This is a continuing research effort into the new field of measuring resistivity of geological formations from within cased wells. Additional data confirming the feasibility of the technology is to be taken in a test well with the existing stop-hold-and-lock apparatus which is called the Thru Casing Resistivity Apparatus (TCRA). After that data is obtained, the already existing mechanical apparatus developed in an earlier phase of the project will then be modified and new electronic components will be fabricated to test the concept of a moving apparatus called the Moving Thru Casing Resistivity Apparatus (Moving TCRA). These steps are considered sufficient for subsequent commercial development by industry. The study by ParaMagnetic Logging, Inc. of measuring resistivity through casing with the Thru Casing Resistivity Apparatus is of great importance to the oil and gas industries. It is important to measure resistivity through casing for at least the following reasons: locating bypassed oil and gas; measuring water breakthrough during water flooding operations; reservoir evaluation; measurements through a drill string when the drilling bit is stopped; and environmental monitoring of disposal wells, water wells, etc.

Demonstration of a passive vapor extraction remediation system is planned for sites in the 200 West Area used in the past for the disposal of waste liquids containing carbon tetrachloride. The passive vapor extraction units will consist of a 4-in.-diameter pipe, a check valve, a canister filled with granular activated carbon, and a wind turbine. The check valve will prevent inflow of air that otherwise would dilute the soil gas and make its subsequent extraction less efficient. The granular activated carbon is used to adsorb the carbon tetrachloride from the air. The wind turbine enhances extraction rates on windy days. Passive vapor extraction units will be designed and operated to meet all applicable or relevant and appropriate requirements. Based on a cost analysis, passive vapor extraction was found to be a cost-effective method for remediation of soils containing lower concentrations of volatile contaminants. Passive vapor extraction used on wells that average 10-stdft{sup 3}/min air flow rates was found to be more cost effective than active vapor extraction for concentrations below 500 parts per million by volume (ppm) of carbon tetrachloride. For wells that average 5-stdft{sup 3}/min air flow rates, passive vapor extraction is more cost effective below 100 ppm.

This report provides the qualitative risk assessment (QRA) for the 100-KR-4 groundwater operable unit at the US Department of Energy`s (DOE) Hanford Site in southeastern Washington State. The extent of the groundwater beneath the 100 K Area is defined in the Remedial Investigation/Feasibility Study Work Plan for the 100-KR-4 Operable Unit (DOE-RL 1992a). The QRA is an evaluation or risk using a limited amount of data and a predefined set of human and environmental exposure scenarios and is not intended to replace or be a substitute for a baseline risk assessment.

This draft Regulatory Compliance Strategy (RCS) report will aid the ER program in developing and implementing Remedial Design/Remedial Action (RD/RA) projects. The intent of the RCS is to provide guidance for the implementation of project management requirements and to allow the implementation of a flexible, graded approach to design requirements depending on the complexity, magnitude, schedule, risk, and cost for any project. The RCS provides a functional management-level guidance document for the identification, classification, and implementation of the managerial and regulatory aspects of an ER project. The RCS has been written from the perspective of the ER Design Manager and provides guidance for the overall management of design processes and elements. The RCS does not address the project engineering or specification level of detail. Topics such as project initiation, funding, or construction are presented only in the context in which these items are important as sources of information or necessary process elements that relate to the design project phases.

This interface control document (ICD) between PUREX/UO{sub 3} Plant Transition (PPT) and Solid Waste Disposal Division (SWD) establishes at a top level the functional responsibilities of each division where interfaces exist between the two divisions. Since the PUREX Transition and Solid Waste Disposal divisions operate autonomously, it is important that each division has a clear understanding of the other division`s expectations regarding these interfaces. This ICD primarily deals with solid wastes generated by the PPT. In addition to delineating functional responsibilities, the ICD includes a baseline description of those wastes that will require management as part of the interface between the divisions. The baseline description of wastes includes waste volumes and timing for use in planning the proper waste management capabilities: the primary purpose of this ICD is to ensure defensibility of expected waste stream volumes and Characteristics for future waste management facilities. Waste descriptions must be as complete as-possible to ensure adequate treatment, storage, and disposal capability will exist. The ICD also facilitates integration of existing or planned waste management capabilities of the PUREX. Transition and Solid Waste Disposal divisions. The ICD does not impact or affect the existing processes or procedures for shipping, packaging, or approval for shipping …

