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Remedial investigation report on Waste Area Group 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1: Technical summary

Description: A remedial investigation (RI) was performed to support environmental restoration activities for Waste Area Grouping (WAG) 5 at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The WAG 5 RI made use of the observational approach, which concentrates on collecting only information needed to assess site risks and support future cleanup work. This information was interpreted and is presented using the framework of the site conceptual model, which relates contaminant sources and release mechanisms to migration pathways and exposure points that are keyed to current and future environmental risks for both human and ecological receptors. The site conceptual model forms the basis of the WAG 5 remedial action strategy and remedial action objectives. The RI provided the data necessary to verify this model and allows recommendations to be made to accomplish those objectives.
Date: March 1, 1995
Partner: UNT Libraries Government Documents Department

Human scenarios for the screening assessment. Columbia River Comprehensive Impact Assessment

Description: Because of past nuclear production operations along the Columbia River, there is intense public and tribal interest in assessing any residual Hanford Site related contamination along the river from the Hanford Reach to the Pacific Ocean. The Columbia River Impact Assessment (CRCIA) was proposed to address these concerns. The assessment of the Columbia River is being conducted in phases. The initial phase is a screening assessment of risk, which addresses current environmental conditions for a range of potential uses. One component of the screening assessment estimates the risk from contaminants in the Columbia River to humans. Because humans affected by the Columbia river are involved in a wide range of activities, various scenarios have been developed on which to base the risk assessments. The scenarios illustrate the range of activities possible by members of the public coming in contact with the Columbia River so that the impact of contaminants in the river on human health can be assessed. Each scenario illustrates particular activity patterns by a specific group. Risk will be assessed at the screening level for each scenario. This report defines the scenarios and the exposure factors that will be the basis for estimating the potential range of risk to human health from Hanford-derived radioactive as well as non-radioactive contaminants associated with the Columbia River.
Date: March 1, 1996
Creator: Napier, B.A.; Harper, B.L.; Lane, N.K.; Strenge, D.L. & Spivey, R.B.
Partner: UNT Libraries Government Documents Department

Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3 -- Appendix B: Technical findings and conclusions

Description: This document provides the Environmental Restoration Program with information about the results of investigations performed at Waste Area Grouping (WAG) 5. It includes information on risk assessments that have evaluated long-term impacts to human health and the environment. Information provided in this document forms the basis for decisions regarding the need for subsequent remediation work at WAG 5. Sections B1.1 through B1.4 present an overview of the environmental setting of WAG 5, including location, population, land uses, ecology, and climate, and Sects. B1.5 through B1.7 give site-specific details (e.g., topography, soils, geology, and hydrology). The remediation investigation (RI) of WAG 5 did not entail en exhaustive characterization of all physical attributes of the site; the information presented here focuses on those most relevant to the development and verification of the WAG 5 conceptual model. Most of the information presented in this appendix was derived from the RI field investigation, which was designed to complement the existing data base from earlier, site-specific studies of Solid Waste Storage Area (SWSA) 5 and related areas.
Date: September 1, 1995
Partner: UNT Libraries Government Documents Department

CO{sub 2} exchange environmental productivity indices, and productivity of agaves and cacti under current and elevated atmospheric CO{sub 2} concentrations. Final report

Description: The research described in the proposal investigated net CO{sub 2} uptake and biomass accumulation for an extremely productive CAM plant, the prickly pear cactus Opuntia ficus-indica, under conditions of elevated CO{sub 2} concentrations for relatively long periods. The influences of soil water status, air temperature, and the photosynthetic photon flux (PPF) on net CO{sub 2} uptake over 24-h periods were evaluated to enable predictions to be made based on an Environmental Productivity Index (EPI). Specifically, EPI predicts the fraction of maximal daily net CO{sub 2} uptake based on prevailing environmental conditions. It is the product of indices for temperature, soil water, and intercepted PPF, each of which range from 0.00 when that index factor completely inhibits net CO{sub 2} uptake to 1.00 when no limitation occurs. For instance, the Water Index is 1.00 under wet conditions and decreases to 0.00 during prolonged drought. Although the major emphasis of the research was on net C0{sub 2} uptake and the resulting biomass production for O. ficus-indica, effects of elevated CO{sub 2} concentrations on root: shoot ratios and on the activities of the two carboxylating enzymes were also investigated. Moreover, experiments were also done on other CAM plants, including Agave deserti, Agave salmiana, and Hylocereus undatus, and Stenocereus queretaroensis.
Date: December 31, 1994
Creator: Nobel, P.S.
Partner: UNT Libraries Government Documents Department

