DOE responses to public comments received on the January 1980 draft of this document. Appendix C is a glossary.

None

1981-02-01

150

Long-term surveillance plan for the Mexican Hat Disposal Site, Mexican Hat, Utah  

SciTech Connect

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.

NONE

1996-02-01

151

Geomorphic criteria for selecting stable uranium tailings disposal sites in New Mexico. Volume 1. Technical report. Final report  

Microsoft Academic Search

Essential to the disposal of uranium mill tailings in northwestern New Mexico is the geomorphic stability of the disposal site. Geomorphic stability assessment involves 3 steps: (1) evaluating the site's past geomorphic stability by determining the age of the landscape and its associated deposits; (2) quantifying short- and long-term geomorphic processes operating in the site area; and (3) evaluating the

S. G. Wells; T. W. Gardner

1985-01-01

152

Hanford Site waste treatment\\/storage\\/disposal integration  

Microsoft Academic Search

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account

Kent M. McDonald

1999-01-01

153

Guidance for implementing the long-term surveillance program for UMTRA Project Title I Disposal Sites  

SciTech Connect

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.

NONE

1996-02-01

154

NEAR-BOTTOM PELAGIC BACTERIA AT A DEEP-WATER SEWAGE SLUDGE DISPOSAL SITE  

EPA Science Inventory

The epibenthic bacterial community at deep-ocean sewage sludge disposal site DWD-106, located approximately 106 miles (ca. 196 km) off the coast of New Jersey, was assessed for changes associated with the introduction of large amounts of sewage sludge. ixed cultures and bacterial...

155

MONITORING REPORT FOR 1995 AND 1996 - SAN FRANCISCO DEEP OCEAN DISPOSAL SITE (SF-DODS)  

EPA Science Inventory

This report documents the findings of Tier 1 monitoring activities at the San Francisco Deep Ocean Disposal Site (SF-DODS) for calendar years 1995 and 1996. The regional monitoring activities included: collection of regional physical oceanographic data; net sampling of plankton ...

156

Selection of biosphere transfer parameter values for radioactive waste disposal impact assessments, a site specific approach  

Microsoft Academic Search

In order to perform radiological impact assessments of radioactive waste disposals, a compartimental model taking into account generic data for biosphere transfer parameters values is usually used. To improve its performance assessments calculations, Andra (French national radioactive waste management agency) decided to adapt this type of biosphere model to its sites conditions. On one hand, specific models have been developed

N. JAUBERT

2005-01-01

157

CSAMT exploration at Sellafield: Characterization of a potential radioactive waste disposal site  

Microsoft Academic Search

The long term disposal of radioactive waste in an un- derground repository requires the detailed geological evaluation of a potential site. Owing to their inherent sensitivity to the presence of fluids in rocks, electromag- netic (EM) methods have an important role in this as- sessment. Controlled-source EM techniques are espe- cially useful in strong anthropogenic noise environments such as industrial

Martyn J. Unsworth; Xinyou Lu; M. Don Wattsz

2000-01-01

158

DRINK: a biogeochemical source term model for low level radioactive waste disposal sites  

Microsoft Academic Search

Interactions between element chemistry and the ambient geochemistry play a significant role in the control of radionuclide migration in the geosphere. These same interactions influence radionuclide release from near surface, low level radioactive waste, disposal sites once physical containment has degraded. In situations where LLW contains significant amounts of metal and organic materials such as cellulose, microbial degradation in conjunction

Paul Humphreys; Ray McGarry; Alex Hoffmann; Peter Binks

1997-01-01

159

NITROGEN REMOVAL FOR ON-SITE SEWAGE DISPOSAL: A RECIRCULATING SAND FILTER/ROCK TANK DESIGN  

E-print Network

NITROGEN REMOVAL FOR ON-SITE SEWAGE DISPOSAL: A RECIRCULATING SAND FILTER/ROCK TANK DESIGN, C. G. McKiel ABSTRACT: The nitrogen removal abilities of recirculating sand filter/rock tank (RSF in recirculating sand filters, with an average of 66% for the two-year study period. Denitrification was achieved

Gold, Art

160

Environmental Monitoring and Impact Assessment of a Solid Waste Disposal Site  

Microsoft Academic Search

The objective of this study is an attempt to conduct an environmentalmonitoring and impact assessment of the On-Nooch solid waste disposal sitein Bangkok, Thailand. Four water and five air sampling stations (2 upwindand 3 downwind directions) were established at the site. Grab water samplesfrom leachate treatment plant and Khlong Song Hong, a nearby stream, werecollected during the rainy and dry

S. Muttamara; Shing Tet Leong

1997-01-01

161

RESTORATION OF FAILING ON-SITE WASTEWATER DISPOSAL SYSTEMS USING WATER CONSERVATION  

EPA Science Inventory

A study was made to determine the ability of existing water conservation hardware to correct malfunctioning on-site wastewater disposal systems resulting from soil clogging and to document, under actual use conditions, possible reduction of wastewater with water conservation hard...

162

Ecological survey for the siting of the Mixed and Low-Level Waste Disposal Facility  

Microsoft Academic Search

This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Lab. (INEL) at two candidate locations for the siting of the Mixed and Low-Level Waste Disposal Facility (MLLWDF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate

Hoskinson

1994-01-01

163

Enhanced detection of groundwater contamination from a leaking waste disposal site by microbial community profiles  

E-print Network

Enhanced detection of groundwater contamination from a leaking waste disposal site by microbial of groundwater contamination. We sampled profiles of the microbial community from monitoring wells surrounding, P. O'Grady, and L. Stevens (2010), Enhanced detection of groundwater contamination from a leaking

Vermont, University of

164

Environmental Protection Agency Pt. 192 disposal sites; and (2) can reduce the likeli-  

E-print Network

of inadvertent and intermittent human intrusion into these disposal sites. Consideration of Inadvertent Human- logic repository are those associated with in- advertent human intrusion. Some types of intrusion would with their activities. Frequency and Severity of Inadvertent Human Intrusion into Geologic Repositories

165

Example of a Risk-Based Disposal Approval: Solidification of Hanford Site Transuranic Waste  

Microsoft Academic Search

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained

B. M. Barnes; J. E. Hyatt; P. W. Martin; A. L. Prignano

2008-01-01

166

15 CFR Appendix C to Subpart M of... - Dredged Material Disposal Sites Within the Sanctuary  

Code of Federal Regulations, 2010 CFR

...System) and are calculated using the North American Datum of 1983] Point ID No. Latitude Longitude Santa Cruz Harbor/Twin Lakes Dredge Disposal Site 1 36.9625 ?122.00056 2 36.9625 ?121.99861 3 36.96139 ?121.99833...

2010-01-01

167

15 CFR Appendix C to Subpart M of... - Dredged Material Disposal Sites Within the Sanctuary  

Code of Federal Regulations, 2013 CFR

...System) and are calculated using the North American Datum of 1983] Point ID No. Latitude Longitude Santa Cruz Harbor/Twin Lakes Dredge Disposal Site 1 36.9625 ?122.00056 2 36.9625 ?121.99861 3 36.96139 ?121.99833...

2013-01-01

168

15 CFR Appendix C to Subpart M of... - Dredged Material Disposal Sites Within the Sanctuary  

Code of Federal Regulations, 2012 CFR

...System) and are calculated using the North American Datum of 1983] Point ID No. Latitude Longitude Santa Cruz Harbor/Twin Lakes Dredge Disposal Site 1 36.9625 ?122.00056 2 36.9625 ?121.99861 3 36.96139 ?121.99833...

2012-01-01

169

15 CFR Appendix C to Subpart M of... - Dredged Material Disposal Sites Within the Sanctuary  

Code of Federal Regulations, 2014 CFR

...System) and are calculated using the North American Datum of 1983] Point ID No. Latitude Longitude Santa Cruz Harbor/Twin Lakes Dredge Disposal Site 1 36.9625 ?122.00056 2 36.9625 ?121.99861 3 36.96139 ?121.99833...

2014-01-01

170

15 CFR Appendix C to Subpart M of... - Dredged Material Disposal Sites Within the Sanctuary  

Code of Federal Regulations, 2011 CFR

...System) and are calculated using the North American Datum of 1983] Point ID No. Latitude Longitude Santa Cruz Harbor/Twin Lakes Dredge Disposal Site 1 36.9625 ?122.00056 2 36.9625 ?121.99861 3 36.96139 ?121.99833...

2011-01-01

171

Hydrogeology of a low-level radioactive-waste disposal site near Sheffield, Illinois  

Microsoft Academic Search

The Sheffield low-level radioactive-waste disposal site is located on 20 acres of rolling terrain 3 miles southwest of Sheffield, Illinois. The site covers parts of three small basins drained by three intermittent streams which empty into a tributary to Lawson Creek. Drainage divides for the basins also delineate the ground-water divides. Precipitation that falls within the basins is the source

J. B. Foster; J. R. Erickson; R. W. Healy

1984-01-01

172

NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147  

SciTech Connect

As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)] [U.S. Nuclear Regulatory Commission (United States)

2013-07-01

173

Comparative approaches to siting low-level radioactive waste disposal facilities  

SciTech Connect

This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

Newberry, W.F.

1994-07-01

174

On site treatment of NORM for surface waste disposal in Texas under Texas Railroad Commission Rule 94  

SciTech Connect

Remediation of Naturally Occurring Radioactive Material (NORM) by surface disposal under the provisions of Texas Railroad Commission Rule 94 and the applicable provisions of the Texas Department of Health Radiation Control Regulations is permitted under current State regulation and represents a viable alternative to commercial disposal under many circumstances. The economic advantages of on-sit disposal compared with commercial disposal can be significant, provided the generator is aware of the limitations of on-site disposal and has enough information and expertise to ensure a successful project. This report examines the experience gained from disposals performed under Rule 94 and summarizes the methods used and the results of actual NORM disposal projects at production sites under varying field conditions.

Landress, M.R. [Growth Resources, Inc., Lafayette, LA (United States)

1997-06-01

175

Program for low-level radioactive waste disposal at the Savannah River Site, A U. S. nuclear materials production facility  

Microsoft Academic Search

An integrated program has been developed for disposal of low-level radioactive wastes and associated mixed (radioactive-hazardous) and transuranic (TRU) wastes generated at the Savannah River Site (SRS). The program, supported by existing as well as new planned facilities, features a systems management approach, in which final disposal sites are specially designed and constructed for appropriately segregated waste streams, and intermediate

E. L. Wilhite; J. R. Cook; W. R. McDonell

1989-01-01

176

36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.  

Code of Federal Regulations, 2014 CFR

...sites within new additions to the National Park System. 6.6 Section 6...Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR...DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM 6.6 Solid...

2014-07-01

177

36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.  

Code of Federal Regulations, 2013 CFR

...sites within new additions to the National Park System. 6.6 Section 6...Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR...DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM 6.6 Solid...

2013-07-01

178

36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.  

Code of Federal Regulations, 2012 CFR

...sites within new additions to the National Park System. 6.6 Section 6...Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR...DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM 6.6 Solid...

2012-07-01

179

36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.  

Code of Federal Regulations, 2011 CFR

...sites within new additions to the National Park System. 6.6 Section 6...Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR...DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM 6.6 Solid...

2011-07-01

180

36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.  

Code of Federal Regulations, 2010 CFR

...sites within new additions to the National Park System. 6.6 Section 6...Forests, and Public Property NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR...DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM 6.6 Solid...

2010-07-01

181

Navajo birth outcomes in the Shiprock uranium mining area  

SciTech Connect

The role of environmental radiation in the etiology of birth defects, stillbirths, and other adverse outcomes of pregnancy was evaluated for 13,329 Navajos born at the Public Health Service/Indian Health Service Hospital in the Shiprock, NM, uranium mining area (1964-1981). More than 320 kinds of defective congenital conditions were abstracted from hospital records. Using a nested case-control design, families of 266 pairs of index and control births were interviewed. The only statistically significant association between uranium operations and unfavorable birth outcome was identified with the mother living near tailings or mine dumps. Among the fathers who worked in the mines, those of the index cases had histories of more years of work exposure but not necessarily greater gonadal dosage of radiation. Also, birth defects increased significantly when either parent worked in the Shiprock electronics assembly plant. Overall, the associations between adverse pregnancy outcome and exposure to radiation were weak and must be interpreted with caution with respect to implying a biogenetic basis.

Shields, L.M.; Wiese, W.H.; Skipper, B.J.; Charley, B.; Benally, L. (Navajo Community College, Shiprock, NM (United States))

1992-11-01

182

Importance of geologic characterization of potential low-level radioactive waste disposal sites  

USGS Publications Warehouse

Using the example of the Geff Alternative Site in Wayne County, Illinois, for the disposal of low-level radioactive waste, this paper demonstrates, from a policy and public opinion perspective, the importance of accurately determining site stratigraphy. Complete and accurate characterization of geologic materials and determination of site stratigraphy at potential low-level waste disposal sites provides the frame-work for subsequent hydrologic and geochemical investigations. Proper geologic characterization is critical to determine the long-term site stability and the extent of interactions of groundwater between the site and its surroundings. Failure to adequately characterize site stratigraphy can lead to the incorrect evaluation of the geology of a site, which in turn may result in a lack of public confidence. A potential problem of lack of public confidence was alleviated as a result of the resolution and proper definition of the Geff Alternative Site stratigraphy. The integrity of the investigation was not questioned and public perception was not compromised. ?? 1991 Springer-Verlag New York Inc.

Weibel, C.P.; Berg, R.C.

1991-01-01

183

Classified Component Disposal at the Nevada National Security Site (NNSS) - 13454  

SciTech Connect

The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012. (authors)

Poling, Jeanne; Arnold, Pat [National Security Technologies, LLC (NSTec), P.O. Box 98521, Las Vegas, NV 89193-8521 (United States)] [National Security Technologies, LLC (NSTec), P.O. Box 98521, Las Vegas, NV 89193-8521 (United States); Saad, Max [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)] [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); DiSanza, Frank [E. Frank DiSanza Consulting, 2250 Alanhurst Drive, Henderson, NV 89052 (United States)] [E. Frank DiSanza Consulting, 2250 Alanhurst Drive, Henderson, NV 89052 (United States); Cabble, Kevin [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)] [U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, P.O. Box 98518, Las Vegas, NV 89193-8518 (United States)

2013-07-01

184

Audit of the deactivation, decontamination, and disposal of surplus facilities at the Savannah River Site  

SciTech Connect

Westinghouse Savannah River Company (Westinghouse) is responsible for managing the Department of Energy`s (Department) surplus facilities at the Savannah River Site (Site). In Fiscal Year (FY) 1996, the Site had 162 surplus facilities and anticipated that 118 more would become surplus within the next 5 years. The objective of this audit was to determine whether the Savannah River Operations Office (Operations Office) and Westinghouse had economically and promptly deactivated, decontaminated, and disposed of surplus facilities at the Site. Departmental regulations require that surplus facilities be deactivated, decontaminated, and disposed of economically and promptly. However, Westinghouse only disposed of one facility and did not completely deactivate or decontaminate any of the 162 facilities identified as surplus at the Site in FY 1996. This occurred because the Operations Office did not compile a Site-wide list, establish priorities, or provide sufficient funding for the deactivation, decontamination, and disposal of surplus facilities. As a result, the Department incurred unnecessary costs for the surveillance and maintenance of surplus facilities. For example, the Department could have avoided annual costs of about $1.3 million in surveillance and maintenance costs by spending $1.2 million to perform a deactivation project on the P-Reactor process-water storage tanks. The Operations Office could have funded the project out of its unobligated FY 1996 operating funds. However, it returned the unobligated funds to the Department`s Headquarters at the end of the fiscal year. The Operations Office concurred with the finding and recommendations and initiated corrective action.

NONE

1997-10-23

185

Assessment of compost application to coal ash disposal sites to promote the rapid vegetation establishment  

NASA Astrophysics Data System (ADS)

In the city of Tuzla, located in Bosnia and Herzegovina, a coal fired thermo electric power plant is operated by the company JP ELEKTROPRIVERDA BIH TERMOELEKTRANA "TUZLA". High amounts of ash are produced by the power plant, which are currently disposed into settlement ponds bordered by dams in natural valleys. A total of four ash disposal sites covering an area of approx. 170 ha have been established during the last decades. Due to the fact that residual ash from coal combustion was found to contain a variety of trace elements (Ni, Cr, As, B), it must be assumed that ash disposal of that magnitude constitutes an environmental problem which is investigated within the EU-FP6 / STREP project "Reintegration of Coal Ash Disposal Sites and Mitigation of Pollution in the West Balkan Area" RECOAL. The main hazards relate to soil and groundwater contamination due to leaching toxins, dust dispersion, and toxins entering the food chain as these disposal sites are used for agricultural purposes. In order to rapidly establish a vegetation cover on barren ash dumps that particularly would prevent dust erosion we assessed the applicability of compost, produced from locally available municipal and industrial organic residues as an amendment to ash to improve substrate fertility. The envisaged remediation technology was considered to be a low cost, easy applicable and rapid method capable of substantially enhancing living conditions of residents in the vicinity of the abandoned disposal sites. Various compost application rates were evaluated in the field on experimental site Divkovici I in Tuzla and additionally in the greenhouse environment at Brandenburg Technical University Cottbus. Field and laboratory tests revealed that plant growth and cover rate can substantially be improved by mixing compost into the upper ash layer to a maximum depth of approx. 20 cm. Besides direct growth observations in the field analysis of soil parameters gave evidence that the fertility of ashy substrates amended with compost produced from locally available sewage sludge and saw dust can be improved. The metal content of grass grown in the various treatments was considered to be elevated compared to normal contents. However, metal uptake in compost treatments was lower than in untreated plots. A preliminary cost assessment, comparing the remediation technology tested on site Divkovici with a standard soil covering technique revealed financial benefits for the compost method due to significant lower application rates.

Repmann, F.; Slazak, A.; Babic, M.; Schneider, B. U.; Schaaf, W.; Httl, R. F.

2009-04-01

186

Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)  

SciTech Connect

The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory constraints based on the intruder analysis are well above conservative estimates of the OSWDF inventory and, based on intruder disposal limits; about 7% of the disposal capacity is reached with the estimated OSWDF inventory.

Smith, Frank G.; Phifer, Mark A.

2014-01-22

187

Modeling Groundwater Flow and Infiltration at Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

NASA Astrophysics Data System (ADS)

Taiwan is evaluating representative sites for the potential disposal of low-level radioactive waste (LLW), including consideration of shallow land burial and cavern disposal concepts. A representative site for shallow land burial is on a small island in the Taiwan Strait with basalt bedrock. The shallow land burial concept includes an engineered cover to limit infiltration into the waste disposal cell. A representative site for cavern disposal is located on the southeast coast of Taiwan. The tunnel system for this disposal concept would be several hundred meters below the mountainous land surface in argillite bedrock. The LLW will consist of about 966,000 drums, primarily from the operation and decommissioning of four nuclear power plants. Sandia National Laboratories and the Institute of Nuclear Energy Research have collaborated to develop performance assessment models to evaluate the long-term safety of LLW disposal at these representative sites. Important components of the system models are sub-models of groundwater flow in the natural system and infiltration through the engineered cover for the shallow land burial concept. The FEHM software code was used to simulate groundwater flow in three-dimensional models at both sites. In addition, a higher-resolution two-dimensional model was developed to simulate flow through the engineered tunnel system at the cavern site. The HELP software was used to simulate infiltration through the cover at the island site. The primary objective of these preliminary models is to provide a modeling framework, given the lack of site-specific data and detailed engineering design specifications. The steady-state groundwater flow model at the island site uses a specified recharge boundary at the land surface and specified head at the island shoreline. Simulated groundwater flow vectors are extracted from the FEHM model along a cross section through one of the LLW disposal cells for utilization in radionuclide transport simulations in the performance assessment model with the BLT-MS software. Infiltration through the engineered cover is simulated to be about 3 mm/yr and 49 mm/yr, with and without a geomembrane layer, respectively. For the cavern LLW disposal site, the FEHM basin-scale flow model uses specified recharge flux, constant head at the ocean shoreline, and head-dependent flux boundaries along flowing streams. Groundwater flow vectors are extracted along a cross section for use in radionuclide transport simulations. Transport simulations indicate that a significant fraction of contaminants may ultimately discharge to nearby streams. FEHM flow simulations with the drift-scale model indicate that the flow rates within the backfilled tunnels may be more than two orders of magnitude lower than in the host rock. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE-AC04-94AL85000.

Arnold, B. W.; Lee, C.; Ma, C.; Knowlton, R. G.

2006-12-01

188

Corrective Action Investigation Plan for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect

Corrective Action Unit (CAU) 139 is located in Areas 3, 4, 6, and 9 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 139 is comprised of the seven corrective action sites (CASs) listed below: (1) 03-35-01, Burn Pit; (2) 04-08-02, Waste Disposal Site; (3) 04-99-01, Contaminated Surface Debris; (4) 06-19-02, Waste Disposal Site/Burn Pit; (5) 06-19-03, Waste Disposal Trenches; (6) 09-23-01, Area 9 Gravel Gertie; and (7) 09-34-01, Underground Detection Station. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives with the exception of CASs 09-23-01 and 09-34-01. Regarding these two CASs, CAS 09-23-01 is a gravel gertie where a zero-yield test was conducted with all contamination confined to below ground within the area of the structure, and CAS 09-34-01 is an underground detection station where no contaminants are present. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for the other five CASs where information is insufficient. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 4, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 139.

Grant Evenson

2006-04-01

189

Long-term surveillance plan for the Falls City Disposal Site, Falls City, Texas. Revision 2  

SciTech Connect

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.

NONE

1996-11-01

190

Quantifying Deep Vadose Zone Soil Water Potential Changes at a Waste Disposal Site  

SciTech Connect

Recent advances in moisture monitoring using tensiometers has resulted in long-duration, high quality data sets from within the deep vadose zone. A network of about 30 advanced tensiometers in 18 wells provided field-scale data to monitor soil water potential conditions and movement in the subsurface in and around a mixed waste disposal site at depths ranging from 6 to over 67 m below land surface (bls). Sensors are located in both sediments and fractured rock within the geologic profile and some have been in operation for over 10 years. The moisture monitoring was able to detect long term declines in soil water potential in response to lower than normal precipitation and resultant infiltration over the time period from 2000 to 2004. This trend was reversed in 2005 and 2006 in more than half of the monitoring sites over the 6 to 33 m depth interval and in several monitoring sites from 33 to 67 m, in response to above normal precipitation. These tensiometer data have the potential to effectively and rapidly validate that a remedial action such as placement of an ET cover would be successful in reducing the water moisture movement inside the disposal area to levels similar to those in undisturbed sites outside of the disposal area. This paper will describe the instrument design, how the instruments were installed, and the resultant data from this monitoring system.

Joel M. Hubbell; Deborah L. McElroy

2007-08-01

191

Movement of tagged dredged sand at thalweg disposal sites in the upper Mississippi River  

SciTech Connect

Thalweg disposal experiments have been conducted at three sites on the upper Mississippi River. During normal channel maintenance, hydraulically dredged sand was tagged with sand coated with fluorescent dye prior to disposal as a pile in the thalweg. In postdisposal surveys surficial bottom sediment samples were collected in the disposal area and in the thalweg and border areas downstream to determine the movement of the dredged sand relative to environmentally sensitive river habitats. The experiments were initiated in successive years, and the tagged sand has been tracked for 1 to 3 years, depending on the site. Although the downstream movement of the dredged sand was not the same at each site, the general pattern of behavior was similar. Downstream movement was confined primarily to the main channel and occurred in response to periods of high river discharge. There was no statistically significant evidence of dredged sand dispersing out of the main channel into nearby border areas or sloughs. The distributions of dyed sand in cores from one site suggest that the dredged sand has been incorporated into natural bed forms. 7 refs., 5 figs.

Ditmars, J.D.; McCown, D.L.; Paddock, R.A.

1986-01-01

192

Potential for effects of land contamination on human health. 2. The case of waste disposal sites.  

PubMed

This review of the epidemiological literature shows that evidence for negative impacts of land contaminated by waste disposal on human health is limited. However, the potential for health impacts cannot be dismissed. The link between residence close to hazardous waste disposal sites and heightened levels of stress and anxiety is relatively well established. However, studies on self-reported outcomes generally suffer from interpretational problems, as subjective symptoms may be due to increased perception and recall. Several recent multiple-site studies support a plausible linkage between residence near waste disposal sites and reproductive effects (including congenital anomalies and low birth weight). There is some conflict in the literature investigating links between land contamination and cancers; the evidence for and against a link is equally balanced and is insufficient to make causal inferences. These are difficult to establish because of lack of data on individual exposures, and other socioeconomic and lifestyle factors that may confound a relationship with area of residence. There is no consistently occurring risk for any specific tumor across multiple studies on sites expected to contain similar contaminants. Further insights on health effects of land contamination are likely to be gained from studies that consider exposure pathways and biomarkers of exposure and effect, similar to those deployed with some success in investigating impacts of cadmium on human health. PMID:23190269

Kah, Melanie; Levy, Len; Brown, Colin

2012-01-01

193

Mercury speciation in sediments at a municipal sewage sludge marine disposal site  

Microsoft Academic Search

Mercury speciation was performed in excess activated sewage sludge (ASS) and in marine sediments collected at the AAS disposal site off the Mediterranean coast of Israel in order to characterize the spatial and vertical distribution of different mercury species and assess their environmental impact. Total Hg (HgT) concentrations ranged between 0.19 and 1003ng\\/g at the polluted stations and 5.7 and

E. Shoham-Frider; G. Shelef; N. Kress

2007-01-01

194

Evapotranspiration and microclimate at a low-level radioactive-waste disposal site in northwestern Illinois  

SciTech Connect

Theory, methods, and results of a 2-yr study of microclimate and evapotranspiration of vegetated trench caps, conducted at the disposal site near Sheffield, Illinois, are presented in the report. Three methods were used to estimate evapotranspiration: energy-budget, aerodynamic-profile, and water-budget. Daily evapotranspiration ranged from 0 to 6 mm. The yearly average for the three methods of 657 mm was equivalent to 70% of precipitation and 75% of potential evapotranspiration.

Healy, R.W.; deVries, M.P.; Sturrock, A.M. Jr.

1989-01-01

195

Geological criteria for the selection of unconfined dredged material disposal sites in estuaries and lagoons  

E-print Network

ASM University Chairman of Advisory Committee: Dr. Christopher C. Mathewson Dredged material islands in estuaries and lagoons are reworked and redistributed by waves and currents. Unless the islands are properly located, the redistribution... disposal sites at any location within a bay. The model re- quires consideration of the interaction of the prevailing and storm wind components with fetch length, water depth, and tides. Because the model is based solely on an understanding of the net...

McHam, Robert Michael

1977-01-01

196

Analysis of core soil and water samples from the Cactus Crater Disposal Site at Enewetak atoll  

SciTech Connect

Core soil samples and water samples were collected from the Cactus Crater Disposal Site at Enewetak for analysis of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu and /sup 241/Am by both gamma spectroscopy and, through a contractor laboratory, by wet chemistry procedures. The samples processing methods, the analytical methods and the analytical quality control are all procedures developed for the continuing Marshall Island radioecology and dose assessment work.

Robison, W.L.; Noshkin, V.E.

1981-02-18

197

Calendar Year 2002 Hanford Site mixed waste land disposal restrictions report (section 1 thru 3)  

Microsoft Academic Search

Volume 1 presents information concerning the storage and minimization of mixed waste and the potential sources for the generation of additional mixed waste. This information, presented in accordance with ''Hanford Federal Facility Agreement and Consent Order'' (Tri-Party Agreement) (Ecology et al. 2001) Milestone M-26-01M, is Volume 1 of a two-volume report on the status of Hanford Site land disposal restricted

2003-01-01

198

CY2003 HANFORD SITE MIXED WASTE LAND DISPOSAL RESTRICTIONS REPORT [SEC 1 THRU 3  

Microsoft Academic Search

Volume 1 presents information concerning the storage and minimization of mixed waste and the potential sources for the generation of additional mixed waste. This information, presented in accordance with Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 2003) Milestone M-26-01N, is Volume 1 of a two-volume report on the status of Hanford Site land disposal restricted

2004-01-01

199

Polycyclic aromatic hydrocarbons in sediments at dredged material disposal sites around England: Concentrations in 2013 and time trend information at selected sites 2008-2013.  

PubMed

The maintenance of navigation channels to ports and the development of their facilities present a need to conduct dredging operations, and the subsequent disposal of dredged material at sea. Contaminant concentrations in candidate dredged material are determined and their possible impacts considered during the licensing process, which can result in the exclusion of some material from sea disposal. Monitoring of disposal sites is conducted in order to ensure that no undesirable impacts are occurring. In this study we consider the levels of polycyclic aromatic hydrocarbons (PAHs) in sediments at a number of disposal sites monitored in 2013 and variations in concentrations over time at three sites during the period 2008-2013. These were assessed using established sediment quality guidelines. Elevated PAH concentrations were generally observed only within the boundaries of the disposal sites studied. PMID:25618523

Rumney, Heather S; Bolam, Stefan G; Law, Robin J

2015-03-15

200

From NIMBY to YIMBY: How generators can support siting LLRW disposal facilities  

SciTech Connect

The most frequently head complaint about siting low-level radioactive waste disposal facilities is the NIMBY (Not In My Back Yard) syndrome. The producers or generators of this waste can help move public opinion form NIMBY to YIMBY (YES! In MY Back Yard!). Generators of low-level radioactive waste often believe it is the responsibility of other organizations to site disposal facilities for the waste, and that their role is to assure the technical aspects of the facility, such as acceptability criteria for the various waste forms, are clearly defined. In reality, generators, using a properly designed and effectively implemented communications plan, can be the most effective advocates for siting a facility. The communications plan must include the following elements: an objective focusing on the importance of generators becoming vocal and active; clearly defined and crafted key messages; specifically defined and targeted audiences for those messages; and speaker training which includes how to communicate with hostile or concerned audiences about a subject they perceive as very risky. Generators must develop coalitions with other groups and form a grassroots support organization. Finally, opportunities must be developed to deliver these messages using a variety of means. Written materials should be distributed often to keep the need for disposal capability in the public`s mind. Can we get from NIMBY to YIMBY? It is difficult, but doable--especially with support from the people who make the waste in the first place.

