This report presents the results of sampling and chemical analyses at Hanford Reservation. The samples were analyzed by Thermo-Analytic Laboratories and Roy F. Weston Laboratories using US Environmental Protection Agency CLP protocols. Sample analyses included: volatile organics; semivolatile organics; inorganics; and general chemical parameters. The data from the chemical analyses were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site.

This report summarizes and documents the results of the radiological surveys conducted from February 11 through February 17 and March 30, 1993 over the 618-10 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-10 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-10 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

This report summarizes and documents the results of the radiological surveys conducted from February 4 through February 10, 1993 over the 618-11 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-11 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-11 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil.

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

This report presents plans for environmental restoration and waste management activities at the Idaho National Engineering Laboratory for fiscal year 1994. This years`s plan focuses on issues affecting the Environmental Restoration and Waste Management Programs. The Environmental Restoration Program is concerned with all aspects of assessment and cleanup of inactive operations. It involves assessing and cleaning up (where necessary) inactive INEL waste areas that could release harmful substances into the environment, as well as safely managing surplus nuclear facilities. The Waste Management program involves treatment, storage, and disposal of radioactive, hazardous, mixed, and industrial waste by DOE activities. This program is designed to protect the safety of INEL employees, the public, and the environment in the design, construction, maintenance, and operation of INEL treatment, storage, and disposal facilities. It operates facilities in a cost-effective, environmentally sound, regulatory compliant, and publicly acceptable manner.

The septic 2607-W6 which supports the 222-S complex is operating at 200% capacity. The septic tank has been inspected and found to be sound. Test hole excavations of the existing drainfield indicate that it is disposing of the current waste water effluent load as opposed to treating it. The system is over 40 years old and has not been approved by the Washington State Department of Health. Under the existing operating conditions it is subject to imminent failure. No additional tie-ins or increases in personnel are allowed which will increase the flow to the 2607-W6 system.

The primary of this project are the development of (1) a general stochastic model for DNA sequencing errors (2) algorithms to restore the original DNA sequence and (3) statistical methods to assess the accuracy of this restoration. A secondary objective is to develop new algorithms for fragment assembly. Initially a stochastic model that assumes errors are independent and uniformly distributed will be developed. Generalizations of the basic model will be developed to account for (1) decay of accuracy along fragments, (2) variable error rates among fragments, (3) sequence dependent errors (e.g. homopolymeric, runs), and (4) strand--specific systematic errors (e.g. compressions). The emphasis of this project will be the development of a theoretical basis for determining sequence accuracy. However, new algorithms are proposed and these will be implemented as software (in the C programming language). This software will be tested using real and simulated data. It will be modular in design and will be made available for distribution to the scientific community.

The Active Sites Environmental Monitoring Program (ASEMP), initiated in 1989, provides early detection and performance monitoring of active low-level-waste (LLW) and transuranic (TRU) waste facilities at Oak Ridge National Laboratory (ORNL). Several changes have recently occurred in regard to the sites that are currently used for waste storage and disposal. These changes require a second set of revisions to the ASEMP program plan. This document incorporates those revisions. This program plan presents the organization and procedures for monitoring the active sites. The program plan also provides internal reporting levels to guide the evaluation of monitoring results.

Demonstration of a direct coal-fueled gas turbine system that is environmentally, technically, and economically viable depends on the satisfactory resolution of several key issues. Solar Turbines, Incorporates technical approach to these issues was to advance a complete direct coal-fueled gas turbine system that incorporated near-term technology solutions to both historically demonstrated problem areas such as deposition, erosion, and hot end corrosion, and to the emergent environmental constraints based on NO{sub x}, SO{sub x}, and particulates. Solar`s program approach was keyed to the full commercialization of the coal-fueled cogeneration gas turbine which would occur after extended field verification demonstrations conducted by the private sector. The program was structured in three phases plus an optional fourth phase: Phase 1 -- system description; Phase 2 -- component development; Phase 3 -- prototype system verification; and Phase 4 -- field evaluation.

The Hall process has always suffered from important problems, among which is the use of consumable carbon anodes, hence, attempts had been made in the past to find an inert anode. A different approach was taken in the present research: a metal anode covered by a protective oxide film is operated so that the film is thick enough to prevent chemical attack of underlying metal, yet thin enough to allow electric current to pass without increase in cell voltage. Specimens of various candidate alloy compositions (Cu-Al, Ni-Al, Cr-Al, Fe-Cr-Al) were electrolyzed; results are promising. Areas for further research on nonconsumable anode for Hall cell are outlined.