The objectives of this integrity test are to (1) inspect the interior of this pipeline by in-line camera survey and (2) if required, conduct a pressure test on a section of the pipeline. The U-1 and U-2 Cribs were constructed in 1951. From March 1952 to June 1967, the site received cell drainage from Tank 5-2 in the 221-U Building nd waste from the 224-U Building via the overflow from the 241-U-361 Settling Tank. From June 1957 to July 1957, the site received waste from the 224-U Building via the overflow from the 241-U-361 Settling Tank and contaminated solvent from the 276-U Settling Tank solvent storage area. The discharge of 221-U waste was discontinued during shutdown of production operations. From July 1957 to May 1967, the site received waste from the 224-U Building and equipment decontamination and reclamation wastes from operations in the 221-U Building canyon. The scope of work is encompassed in five steps: (1) obtaining access to the pipeline in order to perform an in-line camera survey of the line to the greatest extent possible, (2) evaluating the need for further investigation of the pipeline, (3) blanking the line, as needed, to perform a pressure test, (4) conducting …

Remedial investigations at the 307 retention basins and 307 trenches (316-3) in the 300 Area of the Hanford Site were conducted as part of the 300-FF-1 operable unit Phase 1 remedial investigation (RI) in accordance with the approved RI work plan. During the RI, the southwestern boundary of the 300-FF-1 operable unit was modified by all signatories to the Hanford Federal Facility Agreement and Consent Order, which shifted the 307 retention basins and 307 trenches to the 300-FF-3 operable unit. As a consequence, the RI results from these waste management units were not included in the Phase 1 Remedial Investigation Report for the 300-FF-1 Operable Unit. As a results of recent Hanford Federal Facility Agreement and Consent Order negotiations, the 300-FF-2 operable unit now consists of the remaining 300 Area operable units within the 300 Area National Priorities List (NPL), which includes the former 300-FF-3 operable unit. Therefore, this document summarizes the RI results from the 307 retention basins and 307 trenches in the 300-FF-2 operable unit. Analysis and evaluation of these results well be included in the 300-FF-2 RI report.

Several technologies for clean up of solvents such as trichloroethylene, from groundwater were examined to determine the most reasonable strategy for the southern Sector in A/M Area of Savannah River Site. The most promising options identified were: pump and treat technology, airlift recirculation technology, and bioremediation technology. These options range from baseline/traditional methods to more innovative technologies. The traditional methods would be straightforward to implement, while the innovative methods have the potential to improve efficiency and reduce long term costs.

The resistance of two commercial gloves to 20 chemicals commonly used in glove boxes was studied. The chemicals were inorganic acids/bases/salts, organic acids, alcohols, glycols, halogen compounds, sulfur compounds, and hydrocarbons. The ASTM cell was used to study permeation of volatile organic compounds through protective clothing materials using air, flame ionization detector/gas chromatography; a modified version of the cell was used with isopropanol for the nonvolatile organic compounds. Permeation of inorganic compounds through the elastomers was studied using the ASTM cell with water, conductivity meter. A Teflon cell was used with HF and ammonium hydrofluoride. Results: Hypalon protects against all chemicals except trichloroethylene (TCE) and CCl{sub 4}. Acetic acid and ethanol permeated through neoprene, which also did not protect against TCE and CCl{sub 4}. Sulfuric acid dissolved neoprene in 5 h. Kerosene permeated through neoprene in 5 h. Although neoprene showed good resistance to cutting oil, TCE in cutting oil broke through in 61 min. Neoprene showed good protection against all the other chemicals with no breakthrough before 6 h.

Advanced reservoir characterization techniques are being applied to selected reservoirs in the Frio Fluvial-Deltaic Sandstone (Vicksburg Fault Zone) trend of South Texas in order to maximize the economic producibility of resources in this mature oil play. More than half of the reservoirs in this depositionally complex play have already been abandoned, and large volumes of oil may remain unproduced unless advanced characterization techniques are applied to define untapped, incompletely drained, and new pool reservoirs as suitable targets for near-term recovery methods. This project is developing interwell-scale geological facies models and assessing engineering attributes of Frio fluvial-deltaic reservoirs in selected fields in order to characterize reservoir architecture, flow unit boundaries, and the controls that these characteristics exert on the location and volume of unrecovered mobile and residual oil. The results of these studies will lead directly to the identification of specific opportunities to exploit these heterogeneous reservoirs for incremental recovery by recompletion and strategic infill drilling. Work during the second project quarter of 1994 focused on continuation of Phase 2 tasks associated with characterizing stratigraphic heterogeneity in selected Frio fluvial-deltaic sandstone reservoirs. Playwide reservoir assessment continued as reservoir engineering data from fields throughout the Frio Fluvial-Deltaic Sandstone trend were grouped within …