Hoffman, J.P. [GPU Nuclear Corporation, Harrisburg, PA, (United States)

1995-05-01

201

Assessment of microbial processes on gas production at radioactive low-level waste disposal sites  

SciTech Connect

Factors controlling gaseous emanations from low level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide, and possible hydrogen from the site, stems from the inclusion of tritium and/or carbon-14 into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste material, primary emphasis of the study involved an examination of the biochemical pathways producing methane, carbon dioxide, and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Initial examination of the data indicates that the ecosystem is anaerobic. As the result of the complexity of the pathway leading to methane production, factors such as substrate availability, which limit the initial reaction in the sequence, greatly affect the overall rate of methane evolution. Biochemical transformations of methane, hydrogen and carbon dioxide as they pass through the soil profile above the trench are discussed. Results of gas studies performed at three commercial low level radioactive waste disposal sites are reviewed. Methods used to obtain trench and soil gas samples are discussed. Estimates of rates of gas production and amounts released into the atmosphere (by the GASFLOW model) are evaluated. Tritium and carbon-14 gaseous compounds have been measured in these studies; tritiated methane is the major radionuclide species in all disposal trenches studied. The concentration of methane in a typical trench increases with the age of the trench, whereas the concentration of carbon dioxide is similar in all trenches.

Weiss, A.J.; Tate, R.L. III; Colombo, P.

1982-05-01

202

Navajo coal and air quality in Shiprock, New Mexico  

USGS Publications Warehouse

Among the Navajo people, high levels of respiratory disease, such as asthma, exist in a population with low rates of cigarette smoking. Air quality outdoors and indoors affects respiratory health. Many Navajo Nation residents burn locally mined coal in their homes for heat, as coal is the most economical energy source. The U.S. Geological Survey and Dine College, in cooperation with the Navajo Division of Health, are conducting a study in the Shiprock, New Mexico, area to determine if indoor use of this coal might be contributing to some of the respiratory health problems experienced by the residents. Researchers in this study will (1) examine respiratory health data, (2) identify stove type and use, (3) analyze samples of coal that are used locally, and (4) measure and characterize air quality inside selected homes. This Fact Sheet summarizes the interim results of the study in both English and Navajo.

Bunnell, Joseph E.; Garcia, Linda V.

2006-01-01

203

Possibilities of detecting health effects by studies of populations exposed to chemicals from waste disposal sites.  

PubMed Central

Factors affecting the design of an epidemiologic study assessing possible health effects from chemical waste disposal sites are reviewed. Such epidemiologic studies will most likely be prompted either by a known release of chemicals into the environment around the site, or by an unusual disease cluster in a population near the site. In the latter situation, a method for evaluating the health effects is needed, and one possible approach is discussed. In the former situation, it may not be obvious what health outcomes are relevant. Reported associations between health effects and chemicals in humans were reviewed. Studies from the occupational and environmental literature were classified by chemical and target organ affected and presented in tabular form. No attempt was made to critically evaluate the quality of evidence for each health effect, although bibliographic documentation was provided where possible. Episodes of chemical contamination of food, drinking water and other media were also reviewed and presented in a separate table. The organ sites likely to be affected by toxic chemicals from waste disposal sites depend heavily on the route of exposure and the dose that is received. Ingestion is the most frequently reported route of exposure in episodes of environmental contamination. These have affected the hepatic, renal, hematopoietic, reproductive, and central nervous systems. The type and severity of effects were dose-dependent. Direct skin contact is important in the occupational environment where dermal and central nervous system effects have been reported but seems less likely as a route of exposure for populations around waste disposal sites. Inhalation, unless at relative high concentrations or as a result of fire, is unlikely to be important, although hematopoietic, reproductive, and central nervous system effects have been reported in occupational studies. PMID:3910420

Buffler, P A; Crane, M; Key, M M

1985-01-01

204

Acoustic mapping of the regional seafloor geology in and around Hawaiian ocean dredged-material disposal sites  

USGS Publications Warehouse

During January and February 1998 the U.S. Geological Survey Coastal and Marine Geology Team (USGS) conducted regional high-resolution multibeam mapping surveys of the area surrounding EPA-designated ocean disposal sites located offshore of the Hawaiian Islands of Oahu, Kauai, Maui, and Hawaii. The sites are all located within 5 nautical miles of shore on insular shelves or slopes. Regional maps were required of areas much larger than the disposal sites themselves to assess both the regional seafloor geology and the immediate vicinity of the disposal sites. The purpose of the disposal site surveys was to delimit the extent of disposal material by producing detailed bathymetric and backscatter maps of the seafloor with a 1 m spatial accuracy and <1% depth error. The advantage of using multibeam over conventional towed, single-beam sidescan sonar is that the multibeam data are accurately georeferenced for precise location of all imaged features. The multibeam produces a coregistered acoustic-backscatter map that is often required to locate individual disposal deposits. These data were collected by the USGS as part of its regional seafloor mapping and in support of ocean disposal site monitoring studies conducted in cooperation with the US Environmental Protection Agency (EPA) and the US Army Corps of Engineers (COE).

Torresan, Michael E.; Gardner, James V.

2000-01-01

205

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

SciTech Connect

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.

NSTec Environmental Programs

2010-10-04

206

UTILIZING A CHIRP SONAR TO ACCURATELY CHARACTERIZE NEWLY DEPOSITED MATERIAL AT THE CALCASIEU OCEAN DREDGED MATERIAL DISPOSAL SITE, LOUISIANA  

EPA Science Inventory

The distribution of dredged sediments is measured at the Calcasieu Ocean Dredged Material Disposal Site (ODMDS) using a chirp sonar immediately after disposal and two months later. ubbottom reflection data, generated by a chirp sonar transmitting a 4 to 20 kHz FM sweep, is proces...

207

Program for low-level radioactive waste disposal at the Savannah River Plant, a US nuclear materials production site  

Microsoft Academic Search

An integrated program has been developed for disposal of low-level radioactive wastes and associated mixed (radioactive-hazardous) and transuranic (TRU) wastes generated at the Savannah River Plant (SRP). The program, supported by existing as well as new planned facilities, features a systems management approach, in which final disposal sites are specially designed and constructed for appropriately segregated waste streams, and intermediate

E. L. Wilhite; J. R. Cook; W. R. McDonell

1989-01-01

208

Approaches to LLW disposal site selection and current progress of host states  

SciTech Connect

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985 and under the guidance of 10 CFR 61, States have begun entering into compacts to establish and operate regional disposal facilities for low-level radioactive waste. The progress a state makes in implementing a process to identify a specific location for a disposal site is one indication of the level of a state's commitment to meeting its responsibilities under Federal law and interstate compact agreements. During the past few years, several States have been engaged in site selection processes. The purpose of this report is to summarize the site selection approaches of some of the Host States (California, Michigan, Nebraska, New York, North Carolina, Texas, and Illinois), and their progress to date. An additional purpose of the report is to discern whether the Host States's site selection processes were heavily influenced by any common factors. One factor each state held in common was that political and public processes exerted a powerful influence on the site selection process at virtually every stage. 1 ref.

Walsh, J.J.; Kerr, T.A.

1990-11-01

209

Long-term surveillance plan for the Canonsburg, Pennsylvania, disposal site  

SciTech Connect

This document establishes elements of the US Department of Energy`s (DOE) Long-Term Surveillance Plan for the Canonsburg, Pennsylvania, disposal site. The US Nuclear Regulatory Commission (NRC) will use this plan in support of license issuance for the long-term surveillance of the Canonsburg site. The Canonsburg (CAN) site is located within the borough of Canonsburg, Washington County, in southwestern Pennsylvania. The Canonsburg site covers approximately 30 acres (74 hectares). The disposal cell contains approximately 226,000 tons (241,000 tons) of residual radioactive material (RRM). Area C is southeast of the Canonsburg site, between Strabane Avenue and Chartiers Creek. Contaminated soils were removed from Area C during the remedial action, and the area was restored with uncontaminated fill material.After this cleanup, residual quantities of thorium-230 were detected at several Area C locations. The remedial action plan did not consider the ingrowth of radium-226 from thorium-230 as part of the Area C cleanup, and only two locations contained sufficient thorium-230 concentrations to result in radium-226 concentrations slightly above the US Environmental Protection Agency (EPA) standards.

NONE

1995-10-01

210

Quantifying Deep Vadose Zone Soil Water Potential Changes At A Waste Disposal Site  

SciTech Connect

Recent advances in moisture monitoring using tensiometers has allowed long-duration, high quality data sets from within the deep vadose zone. A network of about 30 advanced tensiometers in 18 wells provided field-scale data to monitor moisture conditions and movement in the subsurface in and around a mixed waste disposal site at depths ranging from 6 to over 67 m below land surface (bls). Sensors are located in both sediments and fractured rock within the geologic profile and some have been in operation for over 10 years. The moisture monitoring was able to detect long term declines in moisture content presumably in response to lower than normal precipitation and resultant infiltration over the time period from 2000 to 2004. This trend was reversed in 2005 and 2006 in more than half of the monitoring sites over the 6 to 33 m depth interval and in several monitoring sites from 33 to 67 m, in response to normal to above normal precipitation. This tensiometer data can be used to evaluate the appropriateness of the current conceptual model of flow at this site. It also shows that a moisture monitoring system should be effective to rapidly validate that a proposed remedial action (such as placement of an ET cover) would be effective in reducing the moisture movement to levels similar to those in undisturbed sites outside of the disposal area. This paper will describe the instrument design, how the instruments were installed, and the resultant data from this monitoring system.

Joel M. Hubbell; Deborah L. McElroy

2007-10-01

211

Radiological audit of remedial action activities at the processing site, transfer site, and Cheney disposal site Grand Junction, Colorado: Audit date, August 9--11, 1993. Final report  

SciTech Connect

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.

Not Available

1993-08-01

212

Fuzzy multicriteria disposal method and site selection for municipal solid waste.  

PubMed

The use of fuzzy multiple criteria analysis (MCA) in solid waste management has the advantage of rendering subjective and implicit decision making more objective and analytical, with its ability to accommodate both quantitative and qualitative data. In this paper a modified fuzzy TOPSIS methodology is proposed for the selection of appropriate disposal method and site for municipal solid waste (MSW). Our method is superior to existing methods since it has capability of representing vague qualitative data and presenting all possible results with different degrees of membership. In the first stage of the proposed methodology, a set of criteria of cost, reliability, feasibility, pollution and emission levels, waste and energy recovery is optimized to determine the best MSW disposal method. Landfilling, composting, conventional incineration, and refuse-derived fuel (RDF) combustion are the alternatives considered. The weights of the selection criteria are determined by fuzzy pairwise comparison matrices of Analytic Hierarchy Process (AHP). It is found that RDF combustion is the best disposal method alternative for Istanbul. In the second stage, the same methodology is used to determine the optimum RDF combustion plant location using adjacent land use, climate, road access and cost as the criteria. The results of this study illustrate the importance of the weights on the various factors in deciding the optimized location, with the best site located in Catalca. A sensitivity analysis is also conducted to monitor how sensitive our model is to changes in the various criteria weights. PMID:20303733

Ekmekio?lu, Mehmet; Kaya, Tolga; Kahraman, Cengiz

2010-01-01

213

Fuzzy multicriteria disposal method and site selection for municipal solid waste  

SciTech Connect

The use of fuzzy multiple criteria analysis (MCA) in solid waste management has the advantage of rendering subjective and implicit decision making more objective and analytical, with its ability to accommodate both quantitative and qualitative data. In this paper a modified fuzzy TOPSIS methodology is proposed for the selection of appropriate disposal method and site for municipal solid waste (MSW). Our method is superior to existing methods since it has capability of representing vague qualitative data and presenting all possible results with different degrees of membership. In the first stage of the proposed methodology, a set of criteria of cost, reliability, feasibility, pollution and emission levels, waste and energy recovery is optimized to determine the best MSW disposal method. Landfilling, composting, conventional incineration, and refuse-derived fuel (RDF) combustion are the alternatives considered. The weights of the selection criteria are determined by fuzzy pairwise comparison matrices of Analytic Hierarchy Process (AHP). It is found that RDF combustion is the best disposal method alternative for Istanbul. In the second stage, the same methodology is used to determine the optimum RDF combustion plant location using adjacent land use, climate, road access and cost as the criteria. The results of this study illustrate the importance of the weights on the various factors in deciding the optimized location, with the best site located in Catalca. A sensitivity analysis is also conducted to monitor how sensitive our model is to changes in the various criteria weights.

Ekmekcioglu, Mehmet, E-mail: meceng3584@yahoo.co [Istanbul Technical University, Department of Management Engineering, 34367 Macka, Istanbul (Turkey); Kaya, Tolga [Istanbul Technical University, Department of Management Engineering, 34367 Macka, Istanbul (Turkey); Kahraman, Cengiz [Istanbul Technical University, Department of Industrial Engineering, 34367 Macka, Istanbul (Turkey)

2010-08-15

214

Spatial patterns of serial murder: an analysis of disposal site location choice.  

PubMed

Although the murders committed by serial killers may not be considered rational, there is growing evidence that the locations in which they commit their crimes may be guided by an implicit, if limited rationality. The hypothesized logic of disposal site choice of serial killers led to predictions that (a) their criminal domains would be around their home base and relate to familiar travel distances, (b) they would have a size that was characteristic of each offender, (c) the distribution would be biased towards other non-criminal activities, and (d) the size of the domains would increase over time. Examination of the geographical distribution of the sites at which 126 US and 29 UK serial killers disposed of their victims' bodies supported all four hypotheses. It was found that rational choice and routine activity models of criminal behavior could explain the spatial choices of serial murderers. It was concluded that the locations at which serial killers dispose of their victims' bodies reflect the inherent logic of the choices that underlie their predatory activities. PMID:11568963

Lundrigan, S; Canter, D

2001-01-01

215

Assessment and analysis of industrial liquid waste and sludge disposal at unlined landfill sites in arid climate  

SciTech Connect

Municipal solid waste disposal sites in arid countries such as Kuwait receive various types of waste materials like sewage sludge, chemical waste and other debris. Large amounts of leachate are expected to be generated due to the improper disposal of industrial wastewater, sewage sludge and chemical wastes with municipal solid waste at landfill sites even though the rainwater is scarce. Almost 95% of all solid waste generated in Kuwait during the last 10 years was dumped in five unlined landfills. The sites accepting liquid waste consist of old sand quarries that do not follow any specific engineering guidelines. With the current practice, contamination of the ground water table is possible due to the close location of the water table beneath the bottom of the waste disposal sites. This study determined the percentage of industrial liquid waste and sludge of the total waste dumped at the landfill sites, analyzed the chemical characteristics of liquid waste stream and contaminated water at disposal sites, and finally evaluated the possible risk posed by the continuous dumping of such wastes at the unlined landfills. Statistical analysis has been performed on the disposal and characterization of industrial wastewater and sludge at five active landfill sites. The chemical analysis shows that all the industrial wastes and sludge have high concentrations of COD, suspended solids, and heavy metals. Results show that from 1993 to 2000, 5.14{+-}1.13 million t of total wastes were disposed per year in all active landfill sites in Kuwait. The share of industrial liquid and sludge waste was 1.85{+-}0.19 million t representing 37.22{+-}6.85% of total waste disposed in all landfill sites. Such wastes contribute to landfill leachate which pollutes groundwater and may enter the food chain causing adverse health effects. Lined evaporation ponds are suggested as an economical and safe solution for industrial wastewater and sludge disposal in the arid climate of Kuwait.

Al Yaqout, Anwar F

2003-07-01

216

Natural selection of PAH-degrading bacterial guilds at coal-tar disposal sites.  

PubMed Central

Microbial activity patterns at buried coal-tar disposal sites have been under investigation for several years to determine the response of naturally occurring microflora to polycyclic aromatic hydrocarbons (PAHs) at the sites. At one site in upstate New York, data have shown enrichment of PAH-degrading bacteria in subsurface contaminated zones but not in uncontaminated zones. Similar work at a midwestern site showed that the same trends existed in a heterogeneous disposal site except that a borehole outside the plume showed some PAH-mineralization activity. Polymerase chain reaction amplification of DNA extracted from sediment samples from the New York site indicated the presence of naphthalene metabolism genes nahAc and nahR, similar to those found on the NAH7 plasmid of Pseudomonas putida G7. Significant sequence polymorphism was observed in amplified nahAc products, indicating that divergent homologs of nahAc were present in the native community. Protozoan numbers were elevated in sediment samples displaying relatively high PAH-degrading activity, suggesting that a food chain was established based on PAH-degrading bacteria. Removal of the coal-tar source at the site occurred in 1991. In 1992, sampling of three key borehole stations revealed that mixing and backfilling operations had introduced soil microorganisms into the source area and introduced 14C-PAH-mineralization activity into the previously inactive pristine area. Thus removal of the source of the contaminants and restoration at the site have altered the microbial activity patterns outside the contaminant plume as well as in the source area. PMID:8565896

Ghiorse, W C; Herrick, J B; Sandoli, R L; Madsen, E L

1995-01-01

217

Natural selection of PAH-degrading bacterial guilds at coal-tar disposal sites  

SciTech Connect

Microbial activity patterns at buried coal-tar disposal sites have been under investigation for several years to determine the response of naturally occurring microflora to polycyclic aromatic hydrocarbons (PAHs) at the sites. At one site in upstate New York, data have shown enrichment of PAH-degrading bacteria in subsurface contaminated zones but not in uncontaminated zones. Similar work at a Midwestern site showed that the same trends existed in a heterogeneous disposal site except that a borehole outside the plume showed some PAH-mineralization activity. Polymerase chain reaction amplification of DNA extracted from sediment samples from the New York site indicated the presence of naphthalene metabolism genes nahAc and nahR, similar to those found on the NAH7 plasmid of Pseudomonas putida G7. Significant sequence polymorphism was observed in amplified nahAc products, indicating that divergent homologs of nahAc were present in the native community. Protozoan numbers were elevated in sediment samples displaying relatively high PAH-degrading activity, suggesting that a food chain was established based on PAH-degrading bacteria. Removal of the coal-tar source at the site occurred in 1991. In 1992, sampling of three key borehole stations revealed that mixing and backfilling operations had introduced soil microorganisms into the source area and introduced 14C-PAH-mineralization activity into the previously inactive pristine area. Thus removal of the source of the contaminants and restoration at the site have altered the microbial activity patterns outside the contaminant plume as well as in the source area. 15 refs., 3 figs.

Ghiorse, W.C.; Herrick, J.B.; Sandoli, R.L.; Madsen, E.L. [Cornell Univ., Ithaca, NY (United States)

1995-06-01

218

Use of engineered soils and other site modifications for low-level radioactive waste disposal  

SciTech Connect

The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover.

Not Available

1994-08-01

219

Near-bottom pelagic bacteria at a deep-water sewage sludge disposal site  

SciTech Connect

The epibenthic bacterial community at deep-ocean sewage sludge disposal site DWD-106, located approximately 106 miles (ca. 196 km) off the coast of New Jersey, was assessed for changes associated with the introduction of large amounts of sewage sludge. Mixed cultures and bacterial isolates obtained from water overlying sediment core samples collected at the deep-water (2,500 m) municipal sewage disposal site were tested for the ability to grow under in situ conditions of temperature and pressure. The responses of cultures collected at a DWD-106 station heavily impacted by sewage sludge were compared with those of samples collected from a station at the same depth which was not contaminated by sewage sludge. Significant differences were observed in the ability of mixed bacterial cultures and isolates from the two sites to grow under deep-sea pressure and temperature conditions. The levels of sludge contamination were established by enumerating Clostridium perfringens, a sewage indicator bacterium, in sediment samples from the two sites. (Copyright (c) 1993, American Society for Microbiology.)

Takizawa, M.; Straube, W.L.; Hill, R.T.; Colwell, R.R.

1994-01-01

220

A follow-up study of the community near the McColl waste disposal site.  

PubMed Central

To assess the effect of interim clean-up measures on the current health of a community, we conducted a follow-up survey of 193 residents living near the McColl waste disposal site and a comparison area located approximately 5 miles from the site. Results from this survey were compared with results from a similar survey conducted 7 years earlier. Odors were detected at least once per week by 32.7% of "high-exposed" respondents in 1988 compared with 68.5% in 1981, but prevalence odds ratios (PORs) comparing symptom reporting between "high-exposed" and comparison-area respondents were greater than that of the 1981 survey for 89% of symptoms. PORs comparing symptom reporting between these two areas were greater than 2.0 for 64% of symptoms assessed in the current survey. Symptoms reported in excess did not represent a single organ system or suggest a mechanism of response. PORs comparing respondents who were very worried about the environment and those reporting no worry were greater than 2.0 for 86% of symptoms. These finding, along with environmental data from the area, suggest that living near the waste disposal site and being very worried about the environment, rather than a toxicologic effect of chemical from the site, explain excess symptom reporting found in this follow-up study. PMID:1954927

Lipscomb, J A; Goldman, L R; Satin, K P; Smith, D F; Vance, W A; Neutra, R R

1991-01-01

221

Hydrogeology of a hazardous-waste disposal site near Brentwood, Williamson County, Tennessee  

USGS Publications Warehouse

Approximately 44,000 gal of industrial solvent wastes were disposed in pits on a farm near Brentwood, Tennessee, in 1978, and contaminants were reported in the soil and shallow groundwater on the site in 1985. In order for the State to evaluate possible remedial-action alternatives, an 18-month study was conducted to define the hydrogeologic setting of the site and surrounding area. The area is underlain by four hydrogeologic units: (1) an upper aquifer consisting of saturated regolith, Bigby-Cannon Limestone, and weathered Hermitage Formation; (2) the Hermitage confining unit; (3) a lower aquifer consisting of the Carters Limestone; and (4) the Lebanon confining unit. Wells generally are low yielding less than 1 gal/min ), although locally the aquifers may yield as much as 80 gal/minute. This lower aquifer is anisotropic, and transmissivity of this aquifer is greatest in a northwest-southeast direction. Recharge to the groundwater system is primarily from precipitation, and estimates of average annual recharge rates range from 6 to 15 inches/year. Discharge from the groundwater system is primarily to the Little Harpeth River and its tributaries. Groundwater flow at the disposal site is mainly to a small topographic depression that drains the site. Geochemical data indicate four distinct water types. These types represent (1) shallow, rapidly circulating groundwater; (2) deeper (> than 100 ft), rapidly circulating groundwater; (3) shallow, slow moving groundwater; and (4) deeper, slow moving groundwater. Results of the numerical model indicate that most flow is in the upper aquifer. (USGS)

Tucci, Patrick; Hanchar, D.W.; Lee, R.W.

1990-01-01

222

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01

223

Reclamation and revegetation of fly ash disposal sites - Challenges and research needs.  

PubMed

Coal-fired power generation is a principal energy source throughout the world. Approximately, 70-75% of coal combustion residues are fly ash and its utilization worldwide is only slightly above 30%. The remainder is disposed of in landfills and fly ash basins. It is desirable to revegetate these sites for aesthetic purposes, to stabilize the surface ash against wind and water erosion and to reduce the quantity of water leaching through the deposit. Limitations to plant establishment and growth in fly ash can include a high pH (and consequent deficiencies of Fe, Mn, Cu, Zn and P), high soluble salts, toxic levels of elements such as B, pozzalanic properties of ash resulting in cemented/compacted layers and lack of microbial activity. An integrated organic/biotechnological approach to revegetation seems appropriate and should be investigated further. This would include incorporation of organic matter into the surface layer of ash, mycorrhizal inoculation of establishing vegetation and use of inoculated legumes to add N. Leaching losses from ash disposal sites are likely to be site-specific but a sparse number of studies have revealed enriched concentrations of elements such as Ca, Fe, Cd, Pb, and Sb in surrounding groundwater. This aspect deserves further study particularly in the longer-term. In addition, during weathering of the ash and deposition of organic matter during plant growth, a soil will form with properties vastly different to that of the parent ash. In turn, this will influence the effect that the disposal site has on the surrounding environment. Nevertheless, the effects of ash weathering and organic matter accumulation over time on the chemical, physical and biological properties of the developing ash-derived soil are not well understood and require further study. PMID:18706753

Haynes, R J

2009-01-01

224

Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites  

Microsoft Academic Search

Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratorys proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts

A. Jeff Sondrup; Annette L. Schafter

2010-01-01

225

A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

NASA Astrophysics Data System (ADS)

For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to be evaluated in a performance assessment analysis to determine the likelihood of meeting the regulatory criteria for disposal. Sandia National Laboratories and Taiwan's Institute of Nuclear Energy Research have been working together to develop the necessary performance assessment methodology and associated computer models to perform these analyses. The methodology utilizes both deterministic (e.g., single run) and probabilistic (e.g., multiple statistical realizations) analyses to achieve the goals. The probabilistic approach provides a means of quantitatively evaluating uncertainty in the model predictions and a more robust basis for performing sensitivity analyses to better understand what is driving the dose predictions from the models. Two types of disposal configurations are under consideration: a shallow land burial concept and a cavern disposal concept. The shallow land burial option includes a protective cover to limit infiltration potential to the waste. Both conceptual designs call for the disposal of 55 gallon waste drums within concrete lined trenches or tunnels, and backfilled with grout. Waste emplaced in the drums may be solidified. Both types of sites are underlain or placed within saturated fractured bedrock material. These factors have influenced the conceptual model development of each site, as well as the selection of the models to employ for the performance assessment analyses. Several existing codes were integrated in order to facilitate a comprehensive performance assessment methodology to evaluate the potential disposal sites. First, a need existed to simulate the failure processes of the waste containers, with subsequent leaching of the waste form to the underlying host rock. The Breach, Leach, and Transport Multiple Species (BLT-MS) code was selected to meet these needs. BLT-MS also has a 2-D finite-element advective-dispersive transport module, with radionuclide in-growth and decay. BLT-MS does not solve the groundwater flow equation, but instead requires the input of Darcy flow velocity terms. These terms were abstracted from a groundwater flow model using the FEHM code. For the shallow land burial site, the HELP code was also used to evaluate the performance of the protective cover. The GoldSim code was used for two purposes: quantifying uncertainties in the predictions, and providing a platform to evaluate an alternative conceptual model involving matrix-diffusion transport. Results of the preliminary performance assessment analyses using examples to illustrate the computational framework will be presented. Sandia National Laboratories is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE AC04 94AL85000.

Knowlton, R. G.; Arnold, B. W.; Mattie, P. D.; Kuo, M.; Tien, N.

2006-12-01

226

Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)  

SciTech Connect

During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

NONE

1996-11-01

227

Detection of metal contamination in wild asparagus near a waste disposal site.  

PubMed

Estimating contaminant distributions in environmental media is necesary to evaluate human and ecological hazards. Because of uncertainties in release histories and transport, traditional sampling and statistical techniques applicable to the experimental sciences may not be suitable for exploratory studies at hazardous waste sites. An approach that relies on cluster analysis of principal components (PCA) was used to identify contaminated wild asparagus (Asparagus officinalis) growing in the vicinity of waste disposal sites along the Columbia River at the U.S. Department of Energy's Hanford Site in southeast Washington state. Metals in soil samples taken from the sites contained elevated levels of Ag, Al, Ba, Cd, Cr, Cu, Hg, Ni, Pb, Sb, Zn, and V. Samples of asparagus tissue were collected from the river near the waste site, from Hanford old fields abandoned 52 years ago, and from commercial fields in the neighboring communities. Dried tissues were analyzed for metals content by ICP-mass spectrometry, furnace AA, and cold vapor AA. Tissue concentrations of elements varied over 5 orders of magnitude, from K at 46 900 ppm to As and Ag at maximum concentrations below 1 ppm. PCA produced four components that accounted for 66.2% of the metals variance. Subsequent cluster analysis using Ward's minimum variance separated the data into Columbia River and old-field groups, with the River group further divided into three clusters: plants primarily upriver from the waste sites, plants primarily downriver, and plants growing in or near the waste sites. The clustering showed that the more soluble components of the discharges (Ba and Ca) showed a pattern of distribution in the asparagus plants consistent with the ground water flow pattern, in that these elements were found far downriver of the disposal sites themselves. In contrast, the less mobile elements Al, Cd, Cr, Fe, Mn, Tl, and Zn were elevated only near the most-recently used waste disposal area. Asparagus from agricultural fields, including fields abandoned 50 years ago, contained higher concentrations of Fe, Cu, Pb, K, and Ni than did the wild riverine plants. PMID:24193895

Brandt, C A; Rickard, W H

1996-12-01

228

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory  

SciTech Connect

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Dorries, Alison M [Los Alamos National Laboratory

2010-11-09

229

Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of the completed closure activities, to document waste disposal, and to present analytical data confirming that the remediation goals were met. The closure alternatives consisted of closure in place for two of the CASs, and no further action with implementation of best management practices (BMPs) for the remaining five CASs.

NSTec Environmental Restoration

2008-01-01

230

Application of Probabilistic Performance Assessment Modeling for Optimization of Maintenance Studies for Low-Level Radioactive Waste Disposal Sites at the Nevada Test Site  

Microsoft Academic Search

The U.S. Department of Energy (DOE), National Nuclear Security Administration of the Nevada Operations Office (NNSA\\/NV) operates and maintains two active facilities on the Nevada Test Site (NTS) that dispose defense-generated low-level radioactive waste (LLW), mixed radioactive waste, and ''classified waste'' in shallow trenches and pits. The operation and maintenance of the LLW disposal sites are self-regulated by the DOE

B. Crowe; V. Yucel; S. Rawlinson; P. Black; J. Carilli; F. DiSanza

2002-01-01

231

Meeting performance objectives for Low-Level Radioactive Disposal Waste Facility at the Savannah River Site  

SciTech Connect

A new Low-Level Radioactive Waste (LLW) disposal facility at the Savannah River Site is presently being constructed. The facility was designed to meet specific performance objectives (derived from DOE Order 5820.2A and proposed EPA Regulation 40CFR 193) in the disposal of containerized Class A and B wastes. The disposal units have been designed as below-grade concrete vaults. These vaults will be constructed using uniquely designed blast furnace slag + fly as concrete mix, surrounded by a highly permeable drainage layer, and covered with an engineered clay cap to provide the necessary environmental isolation of the waste form to meet the stated performance objectives. The concrete mix used in this facility, is the first such application in the United States. These vaults become operational in September 1992 and will become the first active facility of its kind, several years ahead of those planned in the commercial theater. This paper will discuss the selection of the performance objectives and conceptual design.