An aerial radiological survey was conducted over the Fort Calhoun Nuclear Power Plant in Fort Calhoun, Nebraska, during the period June 19 through June 28, 1993. The survey was conducted at an altitude of 150 feet (46 meters) over a 25-square-mile (65-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Fort Calhoun Nuclear Power Plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 6 and 12 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and potassium. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey was conducted on August 9 and 10, 1972, before the plant began operation. Exposure rates measured in both surveys were consistent with normal terrestrial background.

An aerial radiological survey was conducted over the Oyster Creek Nuclear Power Plant in Forked River, New Jersey, during the period September 18 through September 24, 1992. The survey was conducted at an altitude of 150 feet (46 meters) over a 26-square-mile (67-square-kilometer) area centered on the power station. The purpose of the survey was to document the terrestrial gamma radiation environment of the Oyster Creek Nuclear Power plant and surrounding area. The results of the aerial survey are reported as inferred gamma radiation exposure rates at 1 meter above ground level in the form of a contour map. Outside the plant boundary, exposure rates were found to vary between 4 and 10 microroentgens per hour and were attributed to naturally-occurring uranium, thorium, and radioactive potassium gamma emitters. The aerial data were compared to ground-based benchmark exposure rate measurements and radionuclide assays of soil samples obtained within the survey boundary. The ground-based measurements were found to be in good agreement with those inferred from the aerial measuring system. A previous survey of the power plant was conducted in August 1969 during its initial startup phase. Exposure rates and radioactive isotopes revealed in both surveys were consistent and within normal terrestrial …

Puncturing of aerosol cans is performed in the Waste Receiving and Processing Facility Module 1 (WRAP 1) process as a requirement of the waste disposal acceptance criteria for both transuranic (TRU) waste and low-level waste (LLW). These cans have contained such things as paints, lubricating oils, paint removers, insecticides, and cleaning supplies which were used in radioactive facilities. Due to Westinghouse Hanford Company (WHC) Fire Protection concerns of the baseline system`s fire/explosion proof characteristics, a study was undertaken to compare the baseline system`s design to commercially available puncturing devices. While the study found no areas which might indicate a risk of fire or explosion, WHC Fire Protection determined that the puncturing system must have a demonstrated record of safe operation. This could be obtained either by testing the baseline design by an independent laboratory, or by substituting a commercially available device. As a result of these efforts, the commercially available Aerosolv can puncturing device was chosen to replace the baseline design. Two concerns were raised with the system. Premature blinding of the coalescing/carbon filter, due to its proximity to the puncture and draining operation; and overpressurization of the collection bottle due to its small volume and by blinding of the …

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

This report addresses the application codes of the AGS to RHIC beam line

This OTA assessment reviews the status of federal government efforts to provide safe sanitation to Alaskan Natives and the technologies that have been used or proposed for this purpose. Finally, the report examines the legislative and institutional setting for the waste sanitation problems, and the criteria that need to be applied in selecting and implementing new technologies.

Technical achievements during the initial budget phase of this study consists of work accomplished under the following categories: (a) Hot Cell Notch Filter; and (b) System Integration. In the two week period just prior to the 1993 shutdown of ATF, the authors were able to make the planned scattering measurement. The experiment was a complete success, and the feasibility of the approach was unambiguously demonstrated. The measurements have been reported in a separate article.

In this report, we reconsider the various approximations made to the full equations of motion and energy transport for treating low-speed flows with significant temperature induced property variations. This entails assessment of the development of so-called anelastic for low-Mach number flows outside the range of validity of the Boussinesq equations. An integral part of this assessment is the development of a finite element-based numerical scheme for obtaining approximate numerical solutions to this class of problems. Several formulations were attempted and are compared.

A contamination depth and cobbly soil characterization study was performed in November and December 1993 at the Uranium Mill Tailings Remedial Action (UMTRA) Projects`s New Rifle, Colorado, processing site. This study was initiated due to a concurrence by the US Nuclear Regulatory Commission (NRC) clarifying that the allowable residual contamination in soil should be averaged over the total mass of the soil volume, including cobbles and gravels (i.e., bulk concentration). The New Rifle processing site has a high percentage of cobbles and gravels underlying the pile and other contaminated areas, which preliminary excavation designs have identified for removal and disposal. The main purpose of this study was to evaluate the relative mass percentage and radionuclide concentrations of cobbles and gravels in order to determine the bulk contamination concentrations, revise the underlying excavation design depths, and improve verification methods. Another important goal of the study was to acquire more accurate contamination depth data (profile) for the subpile material. In summary, this recharacterization study will probably reduce the volume of material for excavation/disposal by several hundred thousand cubic yards and significantly reduce the amount of ground water expected to be pumped out of the excavation during cleanup.