Gamma analysis of environmental samples from the Marshall Islands

Description: Radiological studies of the fate of nuclear test related debris in the Marshall Islands conducted by members of the Lawrence Livermore National Laboratory generate large number of environmental samples. For more than 20 years, the Low-Level Gamma Spectroscopy Facility has been used to perform the analysis of gamma emitting radionuclides. A brief description of the facility, calibration, counting and analysis procedures is given.
Date: September 1, 1995
Creator: Brunk, J.L.
Partner: UNT Libraries Government Documents Department

Lessons learned: Needs for improving human health risk assessment at USDOE Sites

Description: Realistic health risk assessments were performed in a pilot study of three U.S. Department of Energy (USDOE) sites. These assessments, covering a broad spectrum of data and methods, were used to identify needs for improving future health risk assessments at USDOE sites. Topics receiving specific recommendations for additional research include: choice of distributions for Monte Carlo simulation; estimation of risk reduction; analysis of the U.S. Department of Agriculture Database on food and nutrient intakes; investigations on effects of food processing on contaminant levels; background food and environmental concentrations of contaminants; method for handling exposures to groundwater plumes, methods for analyzing less than lifetime exposure to carcinogens; and improvement of bioaccumulation factors.
Date: September 1993
Creator: Hamilton, L. D.; Holtzman, S.; Meinhold, A. F.; Morris, S. C.; Rowe, M. D.; Daniels, J. I. et al.
Partner: UNT Libraries Government Documents Department

Estimation of radionuclide ingestion: Lessons from dose reconstruction for fallout from the Nevada Test Site

Description: The United States conducted atmospheric testing of nuclear devices at the Nevada Test Site from 1951 through 1963. In 1979 the U.S. Department of Energy established the Off-Site Radiation Exposure Review Project to compile a data base related to health effects from nuclear testing and to reconstruct doses to public residing off of the Nevada Test Site. This project is the most comprehensive dose reconstruction project to date, and, since similar assessments are currently underway at several other locations within and outside the U.S., lessons from ORERP can be valuable. A major component of dose reconstruction is estimation of dose from radionuclide ingestion. The PATHWAY food-chain model was developed to estimate the amount of radionuclides ingested. For agricultural components of the human diet, PATHWAY predicts radionuclide concentrations and quantities ingested. To improve accuracy and model credibility, four components of model analysis were conducted: estimation of uncertainty in model predictions, estimation of sensitivity of model predictions to input parameters, and testing of model predictions against independent data (validation), and comparing predictions from PATHWAY with those from other models. These results identified strengths and weaknesses in the model and aided in establishing the confidence associated with model prediction, which is a critical component risk assessment and dose reconstruction. For fallout from the Nevada Test Site, by far, the largest internal doses were received by the thyroid. However, the predicted number of fatal cancers from ingestion dose was generally much smaller than the number predicted from external dose. The number of fatal cancers predicted from ingestion dose was also orders of magnitude below the normal projected cancer rate. Several lessons were learned during the study that are relevant to other dose reconstruction efforts.
Date: September 1, 1994
Creator: Breshears, D.D.; Whicker, F.W.; Kirchner, T.B. & Anspaugh, L.R.
Partner: UNT Libraries Government Documents Department

Nonradiological chemical pathway analysis and identification of chemicals of concern for environmental monitoring at the Hanford Site