Taylor, G.E.

1992-01-01

232

Meeting performance objectives for Low-Level Radioactive Disposal Waste Facility at the Savannah River Site  

SciTech Connect

A new Low-Level Radioactive Waste (LLW) disposal facility at the Savannah River Site is presently being constructed. The facility was designed to meet specific performance objectives (derived from DOE Order 5820.2A and proposed EPA Regulation 40CFR 193) in the disposal of containerized Class A and B wastes. The disposal units have been designed as below-grade concrete vaults. These vaults will be constructed using uniquely designed blast furnace slag + fly as concrete mix, surrounded by a highly permeable drainage layer, and covered with an engineered clay cap to provide the necessary environmental isolation of the waste form to meet the stated performance objectives. The concrete mix used in this facility, is the first such application in the United States. These vaults become operational in September 1992 and will become the first active facility of its kind, several years ahead of those planned in the commercial theater. This paper will discuss the selection of the performance objectives and conceptual design.

Taylor, G.E.

1992-04-01

233

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

USGS Publications Warehouse

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

Bedinger, M.S.

1989-01-01

234

Physical oceanographic processes at candidate dredged-material disposal sites B1B and 1M offshore San Francisco  

SciTech Connect

The US Army Corps of Engineers (USACE), San Francisco District, has identified two candidate sites for ocean disposal of material from several dredging projects in San Francisco Bay. The disposal site is to be designated under Section 103 of the Ocean Dumping Act. One of the specific criteria in the Ocean Dumping Act is that the physical environments of the candidate sites be considered. Toward this goal, the USACE requested that the Pacific Northwest Laboratory conduct a study of physical oceanographic and sediment transport processes at the candidate sites, B1B and 1M. The results of that study are presented in this report. 40 refs., 27 figs., 10 tabs.

Sherwood, C.R.; Denbo, D.W.; Downing, J.P. (Pacific Northwest Lab., Richland, WA (USA)); Coats, D.A. (Marine Research Specialists, Ventura, CA (USA))

1990-10-01

235

Leachate migration from a pesticide waste disposal site in Hardeman County, Tennessee  

USGS Publications Warehouse

Between 1964 and 1972, approximately 300,000 drums (55-gallon steel barrels) of waste derived from the manufacturing of pesticides were buried on 45 acres of land in northern Hardemen County, Tennessee. Leachates from these wastes are migrating from the disposal site in surface runoff, through shallow perched water zones, and through the local water-table aquifer. Compounds identified in the leachates included: dieldrin, endrin , chlordene, heptachlor, heptachlor epoxide, pentachlorocyclopentadiene, and hexachloro-bicycloheptadiene. The rate of migration of some of the leachate compounds in the water-table aquifer was found to be at least 80 feet per year. (Woodard-USGS)

Sprinkle, C.L.

1978-01-01

236

CLASSIFICATION OF THE MGR SITE-GENERATED HAZAROUS NONHAZARDOUS & SANITARY WASTE DISPOSAL SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site generated hazardous, non-hazardous and sanitary waste disposal system system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

J.A. Ziegler

1999-08-31

237

Probabilistic Performance Assessment of a Low-Level Radioactive Waste Disposal Site on the Nevada Test Site  

SciTech Connect

The Area 5 Radioactive Waste Management Site on the Nevada Test Site has been disposing of low-level, mixed low-level, and transuranic radioactive waste since 1961. In 1988, the U.S. Department of Energy implemented performance objectives for low-level radioactive waste disposal site performance and required all site operators to prepare a performance assessment. Since then, an iterative performance assessment process has been implemented that consists of repeated cycles of site characterization, conceptual model formation/revision, and performance assessment modeling. At the end of each cycle uncertainty and sensitivity analysis are used to determine the need for revision and to identify topics requiring additional research and development. The performance assessment model is implemented in the GoldSim{reg_sign} probabilistic simulation platform. The current site conceptual model, based on site characterization data and process model results, assumes that there is no groundwater pathway under current climatic conditions and that radionuclide releases are predominately upward to the land surface. Radionuclides are released to the land surface by upward liquid advection/diffusion, gas diffusion, biointrusion, and inadvertent human intrusion. The model calculates dose for four members of public exposure scenarios and two intruder scenarios. The highest mean-dose, 0.04 mSv yr{sup -1}, is expected for a low-probability exposure scenario: establishment of a rural community at the site boundary at the end of institutional control. At the end of institutional control, doses are contributed primarily by {sup 3}H in agricultural products produced onsite. After approximately 300 years, the doses are contributed equally by {sup 99}Tc and {sup 210}Pb ingested in vegetables grown at the residence. Technetium is released to the surface by the coupled processes of liquid advection/diffusion occurring deep in the cover and plant uptake/animal burrowing occurring at shallower depths. Lead-210 is deposited in shallow cover soil by the radioactive decay of {sup 222}Rn diffusing in the gas phase. The highest mean dose for the more likely exposure scenario of transient recreational use of the site is 0.002 mSv yr{sup -1}. The transient visitor's dose is contributed predominantly by external irradiation from {sup 214}Pb and {sup 214}Bi, deposited in the cover by diffusion of {sup 222}Rn.

G. J. Shott; V. Yucel; L. T. Desotell

2008-03-01

238

Feasibility study for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 plant, Oak Ridge, Tennessee  

SciTech Connect

In July 1990, the US Environmental Protection Agency (EPA) directed the Department of Energy Oak Ridge Operations to comply with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements for the remediation of the United Nuclear Corporation (UNC) Disposal Site located at the Y-12 Plant, Oak Ridge, Tennessee. EPA, Waste Management Branch, had approved a closure plan in December 1989 for the UNC Disposal Site. This feasibility study (FS) is a fully satisfy the National Oil and Hazardous Substances Contingency Plan (NCP) requirements for support of the selection of a remedial response for closure of the UNC Disposal Site. For two years the UNC Disposal Site accepted and disposed of waste from the decommissioning of a UNC uranium recovery facility in Wood River Junction, Rhode Island. Between June 1982 and November 1984, the UNC Disposal Site received 11,000 55-gal drums of sludge fixed in cement, 18,000 drums of contaminated soil, and 288 wooden boxes of contaminated building and process demolition materials. The FS assembles a wide range of remedial technologies so the most appropriate actions could be selected to remediate potential contamination to below MCLs and/or to below the maximum level of acceptable risk. Technologies were evaluated based on technical effectiveness, ease of implementation, and costs. Applicable technologies were then selected for alternative development. 33 refs., 9 figs., 27 tabs.

Not Available

1991-02-01

239

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

PubMed

The main aim of this study was to develop a procedure that minimizes the wasting of space for the siting of hazardous waste landfills as part of a solid waste management system. We wanted to tackle the shortage of land for waste disposal that is a serious and growing problem in most large urban regions. The procedure combines a multi-criteria decision analysis (MCDA) approach with a geographical information system (GIS). The GIS was utilised to obtain an initial screening in order to eliminate unsuitable areas, whereas the MCDA was developed to select the most suitable sites. The novelty of the proposed siting procedure is the introduction of a new screening phase before the macro-siting step aimed at producing a "land use map of potentially suitable areas" for the siting of solid waste facilities which simultaneously takes into consideration all plant types. The issue of obtaining sites evaluations of a specific facility was coupled with the issue of not wasting land appropriate to facilitate other types of waste management options. In the developed case study, the use of an innovative criteria weighting tool (the "Priority Scale") in combination with the Analytic Hierarchy Process was useful to easier define the priorities of the evaluation criteria in comparison with other classic methods such as the Paired Comparison Technique in combination with the Simple Additive Weighting method. PMID:25002369

De Feo, Giovanni; De Gisi, Sabino

2014-11-01

240

APPLICATION OF A HAZARD-ASSESSMENT RESEARCH STRATEGY FOR WASTE DISPOSAL AT 106-MILE OCEAN DISPOSAL SITE  

EPA Science Inventory

An application of a hazard-assessment research strategy was made using waste disposal at Deepwater Dumpsite-l06 (DWD-106) as an example. The strategy involved the synthesis of results from separate exposure and effects components in order to provide a scientific basis for estimat...

241

US DOE-EM On-Site Disposal Cell Working Group - Fostering Communication On Performance Assessment Challenges  

SciTech Connect

On-site disposal cells are in use and being considered at several U.S. Department of Energy (USDOE) sites as the final disposition for large amounts of waste associated with cleanup of contaminated areas and facilities. These facilities are typically developed with regulatory oversight from States and/or the US Environmental Protection Agency (USEPA) in addition to USDOE. The facilities are developed to meet design standards for disposal of hazardous waste as well as the USDOE performance based standards for disposal of radioactive waste. The involvement of multiple and different regulators for facilities across separate sites has resulted in some differences in expectations for performance assessments and risk assessments (PA/RA) that are developed for the disposal facilities. The USDOE-EM Office of Site Restoration formed a working group to foster improved communication and sharing of information for personnel associated with these Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) disposal cells and work towards more consistent assumptions, as appropriate, for technical and policy considerations related to performance and risk assessments in support of a Record of Decision and Disposal Authorization Statement. The working group holds teleconferences, as needed, focusing on specific topics of interest. The topics addressed to date include an assessment of the assumptions used for performance assessments and risk assessments (PA/RAs) for on-site disposal cells, requirements and assumptions related to assessment of inadvertent intrusion, DOE Manual 435.1-1 requirements, and approaches for consideration of the long-term performance of liners and covers in the context of PAs. The working group has improved communication among the staff and oversight personnel responsible for onsite disposal cells and has provided a forum to identify and resolve common concerns.

Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States); Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, Germantown, MD (United States); Phifer, Mark [Savannah River Site (SRS), Aiken, SC (United States)

2014-03-01

242

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

2008-03-01

243

Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 543: Liquid Disposal Units is listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO) which was agreed to by the state of Nevada, the U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). CAU 543 sites are located in Areas 6 and 15 of the Nevada Test Site (NTS), which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven Corrective Action Sites (CASs) (Figure 1): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; and CAS 15-23-03, Contaminated Sump, Piping. All Area 15 CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm, which operated from 1963 to 1981 and was used to support animal experiments involving the uptake of radionuclides. Each of the Area 15 CASs, except CAS 15-23-01, is associated with the disposal of waste effluent from Building 15-06, which was the primary location of the various tests and experiments conducted onsite. Waste effluent disposal from Building 15-06 involved piping, sumps, outfalls, a septic tank with leachfield, underground storage tanks, and an aboveground storage tank (AST). CAS 15-23-01 was associated with decontamination activities of farm equipment potentially contaminated with radiological constituents, pesticides, and herbicides. While the building structures were removed before the investigation took place, all the original tanks, sumps, piping, and concrete building pads remain in place. The Area 6 CAS is located at the Decontamination Facility in Area 6, a facility which operated from 1971 to 2001 and was used to decontaminate vehicles, equipment, clothing, and other materials that had become contaminated during nuclear testing activities. The CAS includes the effluent collection and distribution systems for Buildings 6-605, 6-606, and 6-607, which consists of septic tanks, sumps, piping, floor drains, drain trenches, cleanouts, and a concrete foundation. Additional details of the site history are provided in the CAU 543 Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2004a), and the CAU 543 Corrective Action Decision Document (CADD) (NNSA/NSO, 2005).

NSTec Environmental Restoration

2007-04-01

244

Dose and risk assessment for intrusion into mixed waste disposal sites  

SciTech Connect

Sites previously used for disposal of radioactive and hazardous chemical materials have resulted in situations that pose a potential threat to humans from inadvertent intrusion. An example generic scenario analysis was developed to demonstrate the evaluation of potential exposure to either cleanup workers or members of the public who intrude into buried waste containing both radioactive and hazardous chemical contaminants. The example scenarios consist of a collection of exposure routes (or pathways) with specific modeling assumptions for well-drilling and for excavation to construct buildings. These scenarios are used to describe conceptually some potential patterns of activity by non-protected human beings during intrusion into mixed-waste disposal sites. The dose from exposure to radioactive materials is calculated using the GENII software system and converted to risk by using factors from ICRP Publication 60. The hazard assessment for nonradioactive materials is performed using recent guidelines from the US Environmental Protection Agency (EPA). The example results are in the form of cancer risk for carcinogens and radiation exposure.

Kennedy, W.E. Jr.; Aaberg, R.L.

1991-10-01

245

Greenhouse gas emission potential of the municipal solid waste disposal sites in Thailand.  

PubMed

Open dumping and landfilling are the prevalent solid waste disposal practices in Thailand. Surveys on the disposal sites revealed the presence of 95 landfills and 330 open dumps. Methane emission potential at these sites was estimated by three methods. Results of the Intergovernmental Panel on Climate Change (IPCC) method, Landfill Gas Emission model (LandGEM), and closed flux chamber technique were compared. The methane emission potential of 366 Gg/yr using the IPCC method was higher than the estimations of the LandGEM and closed flux chamber method of 115 Gg/yr and 103 Gg/yr, respectively. An understanding of the methane emission potential initiated the analysis of upgrading the open dumps into landfills, adding landfills to meet the future needs and utilization of landfill gases. Upgrading the open dumps to landfills increased the methane emission rates and their utilization potential. Approximately 20 additional landfills may be required to meet future demands. Landfill gas (LFG) utilization appears to be feasible in the large-scale landfills. PMID:18512439

Chiemchaisri, Chart; Visvanathan, Chettiyappan

2008-05-01

246

Methods for estimating on-site ambient air concentrations at disposal sites  

Microsoft Academic Search

Currently, Gaussian type dispersion modeling and point source approximation are combined to estimate the ambient air concentrations of pollutants dispersed downwind of an areawide emission source, using the approach of virtual point source approximation. This Gaussian dispersion modeling becomes less accurate as the receptor comes closer to the source, and becomes inapplicable for the estimation of on-site ambient air concentrations

S. T. Hwang

1987-01-01

247

Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory  

SciTech Connect

This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau.

Reneau, S.L.; Raymond, R. Jr. [eds.

1995-12-01

248

Navajo coal and air quality in Shiprock, New Mexico  

USGS Publications Warehouse

Among the Navajo people, high levels of respiratory disease, such as asthma, exist in a population with low rates of cigarette smoking. Air quality outdoors and indoors affects respiratory health. Many Navajo Nation residents burn locally mined coal in their homes for heat, as coal is the most economical energy source. The U.S. Geological Survey and Dine College, in cooperation with the Navajo Division of Health, are conducting a study in the Shiprock, New Mexico, area to determine if indoor use of this coal might be contributing to some of the respiratory health problems experienced by the residents. Researchers in this study will (1) examine respiratory health data, (2) identify stove type and use, (3) analyze samples of coal that are used locally, and (4) measure and characterize air quality inside selected homes. This Fact Sheet summarizes the interim results of the study in both English and Navajo. This Fact Sheet is available in three versions: * English [800-KB PDF file ] * Navajo [computer must have Navajo language fonts installed - 304-KB PDF file] * Image of the Navajo language version [19.8-MB PDF file

Bunnell, Joseph E.; Garcia, Linda V.

2006-01-01

249

Study of contaminant transport at an open-tipping waste disposal site.  

PubMed

Field and laboratory studies were conducted to estimate concentration of potential contaminants from landfill in the underlying groundwater, leachate, and surface water. Samples collected in the vicinity of the landfill were analyzed for physiochemical parameters, organic contaminants, and toxic heavy metals. Water quality results obtained were compared from published data and reports. The results indicate serious groundwater and surface water contamination in and around the waste disposal site. Analysis of the organic samples revealed that the site contains polychlorinated biphenyls and other organo-chlorine chemicals, principally chloro-benzenes. Although the amount of PCB concentration discovered was not extreme, their presence indicates a potentially serious environmental threat. Elevated concentrations of lead, copper, nickel, manganese, cadmium, and cobalt at the downgradient indicate that the contamination plume migrated further from the site, and the distribution of metals and metals containing wastes in the site is nonhomogeneous. These results clearly indicate that materials are poorly contained and are at risk of entering the environment. Therefore, full characterization of the dump contents and the integrity of the site are necessary to evaluate the scope of the problem and to identify suitable remediation options. PMID:23292199

Ashraf, Muhammad Aqeel; Yusoff, Ismail; Yusof, Mohamad; Alias, Yatimah

2013-07-01

250

Slope and bank erosional stability of the Canonsburg, Pennsylvania, UMTRA disposal site  

SciTech Connect

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.

Not Available

1994-12-01

251

Development and comparison of five site-specific biosphere models for safety assessment of radioactive waste disposal  

Microsoft Academic Search

This paper describes the development and application of site-specific biosphere models that might be used for assessment of potential exposures in the framework of performance assessment studies of nuclear waste disposals. Model development follows the Reference Biosphere Methodology that has been set up in the framework of the BIOMASS study. In this paper, the application is to real sites at

G. Prhl; G. Olyslaegers; B. Kanyar; P. Pinedo; U. Bergstrm; S. Mobbs; K. Eged; T. Katona; I. Simn; U. B. Hallberg; Q. Chen; R Kowe; T. Zeevaert

2005-01-01

252

Geotechnical, geological, and selected radionuclide retention characteristics of the radioactive waste disposal site near the Farallon Islands  

USGS Publications Warehouse

A geotechnical and geological investigation of the Farallon Islands low-level radioactive waste (LLW) disposal area was conducted to qualitatively assess the host sediments' relative effectiveness as a barrier to radionuclide migration, to estimate the portion of the barrier that is in contact with the waste packages at the three primary disposal sites, and to provide a basic physical description of the sediments. Box cores recovered from within the general disposal area at depths of 500, 1000, and 1500 m were subcored to provide samples (~30 cm in length) for detailed descriptions, textural and mineralogical analyses, and a suite of geotechnical tests (index property, CRS consolidation, and CIU triaxial compression). -from Authors

Booth, J.S.; Winters, W.J.; Poppe, L.J.; Neiheisel, J.; Dyer, R.S.

1989-01-01

253

Definition of intrusion scenarios and example concentration ranges for the disposal of near-surface waste at the Hanford Site  

SciTech Connect

The US Department of Energy (DOE) is in the process of conducting performance assessments of its radioactive waste sites and disposal systems to ensure that public health and safety are protected, the environment is preserved, and that no remedial actions after disposal are required. Hanford Site low-level waste performance assessments are technical evaluations of waste sites or disposal systems that provide a basis for making decisions using established criteria. The purpose of this document is to provide a family of scenarios to be considered when calculating radionuclide exposure to individuals who may inadvertently intrude into near-surface waste disposal sites. Specific performance assessments will use modifications of the general scenarios described here to include additional site/system details concerning the engineering design, waste form, inventory, and environmental setting. This document also describes and example application of the Hanford-specific scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. 24 refs., 2 figs., 5 tabs.

Aaberg, R.L.; Kennedy, W.E. Jr.

1990-10-01

254

Interpretation and Modelling of Data from Site Investigations for a Geological Disposal facility located in the UK  

NASA Astrophysics Data System (ADS)

The Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) has been given the responsibility for implementing geological disposal in the United Kingdom. The implementation process envisaged is that once a candidate site or sites for a geological disposal facility have been identified, NDA-RWMD will undertake surface-based investigations at the site or sites. The information acquired through these investigations would be used as an input to the development of the safety case, for engineering design of the disposal facility and to demonstrate confidence to the key stakeholders that the potential disposal facility site is adequately understood. NDA-RWMD proposes to develop and present the information derived from site characterisation activities in the form of a single integrated Site Descriptive Model, i.e. a description of the geometry, properties of the bedrock and water, and the associated interacting processes and mechanisms, which will be used to address the information requirements of all the end users (including the safety case). It is anticipated that, in a similar way to the approach adopted by international radioactive waste programmes led by SKB (Sweden) and Posiva (Finland), the integrated Site Descriptive Model will be divided into parts comprising clearly defined disciplines which may form either chapters or discipline-based models such as: Geology; Hydrogeology; Hydrochemistry; Geotechnical; Radionuclide Transport Properties; Thermal Properties; and Biosphere. The integrated Site Descriptive Model will evolve as understanding of the particular site advances and will describe the current understanding of a specific site and, where relevant, the historical development of conditions at the site where this supports the conceptual understanding. The Site Descriptive Model will not include prediction of the future evolution of the conditions at the site: this will be an important component of the safety assessment within the environmental safety case. In preparing for these surface-based investigations at a site or sites, NDA-RWMD has explored the processes and tools that have been used in overseas radioactive waste management programmes for processing, interpreting and modelling the various data acquired through site characterisation. This research will inform the scope and approach to site characterisation proposed by NDA-RWMD when a site(s) is selected for a geological disposal facility in the future. This paper discusses the work that has been undertaken to increase the understanding for the interpretation and modelling for each of the Site Descriptive Model disciplines identified. Where appropriate reference will be made to experience from other international radioactive waste management programmes.

Clark, H.; Bailey, L.; Parkes, A.

2012-04-01

255

Long-Term Performance of Uranium Tailings Disposal Cells - 13340  

SciTech Connect

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 hydraulic conductivity after transient drainage, eventually the amount of moisture leaving the tailings has a negligible effect on groundwater quality. Although some of the UMTRA sites are not in compliance with the groundwater standards, the explanation may be legacy contamination from mining, or earlier higher fluxes from the tailings or unlined processing ponds. Investigation of other legacy sources at the UMTRA sites may help explain persistent groundwater contamination. (authors)

Bostick, Kent; Daniel, Anamary; Pill, Ken [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States)] [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)] [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)

2013-07-01

256

Impact of Construction Waste Disposal Charging Scheme on work practices at construction sites in Hong Kong  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer A significant reduction of construction waste was achieved at the first 3 years of CWDCS implementation. Black-Right-Pointing-Pointer However, the reduction cannot be sustained. Black-Right-Pointing-Pointer Implementation of the CWDCS has generated positive effects in waste reduction by all main trades. - Abstract: Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C and D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C and D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C and D waste.

Yu, Ann T.W., E-mail: bsannyu@polyu.edu.hk [Department of Building and Real Estate, The Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong); Poon, C.S.; Wong, Agnes; Yip, Robin; Jaillon, Lara [Department of Civil and Structural Engineering, Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong)

2013-01-15

257

Impact of Construction Waste Disposal Charging Scheme on work practices at construction sites in Hong Kong.  

PubMed

Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C&D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C&D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C&D waste. PMID:23122205

Yu, Ann T W; Poon, C S; Wong, Agnes; Yip, Robin; Jaillon, Lara

2013-01-01

258

Corrective Action Plan for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 543, Liquid Disposal Units, is listed in Appendix III of the Federal Facility Agreement and Consent Order of 1996. CAU 543 consists of seven Corrective Action Sites (CASs) located in Areas 6 and 15 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. CAU 543 consists of the following seven CASs: {sm_bullet} CAS 06-07-01, Decon Pad {sm_bullet} CAS 15-01-03, Aboveground Storage Tank {sm_bullet} CAS 15-04-01, Septic Tank {sm_bullet} CAS 15-05-01, Leachfield {sm_bullet} CAS 15-08-01, Liquid Manure Tank {sm_bullet} CAS 15-23-01, Underground Radioactive Material Area {sm_bullet} CAS 15-23-03, Contaminated Sump, Piping From January 24, 2005 through April 14, 2005, CAU 543 site characterization activities were conducted, and are reported in Appendix A of the CAU 543 Corrective Action Decision Document (CADD) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2005). The recommended corrective action as stated in the approved CADD is No Further Action for five of the CAU 543 CASs, and Closure In Place for the remaining two CASs.

NSTec Environmental Restoration

2006-09-01

259

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

SciTech Connect

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

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

2013-07-01

260

Technical Scope and Approach for the 2004 Composite Analysis of Low Level Waste Disposal at the Hanford Site  

SciTech Connect

A composite analysis is required by U.S. Department of Energy (DOE) Manual 435.1-1 to ensure public safety through the management of active and planned low-level radioactive waste disposal facilities associated with the Hanford Site (DOE/HQ-Manual 435.1-1). A Composite Analysis is defined as ''a reasonably conservative assessment of the cumulative impact from active and planned low-level waste disposal facilities, and all other sources from radioactive contamination that could interact with the low-level waste disposal facility to affect the dose to future members of the public''. At the Hanford Site, a composite analysis is required for continued disposal authorization for the immobilized low-activity waste, tank waste vitrification plant melters, low level waste in the 200 East and 200 West Solid Waste Burial Grounds, and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) waste in the Environmental Restoration Disposal Facility. The 2004 Composite Analysis will be a site-wide analysis, considering final remedial actions for the Columbia River corridor and the Central Plateau at the Hanford Site. The river corridor includes waste sites and facilities in each of the 100 Areas as well as the 300, 400, and 600 Areas. The remedial actions for the river corridor are being conducted to meet residential land use standards with the vision of the river corridor being devoted to a combination of recreation and preservation. The ''Central Plateau'' describes the region associated with operations and waste sites of the 200 Areas. DOE is developing a strategy for closure of the Central Plateau area by 2035. At the time of closure, waste management activities will shrink to a Core Zone within the Central Plateau. The Core Zone will contain the majority of Hanford's permanently disposed waste

Kincaid, Charles T.; Bryce, Robert W.; Buck, John W.

2004-07-09

261

Microbial activity of trench leachates from shallow-land, low-level radioactive waste disposal sites.  

PubMed Central

Trench leachate samples collected anoxically from shallow-land, low-level radioactive waste disposal sites were analyzed for total aerobic and anaerobic populations, sulfate reducers, denitrifiers, and methanogens. Among the several aerobic and anaerobic bacteria isolated, only Bacillus sp., Pseudomonas sp., Citrobacter sp., and Clostridium sp. were identified. Mixed bacterial cultures isolated from the trench leachates were able to grow anaerobically in trench leachates, which indicates that the radionuclides and organic chemicals present were not toxic to these bacteria. Changes in concentrations of several of the organic constituents of the waste leachate samples were observed due to anaerobic microbial activity. Growth of a mixed culture of trench-water bacteria in media containing a mixture of radionuclides, 60Co, 85Sr, and 134,137Cs, was not affected at total activity concentrations of 2.6 X 10(2) and 2.7 X 10(3) pCi/ml. PMID:7406490

Francis, A J; Dobbs, S; Nine, B J

1980-01-01

262

DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE  

SciTech Connect

Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

2011-01-13

263

Microbiology of a coal-tar disposal site: A preliminary assessment  

SciTech Connect

This report contains results of microbiological characterization of a buried coal-tar disposal site located in the Northeastern United States. Objectives were: (1) Collect aquifer sediment samples at various depths from several locations and measure the abundance of microorganisms. (2) Conduct laboratory experiments to examine microbial mineralization of polyaromatic hydrocarbon components of the coal tar (phenanthrene and naphthalene). (3) Correlate the physical and chemical properties of the sediments with the abundance of microorganisms and their biodegradation activity. These objectives were addressed experimentally by combining measurements of site characteristics (coal-tar constituents, temperature, pH, oxygen and nutrient levels, and particle size analysis) with microbiological assays performed on sediments sampled from both inside and outside of the groundwater plume on three occasions (June 1988; April 1989, and September 1989). The microorganisms present and their abundance and distribution generally resembled those at other, previously examined, shallow aquifer sites. Regardless of proximity to the contaminant plume, p-hydroxybenzoate mineralization was observed in sediments from unsaturated, water table, and saturated zone depths. By contrast, up to approximately 20% of the naphthalene and phenanthrene were mineralized by microorganisms in samples from inside, but not outside, the plume area. Increased numbers of protozoa found within the plume area coincided with higher rates of mineralization activity. 24 refs., 3 figs., 20 tabs.

Madsen, E.L.; Levine, S.N.; Ghiorse, W.C. (Cornell Univ., Ithaca, NY (USA). Dept. of Microbiology)

1991-07-01

264

Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada  

SciTech Connect

Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation`s first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey`s continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base.

Carr, M.D.; Yount, J.C. (eds.)

1988-12-31

265

1995 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites  

SciTech Connect

Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in US. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included are tables showing the distribution of waste by state for 1995 and a comparison of waste volumes and radioactivity by state for 1991 through 1995; also included is a list of all commercial nuclear power reactors in US as of Dec. 31, 1994. This report distinguishes low-level radioactive waste shipped directly for disposal by generators and waste handled by an intermediary.

Fuchs, R.L.

1996-09-01

266

Corrective Action Decision Document/Closure Report for Corrective Action Unit 137: Waste Disposal Sites, Nevada Test Site, Nevada (Revision 0) with ROTC 1 and 2  

SciTech Connect

The purpose of this Corrective Action Decision Document/Closure Report is to provide justification and documentation supporting the recommendation for closure of CAU 137 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from February 28 through August 17, 2006, as set forth in the Corrective Action Investigation Plan for Corrective Action Unit 137: Waste Disposal Sites. The purpose of the CAI was to fulfill the following data needs as defined during the data quality objective process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. ROTC-1: Downgrade FFACO UR at CAU 137, CAS 07-23-02, Radioactive Waste Disposal Site to an Administrative UR. ROTC-2: Downgrade FFACO UR at CAU 137, CAS 01-08-01, Waste Disposal Site to an Administrative UR.