This report documents the results from MELCOR calculations of the Long-Term Station Blackout Accident Sequence, with failure to depressurize the reactor vessel, at the Peach Bottom (BWR Mark I) plant, and presents comparisons with Source Term Code Package calculations of the same sequence. STCP has calculated the transient out to 13.5, hours after core uncovery. Most of the MELCOR calculations presented have been carried out to between 15 and 16.7 hours after core uncovery. The results include the release of source terms to the environment. The results of several sensitivity calculations with MELCOR are also presented, which explore the impact of varying user-input modeling and timestep control parameters on the accident progression and release of source terms to the environment. Most of the calculations documented here were performed in FY1990 using MELCOR Version 1.8BC. However, the appendices also document the results of more recent calculations performed in FY1991 using MELCOR versions 1.8CZ and 1.8DNX.

More than 2,000 reports from the Occurrence Reporting and Processing System (ORPS) database were examined in order to identify weaknesses in the implementation of the guidance for the Conduct of Operations (DOE Order 5480.19) at Defense Program (DP) facilities. The analysis revealed recurrent problems involving procedures, training of employees, the occurrence of accidents, planning and scheduling of daily operations, and communications. Changes to DOE 5480.19 and modifications of the Occurrence Reporting and Processing System are recommended to reduce the frequency of these problems. The primary tool used in this analysis was a coding scheme based on the guidelines in 5480.19, which was used to classify the textual content of occurrence reports. The occurrence reports selected for analysis came from across all DP facilities, and listed personnel error as a cause of the event. A number of additional reports, specifically from the Plutonium Processing and Handling Facility (TA55), and the Chemistry and Metallurgy Research Facility (CMR), at Los Alamos National Laboratory, were analyzed separately as a case study. In total, 2070 occurrence reports were examined for this analysis. A number of core issues were consistently found in all analyses conducted, and all subsets of data examined. When individual DP sites were …

The objective of this analysis was to characterize the benefits of the individual energy conservation measures that were applied to an existing large office building. The measures included those for lighting; those for the heating, ventilation, and air conditioning (HVAC) systems; and an energy management and control system (EMCS). The purpose was to improve our understanding of the impacts of the individual measures in contrast to the entire group of measures that were installed during a building improvement project. The scope of the study was primarily analytical; it used an hourly building simulation model to estimate the benefits. Input parameters for this model were adjusted so that the calculated results matched closely with the available monthly electrical billing data. Supplemental building energy use data were collected and used to improve the adjustment of these parameters. The benefits of the individual measures were then calculated using the matched model.

This report examines experimental results obtained from three P Tunnel events -- Mission Cyber, Disko Elm, and Distant Zenith. The objective of the study was to determine if there were any differences in the explosive source coupling for the three events. It was felt that Mission Cyber might not have coupled well because the ground motions recorded for that event were much lower than expected based on experience from N Tunnel. Detailed examination of the physical and chemical properties of the tuff in the vicinity of each explosion indicated only minor differences. In general, the core samples are strong and competent out to at least 60 m from each working point. Qualitative measures of core sample strength indicate that the strength of the tuff near Mission Cyber may be greater than indicated by results of static testing. Slight differences in mineralogic content and saturation of the Mission Cyber tuff were noted relative to the other two tests, but probably would not result in large differences in ground motions. Examination of scaled free-field stress and acceleration records collected by Sandia National Laboratory (SNL) indicated that Disko Elm showed the least scatter and Distant Zenith the most scatter. Mission Cyber measurements tend …

This document introduces QA guidance pertaining to design and implementation of laboratory procedures and processes for collecting DOE Environmental Restoration and Waste Management (EM) ESAA (environmental sampling and analysis activities) data. It addresses several goals: identifying key laboratory issues and program elements to EM HQ and field office managers; providing non-prescriptive guidance; and introducing environmental data collection program elements for EM-263 assessment documents and programs. The guidance describes the implementation of laboratory QA elements within a functional QA program (development of the QA program and data quality objectives are not covered here).