Description: Pacific Northwest`s Surface Environmental Surveillance Project (SESP) is an ongoing effort tot design, review, and conducted monitoring on and off the Hanford site. Chemicals of concern that were selected are listed. Using modeled exposure pathways, the offsite cancer incidence and hazard quotient were calculated and a retrospective pathway analysis performed to estimate what onsite concentrations would be required in the soil for each chemical of concern and other detected chemicals that would be required to obtain an estimated offsite human-health risk of 1.0E-06 cancer incidence or 1.0 hazard quotient. This analysis indicates that current nonradiological chemical contamination occurring on the site does not pose a significant offsite human-health risk; the highest cancer incidence to the offsite maximally exposed individual was from arsenic (1.76E-10); the highest hazard quotient was chromium(VI) (1.48E-04). The most sensitive pathways of exposure were surfacewater and aquatic food consumption. Combined total offsite excess cancer incidence was 2.09E-10 and estimated hazard quotient was 2.40E-04. Of the 17 identified chemicals of concern, the SESP does not currently (routinely) monitor arsenic, benzo(a)pyrene, bis(2- ethylhexyl)phthalate (BEHP), and chrysene. Only 3 of the chemicals of concern (arsenic, BEHP, chloroform) could actually occur in onsite soil at concern high enough to cause a 1.0E-06 excess cancer incidence or a 1.0 hazard index for a given offsite exposure pathway. During the retrospective analysis, 20 other chemicals were also evaluated; only vinyl chloride and thallium could reach targeted offsite risk values.
Date: November 1, 1995
Creator: Blanton, M.L.; Cooper, A.T. & Castleton, K.J.
Partner: UNT Libraries Government Documents Department

Preliminary remediation goals for use at the U.S. Department of Energy Oak Ridge Operations Office

Description: This report presents Preliminary Remediation Goals (PRGs) for use in human health risk assessment efforts under the United States Department of Energy, Oak Ridge Operations Office Environmental Restoration (ER) Division. Chemical-specific PRGs are concentration goals for individual chemicals for specific medium and land use combinations. The PRGs are referred to as risk-based because they have been calculated using risk assessment procedures. Risk-based calculations set concentration limits using both carcinogenic or noncarcinogenic toxicity values under specific exposure pathways. The PRG is a concentration that is derived from a specified excess cancer risk level or hazard quotient. This report provides the ER Division with standardized PRGs which are integral to the Remedial Investigation/Feasibility Study process. By managing the assumptions and systems used in PRG derivation, the Environmental Restoration Risk Assessment Program will be able to control the level of quality assurance associated with these risk-based guideline values.
Date: June 1, 1995
Partner: UNT Libraries Government Documents Department

Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland

Description: The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from ...
Date: March 1, 1995
Creator: Hlohowskyj, I.; Hayse, J. & Kuperman, R.
Partner: UNT Libraries Government Documents Department

Proceedings of the workshop on review of dose modeling methods for demonstration of compliance with the radiological criteria for license termination

Description: The workshop was one in a series to support NRC staff development of guidance for implementing the final rule on ``Radiological Criteria for License Termination.`` The workshop topics included discussion of: dose models used for decommissioning reviews; identification of criteria for evaluating the acceptability of dose models; and selection of parameter values for demonstrating compliance with the final rule. The 2-day public workshop was jointly organized by RES and NMSS staff responsible for reviewing dose modeling methods used in decommissioning reviews. The workshop was noticed in the Federal Register (62 FR 51706). The workshop presenters included: NMSS and RES staff, who discussed both dose modeling needs for licensing reviews, and development of guidance related to dose modeling and parameter selection needs; DOE national laboratory scientists, who provided responses to earlier NRC staff-developed questions and discussed their various Federally-sponsored dose models (i.e., DandD, RESRAD, and MEPAS codes); and an EPA scientist, who presented details on the EPA dose assessment model (i.e., PRESTO code). The workshop was formatted to provide opportunities for the attendees to observe computer demonstrations of the dose codes presented. More than 120 workshop attendees from NRC Headquarters and the Regions, Agreement States; as well as industry representatives and consultants; scientists from EPA, DOD, DNFSB, DOE, and the national laboratories; and interested members of the public participated. A complete transcript of the workshop, including viewgraphs and attendance lists, is available in the NRC Public Document Room. This NUREG/CP documents the formal presentations made during the workshop, and provides a preface outlining the workshop`s focus, objectives, background, topics and questions provided to the invited speakers, and those raised during the panel discussion. NUREG/CP-0163 also provides technical bases supporting the development of decommissioning guidance. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.
Date: May 1, 1998
Creator: Nicholson, T. J. & Parrott, J. D.
Partner: UNT Libraries Government Documents Department