Project W-026, Waste Receiving and Processing (WRAP) Facility Module 1, a 1991 Line Item, is planned for completion and start of operations in the spring of 1997. WRAP Module 1 will have the capability to characterize and repackage newly generated, retrieved and stored transuranic (TRU), TRU mixed, and suspect TRU waste for shipment to the Waste isolation Pilot Plant (WIPP). In addition, the WRAP Facility Module 1 will have the capability to characterize low-level mixed waste for treatment in WRAP Module 2A. This report documents the assumptions and cost estimates for decontamination and clean-up of a maximum possible fire loss (MPFL) as defined by DOE Order 5480.7A, FIRE PROTECTION. The Order defines MPFL as the value of property, excluding land, within a fire area, unless a fire hazards analysis demonstrates a lesser (or greater) loss potential. This assumes failure of both automatic fire suppression systems and manual fire fighting efforts. Estimates were developed for demolition, disposal, decontamination, and rebuilding. Total costs were estimated to be approximately $98M.

An evaluation has been made of the radionuclides produced as products of reactor neutron activation as they exist in high level waste (HLW) and their potential to contaminate and impact low level waste (LLW). Process knowledge was used to define the source terms of tritium, carbon, nickel, and cobalt activation products in HLW in an effort to help characterize these radionuclides in HLW supernate in support of LLW Certification. This report uses waste tank sample data and materials inventory data to determine the potential for waste packages, contaminated with tank supernate, to exceed the E-Area Vault (EAV) Package Acceptance Criteria (PAC).

This report assesses the tank farm`s high level waste supernate to determine any potential impacts on waste certification for the E-Area vaults (EAV). The Waste Acceptance Criteria procedure (i.e., WAC 3.10 of the 1S manual) imposes administrative controls on radioactive material in waste packages sent to the EAV, specifically on six fission products. Waste tank supernates contain various fission products, so any waste package containing material contaminated with supernate will contain these radioactive isotopes. This report develops the process knowledge basis for characterizing the supernate composition for these isotopes, so that appropriate controls can be implemented to ensure that the EAV WAC is met. Six fission products are listed in the SRS 1S Manual WAC 3.10: Se-79, which decays to bromine; Sr-90, which decays to niobium; Tc-99, which decays to ruthenium; Sn-126, which decays to tellurium; I-129, which decays to xenon; and Cs-137, which decays to barium.

The 1S Manual requires that High Level Waste (HLW) implement a waste certification program prior to sending waste packages to the E-Area vaults. To support the waste certification plan, the HLW supernate inventory of uranium, plutonium, neptunium and americium have been characterized. This characterization is based on the chemical, isotopic and radiological properties of these elements in HLW supernate. This report uses process knowledge, solubility data, isotopic inventory data and sample data to determine if any isotopes of the aforementioned elements will exceed the minimum reportable quantity (MRQ) for waste packages contaminated with HLW supernate. If the MRQ can be exceeded for a particular nuclide, then a method for estimating the waste package content is provided. Waste packages contaminated from HLW supernate do not contain sufficient U-233, U-234, U-235, U-236, U-238, Pu-239, Pu-240, Pu-241, Pu-242 or Am-241 to warrant separate reporting on the shipping manifest. Calculations show that, on average, more than 100 gallons of supernate is required to exceed the PAC (package acceptance criteria) for each of these nuclides. Thus it is highly unlikely that the PAC would be exceeded for these nuclides and unlikely that the MRQ would be exceeded. These nuclides should be manifested as zero for …

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In a recent paper, Watanabe, {ital et. al.} used direct simulation Monte Carlo to study Rayleigh-B{acute e}nard convection. They reported that, using stress-free boundary conditions, the onset of convection in the simulation occurred at a Rayleigh number much larger than the critical Rayleigh number predicted by linear stability analysis. We show that the source of their discrepancy is their failure to include the temperature jump effect in the calculation of Rayleigh number.

The objective of the Volatile Organic Compounds in Non-arid Soils Integrated Demonstration at the Savannah River Site is to evaluate innovative remediation, characterization, and monitoring systems to facilitate restoration of contaminated sites. The focus of the third phase of the Integrated Demonstration is to evaluate the use of heating technologies, both radio frequency and ohmic heating, to enhance the removal of contamination from clay layers. This report documents characterization data collected in support of the ohmic heating demonstration performed by researchers from PNL. The data presented and discussed in this report include a general description of the site including location of piezometers and sensors installed to monitor the remedial process, and detailed geologic cross sections of the study site, sampling and analysis procedures for sediment samples, tabulations of moisture and VOC content of the sediments, models of the distribution of contamination before and after the test, and a comparison of the volume estimations of contaminated material before and after the test. The results show that the heating process was successful in mobilizing and removing solvent from the heated interval.

Agency strategic plan for the Texas State Board of Pharmacy describing the organization's planned services, activities, and other goals during fiscal years 1995 through 1999.