Krauss, Mark J

2007-03-01

267

A model for intrusion dose calculations for radioactive waste disposal sites  

Microsoft Academic Search

Safe management and disposal of radioactive waste is one of the main problems for nuclear energy, both for fission or fusion sources. High-level waste from nuclear reactors will have to be disposed of in deep underground repositories. The main purpose of this disposal, from the safety viewpoint, is to avoid the return of the radioactive waste into the biosphere, with

M. Zucchetti; P. Rocco

1999-01-01

268

Post-Closure Inspection Report for Corrective Action Unit 333: U-3auS Disposal Site Annual Report, Nevada Test Site, Nevada  

Microsoft Academic Search

The U-3auS Disposal Site Corrective Action Unit (CAU) 333 is a closed construction landfill located in Area 3 of the Nevada Test Site. The closure of this site was approved by the Nevada Division of Environmental Protection (NDEP) in a letter to the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA\\/NV) dated June 27, 2001. Post-closure

K. K. Knapp

2003-01-01

269

Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

Alfred Wickline

2007-06-01

270

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong  

NASA Astrophysics Data System (ADS)

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr+ ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10-2 g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Setiawan, Budi; Mila, Oktri; Safni

2014-03-01

271

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong  

SciTech Connect

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup ?2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Setiawan, Budi, E-mail: bravo@batan.go.id [Radwaste Technology Center-National Nuclear Energy Agency, PUSPIPTEK, Serpong-Tangerang 15310 (Indonesia); Mila, Oktri; Safni [Dept. of Chemistry, Fac. of Math. and Nat. Sci., Andalas University, Kampus Limau Manis, Padang-West Sumatra 25163 (Indonesia)

2014-03-24

272

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site  

SciTech Connect

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here. Parameters necessary for estimating surface contaminant flux due to native plants expected to inhabit the NTS RWMSS are developed in this report. The model is specific to the plant communities found at the NTS and is designed for both short-term (<1,000 years) and long-term (>1,000 years) modeling efforts. While the model has been crafted for general applicability to any NTS PA, the key radionuclides considered are limited to the transuranic (TRU) wastes disposed of at the NTS.

BROWN,THERESA J.; WIRTH,SHARON

1999-09-01

273

Final Environmental Assessment for solid waste disposal, Nevada Test Site, Nye County, Nevada  

SciTech Connect

New solid waste regulations require that the existing Nevada Test Site (NTS) municipal landfills, which receive less than 20 tons of waste per day, be permitted or closed by October 9, 1995. In order to be permitted, the existing landfills must meet specific location, groundwater monitoring, design, operation, and closure requirements. The issuance of these regulations has resulted in the need of the Department of Energy (DOE) to provide a practical, cost-effective, environmentally sound means of solid waste disposal at the NTS that is in compliance with all applicable federal, state, and local regulations. The current landfills in Areas 9 and 23 on the Nevada Test Site do not meet design requirements specified in new state and federal regulations. The DOE Nevada Operations Office prepared an environmental assessment (EA) to evaluate the potential impacts of the proposal to modify the Area 23 landfill to comply with the new regulations and to close the Area 9 landfill and reopen it as Construction and Demolition debris landfill. Based on information and analyses presented in the EA, DOE has determined that the proposed action would not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act. Therefore, an environmental impact statement (EIS) is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

NONE

1995-08-01

274

Long-Term Performance of Transuranic Waste Inadvertently Disposed in a Shallow Land Burial Trench at the Nevada Test Site  

SciTech Connect

In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes. The Waste Isolation Pilot Plant is the only facility meeting these requirements. The National Research Council, however, has found that exhumation of buried TRU waste for disposal in a deep geologic repository may not be warranted when the effort, exposures, and expense of retrieval are not commensurate with the risk reduction achieved. The long-term risks of leaving the TRU waste in-place are evaluated in two probabilistic performance assessments. A composite analysis, assessing the dose from all disposed waste and interacting sources of residual contamination, estimates an annual total effective dose equivalent (TEDE) of 0.01 mSv, or 3 percent of the dose constraint. A 40 CFR 191 performance assessment also indicates there is reasonable assurance of meeting all requirements. The 40 CFR 191.15 annual mean TEDE for a member of the public is estimated to reach a maximum of 0.055 mSv at 10,000 years, or approximately 37 percent of the 0.15 mSv individual protection requirement. In both assessments greater than 99 percent of the dose is from co-disposed low-level waste. The simulated probability of the 40 CFR 191.13 cumulative release exceeding 1 and 10 times the release limit is estimated to be 0.0093 and less than 0.0001, respectively. Site characterization data and hydrologic process modeling support a conclusion of no groundwater pathway within 10,000 years. Monte Carlo uncertainty analysis indicates that there is reasonable assurance of meeting all regulatory requirements. Sensitivity analysis indicates that the results are insensitive to TRU waste-related parameters. Limited quantities of TRU waste in a shallow land burial trench can meet DOE performance objectives for disposal of TRU waste and contribute negligibly to disposal site risk. Leaving limited quantities of buried TRU waste in-place may be preferred over retrieval for disposal in a deep geologic repository.

Gregory J. Shott; Vefa Yucel

2009-07-16

275

1994 Report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) Milestone M-26-00 (Ecology et al. 1992). The text of this milestone is below. LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the US Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration at other action plan milestones and will not become effective until approved by the US Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: waste characterization plan; storage report; treatment report; treatment plan; waste minimization plan; a schedule depicting the events necessary to achieve full compliance with LDR requirements; a process for establishing interim milestones. The original plan was published in October 1990. This is the fourth of a series of annual updates required by Tri-Party Agreement Milestone M-26-01. A Tri-Party Agreement change request approved in March 1992 changed the annual due date from October to April and consolidated this report with a similar one prepared under Milestone M-25-00. The reporting period for this report is from April 1, 1993, to March 31, 1994.

Black, D.G.

1994-04-01

276

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations  

SciTech Connect

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Waters, R.D.; Gruebel, M.M. [eds.] [eds.

1996-03-01

277

Problems of site selection for nuclear waste disposal in a loess-covered hill environment in Hungary  

Microsoft Academic Search

Problems of the long-term storage of nuclear waste produced by the Paks power plant have recently come to the fore in Hungary. After an extensive debate between investors and the local population the decision makers took the side of those having opposed the establishment of the waste disposal site in the initially proposed environment. Several studies have been conducted to

Jnos Balogh; Ferenc Schweitzer; Tibor Tiner

1995-01-01

278

Faecal contamination of watercourses from farm waste disposal for three sites in the UK with contrasting soil  

E-print Network

Faecal contamination of watercourses from farm waste disposal for three sites in the UK), primarily due to investment in secondary sewage treatment works. In 2003, 98.8% of UK bathing waters sewage treatment has been made (Wyer et al. 1996; Kay et al. 1999). Also, the proportion of compliant

Owens, Philip

279

Health effects of hazardous chemical waste disposal sites in New Jersey and in the United States: a review  

SciTech Connect

The hazardous chemical waste disposal issue is a widespread problem. Large quantities of chemical wastes have been produced by the chemical industries in the past forty years. Estimates now number disposal sites in the United States at least 30,000. The public and scientists have grown increasingly concerned about the effects of these waste disposal sites not only on the environment, but also on the human body. In this article, we review the number of hazardous chemical waste disposal sites (HCWDS), their construction, difficulties in defining their contents, and the establishment of the Superfund Act. We then discuss various studies in the literature that have attempted to define adverse health effects of HCWDS, particularly those examining Love Canal and sites in New Jersey. In our conclusions, we note the difficulties in establishing direct causal links between HCWDS and dangerous health effects. We suggest that more epidemiological studies are needed, with improved methodology for gathering complete data and studying large samples. Both positive and negative findings of epidemiological studies are important. Positive results will substantiate an association of health effects with HCWDS. Negative results may reduce the concerns of people living near HCWDS. Future investigators need sufficient information about HCWDS materials, possible routes of exposure, and measurements of exposure, as well as sufficient statistical power to detect even modest associations of health effects with HCWDS exposure.71 references.

Najem, G.R.; Cappadona, J.L. (Department of Preventive Medicine and Community Health, New Jersey Medical School, University of Medicine and Dentistry of New Jersey, Newark (United States))

1991-11-01

280

Health effects of hazardous chemical waste disposal sites in New Jersey and in the United States: a review.  

PubMed

The hazardous chemical waste disposal issue is a widespread problem. Large quantities of chemical wastes have been produced by the chemical industries in the past forty years. Estimates now number disposal sites in the United States at least 30,000. The public and scientists have grown increasingly concerned about the effects of these waste disposal sites not only on the environment, but also on the human body. In this article, we review the number of hazardous chemical waste disposal sites (HCWDS), their construction, difficulties in defining their contents, and the establishment of the Superfund Act. We then discuss various studies in the literature that have attempted to define adverse health effects of HCWDS, particularly those examining Love Canal and sites in New Jersey. In our conclusions, we note the difficulties in establishing direct causal links between HCWDS and dangerous health effects. We suggest that more epidemiological studies are needed, with improved methodology for gathering complete data and studying large samples. Both positive and negative findings of epidemiological studies are important. Positive results will substantiate an association of health effects with HCWDS. Negative results may reduce the concerns of people living near HCWDS. Future investigators need sufficient information about HCWDS materials, possible routes of exposure, and measurements of exposure, as well as sufficient statistical power to detect even modest associations of health effects with HCWDS exposure. PMID:1790043

Najem, G R; Cappadona, J L

1991-01-01

281

Strategy for identifying natural analogs of the long-term performance of low-level waste disposal sites  

SciTech Connect

The US Department of Energy's Low-Level Waste (LLW) Management Program has asked Pacific Northwest Laboratory (PNL) to explore the feasibility of using natural analogs of anticipated waste site and conditions to help validate predictions of the performance of LLW disposal sites. Current regulations require LLW facilities to control the spread of hazardous substances into the environment for at least the next 500 years. Natural analog studies can provide information about processes affecting waste containment that cannot be fully explored through laboratory experimentation and modeling because of the extended period of required performance. For LLW applications, natural analogs include geochemical systems, pedogenic (soil formation) indicators, proxy climate data, and ecological and archaeological settings that portray long-term changes in disposal site environments and the survivability of proposed waste containment materials and structures. Analog data consist of estimates of performance assessment (PA) model input parameters that define possible future environmental states of waste sites, validation parameters that can be predicted by PA models, and descriptive information that can build public confidence in waste disposal practices. This document describes PNL's overall stategy for identifying analogs for LLW disposal systems, reviews lessons learned from past analogs work, outlines the findings of the workshop, and presents examples of analog studies that workshop participants found to be applicable to LLW performance assessment. The lessons from the high-level waste analogs experience and workshop discussions will be used to develop detailed study plans during FY 1990. 39 refs.

Chatters, J.C.; Waugh, W.J.; Foley, M.G.; Kincaid, C.T.

1990-07-01

282

40 CFR 61.151 - Standard for inactive waste disposal sites for asbestos mills and manufacturing and fabricating...  

Code of Federal Regulations, 2010 CFR

Each owner or operator of any inactive waste disposal site that was operated by sources covered under 61.142, 61.144, or 61.147 and received deposits of asbestos-containing waste material generated by the sources, shall: (a) Comply with one of the...

2010-07-01

283

40 CFR 61.151 - Standard for inactive waste disposal sites for asbestos mills and manufacturing and fabricating...  

Code of Federal Regulations, 2012 CFR

Each owner or operator of any inactive waste disposal site that was operated by sources covered under 61.142, 61.144, or 61.147 and received deposits of asbestos-containing waste material generated by the sources, shall: (a) Comply with one of the...

2012-07-01

284

Nutrient couplings between on-site sewage disposal systems, groundwaters, and nearshore surface waters of the Florida Keys  

Microsoft Academic Search

We performed a one-year study to determine the effects of on-site sewage disposal systems (OSDS, septic tanks) on the nutrient\\u000a relations of limestone groundwaters and nearshore surface waters of the Florida Keys. Monitor wells were installed on canal\\u000a residences with OSDS and a control site in the Key Deer National Wildlife Refuge on Big Pine Key. Groundwater and surface\\u000a water

Brian E. Lapointe; Julie D. O'Connell; George S. Garrett

1999-01-01

285

Estimated PBDE and PBB Congeners in soil from an electronics waste disposal site.  

PubMed

This study estimated PBDE and PBB congener emissions into the environment from three different e-waste disposal sites that consisted of rude broilers (RB), acid baths (AB) and end-up dumps (ED). Different PBDE and PBB congener profiles were analyzed, and some of their emission sources were discussed. For the examined sites, the levels of SigmaPBB and SigmaPBDE were highest at ED (SigmaPBB 1943.86 ng/g, dw; SigmaPBDE 990.87 ng/g, dw), followed by RB (SigmaPBB 704.58 ng/g, dw; SigmaPBDE 799.27 ng/g, dw) and finally AB (SigmaPBB 108.78 ng/g, dw; SigmaPBDE 171.18 ng/g, dw). PBE-209 (AB 48.67 ng/g, 28.43%; RB 160.23 ng/g, 20.05%; ED 234.12 ng/g, 23.63%) and PBE-203 (AB 51.23 ng/g, 29.93%; RB 130.34 ng/g, 16.31%; ED 93.41 ng/g, 9.43%) exhibited the highest concentrations when compared to the other congeners. Furthermore, high levels of deca-BDE (BDE-209) were observed in AB (48.67 ng/g, 28.43%) and RB sites (160.23 ng/g, 20.05%), which was in accordance with the large amount of these materials in electronics products in China. PMID:19768361

Wang, H-M; Yu, Y-J; Han, M; Yang, S-W; Li, Q; Yang, Y

2009-12-01

286

Application of Geographic Information System and Remotesensing in effective solid waste disposal sites selection in Wukro town, Tigray, Ethiopia  

NASA Astrophysics Data System (ADS)

Identifying solid waste disposal sites and appropriately managing them is a challenging task to many developing countries. This is a critical problem too in Ethiopia in general and in Wukro town in particular. The existing site for Wukro town is not sufficient in its capacity and it is damaging the environment due to its location, and the type of waste dumped, while the surrounding area is being irrigated. Due to the swift expansion and urbanization developments in Wukro town, it badly needs to develop controlled solid waste dumping site to prevent several contamination problems. This study was conducted first, to assess the existing waste management strategies in Wukro town; and second, to find out the potential waste disposal sites for the town, using GIS and Remote Sensing techniques. The study exploited the Multi-Criteria Evaluation (MCE) methods to combine necessary factors considered for dumping site selection. The selected method also uses various geographical data including remote sensing data, with GIS spatial analysis tools. Accordingly, site suitability maps for each of the factors were developed in a GIS environment. Results indicate that 12 dumping sites were appropriate and they were further ranked against their suitability in terms of wind direction, proximity to settlement area and distance from the center of the town. Finally, two sites are the best suitable for dumping site. This study indicated that the application of Geographic Information System and Remote Sensing techniques are efficient and low cost tools to study and select appropriate dumping site so as to facilitate decision making processes.

Mohammedshum, A. A.; Gebresilassie, M. A.; Rulinda, C. M.; Kahsay, G. H.; Tesfay, M. S.

2014-11-01

287

Physical oceanographic processes at candidate dredged-material disposal sites B1B and 1M offshore San Francisco  

SciTech Connect

The US Army Corps of Engineers (USACE), San Francisco District, has identified two candidate sites for ocean disposal of material from several dredging projects in San Francisco Bay. The disposal site is to be designated under Section 103 of the Ocean Dumping Act. One of the specific criteria in the Ocean Dumping Act is that the physical environments of the candidate sites be considered. Toward this goal, the USACE requested that the Pacific Northwest Laboratory conduct studies of physical oceanographic and sediment transport processes at the candidate sites. Details of the methods and complete listing or graphical representation of the results are contained in this second volume of the two-volume report. Appendix A describes the methods and results of a pre-disposal bathymetric survey of Site B1B, and provides an analysis of the accuracy and precision of the survey. Appendix B describes the moorings and instruments used to obtain physical oceanographic data at the candidate sites, and also discussed other sources of data used in the analyses. Techniques used to analyze the formation, processed data, and complete results of various analyses are provided in tabular and graphical form. Appendix C provides details of the sediment transport calculations. Appendix D describes the format of the archived current meter data, which is available through the National Oceanographic Data Center. 43 refs., 54 figs., 58 tabs.

Sherwood, C.R.; Denbo, D.W.; Downing, J.P. (Pacific Northwest Lab., Richland, WA (USA)); Coats, D.A. (Marine Research Specialists, Ventura, CA (USA))

1990-10-01

288

Use of geophysical monitoring systems and data to identify and designate ocean sites for disposal of low-level radioactive wastes. Final report  

SciTech Connect

The report provides information applicable to using geophysical instruments and survey methods, and the data collected, in the process of designating sites for ocean disposal of low level radioactive wastes. The geophysical ocean survey methods described in the report are envisioned as preceding any sediment sampling required to characterize disposal sites.

Neiheisel, J.

1988-07-01

289

Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): 02-09-01, Mud Disposal Area 03-08-03, Mud Disposal Site 03-17-01, Waste Consolidation Site 3B 03-23-02, Waste Disposal Site 03-23-05, Europium Disposal Site 03-99-14, Radioactive Material Disposal Area 09-23-02, U-9y Drilling Mud Disposal Crater 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02. This CAS is closed with no further action. For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. No further corrective action for CAU 545. No Corrective Action Plan. Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

Alfred Wickline

2008-04-01

290

Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste  

USGS Publications Warehouse

In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

Fischer, John N.

1986-01-01

291

PORTSMOUTH ON-SITE DISPOSAL CELL HIGH DENSITY POLYETHYLENE GEOMEMBRANE LONGEVITY  

SciTech Connect

It is anticipated that high density polyethylene (HDPE) geomembranes will be utilized within the liner and closure cap of the proposed On-Site Disposal Cell (OSDC) at the Portsmouth Gaseous Diffusion Plant. The likely longevity (i.e. service life) of HDPE geomembranes in OSDC service is evaluated within the following sections of this report: (1) Section 2.0 provides an overview of HDPE geomembranes, (2) Section 3.0 outlines potential HDPE geomembranes degradation mechanisms, (3) Section 4.0 evaluates the applicability of HDPE geomembrane degradation mechanisms to the Portsmouth OSDC, (4) Section 5.0 provides a discussion of the current state of knowledge relative to the longevity (service life) of HDPE geomembranes, including the relation of this knowledge to the Portsmouth OSDC, and (5) Section 6.0 provides summary and conclusions relative to the anticipated service life of HDPE geomembranes in OSDC service. Based upon this evaluation it is anticipated that the service life of HDPE geomembranes in OSDC service would be significantly greater than the 200 year service life assumed for the OSDC closure cap and liner HDPE geomembranes. That is, a 200 year OSDC HDPE geomembrane service life is considered a conservative assumption.

Phifer, M.

2012-01-31

292

Ecological survey for the siting of the Mixed and Low-Level Waste Disposal Facility  

SciTech Connect

This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Lab. (INEL) at two candidate locations for the siting of the Mixed and Low-Level Waste Disposal Facility (MLLWDF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate any potential environmental impacts because of the project. The boundaries of the candidate locations were marked with blaze-orange lath survey marker stakes by the project management. Global Positioning in System (GPS) measurements of the marker stakes were made, and input to the Arc/Info geographic information system (GIS). Field surveys were conducted to assess any potential impact to any important species, important habitats, and to any environmental study areas. The GIS location data were overlayed onto the INEL vegetation map and an analysis of vegetation classes on the locations was done. Two species of rare vascular plants have previously been reported to occur in the vicinity of the candidate locations. Two C2 species, the ferruginous hawk (Buteo regalis) and the loggerhead shrike (Lanius ludovicianus) would also be expected to frequent the candidate locations. No significant ecological impact is anticipated if the MLLWDF were constructed on either candidate location. However, both candidate locations are in the central area of the INEL where there is minimal disturbance to the ecosystem by facilities or humans.

Hoskinson, R.L.

1994-05-01

293

Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites, Nevada Test Site, Nevada with Errata Sheet  

SciTech Connect

This Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 356, Mud Pits and Disposal Sites, in accordance with the Federal Facility Agreement and Consent Order. This CAU is located in Areas 3 and 20 of the Nevada Test Site (NTS) approximately 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 356 consists of seven Corrective Action Sites (CASs): 03-04-01, Area 3 Change House Septic System; 03-09-01, Mud Pit Spill Over; 03-09-03, Mud Pit; 03-09-04, Mud Pit; 03-09-05, Mud Pit; 20-16-01, Landfill; and 20-22-21, Drums. This CR identifies and rationalizes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's (NNSA/NV's) recommendation that no further corrective action and closure in place is deemed necessary for CAU 356. This recommendation is based on the results of field investigation/closure activities conducted November 20, 2001, through January 3, 2002, and March 11 to 14, 2002. These activities were conducted in accordance with the Streamlined Approach for Environmental Restoration Plan (SAFER) for CAU 356. For CASs 03-09-01, 03-09-03, 20-16-01, and 22-20-21, analytes detected in soil during the corrective action investigation were evaluated against Preliminary Action Levels (PALs) and it was determined that no Contaminants of Concern (COCs) were present. Therefore, no further action is necessary for the soil at these CASs. For CASs 03-04-01, 03-09-04, and 03-09-05, analytes detected in soil during the corrective action investigation were evaluated against PALs and identifies total petroleum hydrocarbons (TPHs) and radionuclides (i.e., americium-241 and/or plutonium 239/240) as COCs. The nature, extent, and concentration of the TPH and radionuclide COCs were bounded by sampling and shown to be relatively immobile. Therefore, closure in place is recommended for these CASs in CAU 356. Further, use restrictions are not required at this CAU beyond the NTS use restrictions identified in the SAFER Plan. In addition, the septic tank associated with CAU 356 will be closed in accordance with applicable regulations.

NNSA /NV

2002-11-12

294

Nematodes as Sensitive Indicators of Change at Dredged Material Disposal Sites  

Microsoft Academic Search

Demonstration of the recovery of marine habitats from perturbation, or of the effectiveness of protective measures, is dependent on the sensitivity of the target group in responding to change. This paper highlights the utility of the nematode component of the meiofauna as a tool for assessing disturbance from dredgings disposal. Transect surveys were conducted at three major dredged material disposal

S. E. Boyd; H. L. Rees; C. A. Richardson

2000-01-01

295

Cornell University remote sensing program. [application to waste disposal site selection, study of drainage patterns, and water quality management.  

NASA Technical Reports Server (NTRS)

Aircraft and satellite remote sensing technology were applied in the following areas: (1) evaluation of proposed fly ash disposal sites; (2) development of priorities for drainage improvements; (3) state park analysis for rehabilitation and development; (4) watershed study for water quality planning; and (5) assistance project-landfill site selection. Results are briefly summarized. Other projects conducted include: (1) assessment of vineyard-related problems; (2) LANDSAT analysis for pheasant range management; (3) photo-historic evaluation of Revolutionary War sites; and (4) thermal analysis of building insulation. The objectives, expected benefits and actions, and status of these projects are described.

Liang, T.; Mcnair, A. J.; Philipson, W. R.

1977-01-01

296

Development of a prototype plan for the effective closure of a waste disposal site in Los Alamos, New Mexico  

SciTech Connect

The purpose of this study was to develop a prototype plan for the effective closure and stabilization of a semiarid low-level waste disposal site. This prototype plan will provide demonstrated closure techniques for a trench in a disposal site at Los Alamos based on previous shallow land burial (SLB) field research both at the Los Alamos Experimental Engineered Test Facility (EETF), and at a waste disposal area at Los Alamos. The accuracy of modeling soil water storage by two hydrologic models was tested by comparing simulation results with field measurements of soil moisture in eight experimental landfill cover systems at Waste Disposal Area B having a range of well-defined soil profiles and vegetative covers. Regression analysis showed that one of the two models tested represented soil moisture more accurately than the second model. The accuracy of modeling all of the parameters of the water balance equation was then evaluated using field data from the Integrated Systems Demonstration plots at the EETF. Optimized parameters were developed for one model to describe observed values of deep percolation, evapotranspiration, and runoff from the field plots containing an SLB trench cap configuration.

Nyhan, J.; Barnes, F.

1989-02-01

297

Water-quality and hydrogeologic data for three phosphate industry waste-disposal sites in central Florida, 1979-80  

USGS Publications Warehouse

This report is a complilation of geologic, hydrologic, and water-quality data and information on test holes collected in the vicinity of gypsum stack complexes at two phosphate chemical plants and one phosphatic clayey waste disposal pond at a phosphate mine and beneficiation plant in central Florida. The data were collected from September 1979 to October 1980 at thee AMAX Phosphate, Inc., chemical plant, Piney Point; the USS AgriChemicals chemical plant, Bartow; and the International Minerals and Chemical Corporation Clear Springs mine, Bartow. Approximmmtely 5,400 field and laboratory water-quality determinations on water samples were collected from about 78 test holes and 31 surface-water, rainfall, and other sampling sites at phosphate industry beneficiation and chemical plant waste-disposal operations. Maps show locations of sampling sites. (USGS)

Miller, Ronald L.; Sutcliffe, Horace, Jr.

1982-01-01

298

Groundwater monitoring plan for the Hanford Site 200 Area Treated Effluent Disposal Facility  

SciTech Connect

Seven years of groundwater monitoring at the 200 Area Treated Effluent Disposal Facility (TEDF) have shown that the uppermost aquifer beneath the facility is unaffected by TEDF effluent. Effluent discharges have been well below permitted and expected volumes. Groundwater mounding from TEDF operations predicted by various models has not been observed, and waterlevels in TEDF wells have continued declining with the dissipation of the nearby B Pond System groundwater mound. Analytical results for constituents with enforcement limits indicate that concentrations of all these are below Practical Quantitation Limits, and some have produced no detections. Likewise, other constituents on the permit-required list have produced results that are mostly below sitewide background. Comprehensive geochemical analyses of groundwater from TEDF wells has shown that most constituents are below background levels as calculated by two Hanford Site-wide studies. Additionally, major ion proportions and anomalously low tritium activities suggest that groundwater in the aquifer beneath the TEDF has been sequestered from influences of adjoining portions of the aquifer and any discharge activities. This inference is supported by recent hydrogeologic investigations which indicate an extremely slow rate of groundwater movement beneath the TEDF. Detailed evaluation of TEDF-area hydrogeology and groundwater geochemistry indicate that additional points of compliance for groundwater monitoring would be ineffective for this facility, and would produce ambiguous results. Therefore, the current groundwater monitoring well network is retained for continued monitoring. A quarterly frequency of sampling and analysis is continued for all three TEDF wells. The constituents list is refined to include only those parameters key to discerning subtle changes in groundwater chemistry, those useful in detecting general groundwater quality changes from upgradient sources, or those retained for comparison with end-of-pipe discharge chemistry. Volatile and semivolatile organic compounds, ammonia, total organic carbon, oil and grease, and radium are removed from the constituent list. Annual analysis for low-level tritium is added to the constituent list to help confirm that groundwater beneath the TEDF remains isolated from operational influences.

DB Barnett

2000-05-17

299

Surface-water hydrology at three coal-refuse disposal sites in southern Illinois: Staunton 1, New Kathleen, and Superior  

SciTech Connect

Hydrologic data were collected and analyzed for three coal refuse disposal sites in southern Illinois. The disposal sites were associated with underground mines and consisted of piles of coarse waste (gob) and slurry areas where fine waste rejected from coal washing was deposited. Prereclamation data were available for the Superior washer site in Macoupin County and the New Kathleen site in Perry County. Post-reclamation data were available for the Staunton 1 site in Macoupin County and the New Kathleen site. Data analyzed from each phase (i.e., pre- or post-reclamation) were limited to one year. Storm event runoff coefficients were calculated for each site. Average runoff coefficients were compared for sites within the same reclamation phase to determine the effects of topographical parameters such as gob pile slope and percentage of drainage basin covered by the gob pile. Average runoff coefficients were then compared for pre- and post-reclamation data. Multiple regression analyses were performed on rainfall-runoff data for each site to determine the significance of independent variables other than rainfall in determining runoff. A generalized regression equation corrected data for topographical differences and included only those independent variables that were significant at all sites. Regression coefficients were compared for pre- and post-reclamation sites. The results of rainfall-runoff analysis indicate that the runoff coefficient increases because of reclamation. It is hypothesized that this effect is due to the placement of a soil cover that is less permeable than gob or slurry and occurs despite reduction in slope and the establishment of vegetation.

Mele, L.M.; Prodan, P.F.

1983-04-01

300

Application of organic tracers in characterizing the greater confinement disposal test at the Nevada Test Site  

SciTech Connect

The Greater Confinement Disposal Test (GCDT) is a research project investigating the feasibility of augered-shaft disposal of low-level radioactive waste considered unsuitable for shallow land burial. Gaseous diffusion of radionuclides through alluvial sediments is considered the primary contaminant migration process. Volatile halocarbon tracers are released in the subsurface and their migration is monitored to determine media effective diffusion coefficients, tortuosity values, and sorption terms. Design and instrumentation of the emplacement and monitoring shafts of the disposal facility are detailed. Instrumentation includes a three-dimensional array of soil-air sample stations encircling the disposal waste. Recirculation flow lines minimize induced advection in the alluvial matrix due to tracer sample collection. 6 references, 5 figures, 2 tables.

Olson, M.C.

1985-01-01

301

TRANSPORT OF LOW-LEVEL RADIOACTIVE SOIL AT DEEP-OCEAN DISPOSAL SITE  

EPA Science Inventory

Transport studies were conducted to assess ocean disposal of soil contaminated with low-level natural radioisotopes. he experimental approach involved characterization of the soil for parameters affecting transport and fate of radionuclides- Radioactivity was associated with disc...

302

Decision Support System For Management Of Low-Level Radioactive Waste Disposal At The Nevada Test Site  

Microsoft Academic Search

The long-term safety of U.S. Department of Energy (DOE) low-level radioactive disposal facilities is assessed by conducting a performance assessment -- a systematic analysis that compares estimated risks to the public and the environment with performance objectives contained in DOE Manual 435.1-1, Radioactive Waste Management Manual. Before site operations, facilities design features such as final inventory, waste form characteristics, and

G. Shott; V. Yucel; L. Desotell; J. T. Carilli

2006-01-01

303

An exposure assessment of radionuclide emissions associated with potential mixed-low level waste disposal facilities at fifteen DOE sites  

SciTech Connect

A screening method was developed to compare the doses received via the atmospheric pathway at 15 potential DOE MLLW (mixed low-level waste) sites. Permissible waste concentrations were back calculated using the radioactivity NESHAP (National Emissions Standards for Hazardous Air Pollutants) in 40 FR 61 (DOE Order 5820.2A performance objective). Site-specific soil and meteorological data were used to determine permissible waste concentrations (PORK). For a particular radionuclide, perks for each site do not vary by more than one order of magnitude. perks of {sup 14}C are about six orders of magnitude more restrictive than perks of {sup 3}H because of differences in liquid/vapor partitioning, decay, and exposure dose. When comparing results from the atmospheric pathway to the water and intruder pathways, {sup 14}C disposal concentrations were limited by the atmospheric pathway for most arid sites; for {sup 3}H, the atmospheric pathway was not limiting at any of the sites. Results of this performance evaluation process are to be used for planning for siting of disposal facilities.