The Hazard Ranking System (HRS)

Description: In 1990, the US Environmental Protection Agency (EPA) revised procedures for evaluating uncontrolled releases of hazardous substances under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the Superfund Amendments and Reauthorization Act (SARA). These revised procedures include substantial changes to the Hazard Ranking System (HRS), the scoring system EPA uses to assess a site`s relative threat to public health and the environment. This information brief provides an overview of the HRS as it applies to DOE facilities and the relationship of the HRS to other site activities under CERCLA and the Resource Conservation and Recovery Act (RCRA).
Date: February 1, 1994
Partner: UNT Libraries Government Documents Department

Uncertainty and sensitivity analysis of food pathway results with the MACCS Reactor Accident Consequence Model

Description: Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the food pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 87 imprecisely-known input variables on the following reactor accident consequences are studied: crop growing season dose, crop long-term dose, milk growing season dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, area dependent cost, crop disposal cost, milk disposal cost, condemnation area, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: fraction of cesium deposition on grain fields that is retained on plant surfaces and transferred directly to grain, maximum allowable ground concentrations of Cs-137 and Sr-90 for production of crops, ground concentrations of Cs-134, Cs-137 and I-131 at which the disposal of milk will be initiated due to accidents that occur during the growing season, ground concentrations of Cs-134, I-131 and Sr-90 at which the disposal of crops will be initiated due to accidents that occur during the growing season, rate of depletion of Cs-137 and Sr-90 from the root zone, transfer of Sr-90 from soil to legumes, transfer of Cs-137 from soil to pasture, transfer of cesium from animal feed to meat, and the transfer of cesium, iodine and strontium from animal feed to milk.
Date: January 1, 1995
Creator: Helton, J. C.; Johnson, J. D.; Rollstin, J. A.; Shiver, A. W. & Sprung, J. L.
Partner: UNT Libraries Government Documents Department

Tritium Atmospheric Transport and Deposition Following Acute Releases: Comparisons With a Simple Transport Model

Description: During 35 years of operation of the Savannah River Site (SRS) there have been a small number of inadvertent tritium releases to the atmosphere. After detection of the releases by stack monitors, field crews were dispatched to determine the concentration of tritium in the environment. The objective of the measurement was to verify environmental concentrations calculated by dose assessment models. Air samples were used to verify the concentration levels and tritium forms during the plume passage. It was not feasible to take enough samples in the plume path to determine the two dimensional distribution of tritium concentration in the plume. However, the ground level distribution was very well reflected vegetation samples. Therefore, it is unusually possible to determine plume shape, plume width, and the relative maximum concentration as the plume moves downwind from the vegetation samples. In eight of the nine releases studied, the monitoring data allowed comparison with atmospheric transport models.
Date: Autumn 1991
Creator: Murphy, C. E., Jr.; Bauer, L. R. & Hoel, D.
Partner: UNT Libraries Government Documents Department

Oak Ridge reservation, annual site environmental report summary for 1993

Description: The U.S. Department of Energy requires annual site environmental reports from facilities that operate under its auspices. To fulfill that requirement, such an annual report is published for the Oak Ridge Reservation, which comprises three major sites, each of which has unique monitoring requirements in addition to many shared obligations. As a result, the report is complex and highly detailed. Annual site environmental reports are public documents that are read by government regulators, scientists, engineers, business people, special interest groups, and members of the public at large. For that reason, the reports need to be accessible to a variety of audiences in addition to being accurate and complete. This pamphlet summarizes environmental activities on the reservation, which for some readers may be adequate; for those who seek more detail, it will lend coherence to their approach to the report itself. The content of this summary was taken from Oak Ridge Reservation Annual Site Environmental Report for 1993. Results of the many environmental monitoring and surveillance activities are detailed in this report.
Date: November 1, 1994
Partner: UNT Libraries Government Documents Department

Exposure to radon and radon progeny in the indoor environment. Technical progress report, January 1, 1990--December 30, 1991

Description: The objective of this work is to measure experimentally the activity-weighted particle size distribution in conjunction with other relevant house parameters in occupied houses in order to improve the estimate of exposure to radon and radon progeny indoors. Our methodology requires that building construction and operation be studied and understood both experimentally and theoretically in a small number of buildings and that results of side applicability be inferred from the particular case studies. Results are discussed.
Date: December 31, 1991
Creator: Socolow, R. H.
Partner: UNT Libraries Government Documents Department

Radioecological implications of the Par Pond drawdown

Description: The drawdown of the Par Pond reservoir created dramatic alterations in this formerly stable lentic ecosystem. In addition, the radiation environment at Par Pond has changed significantly because of the exposure of Cesium 137-contaminated sediments and the appearance of new transport pathways to the terrestrial environment. In response to this situation, SREL was asked to study the radioecological implications of the reservoir drawdown. This report contains the objectives, methods, and results of the SREL study.
Date: December 5, 1991
Creator: Hickey, H. & Whicker, F. W.
Partner: UNT Libraries Government Documents Department

MACCS2 development and verification efforts

Description: MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, released in 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS/MACCS2 are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. In addition, errors that had been identified in MACCS version1.5.11.1 were corrected, including an error that prevented the code from providing intermediate-phase results. MACCS2 version 1.10 beta test was released to the beta-test group in May, 1995. In addition, the University of New Mexico (UNM) has completed an independent verification study of the code package. Since the beta-test release of MACCS2 version 1.10, a number of minor errors have been identified and corrected, and a number of enhancements have been added to the code package. The code enhancements added since the beta-test release of version 1.10 include: (1) an option to allow the user to input the {sigma}{sub y} and {sigma}{sub z} plume expansion parameters in a table-lookup form for incremental downwind distances, (2) an option to define different initial dimensions for up to four segments of a release, (3) an enhancement to the COMIDA2 food-chain model preprocessor to allow the user to supply externally calculated tables of tritium food-chain dose per unit deposition on farmland to support analyses of tritium releases, and (4) the capability to calculate direction-dependent doses.
Date: March 1, 1997
Creator: Young, M. & Chanin, D.
Partner: UNT Libraries Government Documents Department

Princeton Plasma Physics Laboratory (PPPL) annual site environmental report for calendar year 1994

Description: This report gives the results of the environmental activities and monitoring programs at the Princeton Plasma Physics Laboratory (PPPL) for CY94. The report is prepared to provide the US Department of Energy (DOE) and the public with information on the level of radioactive and nonradioactive pollutants, if any, added to the environment as a result of PPPL operations, as well as environmental initiatives, assessments, and programs that were undertaken in 1994. The objective of the Annual Site Environmental Report is to document evidence that PPPL`s environmental protection programs adequately protect the environment and the public health. The Princeton Plasma Physics Laboratory has engaged in fusion energy research since 195 1. The long-range goal of the US Magnetic Fusion Energy Research Program is to develop and demonstrate the practical application of fusion power as an alternate energy source. In 1994, PPPL had one of its two large tokamak devices in operation-the Tokamak Fusion Test Reactor (TFTR). The Princeton Beta Experiment-Modification or PBX-M completed its modifications and upgrades and resumed operation in November 1991 and operated periodically during 1992 and 1993; it did not operate in 1994 for funding reasons. In December 1993, TFTR began conducting the deuterium-tritium (D-T) experiments and set new records by producing over ten @on watts of energy in 1994. The engineering design phase of the Tokamak Physics Experiment (T?X), which replaced the cancelled Burning Plasma Experiment in 1992 as PPPL`s next machine, began in 1993 with the planned start up set for the year 2001. In December 1994, the Environmental Assessment (EA) for the TFTR Shutdown and Removal (S&R) and TPX was submitted to the regulatory agencies, and a finding of no significant impact (FONSI) was issued by DOE for these projects.
Date: February 1, 1996
Creator: Finley, V.L. & Wieczorek, M.A.
Partner: UNT Libraries Government Documents Department