Lombardi, D.A.; Socolof, M.L.

1996-05-01

304

Health assessment for Fadrowski Drum Disposal Site, Franklin, Wisconsin, Region 5. CERCLIS No. WID980901227. Preliminary report  

SciTech Connect

The Fadrowski Drum Disposal Site is listed on the National Priorities List. Virtually no testing has been conducted at the Fadrowski site. Site characterization was only beginning at the time of the site visit. The only testing that had been done was of the contents of drums uncovered during excavations involved in construction. Samples of the contents of the drums - sludges, oily water, and paint waste - showed concentrations of lead (400 - 32,700 ppm), chromium (< 100 - 6,800 ppm), DDT (p.p. DDT - 1,000 ppm; o.p. DDT - 450 ppm), and petroleum distillates. The uncovered wastes were re-covered with clay. At that time, the presence of hazardous materials on site was verified, but the extent and limits of contamination were not and have not yet been determined.

Not Available

1989-06-06

305

RESULTS OF TRITIUM TRACKING AND GROUNDWATER MONITORING AT THE HANFORD SITE 200 AREA STATE APPROVED LAND DISPOSAL SITE FY2008  

SciTech Connect

The Hanford Site's 200 Area Effluent Treatment Facility (ETF) processes contaminated aqueous wastes derived from Hanford Site facilities. The treated wastewater occasionally contains tritium, which cannot be removed by the ETF prior to the wastewater being discharged to the 200 Area State-Approved Land Disposal Site (SALDS). During the first 11 months of fiscal year 2008 (FY08) (September 1, 2007, to July 31, 2008), approximately 75.15 million L (19.85 million gal) of water were discharged to the SALDS. Groundwater monitoring for tritium and other constituents, as well as water-level measurements, is required for the SALDS by State Waste Discharge Permit Number ST-4500 (Ecology 2000). The current monitoring network consists of three proximal (compliance) monitoring wells and nine tritium-tracking wells. Quarterly sampling of the proximal wells occurred in October 2007 and in January/February 2008, April 2008, and August 2008. The nine tritium-tracking wells, including groundwater monitoring wells located upgradient and downgradient of the SALDS, were sampled in January through April 2008. Water-level measurements taken in the three proximal SALDS wells indicate that a small groundwater mound is present beneath the facility, which is a result of operational discharges. The mound increased in FY08 due to increased ETF discharges from treating groundwater from extraction wells at the 200-UP-l Operable Unit and the 241-T Tank Farm. Maximum tritium activities increased by an order of magnitude at well 699-48-77A (to 820,000 pCi/L in April 2008) but remained unchanged in the other two proximal wells. The increase was due to higher quantities of tritium in wastewaters that were treated and discharged in FY07 beginning to appear at the proximal wells. The FY08 tritium activities for the other two proximal wells were 68,000 pCi/L at well 699-48-77C (October 2007) and 120,000 pCi/L at well 699-48-77D (October 2007). To date, no indications of a tritium incursion from the SALDS have been detected in the tritium-tracking wells. Concentrations of all chemical constituents were within Permit limits or were below method detection limits when sampled during FY08. A summary of the chemical constituent concentrations or method detection limits is provided in Table 3-2 in the main text discussion. This report presents the results of groundwater monitoring and tritium-tracking samples from the SALDS facility during FY08. Due to the 30-day laboratory turnaround for analysis of proximal well groundwater samples, this report addresses available date extending from August 1, 2007, through September 30, 2008 (August 2007 data were not included in the FY07 report). Updated background information, which is necessary to understand the results of the groundwater analyses, is also provided on facility operations. Interpretive discussions and recommendations for future monitoring are also provided, where possible.

ERB DB

2008-11-19

306

Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: a case study in southern China.  

PubMed

Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north-south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose zone has low saturated hydraulic conductivities on the order of 10(-5)cm/s and in this respect is well-suited for the disposal of LILW. The saturated formations are primarily made up of silt and moderately-to-slightly weathered granite, which exhibit even lower hydraulic conductivities, on the order of 10(-6)cm/s, also favorable for restraining the transport of radionuclides. Chemical analyses indicate that the groundwaters at the site are of the HCO(3)-Na Ca and HCO(3) SO(4)-Na Ca types and are weakly corrosive to concrete and steel. Geochemical analyses indicate that the rock and soil materials (particularly weathered granite) at the site contain very small fractions of colloidal particles and exhibit low Cation Exchange Capacities (CEC), and would therefore have limited capacity for sorption of radionuclides. Groundwater flow and solute transport models of the candidate site have been developed using MODFLOW and MT3DMS, incorporating the data obtained during the assessment program. Calibration was based on the available measured groundwater level fluctuations and tracer concentrations from in situ dispersion tests. The longitudinal dispersion coefficient as determined in calibration is equal to 5.0 10(-3) m(2)/d. Numerical sensitivity analyses indicate that the hydraulic conductivity and the longitudinal dispersion coefficient are the key parameters controlling the transport of radionuclides, while the numerical model is not sensitive to changes in the effective porosity and the specific yield. Preliminary predictions have been performed with the calibrated model both for the natural setting of the site and the graded site in which the valleys of the site are backfilled with low permeable materials. Results indicate that the proposed site grading increases the safety of the site for disposal of LILW by reducing both the groundwater level and the hydraulic gradient and that radionuclide transport would not likely be a problem or cause groundwater contamination. Although there are some problems remaining to be addressed in future work, the conclusion

Yi, Shuping; Ma, Haiyi; Zheng, Chunmiao; Zhu, Xiaobin; Wang, Hua'an; Li, Xueshan; Hu, Xueling; Qin, Jianbo

2012-01-01

307

Utilization of the Baker soil test in synthetic soil preparation for reclamation of coal ash disposal sites  

SciTech Connect

Application of procedures developed for preparation of synthetic soils for reclamation of two coal ash disposal sites in Pennsylvania is presented. These procedures include determination of water holding properties, lime requirement, and the Baker Soil Test (BST) for chemical element analysis. Results from soil and plant analyses following establishment of vegetation on the sites have shown that the BST predicts plant incorporation of chemical elements from the synthetic soils. The results confirm the utility of the BST in planning and executing successful reclamation on disturbed lands in a manner which protects the soil-plant-animal food chain.

Senft, J.P.; Baker, D.E.; Amistadi, M.K. [Pennsylvania State Univ., University Park, PA (United States). Dept. of Agronomy

1993-12-01

308

Alternative Site Technology Deployment-Monitoring System for the U-3ax\\/bl Disposal Unit at the Nevada Test Site  

Microsoft Academic Search

In December 2000, a performance monitoring facility was constructed adjacent to the U-3ax\\/bl mixed waste disposal unit at the Nevada Test Site (NTS). Recent studies conducted in the arid southwestern United States suggest that a vegetated monolayer evapotranspiration (ET) closure cover may be more effective at isolating waste than traditional Resource Conservation and Recovery Act (RCRA) multi-layered designs. The monitoring

Jason M. Dixon; Daniel G. Levitt; Stuart E. Rawlinson

2001-01-01

309

Composite analysis for low-level waste disposal in the 200 area plateau of the Hanford Site  

SciTech Connect

This report presents the first iteration of the Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site (Composite Analysis) prepared in response to the U.S. Department of Energy Implementation Plan for the Defense Nuclear Facility Safety Board Recommendation 94-2. The Composite Analysis is a companion document to published analyses of four active or planned low-level waste disposal actions: the solid waste burial grounds in the 200 West Area, the solid waste burial grounds in the 200 East Area, the Environmental Restoration Disposal Facility, and the disposal facilities for immobilized low-activity waste. A single Composite Analysis was prepared for the Hanford Site considering only sources on the 200 Area Plateau. The performance objectives prescribed in U.S. Department of Energy guidance for the Composite Analysis were 100 mrem in a year and examination of a lower dose (30 mrem in a year) to ensure the {open_quotes}as low as reasonably achievable{close_quotes} concept is followed. The 100 mrem in a year limit was the maximum allowable all-pathways dose for 1000 years following Hanford Site closure, which is assumed to occur in 2050. These performance objectives apply to an accessible environment defined as the area between a buffer zone surrounding an exclusive waste management area on the 200 Area Plateau, and the Columbia River. Estimating doses to hypothetical future members of the public for the Composite Analysis was a multistep process involving the estimation or simulation of inventories; waste release to the environment; migration through the vadose zone, groundwater, and atmospheric pathways; and exposure and dose. Doses were estimated for scenarios based on agriculture, residential, industrial, and recreational land use. The radionuclides included in the vadose zone and groundwater pathway analyses of future releases were carbon-14, chlorine-36, selenium-79, technetium-99, iodine-129, and uranium isotopes.

Kincaid, C.T.; Bergeron, M.P.; Cole, C.R. [and others

1998-03-01

310

Remote Sensing Analysis of the Sierra Blanca (Faskin Ranch) Low-Level Radioactive Waste Disposal Site, Hudspeth County, Texas  

SciTech Connect

Remote sensing images provide useful physical information, revealing such features as geological structure, vegetation, drainage patterns, and variations in consolidated and unconsolidated lithologies. That technology has been applied to the failed Sierra Blanca (Faskin Ranch) shallow burial low-level radioactive waste disposal site selected by the Texas Low-Level Radioactive Waste Disposal Authority. It has been re-examined using data from LANDSAT satellite series. The comparison of the earlier LANDSAT V (5/20/86) (30-m resolution) with the later new, higher resolution ETM imagery (10/23/99) LANDSAT VII data (15-m resolution) clearly shows the superiority of the LANDSAT VII data. The search for surficial indications of evidence of fatal flaws at the Sierra Blanca site utilizing was not successful, as it had been in the case of the earlier remote sensing analysis of the failed Fort Hancock site utilizing LANDSAT V data. The authors conclude that the tectonic activity at the Sierra Blanca site is much less recent and active than in the previously studied Fort Hancock site. The Sierra Blanca site failed primarily on the further needed documentation concerning a subsurface fault underneath the site and environmental justice issues. The presence of this fault was not revealed using the newer LANDSAT VII data. Despite this fact, it must be remembered that remote sensing provides baseline documentation for determining future physical and financial remediation responsibilities. On the basis of the two sites examined by LANDSAT remote sensing imaging, it is concluded that it is an essential, cost-effective tool that should be utilized not only in site examination but also in all nuclear-related facilities.

LeMone, D. V.; Dodge, R.; Xie, H.; Langford, R. P.; Keller, G. R.

2002-02-26

311

Evapotranspiration and microclimate at a low-level radioactive-waste disposal site in northwestern Illinois  

USGS Publications Warehouse

From July 1982 through June 1984, a study was made of the evapotranspiration and microclimate at a low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois. Vegetation at the site consists of mixed pasture grasses, primarily awnless brome (Bromus inermis) and red clover (Trifoleum pratense). Three methods were used to estimate evapotranspiration: (1) an energy budget with the Bowen ratio, (2) an aerodynamic profile, and (3) a soil-based water budget. For the aerodynamic-profile method, sensible-heat flux was estimated by a profile equation and evapotranspiration was then calculated as the residual in the energy-balance equation. Estimates by the energy-budget and aerodynamic-profile methods were computed from hourly data and then summed by days and months. Yearly estimates (for March through November) by these methods were in close agreement: 648 and 626 millimeters, respectively. Daily estimates reach a maximum of about 6 millimeters. The water-budget method produced only monthly estimates based on weekly or biweekly soil-moisture content measurements. The yearly evapotranspiration estimated by this method (which actually included only the months of April through October) was 655 millimeters. The March-through-November average for the three methods of 657 millimeters was equivalent to 70 percent of total precipitation. Continuous measurements were made of incoming and reflected shortwave radiation, incoming and emitted longwave radiation, net radiation, soil-heat flux, soil temperature, horizontal windspeed, and wet- and dry-bulb air temperature. Windspeed and air temperature were measured at heights of 0.5 and 2.0 meters (and also at 1.0 meter after September 1983). Soilmoisture content of the soil zone was measured with a gamma-attenuation gage. Annual precipitation (938 millimeters) and average temperature (10.8 degrees Celsius) at the Sheffield site were virtually identical to long-term averages from nearby National Weather Service stations. Solar radiation averaged 65 percent of that normally expected under clear skies. Net radiation averaged 70.1 watts per square meter and was highest in July and negative during some winter months. Wind direction varied but was predominately south-southeasterly. Wind speed at the 2-meter height averaged 3.5 meters per second and was slightly higher in winter months than the rest of the year. The amount of water stored within the soil zone was greatest in early spring and least in late summer. Seasonal and diurnal trends of evapotranspiration rates mirrored those of net radiation; July was usually the month with the highest evapotranspiration rate. The ratio of sensible- to latentheat fluxes (commonly called the Bowen ratio) for the 2-year study period was 0.38, as averaged from the three methods. Monthly Bowen ratios fluctuated somewhat but averaged about 0.35 for late spring through summer. In fall, the ratio declined to zero or to slightly negative values. When the ratio was negative, the latent-heat flux was slightly greater than the net radiation because of additional energy supplied by' the cooling soil and air. Evapotranspiration calculated by the three methods averaged 75 percent of potential evapotranspiration, as estimated by the Penman equation. There was no apparent seasonal trend in the relation between actual and potential evapotranspiration rates.

Healy, R.W.; DeVries, M.P.; Sturrock, Alex M., Jr.

1989-01-01

312

ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY  

SciTech Connect

A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the Berea sandstone aquiver over time and does not conform to standard private water well construction practices. The bottom-line is that all predicted doses from the base case and five sensitivity cases fall well below the DOE all-pathways 25 mrem/yr Performance Objective.

Smith, F.; Phifer, M.

2014-04-10

313

Distribution of radionuclides and water in Bandelier Tuff beneath a former Los Alamos liquid waste disposal site after 33 years  

SciTech Connect

The distribution of radionuclides and water in Bandelier Tuff beneath a former liquid waste disposal site at Los Alamos was investigated. The waste use history of the site was described, as well as several pertinent laboratory and field studies of water and radionuclide migration in Bandelier Tuff. The distribution of plutonium, /sup 241/Am, and water was determined in a set of about 800 tuff samples collected to sampling depths of 30 m beneath two absorption beds. These data were then related to site geohydrologic data. Water and radionuclide concentrations found after 33 years were compared with the results of similar studies previously performed at this site, and the implications of these comparisons are discussed relative to nuclear waste management. 19 references, 6 figures, 4 tables.

Nyhan, J.W.; Drennon, B.J.; Abeele, W.V.; Trujillo, G.; Herrera, W.J.; Wheeler, M.L.; Booth, J.W.; Purtymun, W.D.

1984-07-01

314

Gas production, composition and emission at a modern disposal site receiving waste with a low-organic content.  

PubMed

AV Milj is a modern waste disposal site receiving non-combustible waste with a low-organic content. The objective of the current project was to determine the gas generation, composition, emission, and oxidation in top covers on selected waste cells as well as the total methane (CH(4)) emission from the disposal site. The investigations focused particularly on three waste disposal cells containing shredder waste (cell 1.5.1), mixed industrial waste (cell 2.2.2), and mixed combustible waste (cell 1.3). Laboratory waste incubation experiments as well as gas modeling showed that significant gas generation was occurring in all three cells. Field analysis showed that the gas generated in the cell with mixed combustible waste consisted of mainly CH(4) (70%) and carbon dioxide (CO(2)) (29%) whereas the gas generated within the shredder waste, primarily consisted of CH(4) (27%) and nitrogen (N(2)) (71%), containing no CO(2). The results indicated that the gas composition in the shredder waste was governed by chemical reactions as well as microbial reactions. CH(4) mass balances from three individual waste cells showed that a significant part (between 15% and 67%) of the CH(4) generated in cell 1.3 and 2.2.2 was emitted through leachate collection wells, as a result of the relatively impermeable covers in place at these two cells preventing vertical migration of the gas. At cell 1.5.1, which is un-covered, the CH(4) emission through the leachate system was low due to the high gas permeability of the shredder waste. Instead the gas was emitted through the waste resulting in some hotspot observations on the shredder surface with higher emission rates. The remaining gas that was not emitted through surfaces or the leachate collection system could potentially be oxidized as the measured oxidation capacity exceeded the potential emission rate. The whole CH(4) emission from the disposal site was found to be 820 202 kg CH(4)d(-1). The total emission rate through the leachate collection system at AV Milj was found to be 211 kg CH(4)d(-1). This showed that approximately of the emitted gas was emitted through the leachate collections system making the leachate collection system an important source controlling the overall gas migration from the site. The emission pathway for the remaining part of the gas was more uncertain, but emission from open cells where waste is being disposed of or being excavated for incineration, or from horizontal leachate drainage pipes placed in permeable gravel layers in the bottom of empty cells was likely. PMID:21186118

Scheutz, Charlotte; Fredenslund, Anders M; Nedenskov, Jonas; Samuelsson, Jerker; Kjeldsen, Peter

2011-05-01

315

Geohydrologic evaluation for the 200 Area Effluent Treatment Facility State-Approved Land Disposal Site: Addendum to WAC 173-240 Engineering Report  

SciTech Connect

This document provides a geohydrologic evaluation for the disposal of liquid effluent from the 200 Area Effluent Treatment Facility (ETF) at the Hanford Site. This work forms an addendum to the engineering report that supports the completion of the ETF.

Ballantyne, N.A.

1993-08-01

316

Evapotranspiration and microclimate at a low-level radioactive-waste disposal site in northwestern Illinois  

USGS Publications Warehouse

From July 1982 through June 1984, a study was made of the microclimate and evapotranspiration at a low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois. Vegetation at the site consists of mixed pasture grasses, primarily brome (Bromus inermis) and red clover (Trifoleum pratense). Three methods were used to estimate evapotranspiration: (1) an energy-budget with the Bowen ratio, (2) an aerodynamic-profile, and (3) a soil-based water-budget. For the aerodynamic-profile method, sensible-heat flux was estimated by a profile equation and evapotranspiration was then calculated as the residual in the energy-balance equation. Estimates by the energy-budget and aerodynamic-profile methods were computed from hourly data, then summed by days and months. Yearly estimates for March through November, by these methods, were quite close--648 and 626 millimeters, respectively. Daily estimates range up to a maximum of about 6 millimeters. The water-budget method produced only monthly estimates based on weekly or biweekly soil-moisture content measurements. The yearly evapotranspiration estimated by this method (which actually included only the months of April through October) was 655 millimeters. The March-through-November average for the three methods of 657 millimeters was equivalent to 70 percent of precipitation. Continuous measurements were made of incoming and reflected shortwave radiation, incoming and emitted longwave radiation, net radiation, soil-heat flux, soil temperature, horizontal windspeed, and wet- and dry-bulb air temperature. Windspeed and air temperature were measured at heights of 0.5 and 2.0 meters (and also at 1.0 meter after September 1983). Soil-moisture content of the soil zone was measured with a gamma-attenuation gage. Annual precipitation (938 millimeters) and average temperature (10.8 degrees Celsius) were virtually identical to long-term averages from nearby National Weather Service stations. Solar radiation averaged 65 percent of that normally expected under clear skies. Net radiation averaged 70.1 watts per square meter and was highest in July and negative during some winter months. Wind direction varied but was predominately out of the south-southeast. Wind speed at the 2-meter height averaged 3.5 meters per second and was slightly higher in winter months than the rest of the year. The amount of water stored within the soil zone was greatest in early spring and least in late summer. Seasonal and diurnal trends in evapotranspiration rates mirrored those in net radiation; July was usually the month with the highest rate. The ratio of sensible- to latent-heat fluxes (commonly called the Bowen ratio) for the 2-year period was 0.38, as averaged from the three methods. Monthly Bowen ratios fluctuated somewhat but averaged about 0.35 for late spring through summer. In fall, the ratio declined to zero or to slightly negative values. When the ratio was negative, the latent-heat flux was slightly greater than the net radiation because of additional energy supplied by the cooling soil and air. Evapotranspiration calculated by the three methods averaged 75 percent of potential evapotranspiration, as estimated by the Penman equation. There was no apparent seasonal trend in the relation between actual and potential evapotranspiration rates.

Healy, R.W.; DeVries, M.P.; Sturrock, A.M.

1987-01-01

317

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites  

SciTech Connect

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01

318

EVALUATION AND MANAGEMENT OF ON-SITE SEWAGE DISPOSAL SYSTEMS: NEW CHALLENGES, NEW INITIATIVES, NEW PARTNERSHIPS  

Microsoft Academic Search

Management of onsite sewage disposal systems (OSDS) is necessary to assure proper performance of these systems, protect public health and protect surface water and groundwater quality. In the Rouge River Watershed, studies identified failure rates of OSDS ranging from 20% to 52%. As part of the storm water discharge permits issued by the Michigan Department of Environmental Quality (MDEQ), failing

Barry Johnson; Richard Fleece; Wayne County

319

Grout for closure of waste-disposal vaults at the US DOE Hanford Site  

Microsoft Academic Search

For permanent disposal of radioactive wastes from reprocessing, the US Department of Energy (DOE) has chosen to grout wastes in concrete vaults within a subsurface multiple-barrier system. The subject of this research is the non-radioactive, or ``cold cap`` grout, which fills the upper 120 cm of these vaults, and provides support for overlying barriers. Because of the heat evolved by

L. D. Wakeley; J. J. Ernzen; E. W. McDaniel; J. Voogd

1991-01-01

320

Grout for closure of waste-disposal vaults at the US DOE Hanford Site  

Microsoft Academic Search

For permanent disposal of radioactive wastes from reprocessing, the US Department of Energy (DOE) has chosen to grout wastes in concrete vaults within a subsurface multiple-barrier system. The subject of this research is the non-radioactive, or cold cap'' grout, which fills the upper 120 cm of these vaults, and provides support for overlying barriers. Because of the heat evolved by

L. D. Wakeley; J. J. Ernzen; E. W. McDaniel; J. Voogd

1991-01-01

321

Structural constraints for proposed Fort Hancock low-level radioactive waste disposal site (NTP-S34), southern Hudspeth County, Texas  

Microsoft Academic Search

Structural complexities reduce the homogeneity necessary for a site characterization model to an unacceptable level for performance assessment for radioactive waste disposal sites. The proposed site lies between the northern, stable Diablo platform and the southern, mobile Mesozoic Chihuahua tectonic belt. Structural movement along this interface has been active for the past 14,000 years. In addition, the area lies along

David V. Lemone

1989-01-01

322

Monitoring the remediation of a near shore waste disposal site in Antarctica using the amphipod Paramoera walkeri and diffusive gradients in thin films (DGTs)  

Microsoft Academic Search

The water quality of a marine embayment (Brown Bay) was monitored during the remediation of an abandoned waste disposal site at Casey Station, East Antarctica, using a combination of biomonitoring and chemical methods. The Antarctic amphipod Paramoera walkeri, in field mesocosms suspended in the water column, was deployed adjacent to the site and at two reference sites for periods of

Jonathan S. Stark; Glenn J. Johnstone; Anne S. Palmer; Ian Snape; Bronwyn L. Larner; Martin J. Riddle

2006-01-01

323

Scoping evaluation of the technical capabilities of DOE sites for disposal of hazardous metals in mixed low-level waste  

SciTech Connect

A team of analysts designed and conducted a scoping evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of the hazardous metals in mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Eight hazardous metals were evaluated: arsenic, barium, cadmium, chromium, lead, mercury, selenium, and silver. The analysis considered transport only through the groundwater pathway. The results are reported as site-specific estimates of maximum concentrations of each hazardous metal in treated mixed low-level waste that do not exceed the performance measures established for the analysis. Also reported are site-specific estimates of travel times of each hazardous metal to the point of compliance.

Gruebel, M.M.; Waters, R.D.; Langkopf, B.S.

1997-05-01

324

Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site  

SciTech Connect

The U.S. Department of Energy Office of Legacy Management (DOE) and the U.S. Environmental Protection Agency (EPA) collaborated on the design and monitoring of an alternative cover for the Monticello uranium mill tailings disposal cell, a Superfund site in southeastern Utah. Ground-water recharge is naturally limited at sites like Monticello where thick, fine-textured soils store precipitation until evaporation and plant transpiration seasonally return it to the atmosphere. The cover at Monticello uses local soils and a native plant community to mimic the natural soil water balance. The cover is fundamentally an evapotranspiration (ET) design with a capillary barrier. A 3-hectare drainage lysimeter was embedded in the cover during construction of the disposal cell in 2000. The lysimeter consists of a geo-membrane liner below the capillary barrier that directs percolation water to a monitoring system. Soil water storage is determined by integration of point water content measurements. Meteorological parameters are measured nearby. Plant cover, shrub density, and leaf area index (LAI) are monitored annually. The cover performed well over the 7-year monitoring period (2000-2007). The cumulative percolation was 4.2 mm (0.6 mm yr{sup -1}), satisfying an EPA goal of an average percolation of <3.0 mm yr{sup -1}. Almost all percolation can be attributed to the exceptionally wet winter and spring of 2004-2005 when soil water content slightly exceeded the water storage capacity of the cover. The diversity, percent cover, and LAI of vegetation increased over the monitoring period, although the density of native shrubs that extract water from deeper in the cover has remained less than revegetation targets. DOE and EPA are applying the monitoring results to plan for long-term surveillance and maintenance and to evaluate alternative cover designs for other waste disposal sites. (authors)

Waugh, W.J.; Kastens, M.K.; Sheader, L.R.L. [Environmental Sciences Laboratory, Grand Junction, CO (United States); Benson, C.H. [University of Wisconsin, Madison, WI (United States); Albright, W.H. [Desert Research Institute, Reno, NV (United States); Mushovic, P.S. [U.S. Environmental Protection Agency, Denver, CO (United States)

2008-07-01

325

State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site  

SciTech Connect

Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

Not Available

1993-08-01

326

Analysis of multi-temporal landsat satellite images for monitoring land surface temperature of municipal solid waste disposal sites.  

PubMed

This studypresents a remote sensing application of using time series Landsat satellite images for monitoring the Trail Road and Nepean municipal solid waste (MSW) disposal sites in Ottawa, Ontario, Canada. Currently, the Trail Road landfill is in operation; however, during the 1960s and 1980s, the city relied heavily on the Nepean landfill. More than 400 Landsat satellite images were acquired from the US Geological Survey (USGS) data archive between 1984 and 2011. Atmospheric correction was conducted on the Landsat images in order to derive the landfill sites' land surface temperature (LST). The findings unveil that the average LST of the landfill was always higher than the immediate surrounding vegetation and air temperature by 4 to 10 C and 5 to 11.5 C, respectively. During the summer, higher differences of LST between the landfill and its immediate surrounding vegetation were apparent, while minima were mostly found in fall. Furthermore, there was no significant temperature difference between the Nepean landfill (closed) and the Trail Road landfill (active) from 1984 to 2007. Nevertheless, the LST of the Trail Road landfill was much higher than the Nepean by 15 to 20 C after 2007. This is mainly due to the construction and dumping activities (which were found to be active within the past few years) associated with the expansion of the Trail Road landfill. The study demonstrates that the use of the Landsat data archive can provide additional and viable information for the aid of MSW disposal site monitoring. PMID:25150051

Yan, Wai Yeung; Mahendrarajah, Prathees; Shaker, Ahmed; Faisal, Kamil; Luong, Robin; Al-Ahmad, Mohamed

2014-12-01

327

Guidance on the application of quality assurance for characterizing a low-level radioactive waste disposal site  

SciTech Connect

This document provides the Nuclear Regulatory Commission's staff guidance to an applicant on meeting the quality control (QC) requirements of Title 10 of the Code of Federal Regulations, Part 61, Section 61.12 (10 CFR 61.12), for a low-level waste disposal facility. The QC requirements combined with the requirements for managerial controls and audits are the basis for developing a quality assurance (QA) program and for the guidance provided herein. QA guidance is specified for site characterization activities necessary to meet the performance objectives of 10 CFR Part 61 and to limit exposure to or the release of radioactivity. 1 tab.

Pittiglio, C.L. Jr.; Starmer, R.J.; Hedges, D.

1990-10-01

328

Corrective Action Investigation Plan for Corrective Action Unit 542: Disposal Holes, Nevada Test Site, Nevada, Rev. No.: 0  

SciTech Connect

Corrective Action Unit (CAU) 542 is located in Areas 3, 8, 9, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 542 is comprised of eight corrective action sites (CASs): (1) 03-20-07, ''UD-3a Disposal Hole''; (2) 03-20-09, ''UD-3b Disposal Hole''; (3) 03-20-10, ''UD-3c Disposal Hole''; (4) 03-20-11, ''UD-3d Disposal Hole''; (5) 06-20-03, ''UD-6 and UD-6s Disposal Holes''; (6) 08-20-01, ''U-8d PS No.1A Injection Well Surface Release''; (7) 09-20-03, ''U-9itsy30 PS No.1A Injection Well Surface Release''; and (8) 20-20-02, ''U-20av PS No.1A Injection Well Surface Release''. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on January 30, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 542. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 542 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Conduct geophysical surveys to locate previously unidentified features at CASs 03-20-07, 03-20-09, 03-20-10, 03-20-11, and 06-20-03. (4) Perform field screening. (5) Collect and submit environmental samples for laboratory analysis to determine whether contaminants of concern (COCs) are present. (6) Collect quality control samples for laboratory analyses to evaluate the performance of measurement systems and controls based on the requirements of the data quality indicators. (7) If COCs are present at the surface/near surface (< 15 feet below ground surface), collect additional step-out samples to define the extent of the contamination. (8) If COCs are present in the subsurface (i.e., base of disposal hole), collect additional samples to define the vertical extent of contamination. A conservative use restriction will be used to encompass the lateral extent of subsurface contamination. (9) Stake or flag sample locations in the field, and record coordinates through global positioning systems surveying. (10) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Field work will be conducted following approval of the plan.

Laura Pastor

2006-05-01

329

CENSUS AND STATISTICAL CHARACTERIZATION OF SOIL AND WATER QUALITY AT ABANDONED AND OTHER CENTRALIZED AND COMMERCIAL DRILLING-FLUID DISPOSAL SITES IN LOUISIANA, NEW MEXICO, OKLAHOMA, AND TEXAS  

SciTech Connect

Commercial and centralized drilling-fluid disposal (CCDD) sites receive a portion of spent drilling fluids for disposal from oil and gas exploration and production (E&P) operations. Many older and some abandoned sites may have operated under less stringent regulations than are currently enforced. This study provides a census, compilation, and summary of information on active, inactive, and abandoned CCDD sites in Louisiana, New Mexico, Oklahoma, and Texas, intended as a basis for supporting State-funded assessment and remediation of abandoned sites. Closure of abandoned CCDD sites is within the jurisdiction of State regulatory agencies. Sources of data used in this study on abandoned CCDD sites mainly are permit files at State regulatory agencies. Active and inactive sites were included because data on abandoned sites are sparse. Onsite reserve pits at individual wells for disposal of spent drilling fluid are not part of this study. Of 287 CCDD sites in the four States for which we compiled data, 34 had been abandoned whereas 54 were active and 199 were inactive as of January 2002. Most were disposal-pit facilities; five percent were land treatment facilities. A typical disposal-pit facility has fewer than 3 disposal pits or cells, which have a median size of approximately 2 acres each. Data from well-documented sites may be used to predict some conditions at abandoned sites; older abandoned sites might have outlier concentrations for some metal and organic constituents. Groundwater at a significant number of sites had an average chloride concentration that exceeded nonactionable secondary drinking water standard of 250 mg/L, or a total dissolved solids content of >10,000 mg/L, the limiting definition for underground sources of drinking water source, or both. Background data were lacking, however, so we did not determine whether these concentrations in groundwater reflected site operations. Site remediation has not been found necessary to date for most abandoned CCDD sites; site assessments and remedial feasibility studies are ongoing in each State. Remediation alternatives addressed physical hazards and potential for groundwater transport of dissolved salt and petroleum hydrocarbons that might be leached from wastes. Remediation options included excavation of wastes and contaminated adjacent soils followed by removal to permitted disposal facilities or land farming if sufficient on-site area were available.

Alan R. Dutton; H. Seay Nance

2003-06-01

330

Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites  

SciTech Connect

Rates, depths, erosion potential, increased subsurface transport rates, and annual exceedance probability for potential flooding scenarios have been evaluated for the on-site alternatives of Idaho National Laboratorys proposed remote handled low-level waste disposal facility. The on-site disposal facility is being evaluated in anticipation of the closure of the Radioactive Waste Management Complex at the INL. An assessment of flood impacts are required to meet the Department of Energys Low-Level Waste requirements (DOE-O 435.1), its natural phenomena hazards assessment criteria (DOE-STD-1023-95), and the Radioactive Waste Management Manual (DOE M 435.1-1) guidance in addition to being required by the National Environmental Policy Act (NEPA) environmental assessment (EA). Potential sources of water evaluated include those arising from (1) local precipitation events, (2) precipitation events occurring off of the INL (off-site precipitation), and (3) increased flows in the Big Lost River in the event of a Mackay Dam failure. On-site precipitation events include potential snow-melt and rainfall. Extreme rainfall events were evaluated for the potential to create local erosion, particularly of the barrier placed over the disposal facility. Off-site precipitation carried onto the INL by the Big Lost River channel was evaluated for overland migration of water away from the river channel. Off-site precipitation sources evaluated were those occurring in the drainage basin above Mackay Reservoir. In the worst-case scenarios, precipitation occurring above Mackay Dam could exceed the dams capacity, leading to overtopping, and eventually complete dam failure. Mackay Dam could also fail during a seismic event or as a result of mechanical piping. Some of the water released during dam failure, and contributing precipitation, has the potential of being carried onto the INL in the Big Lost River channel. Resulting overland flows from these flood sources were evaluated for their erosion potential, ability to overflow the proposed disposal facility, and for their ability to increase migration of contaminants from the facility. The assessment of available literature suggests that the likelihood of detrimental flood water impacting the proposed RH-LLW facility is extremely low. The annual exceedance probability associated with uncontrolled flows in the Big Lost River impacting either of the proposed sites is 1x10-5, with return interval (RI) of 10,000yrs. The most probable dam failure scenario has an annual exceedance probability of 6.3x10-6 (1.6x105 yr RI). In any of the scenarios generating possible on-site water, the duration is expected to be quite short, water depths are not expected to exceed 0.5 m, and the erosion potential can easily be mitigated by emplacement of a berm (operational period), and an engineered cover (post closure period). Subsurface mobilization of radionuclides was evaluated for a very conservative flooding scenario resulting in 50 cm deep, 30.5 day on-site water. The annual exceedance probability for which is much smaller than 3.6x10-7 (2.8x106 yr RI). For the purposes of illustration, the facility was assumed to flood every 500 years. The periodically recurring flood waters were predicted to marginally increase peak radionuclide fluxes into the aquifer by at most by a factor of three for non-sorbing radionuclides, and to have limited impact on peak radionuclide fluxes into the aquifer for contaminants that do sorb.

A. Jeff Sondrup; Annette L. Schafter

2010-09-01

331

ALTERNATIVE ONSITE WASTEWATER TREATMENT AND DISPOSAL SYSTEMS ON SEVERELY LIMITED SITES  

EPA Science Inventory

Several research and evaluation studies were performed on alternative onsite systems on sites with severe limitations for conventional systems. The major limitations included slow permeability, a seasonally high water table, and limiting soil horizons. Several typical site evalua...

332

Three-year summary report of biological monitoring at the Southwest Ocean dredged-material disposal site and additional locations off Grays Harbor, Washington, 1990--1992  

SciTech Connect

The Grays Harbor Navigation Improvement Project was initiated to improve navigation by widening and deepening the federal channel at Grays Harbor. Dredged-material disposal sites were selected after an extensive review process that included inter-agency agreements, biological surveys, other laboratory and field studies, and preparation of environmental impact statements The Southwest Site, was designated to receive materials dredged during annual maintenance dredging as well as the initial construction phase of the project. The Southwest Site was located, and the disposal operations designed, primarily to avoid impacts to Dungeness crab. The Final Environmental Impact Statement Supplement for the project incorporated a Site Monitoring Plan in which a tiered approach to disposal site monitoring was recommended. Under Tier I of the Site Monitoring Plan, Dungeness crab densities are monitored to confirm that large aggregations of newly settled Dungeness crab have not moved onto the Southwest Site. Tier 2 entails an increased sampling effort to determine whether a change in disposal operations is needed. Four epibenthic surveys using beam trawls were conducted in 1990, 1991, and 1992 at the Southwest Site and North Reference area, where high crab concentrations were found in the spring of 1985. Survey results during these three years prompted no Tier 2 activities. Epibenthic surveys were also conducted at two nearshore sites where construction of sediment berms has been proposed. This work is summarized in an appendix to this report.

Antrim, L.D.; Shreffler, D.K.; Pearson, W.H.; Cullinan, V.I. [Battelle Marine Research Lab., Sequim, WA (United States)

1992-12-01

333

Preliminary identification of potentially disruptive scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site  

SciTech Connect

The Greater Confinement Disposal location is being evaluated to determine whether defense-generated transuranic waste buried at this location complies with the Containment Requirements established by the US Environmental Protection Agency. One step in determining compliance is to identify those combinations of events and processes (scenarios) that define possible future states of the disposal system for which performance assessments must be performed. An established scenario-development procedure was used to identify a comprehensive set of mutually exclusive scenarios. To assure completeness, 761 features, events, processes, and other listings (FEPS) were compiled from 11 references. This number was reduced to 205 primarily through the elimination of duplications. The 205 FEPs were screened based on site-specific, goal-specific, and regulatory criteria. Four events survived screening and were used in preliminary scenario development: (1) exploratory drilling penetrates a GCD borehole, (2) drilling of a withdrawal/injection well penetrates a GCD borehole, (3) subsidence occurs at the RWMS, and (4) irrigation occurs at the RWMS. A logic diagram was used to develop 16 scenarios from the four events. No screening of these scenarios was attempted at this time. Additional screening of the currently retained events and processes will be based on additional data and information from site-characterization activities. When screening of the events and processes is completed, a final set of scenarios will be developed and screened based on consequence and probability of occurrence.

Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Newman, G. [GRAM, Inc., Albuquerque, NM (United States)

1993-12-01

334

Delineation of soil and groundwater contamination using geophysical methods at a waste disposal site in Canakkale, Turkey.  

PubMed

Direct current (DC) resistivity, self potential (SP) and very low frequency electromagnetic (VLF-EM) measurements are carried out to detect the spread of groundwater contamination and to locate possible pathways of leachate plumes, that resulted from an open waste disposal site of Canakkale municipality. There is no proper management of the waste disposal site in which industrial and domestic wastes were improperly dumped. Furthermore, because of the dumpsite is being located at the catchment area borders of a small creek and is being topographically at a high elevation relative to the urban area, the groundwater is expected to be hazardously contaminated. Interpretations of DC resistivity geoelectrical data showed a low resistivity zone (<5 ohm-m), which appears to be a zone, that is fully saturated with leachate from an open dumpsite. The VLF-EM and SP method, support the results of geoelectrical method relating a contaminated zone in the survey area. There is a good correlation between the geophysical investigations and the results of previously collected geochemical and hydrochemical measurements. PMID:17385055

Kaya, M Ali; Ozrlan, Glin; Sengl, Ebru

2007-12-01

335

Managing dredged sediment placement in open-water disposal sites, Upper Chesapeake Bay  

USGS Publications Warehouse

The maintenance dredging of fine-grained sediment which accumulated in shipping channels in the Upper Chesapeake was discussed. The capacity of open-water sites was maximized in an environmentally acceptable manner to provide adequate time for the development of beneficial use or confined placement sites. The additional water column turbidity generated by dragging operations and bottom sediment movement during placement raised environmental concerns which weighted against the need to maximize capacity. The inter-agency team overseeing site management provided a mechanism to implement operational changes which maximized site capacity and insured operational use through the projected life span of the site.

Panageotou, W.

2002-01-01

336

Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling  

SciTech Connect

A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

Phifer, Mark A.; Smith, Frank G. III

2013-06-21

337

Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site  

SciTech Connect

The 200 Area State-Approved Land Disposal Site (SALDS) is a drainfield which receives treated wastewater, occasionally containing tritium from treatment of Hanford Site liquid wastes at the 200 Area Effluent Treatment Facility (ETF). Since operation of the SALDS began in December 1995, discharges of tritium have totaled {approx}304 Ci, only half of what was originally predicted for tritium quantity through 1999. Total discharge volumes ({approx}2.7E+8 L) have been commensurate with predicted volumes to date. This document reports the results of all tritium analyses in groundwater as determined from the SALDS tritium-tracking network since the first SALDS wells were installed in 1992 through July 1999, and provides interpretation of these results as they relate to SALDS operation and its effect on groundwater. Hydrologic and geochemical information are synthesized to derive a conceptual model, which is in turn used to arrive at an appropriate approach to continued groundwater monitoring at the facility.

DB Barnett

2000-08-31

338

Hydrologic data for the Weldon Spring radioactive waste-disposal sites, St. Charles County, Missouri; 1984-1986  

USGS Publications Warehouse

Hydrologic and water quality data were collected during an investigation of the Weldon Spring radioactive waste disposal sites and surroundings area in St. Charles County, Missouri, from 1984 to 1986. The data consists of water quality analyses of samples collected from 45 groundwater and 27 surface water sites. This includes analyses of water from four raffinate pits and from the Weldon Spring quarry. Also included in the report are the results of a seepage run on north flowing tributaries to Dardenne Creek from Kraut Run to Crooked Creek. Mean daily discharge from April 1985 to April 1986 is given for two springs located about 1.5 mi north of the chemical plant. (USGS)

Kleeschulte, M.J.; Emmett, L.F.; Barks, J.H.

1986-01-01

339

Hydrogeology, ground-water flow, and tritium movement at low-level radioactive-waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

Groundwater flow and tritium movement are described at and near a low-level radioactive waste disposal site near Sheffield, Illinois. Flow in the shallow aquifer is confined to three basins that ultimately drain into a stripmine lake. Most of the flow from the site is through a buried, pebbly sandfilled channel. Remaining flow is toward alluvium of an existing stream. Conceptual flow models for the two largest basins are used to improve definition of flow velocity and direction. Flow velocities range from about 25 to 2,500 ft/yr. Tritium was found in all three basins. The most extensive migration of tritium is coincident with buried channel. Tritium concentrations ranged from detection level to more than 300 nanocuries/L. (USGS)

Garklavs, George; Healy, R.W.

1986-01-01

340

Performance assessment methodology as applied to the Greater Confinement Disposal site: Preliminary results of the third performance iteration  

SciTech Connect

The US Department of Energy has contracted Sandia National Laboratories to conduct a performance assessment of the Greater Confinement Disposal facility, Nevada. The performance assessment is an iterative process in which transport models are used to prioritize site characterization data collection. Then the data are used to refine the conceptual and performance assessment models. The results of the first two performance assessment iterations indicate that the site is likely to comply with the performance standards under the existing hydrologic conditions. The third performance iteration expands the conceptual model of the existing transport system to include possible future events and incorporates these processes in the performance assessment models. The processes included in the third performance assessment are climate change, bioturbation, plant uptake, erosion, upward advection, human intrusion and subsidence. The work completed to date incorporates the effects of bioturbation, erosion and subsidence in the performance assessment model. Preliminary analyses indicate that the development of relatively deep-rooting plant species at the site, which could occur due to climate change, irrigated farming or subsidence, poses the greatest threat to the site`s performance.

Brown, T.J. [Sandia National Labs., Albuquerque, NM (United States); Baer, T.A. [GRAM Inc., Albuquerque, NM (United States)

1994-12-31

341

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

PubMed

During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. Because of periodic saturation and overflowing of the former disposal trenches, Pu and Am have been transferred from the buried wastes into the surrounding surface soils. The presence of readily detected amounts of Pu and Am in the trench waters provides a unique opportunity to study their aqueous speciation under environmentally relevant conditions. This study aims to comprehensively investigate the chemical speciation of Pu and Am in the trench water by combining fluoride coprecipitation, solvent extraction, particle size fractionation, and thermochemical modeling. The predominant oxidation states of dissolved Pu and Am species were found to be Pu(IV) and Am(III), and large proportions of both actinides (Pu, 97.7%; Am, 86.8%) were associated with mobile colloids in the submicron size range. On the basis of this information, possible management options are assessed. PMID:25126837

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

2014-09-01

342

EXECUTIVE SUMMARY OF STATE DATA RELATED TO ABANDONED CENTRALIZED AND COMMERCIAL DRILLING-FLUID DISPOSAL SITES IN LOUISIANA, NEW MEXICO, OKLAHOMA, AND TEXAS  

SciTech Connect

This 2003 Spring Semi-Annual Report contains a summary of the Final Technical Report being prepared for the Soil Remediation Requirements at Commercial and Centralized Drilling-Fluid Disposal (CCDD) Sites project funded by the United States Department of Energy under DOE Award No. DE-AC26-99BC15225. The summary describes (1) the objectives of the investigation, (2) a rationale and methodology of the investigation, (3) sources of data, assessment of data quality, and data availability, (4) examples of well documented centralized and commercial drilling-fluid disposal (CCDD) sites and other sites where drilling fluid was disposed of, and (5) examples of abandoned sites and measures undertaken for their assessment and remediation. The report also includes most of the figures, tables, and appendices that will be included in the final report.

H. Seay Nance

2003-03-01

343

Alternative Evaluation Study: Methods to Mitigate/Accommodate Subsidence for the Radioactive Waste Management Sites at the Nevada Test Site, Nye County Nevada, with Special Focus on Disposal Cell U-3ax/bl  

SciTech Connect

An Alternative Evaluation Study is a type of systematic approach to problem identification and solution. An Alternative Evaluation Study was convened August 12-15, 1997, for the purpose of making recommendations concerning closure of Disposal Cell U-3ax/bl and other disposal cells and mitigation/accommodation of waste subsidence at the Radioactive Waste Management Sites at the Nevada Test Site. This report includes results of the Alternative Evaluation Study and specific recommendations.

Barker, L.

1997-09-01

344

Corrective Action Investigation Plan for Corrective Action Unit 543: Liquid Disposal Units Nevada Test Site, Nevada, Rev. No.: 0 with ROTC 1 and 2  

Microsoft Academic Search

This Corrective Action Investigation Plan (CAIP) contains project-specific information including facility descriptions, environmental sample collection objectives, and criteria for conducting site investigation activities at Corrective Action Unit (CAU) 543: Liquid Disposal Units, Nevada Test Site (NTS), Nevada. This CAIP has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) (1996) that was agreed to by the

David A. Strand

2004-01-01

345

Respiratory and general health impairments of workers employed in a municipal solid waste disposal at an open landfill site in Delhi  

Microsoft Academic Search

The objective of this study was to examine the respiratory and general health of workers employed in a municipal solid waste (MSW) disposal at an open landfill site in India. Ninety-six landfill workers of Okhla landfill site, Delhi, and 90 controls matched for age, sex, and socioeconomic conditions were enrolled. Health data was obtained from questionnaire surveys, clinical examination and

Manas Ranjan Ray; Sanghita Roychoudhury; Gopeshwar Mukherjee; Senjuti Roy; Twisha Lahiri

2005-01-01

346

Ancient Glass Studies: Potential Archaeological Sites Relevant to Low-Activity Waste Disposal at Hanford  

SciTech Connect

In this document we identify several archaeological sites that may be of use in validating the ILAW performance assessment. Glasses that might be recovered at these sites would be recovered with the surrounding soil. This soil would be analyzed and the distribution of elements released from the glass to the soil would be mapped. Coincidence of the actual migration and the modeled migration would constitute a validation exercise of the current performance assessment model for the Hanford Site.

Strachan, Denis M.

2003-03-24

347

Finding of no significant impact shipment of stabilized mixed waste from the K-25 Site to an off-site commercial disposal facility, Oak Ridge K-25 Site, Oak Ridge, Tennessee  

SciTech Connect

The Department of Energy (DOE) has prepared an Environmental Assessment (EA) for the shipment of stabilized mixed waste, removed from K-1407-B and -C ponds, to an off-site commercial disposal facility (Envirocare) for permanent land disposal. Based on the analysis in the EA, DOE has determined that the proposed action is not a major federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issuing this Finding of No Significant Impact (FONSI).

NONE

1994-12-31

348

76 FR 19003 - Land Disposal Restrictions: Nevada and California; Site Specific Treatment Variances for...  

Federal Register 2010, 2011, 2012, 2013, 2014

...site-specific treatment variance to U.S. Ecology Nevada (USEN) located in Beatty, Nevada...site-specific treatment variance to U.S. Ecology Nevada (USEN) located in Beatty, Nevada...This proposal applies only to U. S. Ecology Nevada located in Beatty, Nevada...

2011-04-06

349

Post-Closure Inspection Report for Corrective Action Unit 333: U-3auS Disposal Site Annual Report, Nevada Test Site, Nevada  

SciTech Connect

The U-3auS Disposal Site Corrective Action Unit (CAU) 333 is a closed construction landfill located in Area 3 of the Nevada Test Site. The closure of this site was approved by the Nevada Division of Environmental Protection (NDEP) in a letter to the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV) dated June 27, 2001. Post-closure monitoring requirements are described in a letter from NNSA/NV to NDEP dated October 9, 2001, and were approved by the NDEP in a letter from NDEP to NNSA/NV dated November 5, 2001. Post-closure care consists of the following: Semiannual inspections of the unit using an inspection checklist; Photographic documentation of site conditions; Field note documentation; Performing minor site maintenance as necessary; and Preparation and submittal of an annual report. The annual report consists of copies of the inspection checklist, repair records (if any), photographs, and recommendations and conclusions. The Post-Closure Inspection Checklists are provided in Attachment A, a copy of the field notes is found in Attachment B, and copies of the inspection photographs are provided in Attachment C. Field note documentation is not formally required for this CAU, however in order to be consistent with other reports, it has been added to this report.

K. K. Knapp

2003-09-01

350

The Site Investigation Of Low-Level Radioactive Waste For Sub-Surface Disposal Facility In Japan  

NASA Astrophysics Data System (ADS)

[1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short "the sub-surface disposal facility".This facility can accept the relatively higher low-level waste from unclear power plant operation and in core materials from the decommissioning, estimated about 20 thousands cubic meter in total.In addition, this will accept transuranim (TRU) slightly contaminated waste from reprocessing plant operation and decommissioning. It shall be located at a sufficient depth enough to avoid normal human activities in future. [2.Site investigation] From 2001 to 2006,the site investigation on geology and hydrogeology has been performed in order to acquire the basic data for the design and the safety assessment for the sub-surface disposal facility.The candidate area is located at the site of JNFL, where Rokkasho-mura, Aomori Prefecture in the northern area of the Mainland of Japan.To confirm geology hydraulic conditions and geo-chemistry, 22 boring survey including 6 holes in swamp and marsh have been performed. The 1km long access tunnel (the entrance level EL 8.0m, incline of 1/10) to the altitude of EL -86m underground, around 100m depth from surface, has excavated. During excavating the tunnel, observation of geology, permeability tests, pore water pressure measurements and so on has been performed in situ.And the large size test cavern of 18m diameters was constructed at the end of the tunnel to demonstrate stability of the tunnel. Prior to the excavation, 3 measuring tunnels were excavated surrounding the test cavern to examine the excavation. [3.Geological features] The sedimentary rock called Takahoko formation at the Neogene period is distributed upper than EL-500m in the candidate area.The quaternary stratum about 10m in thickness is distributed on the plateau and covers Takahoko formation.The stratum which consists of sandstone and tuff can be roughly subdivided into two stratums above EL-100m of the candidate area.The upper stratum is a little sandy, and is called pumice mixed sandstone. The lower stratum is called pumice tuff.Several faults have been observed in it.It is inferred that these faults had moved under unconsolidation condition in the early phase of sedimentation.The faults are considered not to become 'water conducting feature' because the interface of fault adheres completely and there is no fracture according to the observation of the drilling core and tunnel through the fault plane. [4. Groundwater] According to the logarithmic mean of hydraulic conductivity estimated by the injection test method with interval of 5-10m, hydraulic conductivity of pumice mixed sandstone and pumice tuff are 9.9E-8m/s, 1.9E-8m/s respectively.The direction of groundwater flow is to the central swamp or to the marsh which connected to the ocean.It is found that the groundwater flow is enough slow and movement of the nuclides will be limited.Groundwater velocity is around 10cm/y.There is no harmful constituent in the groundwater that affect to engineered barrier significantly.Reduction environment observed around the test cavern. [5. Mechanical stability] Its uniaxial compressive strength is around 4MPa, which is sufficient to excavate tunnels.Displacement of the test cavern of 18m diameters is less than 1cm during tunnel excavation.It is strong enough to excavate large tunnels.

Hosoya, S.; Sasaki, T.

2006-12-01

351

Site selection and characterization processes for deep geologic disposal of high level nuclear waste  

SciTech Connect

In this paper, the major elements of the site selection and characterization processes used in the US high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the US program, these processes, which are well defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the US program.

Costin, L.S.

1997-10-01

352

Distribution of gases in the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

The unsaturated zone is a medium that provides pneumatic communication for the movement of gases from wastes buried in landfills to the atmosphere, biota, and groundwater. Gases in unsaturated glacial and eolian deposits near a waste-disposal trench at the low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois, were identified, and the spatial and temporal distributions of the partial pressures of those gases were determined for the period January 1984 through January 1986. Methods for the collection and analyses of the gases are described, as are geologic and hydrologic characteristics of the unsaturated zone that affect gas transport. The identified gases, which are of natural and of waste origin, include nitrogen, oxygen, and argon, carbon dioxide, methane, propane, butane, tritiated water vapor, 14carbon dioxide, and 222 radon. Concentrations of methane and 14carbon dioxide originated at the waste, as shown by partial-pressure gradients of the gases; 14carbon dioxide partial pressures exceeded natural background partial pressures by factors greater than 1 million at some locations. Variations in partial pressures of oxygen and carbon dioxide were seasonal among piezometers because of increased root and soil-microbe respiration during summer. Variations in methane and 14carbon dioxide partial pressures were apparently related to discrete releases from waste sources at unpredictable intervals of time. No greater than background partial pressures for tritiated water vapor or 222 radon were measured. (USGS)

Striegl, Robert G.

1988-01-01

353

Performance assessment of the geological disposal of radioactive wastes in a clay layer: Status for the Mol site  

SciTech Connect

The long-term radiological consequences of the disposal of high-level, long-lived and medium-level wastes, which result from the reprocessing of spent fuel, have been evaluated via two individual steps: a scenario analysis followed by a consequence analysis. The characteristics of the Boom clay and the conditions at the Mol site, as well as a hypothetical repository concept developed for that formation were taken as reference for the performance assessments. In the ``UPDATING 1990`` study the scenario analysis was based on: previous geological evolution scenarios, a fault tree analysis and a geo-prospective approach. A normal evolution scenario as well as some altered evolution scenarios have been identified this way. The altered evolution scenarios selected for further analysis were: a water well scenario, a climatic change scenario and a tectonic fault scenario. Consequence analyses have been carried out for these scenarios and for the various waste types considered. Important dose peaks were calculated for iodine waste. Since 1991 additional studies have been started. In a first study a systematic ``top-down`` approach for the scenario selection process has been applied. In another study additional sensitivity studies are elaborated in order to determine which components of the geological repository excavated in a clay layer influence the most the performance of the disposal system.

Marivoet, J.L.; Bonne, A.A.; Volckaert, G.; Zeevaert, T. [Nuclear Research Center SCK/CEN, Mol (Belgium)

1993-12-31

354

Siting of low-level radioactive waste disposal facilities in Texas  

E-print Network

. Resistivity soundings--Sounding Z . Resistivity soundings--Sounding 3 . Location of resistivity profiles. Resistivity contour map of site . Soil classification by Atterberg limits Falling head permeability test apparatus (Bowman, 1978). The slug test...

Isenhower, Daniel Bruce

1982-01-01

355

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

Microsoft Academic Search

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by groundwater. Low-level radioactive waste may need to

Bedinger

1991-01-01

356

Use of chemometrics methods and multicriteria decision-making for site selection for sustainable on-site sewage effluent disposal  

Microsoft Academic Search

This paper presents a study undertaken to evaluate site suitability for sewage effluent renovation based on physico-chemical characteristics of the soil. The results obtained showed that as the soil becomes acidic, the phosphorus concentration in the soil reduces accordingly. The chloride ion concentration was found to be a reliable indicator for evaluating the soil capacity to remove nitrogen. A high

Wael Al-Shiekh Khalil; Ashantha Goonetilleke; Serge Kokot; Steven Carroll

2004-01-01

357

Comparison of Olkiluoto (Finland) and Forsmark (Sweden) candidate sites for radioactive-waste disposal  

NASA Astrophysics Data System (ADS)

Site characterizations for deep radioactive-waste repositories consider rock properties, groundwater conditions, and the influences of regional settings and site-specific evolution. We present a comparison of these aspects for two candidate repository sites that have similar rocks and coastal settings, but are 200 km apart on opposite sides of the Gulf of Bothnia. The Olkiluoto site in Finland and the Forsmark site in Sweden are both in hard crystalline rock (migmatite gneiss and metagranite, respectively) with groundwater flow mainly via fractures. Both sites are undergoing licensing for a high-level radioactive-waste repository. The licensing is stepwise in Finland, and operation in both countries will be strictly regulated, but all responsibility lies with the implementers until accepted closure. The comparison reveals many expected similarities but also unexplained differences, which illustrate the complexities of site characterization in fractured crystalline rock. Both sites underwent a similar sequence of hydrologic conditions over the Weichselian and earlier glacial cycles. Hydrogeologically, Forsmark has more conductive upper bedrock, contributing to a very flat water table. Deep bedrock at Olkiluoto is more fractured in the horizontal plane. At repository depth and below, Forsmark likely contains larger volumes of low-conductivity rock. At both sites, the local model is connected to regional-scale boundaries via submarine deformation zones which (especially at Olkiluoto) are poorly characterized. Stress measurements at the two sites have shown that vertical stress is in agreement with the weight of overburden while horizontal stresses differ in magnitude and orientation. Interpreted overcoring stress measurements from Forsmark are almost twice the magnitudes estimated from hydraulic methods. Rock mechanical differences include the possibility that Olkiluoto bedrock is more prone to spalling than Forsmark. Olkiluoto bedrock is more anisotropic in terms of thermal properties. Groundwater salinities at proposed repository depth are similar at the two sites, though the salinity gradient at greater depths is steeper at Olkiluoto. Differing depths of penetration of post-glacial groundwater components, and differing patterns of salinity between groundwaters in fractures and pore waters in rock matrix, indicate paleohydrogeological differences. While having broadly similar redox and pH conditions, there is more dissolved methane and lower sulfate below 300 m depth at Olkiluoto than at Forsmark. Water-rock reaction modeling does not explain these and other differences in groundwater compositions and secondary minerals at the two sites. Many of the similarities and differences can be attributed to known regional and local conditions such as stress fields, rock types, fractured-rock hydrodynamics and paleohydrogeology. The processes accounting for some differences are not yet understood, illustrating the limitations of existing models for regional-scale variability in fractured crystalline rock. Site characterization, with the possibility for improved understanding, is expected to continue at both sites in the event of licensing.

Geier, J. E.; Bath, A.; Stephansson, O.; Luukkonen, A.