Mercury-selenium interactions in the environment

Description: The Clean Air Act Amendments of 1990 require the U.S. Environmental Protection Agency (EPA) to consider the need to control emissions of trace elements and compounds emitted from coal combustion, including coal-fired power plants. Concern has been expressed about emissions of mercury and arsenic, for example, since health effects may be associated with exposure to some of these compounds. By and large, effects of trace element emissions have been considered individually, without regard for possible interactions. To the extent that the relevant environmental pathways and health endpoints differ, this mode of analysis is appropriate. For example, arsenic is considered a carcinogen and mercury affects the brain. However, there may be compelling reasons to consider emissions of mercury (Hg) and selenium (Se) together: (1) Both Se and Hg are emitted from power plants primarily as vapors. (2) Hg and Se are both found in fish, which is the primary pathway for Hg health effects. (3) Se has been shown to suppress Hg methylation in aqueous systems, which is a necessary step for Hg health effects at current environmental concentrations. (4) Se is a trace element that is essential for health but that can also be toxic at high concentrations; it can thus have both beneficial and adverse health effects, depending on the dosage. This paper reviews some of the salient characteristics and interactions of the Hg-Se system, to consider the hypothesis that the effects of emissions of these compounds should be considered jointly.
Date: February 1, 1996
Creator: Saroff, L.; Lipfert, W. & Moskowitz, P.D.
Partner: UNT Libraries Government Documents Department

Site restoration: Estimation of attributable costs from plutonium-dispersal accidents

Description: A nuclear weapons accident is an extremely unlikely event due to the extensive care taken in operations. However, under some hypothetical accident conditions, plutonium might be dispersed to the environment. This would result in costs being incurred by the government to remediate the site and compensate for losses. This study is a multi-disciplinary evaluation of the potential scope of the post-accident response that includes technical factors, current and proposed legal requirements and constraints, as well as social/political factors that could influence decision making. The study provides parameters that can be used to assess economic costs for accidents postulated to occur in urban areas, Midwest farmland, Western rangeland, and forest. Per-area remediation costs have been estimated, using industry-standard methods, for both expedited and extended remediation. Expedited remediation costs have been evaluated for highways, airports, and urban areas. Extended remediation costs have been evaluated for all land uses except highways and airports. The inclusion of cost estimates in risk assessments, together with the conventional estimation of doses and health effects, allows a fuller understanding of the post-accident environment. The insights obtained can be used to minimize economic risks by evaluation of operational and design alternatives, and through development of improved capabilities for accident response.
Date: May 1, 1996
Creator: Chanin, D.I. & Murfin, W.B.
Partner: UNT Libraries Government Documents Department

Methodology for calculating guideline concentrations for safety shot sites

Description: Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination.
Date: June 1, 1997
Partner: UNT Libraries Government Documents Department

Environmental surveillance at Los Alamos during 1994

Description: This report describes environmental monitoring activities at Los Alamos National Laboratory for 1994. Data were collected to assess external penetrating radiation, airborne emissions, liquid effluents, radioactivity of environmental materials and food stuffs, and environmental compliance.
Date: July 1, 1996
Partner: UNT Libraries Government Documents Department

Species for the screening assessment. Columbia River Comprehensive Impact Assessment

Description: Because of past nuclear production operations along the Columbia River, there is intense public and tribal interest in assessing any residual Hanford Site related contamination along the river from the Hanford Reach to the Pacific Ocean. The Columbia River Comprehensive Impact Assessment was proposed to address these concerns. The assessment of the Columbia River is being conducted in phases. The initial phase is a screening assessment of the risk, which addresses current environmental conditions for a range of potential uses. One component of the screening assessment estimates the risk from contaminants in the Columbia River to the environment. The objective of the ecological risk assessment is to determine whether contaminants from the Columbia River pose a significant threat to selected receptor species that exist in the river and riparian communities of the study area. This report (1) identifies the receptor species selected for the screening assessment of ecological risk and (2) describes the selection process. The species selection process consisted of two tiers. In Tier 1, a master species list was developed that included many plant and animal species known to occur in the aquatic and riparian systems of the Columbia River between Priest Rapids Dam and the Columbia River estuary. This master list was reduced to 368 species that occur in the study area (Priest Rapids Dam to McNary Dam). In Tier 2, the 181 Tier 1 species were qualitatively ranked based on a scoring of their potential exposure and sensitivity to contaminants using a conceptual exposure model for the study area.
Date: March 1, 1996
Creator: Becker, J.M.; Brandt, C.A.; Dauble, D.D.; Maughan, A.D. & O`Neil, T.K.
Partner: UNT Libraries Government Documents Department