2012-12-01

358

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

SciTech Connect

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

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

2006-01-18

359

An electrical resistivity logging study of the marine sediments at the offshore dredge disposal site, Galveston, Texas  

E-print Network

A ~ & F L E C T R I C A L R E S I S T I V I T Y L O G G I N G S l U D Y 0 F T H E M A R I N c S F D I M E N T S AT THE OFFSHORE DREDGE DISPOSAL SITE GAI VESTON TEXAS A Thesis by Gerhard William Hill, Jr. Submitted to the Graduate College..., GALVESTON, TEXAS A Thesis by Gerhard Nilliam Hi 11, Jr. , Approved as to style and content by: . )~ j (Co-Chairman of Committee) (Co-Chairman of Committee) (Head of Department (Member) (Member) August 1976 @4QSiG ABSTRACT An Electrical...

Hill, Gerhard William

1976-01-01

360

NRC Consultation and Monitoring at the Savannah River Site: Focusing Reviews of Two Different Disposal Actions - 12181  

SciTech Connect

Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste determinations. The NDAA also requires NRC to monitor DOE's disposal actions related to those determinations. In Fiscal Year 2011, the NRC staff reviewed DOE performance assessments for tank closure at the F-Tank Farm (FTF) Facility and salt waste disposal at the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) as part of consultation and monitoring, respectively. Differences in inventories, waste forms, and key barriers led to different areas of focus in the NRC reviews of these two activities at the SRS. Because of the key role of chemically reducing grouts in both applications, the evaluation of chemical barriers was significant to both reviews. However, radionuclide solubility in precipitated metal oxides is expected to play a significant role in FTF performance whereas release of several key radionuclides from the SDF is controlled by sorption or precipitation within the cementitious wasteform itself. Similarly, both reviews included an evaluation of physical barriers to flow, but differences in the physical configurations of the waste led to differences in the reviews. For example, NRC's review of the FTF focused on the modeled degradation of carbon steel tank liners while the staff's review of the SDF performance included a detailed evaluation of the physical degradation of the saltstone wasteform and infiltration-limiting closure cap. Because of the long time periods considered (i.e., tens of thousands of years), the NRC reviews of both facilities included detailed evaluation of the engineered chemical and physical barriers. The NRC staff reviews of residual waste disposal in the FTF and salt waste disposal in the SDF focused on physical barriers to flow and chemical barriers to radionuclide release from the waste. Because the waste inventory and concentration at both sites is sufficient to generate unacceptable doses to an off-site member of the public or inadvertent intruder in the absence of engineered barriers, the NRC staff review focused on the engineering features DOE plans to put in place to limit radionuclide release. At the FTF, DOE expects that peak doses are delayed beyond a 10,000 year performance period by a combination of (1) the flow-limiting effect of the steel tank liner and (2) chemical conditions created by the stabilizing grout overlying the waste that limit the solubility of key radionuclides for tens of thousands of years. At the SDF, DOE expects that flow will be significantly limited by water shedding along the closure cap lower drainage layer and that radionuclide release will be further limited by radionuclide precipitation or sorption within the high pH, chemically reducing conditions created within the saltstone waste form. Because the performance of both facilities depends on the performance of engineered barriers for thousands of years, the reviews included a detailed evaluation of the expected long-term behavior of these barriers. As previously discussed, NRC staff reviews of DOE waste determinations during consultation are designed to evaluate the three NDAA criteria, whereas the review of an updated PA during monitoring only addresses whether the NRC staff has reasonable assurance that the planned disposal action will meet the performance objectives of 10 CFR Part 61. The NRC staff review of the Waste Determination for the FTF did not include conclusions about whether the planned disposal of residual waste at the FTF would meet the NDAA criteria because of the substantial uncertainties in the degree of waste removal DOE would achieve and other technical uncertainties. The main product of the NRC staff review of the planned FTF disposal action is the recommendation that DOE should conduct waste release experiments to increase support for key modeling assumptions related to: (1) the evolution of pH and Eh in the grouted tank syst

Ridge, A. Christianne; Barr, Cynthia S.; Pinkston, Karen E.; Parks, Leah S.; Grossman, Christopher J.; Alexander, George W. [U.S. Nuclear Regulatory Commission (United States)

2012-07-01

361

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

SciTech Connect

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

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

2004-05-03

362

Revegetation and rock cover for stabilization of inactive uranium mill tailings disposal sites. Final report  

SciTech Connect

Guidelines for using vegetation and rock to protect inactive uranium mill tailings from erosion were developed by Pacific Northwest Laboratory as part of the Department of Energy's Uranium Mill Tailings Remedial Action Project (UMTRAP) Technology Development program. Information on soils, climate, and vegetation were collected for 20 inactive tailings sites in the western United States. Sites were grouped according to similarities in climate and vegetation. Soil loss for those sites was characterized using the Universal Soil Loss Equation. Test plots were used to evaluate (1) the interaction between vegetation and sealant barrier systems and (2) the effects of surface rock on soil water and vegetation. Lysimeter and simulation studies were used to direct and support field experiments. 49 references, 17 figures, 16 tables.

Beedlow, P.A.

1984-05-01

363

Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.  

PubMed

The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place. PMID:24654382

Korucu, M Kemal; Karademir, Aykan

2014-02-01

364

1992 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites. National Low-Level Waste Management Program  

SciTech Connect

Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1992 and a comparison of waste volumes and radioactivity by state for 1988 through 1992; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1992. This report distinguishes between low-level radioactive waste shipped directly for disposal by generators and waste that was handled by an intermediary, a reporting change introduced in the 1988 state-by-state report.

Fuchs, R.L.; McDonald, S.D.

1993-09-01

365

ASSESSMENT OF SYNTHETIC MEMBRANE SUCCESSES AND FAILURES AT WASTE STORAGE AND DISPOSAL SITES  

EPA Science Inventory

Data from 27 lined facilities provided by five vendors was analyzed to determine the factors which contributed to success or failure of the liner at those facilities. The sites studied included a wide variety of wastes handled, liner types, geographic locations, facility ages, fa...

366

76 FR 18921 - Land Disposal Restrictions: Nevada and California; Site Specific Treatment Variances for...  

Federal Register 2010, 2011, 2012, 2013, 2014

...Kettleman Hills, California a site-specific...hazardous selenium-bearing waste generated...their Vernon, California manufacturing...waste to reagent ratio of 1 to 2.7...hazardous selenium-bearing waste generated...Owens-Brockway in Vernon, California, with the RCRA...waste to reagent ratio not exceed...

2011-04-06

367

Mineral precipitation and dissolution at two slag-disposal sites in northwestern Indiana, USA  

USGS Publications Warehouse

Slag is a ubiquitous byproduct of the iron- and steel-refining industries. In northwestern Indiana and northeastern Illinois, slag has been deposited over more than 52 km2 of land surface. Despite the widespread use of slag for fill and construction purposes, little is known about its chemical effects on the environment. Two slagdisposal sites were examined in northwestern Indiana where slag was deposited over the native glacial deposits. At a third site, where slag was not present, background conditions were defined. Samples were collected from cores and drill cuttings and described with scanning electron microscopy and electron microprobe analysis. Ground-water samples were collected and used to assess thermodynamic equilibria between authigenic minerals and existing conditions. Differences in the mineralogy at background and slag-affected sites were apparent. Calcite, dolomite, gypsum, iron oxides, and clay minerals were abundant in native sediments immediately beneath the slag. Mineral features indicated that these minerals precipitated rapidly from slag drainage and co-precipitated minor amounts of non-calcium metals and trace elements. Quartz fragments immediately beneath the slag showed extensive pitting that was not apparent in sediments from the background site, indicating chemical weathering by the hyperalkaline slag drainage. The environmental impacts of slag-related mineral precipitation include disruption of natural ground-water flow patterns and bed-sediment armoring in adjacent surface-water systems. Dissolution of native quartz by the hyperalkaline drainage may cause instability in structures situated over slag fill or in roadways comprised of slag aggregates.

Bayless, E.R.; Schulz, M.S.

2003-01-01

368

On-site disposal of commercial radioactive waste: the ONSITE\\/MAXI1 computer program  

Microsoft Academic Search

Because of uncertainties associated with assessing the potential risk from on-site burial of commercial radioactive wastes, the US Nuclear Regulatory Commission (NRC) has amended its regulations to provide greater assurance that buried radioactive material will not present a hazard to public health and safety. The current policy of NRC is to review requests by operators to bury radioactive waste on

W. E. Jr. Kennedy; R. A. Peloquin; B. A. Napier; S. M. Neuder

1985-01-01

369

Analysis of the technical capabilities of DOE sites for disposal of residuals from the treatment of mixed low-level waste  

SciTech Connect

The US Department of Energy (DOE) has stored or expects to generate over the next five years more than 130,000 m{sup 3} of mixed low-level waste (MLLW). Before disposal, MLLW is usually treated to comply with the land disposal restrictions of the Resource Conservation and Recovery Act. Depending on the type of treatment, the original volume of MLLW and the radionuclide concentrations in the waste streams may change. These changes must be taken into account in determining the necessary disposal capacity at a site. Treatment may remove the characteristic in some waste that caused it to be classified as mixed. Treatment of some waste may, by reduction of the mass, increase the concentrations of some transuranic radionuclides sufficiently so that it becomes transuranic waste. In this report, the DOE MLLW streams were analyzed to determine after-treatment volumes and radionuclide concentrations. The waste streams were reclassified as residual MLLW or low-level or transuranic waste resulting from treatment. The volume analysis indicated that about 89,000 m{sup 3} of waste will require disposal as residual MLLW. Fifteen DOE sites were then evaluated to determine their capabilities for hosting disposal facilities for some or all of the residual MLLW. Waste streams associated with about 90% of the total residual MLLW volume are likely to present no significant issues for disposal and require little additional analysis. Future studies should focus on the remaining waste streams that are potentially problematic by examining site-specific waste acceptance criteria, alternative treatment processes, alternative waste forms for disposal, and pending changes in regulatory requirements.

Waters, R.D.; Gruebel, M.M.; Langkopf, B.S.; Kuehne, P.B.

1997-04-01

370

Wastewater movement near four treatment and disposal sites in Yellowstone National Park, Wyoming  

USGS Publications Warehouse

The U.S. Geological Survey, in cooperation with the National Park Service, studied the effects on nearby streams and lakes of treated wastewater effluents that percolate from sewage lagoons at four sites in Yellowstone National Park. A network of observation wells has been established near the sites, and water level and water quality data were collected from 1974 through 1982. Groundwater mounds occur under the lagoons as percolation of effluents occurs. The percolating effluents mix with groundwater and form plumes of water that contain chemical constituents from the effluents. These plumes move down the hydraulic gradient toward groundwater discharge areas. The directions of movement of percolating effluents have been determined by analyzing water samples from wells near the lagoons for specific conductance, chloride concentration, and nitrite plus nitrate concentration. Other constituents and properties also were determined. The percolating effluents are diluted by groundwater and have no discernible effects on the quality of water in the nearby streams and lakes. (USGS)

Cox, E.R.

1986-01-01

371

Evaluation of geologic materials to limit biological intrusion into low-level radioactive waste disposal sites  

SciTech Connect

This report describes the results of a three-year research program to evaluate the performance of selected soil and rock trench cap designs in limiting biological intrusion into simulated waste. The report is divided into three sections including a discussion of background material on biological interactions with waste site trench caps, a presentation of experimental data from field studies conducted at several scales, and a final section on the interpretation and limitations of the data including implications for the user.

Hakonson, T.E.

1986-02-01

372

Rooting depths of plants on low-level waste disposal sites  

Microsoft Academic Search

In 1981-1982 an extensive bibliographic study was done to reference rooting depths of native plants in the United States. The data base presently contains 1034 different rooting citations with approximately 12,000 data elements. For this report, data were analyzed for rooting depths related to species found on low-level waste (LLW) sites at Los Alamos National Laboratory. Average rooting depth and

T. S. Foxx; G. D. Tierney; J. M. Williams

1984-01-01

373

The determination of settling velocities for sewage sludge disposed at 106-Mile Site  

E-print Network

THE DBTERMZNATZON OF SETTLING VELOCZTZES FOR SEWAGE SLUDGE DZSPOSED AT 106-MILE SITE A Thesis by DANIEL SAUL HERNANDEZ Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of requirements for the degree... of MASTER OF SCIENCE December 1991 Major Subject: Civil Engineering THB DETERMZNATZON OF SBTTLZNG VELOCZTZES FOR SEWAGE SLUDGE DZSPOSBD AT 106-MZLE SZTB A Thesis by DANIEL SAUL HERNANDEZ Approved as to style and content by: James S. Bonner '(Chair...

Hernandez, Daniel Saul

1991-01-01

374

Hydrogeology of a low-level radioactive-waste disposal site near Sheffield, Illinois  

USGS Publications Warehouse

The Sheffield low-level radioactive-waste facility is located on 20 acres of rolling terrain 3 miles southwest of Sheffield, Illinois. The shallow hydrogeologic system is composed of glacial sediments. Pennsylvania shale and mudstone bedrock isolate the regional aquifers below from the hydrogeologic system in the overlying glacial deposits. Pebbly sand underlies 67 percent of the site. Two ground-water flow paths were identified. The primary path conveys ground water from the site to the east through the pebbly-sand unit; a secondary path conveys ground water to the south and east through less permeable material. The pebbly-sand unit provides an underdrain that eliminates the risk of water rising into the trenches. Digital computer model results indicate that the pebbly-sand unit controls ground-water movement. Tritium found migrating in ground water in the southeast corner of the site travels approximately 25 feet per year. A group of water samples from wells which contained the highest tritium concentrations had specific conductivities, alkalinities, hardness, and chloride, sulfate, calcium, and magnesium contents higher than normal for local shallow ground water. (USGS)

Foster, J.B.; Erickson, J.R.; Healy, R.W.

1984-01-01

375

Rooting depths of plants on low-level waste disposal sites  

SciTech Connect

In 1981-1982 an extensive bibliographic study was done to reference rooting depths of native plants in the United States. The data base presently contains 1034 different rooting citations with approximately 12,000 data elements. For this report, data were analyzed for rooting depths related to species found on low-level waste (LLW) sites at Los Alamos National Laboratory. Average rooting depth and rooting frequencies were determined and related to present LLW maintenance. The data base was searched for information on rooting depths of 53 species found on LLW sites at Los Alamos National Laboratory. The study indicates 12 out of 13 grasses found on LLW sites root below 91 cm. June grass (Koeleria cristata (L.) Pers.) (76 cm) was the shallowest rooting grass and side-oats grama (Bouteloua curtipendula (Michx.) Torr.) was the deepest rooting grass (396 cm). Forbs were more variable in rooting depths. Indian paintbrush (Castelleja spp.) (30 cm) was the shallowest rooting forb and alfalfa (Medicago sativa L.) was the deepest (>3900 cm). Trees and shrubs commonly rooted below 457 cm. The shallowest rooting tree was elm (Ulmus pumila L.) (127 cm) and the deepest was one-seed juniper (Juniperus monosperma (Engelm) Sarg.) (>6000 cm). Apache plume (Fallugia paradoxa (D. Don) Endl.) rooted to 140 cm, whereas fourwing saltbush (Atriplex canecens (Pursh) Nutt.) rooted to 762 cm.

Foxx, T.S.; Tierney, G.D.; Williams, J.M.

1984-11-01

376

Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State-Approved Land Disposal Site-FY1999  

SciTech Connect

The Hanford Site 200 Area Effluent Treatment Facility (ETF) processes contaminated liquids derived from Hanford Site facilities. The clean water generated by these processes is occasionally enriched in tritium and is discharged to the 200 Area State Approved Land Disposal Site (SALDS). Groundwater monitoring for tritium and other constituents is required by the state-issued permit at 21 wells surrounding the facility. During FY 1999, average tritium activities in most wells declined from average activities in 1998. The exception was deep well 69948-77C, where tritium results were at an all-time high (77,000 pCi/L) as a result of the delayed penetration of effluent deeper into the aquifer. Of the 12 constituents with permit enforcement limits, which are monitored in SALDS proximal wells, all were within limits during FY 1999. Water level measurements in nearby wells indicate that a small hydraulic mound exists around the SALDS facility as a result of discharges. This feature is directing groundwater flow radially outward a short distance before the regional northeasterly flow predominates. Evaluation of this condition indicates that the network is currently adequate for tracking potential effects of the SALDS on the groundwater. Recommendations include the discontinuation of ammonia, benzene, tetrahydrofuran, and acetone from the regular groundwater constituent list; designating background well 299-W8-1 as a tritium-tracking well only, and the use of quadruplicate averages of field pH, instead of a single laboratory measurement, as a permit compliance parameter.

Barnett, D.B.

1999-10-20

377

Groundwater Monitoring and Tritium-Tracking Plan for the 200 Area State-Approved Land Disposal Site  

SciTech Connect

The 200 Area State-Approved Land Disposal Site (SALDS) is a drainfield which receives treated wastewater, occasionally containing high levels of tritium from treatment of Hanford Site liquid wastes. Only the SALDS proximal wells (699-48-77A, 699-48-77C, and 699-48-77D) have been affected by tritium from the facility thus far; the highest activity observed (2.1E+6 pCi/L) occurred in well 699-48-77D in February 1998. Analytical results of groundwater geochemistry since groundwater monitoring began at the SALDS indicate that all constituents with permit enforcement limits have been below those limits with the exception of one measurement of total dissolved solids (TDS) in 1996. The revised groundwater monitoring sampling and analysis plan eliminates chloroform, acetone, tetrahydrofuran, benzene, and ammonia as constituents. Replicate field measurements will replace laboratory measurements of pH for compliance purposes. A deep companion well to well 699-51-75 will be monitored for tritium deeper in the uppermost aquifer.

Barnett, D. Brent

2000-08-31

378

Transport and fate of organic wastes in groundwater at the Stringfellow hazardous waste disposal site, southern California  

USGS Publications Warehouse

In January 1999, wastewater influent and effluent from the pretreatment plant at the Stringfellow hazardous waste disposal site were sampled along with groundwater at six locations along the groundwater contaminant plume. The objectives of this sampling and study were to identify at the compound class level the unidentified 40-60% of wastewater organic contaminants, and to determine what organic compound classes were being removed by the wastewater pretreatment plant, and what organic compound classes persisted during subsurface waste migration. The unidentified organic wastes are primarily chlorinated aromatic sulfonic acids derived from wastes from DDT manufacture. Trace amounts of EDTA and NTA organic complexing agents were discovered along with carboxylate metabolites of the common alkylphenolpolyethoxylate plasticizers and nonionic surfactants. The wastewater pretreatment plant removed most of the aromatic chlorinated sulfonic acids that have hydrophobic neutral properties, but the p-chlorobenzenesulfonic acid which is the primary waste constituent passed through the pretreatment plant and was discharged in the treated wastewaters transported to an industrial sewer. During migration in groundwater, p-chlorobenzenesulfonic acid is removed by natural remediation processes. Wastewater organic contaminants have decreased 3- to 45-fold in the groundwater from 1985 to 1999 as a result of site remediation and natural remediation processes. The chlorinated aromatic sulfonic acids with hydrophobic neutral properties persist and have migrated into groundwater that underlies the adjacent residential community. Copyright ?? 2001 .

Leenheer, J.A.; Hsu, J.; Barber, L.B.

2001-01-01

379

Application of the Spanish methodological approach for biosphere assessment to a generic high-level waste disposal site.  

PubMed

A methodological approach which includes conceptual developments, methodological aspects and software tools have been developed in the Spanish context, based on the BIOMASS "Reference Biospheres Methodology". The biosphere assessments have to be undertaken with the aim of demonstrating compliance with principles and regulations established to limit the possible radiological impact of radioactive waste disposals on human health and on the environment, and to ensure that future generations will not be exposed to higher radiation levels than those that would be acceptable today. The biosphere in the context of high-level waste disposal is defined as the collection of various radionuclide transfer pathways that may result in releases into the surface environment, transport within and between the biosphere receptors, exposure of humans and biota, and the doses/risks associated with such exposures. The assessments need to take into account the complexity of the biosphere, the nature of the radionuclides released and the long timescales considered. It is also necessary to make assumptions related to the habits and lifestyle of the exposed population, human activities in the long term and possible modifications of the biosphere. A summary on the Spanish methodological approach for biosphere assessment are presented here as well as its application in a Spanish generic case study. A reference scenario has been developed based on current conditions at a site located in Central-West Spain, to indicate the potential impact to the actual population. In addition, environmental change has been considered qualitatively through the use of interaction matrices and transition diagrams. Unit source terms of (36)Cl, (79)Se, (99)Tc, (129)I, (135)Cs, (226)Ra, (231)Pa, (238)U, (237)Np and (239)Pu have been taken. Two exposure groups of infants and adults have been chosen for dose calculations. Results are presented and their robustness is evaluated through the use of uncertainty and sensitivity analyses. PMID:18614203

Agero, A; Pinedo, P; Simn, I; Cancio, D; Moraleda, M; Trueba, C; Prez-Snchez, D

2008-09-15

380

Accumulation and persistence of chlorobiphenyls, organochlorine pesticides and faecal sterols at the Garroch Head sewage sludge disposal site, Firth of Clyde  

Microsoft Academic Search

The sediment concentrations of organic carbon, faecal sterols, individual chlorobiphenyl congeners and organochlorine pesticides have been measured in seabed cores from the sewage sludge disposal area at Garroch Head in the Firth of Clyde. The measurements confirm the accumulative nature of the site with high levels of sedimentary faecal sterols (152 mg kg?1 coprostanol). Levels of chlorobiphenyls, DDT compounds and

A. G. Kelly

1995-01-01

381

Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax\\/bl at the Nevada Test Site  

Microsoft Academic Search

In October 2000, final closure was initiated of U-3ax\\/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to

Daniel G. Levitt; Thomas M. Fitzmaurice

2001-01-01

382

Addendum to the Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This document constitutes an addendum to the November 2002, Closure Report for Corrective Action Unit 356: Mud Pits and Disposal Sites as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: This cover page that refers the reader to the UR Modification document for additional information The cover and signature pages of the UR Modification document The NDEP approval letter The corresponding section of the UR Modification document This addendum provides the documentation justifying the cancellation of the URs for: CAS 03-04-01, Area 3 Change House Septic System CAS 03-09-04, Mud Pit These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004f). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

Lynn Kidman

2008-10-01

383

Organizational approach to estimating public resistance at proposed disposal sites for radioactive and hazardous wastes  

SciTech Connect

This paper was intended to present an organizational approach to predicting collective action and then to apply that approach to the issue of siting of a nuclear or other hazardous waste repository. Borrowing largely from two previously developed models (one by Perry et al. at Battelle's Human Affairs Research Center and one by Charles Tilly), I developed a theoretical model. Indicators were identified for many of the variables, but they are not easily measured, requiring a number of decisions on thresholds which were not clarified in the paper. What remains is further discussion of these measurement problems, evaluation of the confirmation status of the propositions, and empirical tests of the model. In the meantime, however, the discussion should provide assessors of public resistance with a theoretical basis for their thinking and a guide to some revealing indicators of the potential for collective action.

Payne, B.A.

1982-01-01

384

Evaluation of liners for a uranium-mill tailings disposal site: a status report  

SciTech Connect

The United States Department of Energy is conducting a program designed to reclaim or stabilize inactive uranium-mill tailings sites. This report presents the status of the Liner Evaluation Program. The purpose of the study was to identify eight prospective lining materials or composites for laboratory testing. The evaluation was performed by 1) reviewing proposed regulatory requirements to define the material performance criteria; 2) reviewing published literature and communicating with industrial and government experts experienced with lining materials and techniques; and 3) characterizing the tailings at three of the sites for calcium concentration, a selection of anions, radionuclides, organic solvents, and acidity levels. The eight materials selected for laboratory testing are: natural soil amended with sodium-saturated montmorillonite (Volclay); locally available clay in conjunction with an asphalt emulsion radon suppression cover; locally available clay in conjunction with a multibarrier radon suppression cover; rubberized asphalt membrane; hydraulic asphalt concrete; chlorosulfonated polyethylene (hypalon) or high-density polyethylene; bentonite, sand and gravel mixture; and catalytic airblown asphalt membrane. The materials will be exposed in test units now being constructed to conditions such as wet/dry cycles, temperature cycles, oxidative environments, ion-exchange elements, etc. The results of the tests will identify the best material for field study. The status report also presents the information gathered during the field studies at Grand Junction, Colorado. Two liners, a bentonite, sand and gravel mixture, and a catalytic airblown asphalt membrane, were installed in a prepared trench and covered with tailings. The liners were instrumented and are being monitored for migration of moisture, radionuclides, and hazardous chemicals. The two liner materials will also be subjected to accelerated laboratory tests for a comparative assessment.

Buelt, J.L.; Hale, V.Q.; Barnes, S.M.; Silviera, D.J.

1981-05-01

385

Effects of low-level radioactive-waste disposal on water chemistry in the unsaturated zone at a site near Sheffield, Illinois, 1982-1984  

Microsoft Academic Search

The report details the changes in the chemistry of pore water as it infiltrates areas undisturbed and disturbed by waste-disposal operations. The report (1) describes the techniques used to obtain representative samples of geologic materials and water from the unsaturated zone; (2) describes the chemistry of geologic materials and water in the unsaturated and saturated zones at off-site and on-site

C. A. Peters; R. G. Striegl; P. C. Mills; R. W. Healy

1993-01-01

386

Modeling the Hydrogeochemical Transport of Radionuclides through Engineered Barriers System in the Proposed LLW Disposal Site of Taiwan - 12082  

SciTech Connect

A proposed site for final disposal of low-level radioactive waste located in Daren Township of Taitung County along the southeastern coast has been on the selected list in Taiwan. The geology of the Daren site consists of argillite and meta-sedimentary rocks. A mined cavern design with a tunnel system of 500 m below the surface is proposed. Concrete is used as the main confinement material for the engineered barrier. To investigate the hydrogeochemical transport of radionuclides through engineered barriers system, HYDROGEOCHEM5.0 model was applied to simulate the complex chemical interactions among radionuclides, the cement minerals of the concrete, groundwater flow, and transport in the proposed site. The simulation results showed that the engineered barriers system with the side ditch efficiently drained the ground water and lowered the concentration of the concrete degradation induced species (e.g., hydrogen ion, sulfate, and chloride). The velocity of groundwater observed at side ditch gradually decreased with time due to the fouling of pore space by the mineral formation of ettringite and thaumasite. The short half-life of Co-60, Sr-90 and Cs-137 significantly reduced the concentrations, whereas the long half-life of I-129(1.57x10{sup 7} years) and Am-241(432 years) remain stable concentrations at the interface of waste canister and concrete barrier after 300 years. The mineral saturation index (SI) was much less than zero due to the low aqueous concentration of radionuclide, so that the precipitation formation of Co-60, Sr-90, I-129, Cs-137 and Am-241 related minerals were not found. The effect of adsorption/desorption (i.e., surface complexation model) could be a crucial geochemical mechanism for the modeling of liquid-solid phase behavior of radionuclide in geochemically dynamic environments. Moreover, the development of advanced numerical models that are coupled with hydrogeochemical transport and dose assessment of radionuclide is required in the future. (authors)

Lin, Wen-Sheng [Hydrotech Research Institute, National Taiwan University, Taipei, Taiwan (China); Liu, Chen-Wuing; Tsao, Jui-Hsuan [Department of Bioenvironmental Systems Engineering, National Taiwan University, Taipei, Taiwan (China); Li, Ming-Hsu [Institute of Hydrological and Oceanic Sciences, National Central University, Jhongli, Taiwan (China)

2012-07-01

387

Mobilization of colloids in groundwater due to infiltration of water at a coal ash disposal site  

NASA Astrophysics Data System (ADS)

We investigated groundwaters in the vicinity of a coal ash site near an electric generating station in the western U.S.A. The purpose of the study was to ascertain why fine particles or colloids appear in some subsurface water samples there. If such fine particles are merely introduced during bailing or pumping operations which suspend otherwise immobile soil colloids, we should exclude these particulate materials from the water samples before analysis intended to quantify what is moving through the aquifer. However, if the colloids were truly suspended and moving with the groundwater flow in situ, then we should includes their contribution to our assessment of the mobile loads. Application of very careful sampling techniques (slow pumping rates, no atmospheric exposure) did not cause the large quantities of colloids observed previously to disappear from well water in which they occured. Additionally, the same sampling procedures did not cause similar abundances of colloids to appear in waters collected from neighboring wells installed and developed in the same manner and in the same geologic strata. Thus we believe sampling artifacts do not explain the colloids' presence in the groundwater samples. On the other hand, the groundwater chemistry and the nature of the suspended colloids (size, composition) strongly suggest these fine particles were suspended and therefore moving with the groundwater flow. At wells exhibiting large amounts of suspended colloids (?10-100 mg L -1), the water was enriched in CO 2 and depleted in O 2 relative to nearby locations. The colloids were typically between 0.1 and 2 ?m in size and were primarily silicates. These results suggest to us that, where infiltrating water is percolating through a site that has been mixed with coal ash, the secondary carbonate mineral in the soils are being dissolved; removal of this cementing carbonate phase may consequently release soil silicate colloids to be carried in the flowing water. Such processes may enhance contaminant transport in groundwater by augmenting the pollutant load moving in the groundwater, and increasing the permeability of the porous medium to pollutant infiltration with water water and/or rainwater.

Gschwend, Philip M.; Backhus, Debera A.; MacFarlane, John K.; Page, A. L.

1990-12-01

388

Uranium mill tailings remedial action program. Radiological survey of Shiprock vicinity property SH03, Shiprock, NM, July-November 1982  

SciTech Connect

A comprehensive survey of the vicinity property designated as SH03 was conducted on an intermittent basis from July 26 to November 11, 1982. At the time of the survey, three structures were located on the property - a residential trailer, the main structure, and an old gas pump housing. The lands surrounding the structures were either sparsely covered with arid vegetation or paved. The assessment activities included determination of indoor and outdoor surface radiation levels, for both fixed and removable contamination, through direct instrument and smear (indoor only) surveys; measurement of ambient external penetrating radiation levels at 1-meter heights; and analyses of air, soil, and other material samples. No evidence of radioactive contamination was found inside the trailer. However, the results of the radiological assessment did indicate the occurrence of elevated levels of gamma, surface alpha, and radon daughter radioactivity within the main structure. The short-term radon daughter measurements exceeded the limit of 0.02 Working Level for average annual concentration including background. The assessment also indicated elevated levels of radioactivity in the outdoor environs, encompassing about 32,000 ft/sup 2/ of the grounds adjacent to and surrounding the main structure on the east, south, and west sides. The contamination appeared to be due to the presence of unprocessed uranium ore. Analysis of surface soil samples collected from the environs indicated radium concentrations in excess of the limit of 5 pCi/g above background specified in the EPA Standard. Subsurface soil sampling was not conducted, and thus the vertical extent of the radiological contamination is not known. Since the surface soil contamination levels exceeded the limits specified in the EPA Standard, remedial action for this vicinity site should be considered.

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

1984-04-01

389

Enhanced detection of groundwater contamination from a leaking waste disposal site by microbial community profiles  

NASA Astrophysics Data System (ADS)

Groundwater biogeochemistry is adversely impacted when municipal solid waste leachate, rich in nutrients and anthropogenic compounds, percolates into the subsurface from leaking landfills. Detecting leachate contamination using statistical techniques is challenging because well strategies or analytical techniques may be insufficient for detecting low levels of groundwater contamination. We sampled profiles of the microbial community from monitoring wells surrounding a leaking landfill using terminal restriction fragment length polymorphism (T-RFLP) targeting the 16S rRNA gene. Results show in situ monitoring of bacteria, archaea, and the family Geobacteraceae improves characterization of groundwater quality. Bacterial T-RFLP profiles showed shifts correlated to known gradients of leachate and effectively detected changes along plume fringes that were not detected using hydrochemical data. Experimental sediment microcosms exposed to leachate-contaminated groundwater revealed a shift from a ?-Proteobacteria and Actinobacteria dominated community to one dominated by Firmicutes and ?-Proteobacteria. This shift is consistent with the transition from oxic conditions to an anoxic, iron-reducing environment as a result of landfill leachate-derived contaminants and associated redox conditions. We suggest microbial communities are more sensitive than hydrochemistry data for characterizing low levels of groundwater contamination and thus provide a novel source of information for optimizing detection and long-term monitoring strategies at landfill sites.

Mouser, Paula J.; Rizzo, Donna M.; Druschel, Gregory K.; Morales, Sergio E.; Hayden, Nancy; O'Grady, Patrick; Stevens, Lori

2010-12-01

390

Corrective Action Decision Document\\/Closure Report for Corrective Action Unit 561: Waste Disposal Areas, Nevada National Security Site, Nevada, Revision 0  

Microsoft Academic Search

CAU 561 comprises 10 CASs: (1) 01-19-01, Waste Dump; (2) 02-08-02, Waste Dump and Burn Area; (3) 03-19-02, Debris Pile; (4) 05-62-01, Radioactive Gravel Pile; (5) 12-23-09, Radioactive Waste Dump; (6) 22-19-06, Buried Waste Disposal Site; (7) 23-21-04, Waste Disposal Trenches ; (8) 25-08-02, Waste Dump; (9) 25-23-21, Radioactive Waste Dump; and (10) 25-25-19, Hydrocarbon Stains and Trench. The purpose

Mark Krauss

2011-01-01

391

Geohydrology of the upper part of the Galena-Platteville aquifer underlying a waste-disposal site near Wempletown, Illinois  

USGS Publications Warehouse

The uppermost bedrock of the Galena-Platteville aquifer underlying a waste-disposal site near Wempletown, Illinois, is composed of dolomite of the St. James, Beecher, Eagle Point, and Fairplay Members of the Dunleith Formation of the Galena Group. Chert beds in these formations have a higher porosity than the dolomite. Ground-water flow is from a drum-storage area to the west and northwest toward low points west and northwest of the drum-storage area and the topographic low at the intermittent stream south of the landfill area. The direction of ground-water flow at the landfill area is affected by seasonal changes in precipitation. Calculated horizontal ground-water velocities ranged from 3.5 x 10-2 to 8.8 x 10-2 feet per day; the lowest value was in the vicinity of the landfill area. Horizontal hydraulic-conductivity values calculated from single-well aquifer tests ranged from 1.0 x 10-2 to 1.0 x 100 feet per day with an average of 4.0 x 10-1 feet per day.

Robinson, Steven M.; Yeskis, Douglas J.

1998-01-01

392

Ground-water levels and precipitation data at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky, October 1988-September 2000  

USGS Publications Warehouse

The U.S. Geological Survey, in cooperation with the Kentucky Natural Resources and Environmental Protection Cabinet--Department for Environmental Protection--Division of Waste Management, has an ongoing program to monitor water levels at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky. Ground-water-level and precipitation data were collected from 112 wells and 1 rain gage at the Maxey Flats low-level radioactive waste disposal site during October 1988-September 2000. Data were collected on a semi-annual basis from 62 wells, continuously from 6 wells, and monthly or bimonthly from 44 wells (13 of which had continuous recorders installed for the period October 1998-September 2000). One tipping-bucket rain gage was used to collect data at the Maxey Flats site for the period October 1988-September 2000.

Zettwoch, Douglas D.

2002-01-01

393

Effects of land disposal of municipal sewage sludge on soil, streambed sediment, and ground- and surface-water quality at a site near Denver, Colorado  

SciTech Connect

The report describes the effects of burial and land application of municipal sewage sludge on soil and streambed sediment and water quality in the underlying aquifers and surface water within and around the Lowry sewage-sludge-disposal area. The existing ground-water observation-well network at the disposal area was expanded for the study. Surface-water-sampling sites were selected so that runoff could be sampled from intense rainstorms or snowmelt. The sampling frequency for ground-water and surface-water runoff was changed from yearly to quarterly, and soil samples were collected. Four years of data were collected from 1984 to 1987 during the expanded monitoring program at the Lowry sewage-sludge-disposal area. These data, in addition to the data collected by the U.S. Geological Survey from 1981 to 1983, were used to determine effects of sewage-sludge-disposal on soil and streambed sediment and surface- and ground-water quality at the disposal area.

Gaggiani, N.G.

1991-01-01

394

CHARACTERIZATION OF DEFENSE NUCLEAR WASTE USING HAZARDOUS WASTE GUIDANCE. APPLICATIONS TO HANFORD SITE ACCELERATED HIGH-LEVEL WASTE TREATMENT AND DISPOSAL MISSION0  

SciTech Connect

Federal hazardous waste regulations were developed for management of industrial waste. These same regulations are also applicable for much of the nation's defense nuclear wastes. At the U.S. Department of Energy's (DOE) Hanford Site in southeast Washington State, one of the nation's largest inventories of nuclear waste remains in storage in large underground tanks. The waste's regulatory designation and its composition and form constrain acceptable treatment and disposal options. Obtaining detailed knowledge of the tank waste composition presents a significant portion of the many challenges in meeting the regulatory-driven treatment and disposal requirements for this waste. Key in applying the hazardous waste regulations to defense nuclear wastes is defining the appropriate and achievable quality for waste feed characterization data and the supporting evidence demonstrating that applicable requirements have been met at the time of disposal. Application of a performance-based approach to demonstrating achievable quality standards will be discussed in the context of the accelerated high-level waste treatment and disposal mission at the Hanford Site.

Hamel, William; Huffman, Lori; Lerchen, Megan; Wiemers, Karyn

2003-02-27

395

Performance Assessment of a Low-Level Radioactive Waste Disposal Site using GoldSim Integrated Systems Model  

NASA Astrophysics Data System (ADS)

Texas Commission on Environmental Quality has approved licenses for four landfills at the Waste Control Specialists (WCS) site located in Andrews County, West Texas. The site includes a hazardous waste landfill and three landfills for radioactive waste. An updated performance assessment is necessary prior to acceptance of waste at the landfills. The updated performance assessment a) provides for more realistic and flexible dose modeling capabilities, b) addresses all plausible release and accident scenarios as they relate to the performance objectives, c) includes impact of climate and hydrologic scenarios that may impact long-term performance of the landfill, d) addresses impact of cover naturalization and degradation on the landfill, and e) incorporates uncertainty and sensitivity analysis for critical parameters. For the updated performance assessment, WCS has developed an integrated systems level performance assessment model using the GoldSim platform. GoldSim serves as a model for integrating all of the major components of a performance assessment, which include the radionuclide source term, facility design, environmental transport pathways, exposure scenarios, and radiological doses. Unlike many computer models that are based on first principles, GoldSim is a systems level model that can be used to integrate and abstract more complex sub-models into one system. This can then be used to assess the results into a unified model of the disposal system and environment. In this particular application, the GoldSim model consists of a) hydrogeologic model that simulates flow and transport through the Dockum geologic unit that underlies all of the waste facilities, b) waste cells that represent the containment unit and simulate degradation of waste forms, radionuclide leaching, and partitioning into the liquid and vapor phase within the waste unit, c) a cover system model that simulates upward diffusive transport from the underground repository to the atmosphere. In addition modules are included for human intrusion scenarios. Inputs and parameters for the hydrogeologic model are developed from a more detailed, numerical, vadose zone model (implemented in HYDRUS 2D). The Vadose zone model calculates fluxes through the waste under various climatic and cover-degradation scenarios. Uncertainty related to model parameters and boundary/initial conditions is also incorporated in the flux distribution through sensitivity analyses in the vadose zone model. Doses are calculated for onsite and offsite receptors through ingestion, inhalation, and external exposure, for comparison with regulatory dose standards. This modeling is part of an ongoing licensing effort to demonstrate compliance with low-level waste site performance objectives.

Merrell, G.; Singh, A.; Tauxe, J.; Perona, R.; Dornsife, W.; grisak, G. E.; Holt, R. M.

2011-12-01

396

Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio  

SciTech Connect

On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and strategies to reduce uranium concentration in the leachate.

Hazen, Terry

2002-08-26

397

A sediment mesocosm experiment to determine if the remediation of a shoreline waste disposal site in Antarctica caused further environmental impacts.  

PubMed

A shoreline waste disposal site at Casey Station, Antarctica was removed because it was causing impacts in the adjacent marine environment (Brown Bay). We conducted a field experiment to determine whether the excavation created further impacts. Trays of clean, defaunated sediment were deployed at two locations within Brown Bay and two control locations, two years prior to remediation. Trays were sampled one year before, 1month before, 1month after and two years after the excavation. An increase in metals was found at Brown Bay two years after the remediation. However there was little evidence of impacts on sediment assemblages. Communities at each location were different, but differences from before to after the remediation were comparable, indicating there were unlikely to have been further impacts. We demonstrate that abandoned waste disposal sites in hydrologically active places in Antarctica can be removed without creating greater adverse impacts to ecosystems downstream. PMID:25306301

Stark, Jonathan S; Johnstone, Glenn J; Riddle, Martin J

2014-12-15

398

Estimation of ground-water recharge from precipitation, runoff into drywells, and on-site waste-disposal systems in the Portland Basin, Oregon and Washington  

USGS Publications Warehouse

The average recharge rate in the Portland Basin, in northwestern Oregon and southwestern Washington, is estimated to be about 22.0 inches per year. Of that amount, precipitation accounts for about 20.8 inches per year, runoff into drywells 0.9 inches per year, and on-site waste disposal about 0.4 inches per year. Recharge is highest, about 49 inches per year, in the Cascade Range. Recharge is lowest, near zero, along and between the Columbia and Willamette Rivers. Recharge is higher locally in discrete areas owing to recharge from runoff into drywells and on-site, waste-disposal systems in urbanized parts of the study area. In these urbanized areas, recharge ranges from 0 to 49 inches per year.

Snyder, D.T.; Morgan, D.S.; McGrath, T.S.

1994-01-01

399

76 FR 26720 - Notice of Intent: Designation of an Expanded Ocean Dredged Material Disposal Site (ODMDS) off...  

Federal Register 2010, 2011, 2012, 2013, 2014

...ODMDS, approximately 4 square nautical miles in size, for the disposal of dredged material from the potential construction dredging at Port Everglades Harbor. The need for an expanded ODMDS is based on capacity computer modeling results....

2011-05-09

400

Simulation of radionuclides in the saturated zone at the E-Area low- level radioactive waste disposal facility, Savannah River Site  

Microsoft Academic Search

Numerical simulation of migration of Technetium-99 and Tritium beneath a proposed low-level radioactive waste disposal facility at the Savannah River Site was conducted utilizing the Porflow code. These species were selected for preliminary analysis based upon screening exercises designed to identify species of concern and because each has contrasting properties in regard to adsorption and half-life. Numerous field data describing

R. A. Hiergesell; P. M. Kearl

1993-01-01

401

CY2000 Hanford Site Mixed Waste Land Disposal Restrictions Report Vol. 1 Storage Report & Vol 2: Characterization & Treatment Report [SEC 1 thru SEC 4  

Microsoft Academic Search

This volume presents information about the storage and minimization of mixed waste and potential sources for the generation of additional mixed waste. This information is presented in accordance with Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1996) Milestone M-26-01K. It is Volume 1 of a two-volume report on the status of Hanford Site land-disposal-restricted mixed

2001-01-01

402

Results of Tritium Tracking and Groundwater Monitoring at the Hanford Site 200 Area State Approved Land Disposal SiteFiscal Year 2003  

SciTech Connect

The Hanford Site 200 Area Effluent Treatment Facility (ETF) processes contaminated aqueous wastes derived from Hanford Site facilities. The treated wastewater occasionally contains tritium, which is not removed by the ETF, and is discharged to the 200 Area State-Approved Land Disposal Site (SALDS). During fiscal year (FY) 2003 to date (through August 31, 2003), approximately 96-million liters (25.3-million gallons) of water have been discharged to the SALDS. Groundwater monitoring for tritium and other constituents, and water-level measurements are required by the state-issued permit at the SALDS. The current network consists of 3 proximal monitoring wells and 16 tritium-tracking wells. Proximal wells were sampled in October 2002, and January, February, April, and September of 2003. Tritium-tracking wells were sampled in January and September of 2003, but September results were delayed because of fire hazards near the wellheads. Water-level measurements in three wells nearest the SALDS indicate the continuation of a small hydraulic mound beneath the SALDS facility as a result of discharges. This feature is directing groundwater flow radially outward a short distance before the regional northeasterly flow predominates. This condition also places several wells south of the SALDS hydraulically downgradient of the facility. Some of the wells south of the SALDS in the tritium-tracking network have dried or are projected to soon be dry. Wells 299-W7-6 went dry during FY 2003, preventing collection of the September sample from this well. Tritium activities decreased in all three SALDS proximal wells during FY 2003, compared with FY 2002. Timing between detections of tritium and other constituents in well 699-48-77C suggest a delay of approximately 3 years from detection in wells 699-48-77A and 699-48-77D. Sporadic detections in well 299-W7-5 suggest that tritium from SALDS may be reaching the northern edge of the 200 West Area, south of the facility and may be at the extreme southern edge of the plume. Comparison of head distribution in March 2003 and reported FY 2003 tritium activities, with numerical predictions of these quantities for 2000 and 2005, suggests that modeling performed in 1997 only slightly overestimated the areal spread of tritium around the SALDS to date.

Barnett, D BRENT.; Rieger, JoAnne T.; Thornton, Edward C.

2003-11-30

403

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary  

SciTech Connect

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site.

NONE

1996-03-01

404

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 356: Mud Pits and Disposal Sites, Nevada Test Site, Nevada (Revision No. 0, August 2001)  

SciTech Connect

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions necessary for the characterization and closure of Corrective Action Unit (CAU) 356, Mud Pits and Disposal Sites, as identified in the Federal Facility Agreement and Consent Order (FFACO). The CAU, located on the Nevada Test Site in Nevada, consists of seven Corrective Action Sites (CASs): CAS 03-04-01, Area 3 Change House Septic System; CAS 03-09-01, Mud Pit Spill Over; CAS 03-09-03, Mud Pit; CAS 03-09-04, Mud Pit; CAS 03-09-05, Mud Pit; CAS 20-16-01, Landfill; CAS 20-22-21, Drums. Sufficient information and process knowledge from historical documentation and investigations are the basis for the development of the phased approach chosen to address the data collection activities prior to implementing the preferred closure alternative for each CAS. The Phase I investigation will determine through collection of environmental samples from targeted populations (i.e., mud/soil cuttings above textural discontinuity) if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels (PALs) at each of the CASs. If COPCs are present above PALs, a Phase II investigation will be implemented to determine the extent of contamination to support the appropriate corrective action alternative to complete closure of the site. Groundwater impacts from potentially migrating contaminants are not expected due to the depths to groundwater and limiting hydrologic drivers of low precipitation and high evaporation rates. Future land-use scenarios limit future uses to industrial activities; therefore, future residential uses are not considered. Potential exposure routes to site workers from contaminants of concern in septage and soils include oral ingestion, inhalation, or dermal contact (absorption) through in-advertent disturbance of contaminated structures and/or soils. Diesel within drilling muds is expected to be the primary COPC based on process knowledge. Recirculation processes within the mud pits enhance volatilization of volatile organic compounds (VOCs), thereby reducing the potential concentrations of any VOCs that may be present. A secondary source of contaminants from random truck dumping activities and leaking vehicle discharge may have released fuels, grease, motor oil, and hydraulic fluids into the mud pit effluent stream. Radionuclide contamination is not expected at these CASs based on historical information. The primary radioisotopes that could be expected, if present, are cesium-137, tritium, and strontium-90. The SAFER process ends with closure of the site based on the laboratory analytical results of the environmental samples. There is sufficient information and process knowledge from historical documentation regarding the expected nature and extent of potential contaminants to recommend closure of CAU 356 using the SAFER process. On completion of the field activities, a Closure Report will be prepared and submitted to the Nevada Division of Environmental Protection for review and approval.

U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV)

2001-08-21

405

Work plan for monitor well/groundwater elevation data recorder installation at the Cheney Disposal site, Grand Junction, Colorado  

SciTech Connect

In May 1990, during the excavation for the Grand Junction, Colorado, Cheney Reservoir disposal cell (Cheney), a water bearing paleochannel was encountered along the northern boundary of the excavation (designated the Northwest Paleochannel). To ensure the long-term integrity of the disposal embankment, remedial actions were taken including the excavation of the paleochannel and underlying material to bedrock, backfilling of the trapezoidal trench with granular material, and placement of a geotextile liner above the granular material. Compacted clay backfill was placed above the reconstructed paleochannel trench, and the northwest corner was restored to the designated grade. Investigation of other paleochannels determined that ground water flow terminated before it migrated as far west as the disposal cell. Therefore, flow in these paleochannels would have no impact on the disposal cell. Although characterization efforts did not indicate the presence of a ground water-bearing paleochannel south of the disposal cell, the potential could not be ruled out. As a best management practice for long-term monitoring at Cheney, two monitor wells will be installed within the paleochannels. One well will be installed within 50 feet (ft) west of the reconstructed Northwest Paleochannel. The second well will be installed near the southwestern (downgradient) corner of the disposal cell. The purposes of these wells are to characterize ground water flow (if any) within the paleochannels and to monitor the potential for water movement (seepage) into or out of the disposal cell. Initial monitoring of the paleochannels will consist of water level elevation measurement collection and trend analysis to evaluate fluctuations in storage. The purpose of this document is to describe the work that will be performed and the procedures that will be followed during installation of two ground water monitor wells and two ground water elevation data recorders (data loggers) at Cheney.

Not Available

1994-09-01

406

Closure Report for Corrective Action Unit 110: Areas 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada  

SciTech Connect

This Closure Report (CR) has been prepared for the Area 3 Radioactive Waste Management Site (RWMS) U-3ax/bl Disposal Unit Corrective Action Unit (CAU) 110 in accordance with the reissued (November 2000) Resource Conservation and Recovery Act (RCRA) Part B operational permit NEV HW009 (Nevada Division of Environmental Protection [NDEP], 2000) and the Federal Facility and Consent Order (FFACO) (NDEP et al., 1996). CAU 110 consists of one Corrective Action Site 03-23-04, described as the U-3ax/bl Subsidence Crater. Certifications of closure are located in Appendix A. The U-3ax/bl is a historic disposal unit within the Area 3 RWMS located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit was closed under the RCRA, as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (m{sup 3}) (8.12 x 10{sup 6} cubic feet [ft{sup 3}]) of waste. NTS atmospheric nuclear device testing generated approximately 95% of the total waste volume disposed of in U-3ax/bl; 80% of the total volume was generated from the Waste Consolidation Project. Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is normally in a state of moisture deficit.

J. L. Smith

2001-08-01

407

Deployment of an Alternative Closure Cover and Monitoring System at the Mixed Waste Disposal Unit U-3ax/bl at the Nevada Test Site  

SciTech Connect

In October 2000, final closure was initiated of U-3ax/bl, a mixed waste disposal unit at the Nevada Test Site (NTS). The application of approximately 30 cm of topsoil, composed of compacted native alluvium onto an operational cover, seeding of the topsoil, installation of soil water content sensors within the cover, and deployment of a drainage lysimeter facility immediately adjacent to the disposal unit initiated closure. This closure is unique in that it required the involvement of several U.S. Department of Energy (DOE) Environmental Management (EM) groups: Waste Management (WM), Environmental Restoration (ER), and Technology Development (TD). Initial site characterization of the disposal unit was conducted by WM. Regulatory approval for closure of the disposal unit was obtained by ER, closure of the disposal unit was conducted by ER, and deployment of the drainage lysimeter facility was conducted by WM and ER, with funding provided by the Accelerated Site Technology Deployment ( ASTD) program, administered under TD. In addition, this closure is unique in that a monolayer closure cover, also known as an evapotranspiration (ET) cover, consisting of native alluvium, received regulatory approval instead of a traditional Resource Conservation and Recovery Act (RCRA) multi-layered cover. Recent studies indicate that in the arid southwestern United States, monolayer covers may be more effective at isolating waste than layered covers because of the tendency of clay layers to desiccate and crack, and subsequently develop preferential pathways. The lysimeter facility deployed immediately adjacent to the closure cover consists of eight drainage lysimeters with three surface treatments: two were left bare; two were revegetated with native species; two were allowed to revegetate with invader species; and two are reserved for future studies. The lysimeters are constructed such that any drainage through the bottoms of the lysimeters can be measured. Sensors installed in the closure cover provide soil water content data, whereas sensors installed in the lysimeters provide soil water content, soil water potential, soil temperature, and drainage data for a detailed evaluation of the cover performance. Revegetation establishes a stable plant community that maximizes water loss through transpiration and reduces water and wind erosion and ultimately restores the disposal unit to its surrounding Great Basin Desert environment.

Levitt, D.G.; Fitzmaurice, T.M.

2001-02-01

408

Geologic, hydrologic, and cultural factors in the selection of sites for the land disposal of wastes in Washington  

USGS Publications Warehouse

As part of a program to deal with the problems of waste disposal in Washington, the Department of Ecology (WDOE), in cooperation with the U.S. Geological Survey, completed a study designed to provide the geologic, hydrologic, and cultural data needed to evaluate the suitability of State land areas for the disposal of wastes. Data portraying the distribution of factors that could affect the suitability of areas in Washington for waste disposal were presented in a series of 18 maps (overlays). The factors selected include major geologic units; natural hazards from earthquakes, faulting, and volcanoes; climate; locations of major surface-water and groundwater bodies; population density; and land and water uses. Within each factor (map) the data were grouped into class intervals and the intervals for most factors ranked according to their relative suitability/unsuitability for land disposal of wastes following criteria supplied by WDOE. Areas of the State considered completely unsuitable (as determined by WDOE personnel) for waste disposal because of current or proposed land uses were excluded from ranking. (USGS)

Dion, N.P.; Alvord, R.C.; Olson, T.D.

1986-01-01

409

Demonstration of In-Situ Stabilization of Buried Waste at Pit G-11 at the Brookhaven National laboratory Glass Pits Disposal Site  

SciTech Connect

In 1989 BNL was added to the EPAs National Priorities List. The site is divided into seven operable units (OU). OU-I includes the former landfill area. The field task site is noted as the AOC 2C Glass Holes location. Beginning in the 1960s and continuing into the 1980s, BNL disposed of laboratory waste (glassware, chemicals and animal carcasses) in numerous shallow pits. The drivers for remediating the pits are; historical records that indicate hazardous materials may have been disposed of in the pits; ground water contamination down gradient of the pits; a test excavation of one of the glass holes that unearthed laboratory glass bottles with unidentified liquids still contained; and the fact that BNL rests atop an EPA designated sole-source aquifer. The specific site chosen for this demonstration was pit G-11. The requirements that lead to choosing this pit were; a well characterized pit and a relatively isolated pit where our construction operations would not impact on adjacent pits. The glass holes area, including pit G-11, was comprehensively surveyed using a suite of geophysical techniques (e.g., EM-31, EM-61, GPR). Prior to stabilizing the waste form a subsurface barrier was constructed to contain the entire waste pit. The pit contents were then stabilized using a cement grout applied via jet grouting. The stabilization was performed to make removal of the waste from the pit easier and safer in terms of worker exposure. The grouting process would mix and masticate the waste and grout and form a single monolithic waste form. This large monolith would then be subdivided into smaller 4 foot by 4 foot by 10-12 foot block using a demolition grout. The smaller blocks would then be easily removed from the site and disposed of in a CERCLA waste site.

Dwyer, B.P.; Gilbert, J.; Heiser, J.

1999-01-01

410

A method for the processing and analysis of digital terrain elevation data. [Shiprock and Gallup Quadrangles, Arizona and New Mexico  

NASA Technical Reports Server (NTRS)

A method is presented for the processing and analysis of digital topography data that can subsequently be entered in an interactive data base in the form of slope, slope length, elevation, and aspect angle. A discussion of the data source and specific descriptions of the data processing software programs are included. In addition, the mathematical considerations involved in the registration of raw digitized coordinate points to the UTM coordinate system are presented. Scale factor considerations are also included. Results of the processing and analysis are illustrated using the Shiprock and Gallup Quadrangle test data.

Junkin, B. G. (principal investigator)

1979-01-01

411

Geophysical and chemical investigations of ground water at five industrial or waste-disposal sites in Logan Township, Gloucester County, New Jersey, 1983-87  

SciTech Connect

Five former or active industrial or waste disposal sites in Logan Township were identified by the Federal government and by the State of New Jersey as potential threats to the quality of groundwater there. The sites are: (1) Air Products and Chemicals, Inc. waste disposal site; (2) Bridgeport Rental and Oil Services, Inc.; (3) Chemical Leaman Tank Lines, Inc.; (4) Monsanto Company; and (5) Rollins Environmental Services, Inc. Quality of groundwater was determined by chemical analysis of samples from wells at four of the five sites and elsewhere in the township. Groundwater in the lower aquifer of the Potomac-Raritan-magothy aquifer system in Logan Township and surrounding areas is dominated by sodium and chloride ions and is slightly saline. Calcium, sodium, and bicarbonate are the predominant ions in the upper and middle aquifers; the concentration of dissolved solids is low. Concentrations of iron and manganese in the groundwater range from 6 to 73,000 microgm/L, and from 33 to 1,100 microgm/L. Concentrations of organic carbon range from 0.60 to 4.2 mg/L. Areas of high apparent conductivity were detected east of the waste oil lagoon at the Bridgeport Rental and Oil Services, Inc. site. Inorganic groundwater contamination at the site is characterized by concentrations of cadmium and lead that exceed Federal and State primary drinking water regulations. Groundwater at the Chemical Leaman site also is characterized by elevated concentrations of organic nitrogen, and concentrations of As, Cr, Pb, and Hg that exceed Federal primary drinking water regulations. Concentrations of dissolved solids ranged from 339 to 3,530 mg/L at the Monsanto Site and typically are much higher than background levels, but the cause is unclear. 86 refs., 14 figs., 9 tabs.

Kzonski, J.; Lacombe, P.J.; Hochreiter, J.J.; Lewis, J.C. (Geological Survey, West Trenton, NJ (United States))

1990-01-01

412

Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect

Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen.

Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

1993-06-01

413

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site  

SciTech Connect

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01

414

Closure Plan for Corrective Action Unit 110: Area 3 RWMS U-3ax/bl Disposal Unit, Nevada Test Site, Nevada  

SciTech Connect

This Closure Plan has been prepared for the Area 3 RWMS U-3ax/bl Disposal Unit Corrective Action Unit 110 in accordance with the Federal Facility and Consent Order (Nevada Division of Environmental Protection [NDEP] et al., 1996). The U-3ax/bl is a historic disposal unit within the Area 3 Radioactive Waste Management Site located on the Nevada Test Site (NTS). The unit, which was formed by excavating the area between two subsidence craters (U-3ax and U-3bl), was operationally closed in 1987. The U-3ax/bl disposal unit is scheduled for permanent closure under the Resource Conservation and Recovery Act as a hazardous waste landfill. Existing records indicate that, from July 1968 to December 1987, U-3ax/bl received 2.3 x 10{sup 5} cubic meters (8.12 x 10{sup 6} cubic feet) of waste. NTS nuclear device testing generated approximately 95 percent of the total volume disposed of in U-3ax/bl, the majority of which came from the Waste Consolidation Project (80 percent of the total volume) (Elletson and Johnejack, 1995). Area 3 is located in Yucca Flat, within the northeast quadrant of the NTS. The Yucca Flat watershed is a structurally closed basin encompassing an area of approximately 780 square kilometers (300 square miles). The structural geomorphology of Yucca Flat is typical of the Basin and Range Physiographic Province. Yucca Flat lies in one of the most arid regions of the country. Water balance calculations for Area 3 indicate that it is continuously in a state of moisture deficit. The U-3ax/bl Disposal Unit will be closed in place by installing a Resource Conservation and Recovery Act equivalent cover. Following cover construction a fence will be installed around the cover to prevent accidental damage to the cover. Post-closure monitoring will consist of site inspections to determine the condition of the engineered cover and cover performance monitoring using Time-Domain Reflectometry arrays to monitor moisture migration in the cover. Any identified maintenance and repair requirements will be remedied within 60 working days of discovery and documented in writing at the time of repair. Results of all inspections/repairs for a given year will be addressed in a single report submitted annually to the NDEP. Soil moisture will be monitored within the cover for a period of at least two years prior to establishing performance criteria for NDEP regulatory purposes.

T. M. Fitzmaurice

2000-08-01

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