This report evaluates the soil sampling activities, soil sample analysis, and soil sample data associated with the closure activities at the 105-DR Large Sodium Fire Facility. The evaluation compares these activities to the regulatory requirements for meeting clean closure. The report concludes that there is no soil contamination from the waste treatment activities.

This document is the final, format IV, laboratory report for characterization of tank 241-U-101 (U-101) grab samples from risers 1 and 7. It transmits additional analytical data for specific gravity (Sp.G.), and all raw analytical data which were not provided in the 45-day report. The 45-day report is attached to this final report as Part II. Secondary analyses were not performed on any of the U-101 samples. This is because none of the primary analyte limits, which trigger the performance of secondary analyses, were exceeded. Grab samples were taken on May 29, 1996 and May 30, 1996 from risers 1 and 7, respectively, and were received at the 222-S Laboratory on the same days that they were collected. Analyses were performed in accordance with the Tank Sampling and Analysis Plan (TSAP) for this tank and the Safety Screening Data Quality Objective (DQO). The samples were analyzed for differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha activity (AT), visual appearance, bulk density, and specific gravity. A sample data summary table, includes sample analytical data accompanied by quality control data (for example, duplicate, spike, blank and standard results and detection limits and counting efforts). The table includes data for DSC, TGA, …

Tennessee`s Resource Valley, a regional economic development organization, was asked to facilitate a two-year, $750,000 grant from the Department of Energy. The grant`s purpose was to make the East Tennessee region less dependent on federal funds for its economic well-being and to increase regional awareness of the advantages of proximity to the Department of Energy facilities in Oak Ridge. The mission of Tennessee`s Resource Valley is to market the business location advantages of mid-East Tennessee to corporate decision makers and to facilitate regional initiatives that impact the creation of quality job opportunities. Tennessee`s Resource Valley represents fifteen (15) counties in East Tennessee: Anderson, Blount, Campbell, Claiborne, Cocke, Grainger, Jefferson, Knox, Loudon, Monroe, Morgan, Roane, Scott, Sevier and Union.

This Acceptance Test Report (ATR) will summarize the results of performing ATP-183 which tested the modifications to the DACS Test Strategy software.

Tank 241-C-106 is a single shell tank at the Hanford Site in south central Washington State, and is the only tank on Hanford`s High-Heat Tank Watch List. This action plan defines possible abnormal conditions (such as ventilation system failure or a leaking tank) that could lead to excessive temperature increases in tank 241-C-106, and documents pre-planned contingency actions would effectively mitigate the consequences of such increased temperatures. Potential structural damage may result from high temperatures caused by inadequate cooling. Tank 241-C-106 contains a significant amount of high-heat radioactive waste, mainly strontium, and requires forced ventilation combined with evaporation for adequate cooling. Forced ventilation at 2,400 ft/min, along with periodic water additions of approximately 6,000 gal/month, is currently maintaining the tank temperature within the required range. This action plan addresses high-heat concerns and corrective measures unique to tank 241-C-106 and to proposed sluicing activities in tank 241-C-106. Other general emergency actions for the 200 Area Tank Farms, such as those forest fires and earthquakes, are described in WHC-CM-4-43, `Emergency Management Procedures` and are not included in this document.

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

The Appalachian Clean Coal Technology Consortium has been established to help U.S. Coal producers, particularly those in the Appalachian region, increase the production of lower-sulfur coal. In keeping with the recommendations of the Advisory Committee, first-year R&D activities are focused on two areas of research: fine coal dewatering and modeling of spirals. The industry representatives to the Consortium identified fine coal dewatering as the most needed area of technology development. Dewatering studies are conducted by Virginia Tech`s Center for Coal and Minerals Processing. A spiral model will be developed by West Virginia University. The research to be performed by the University of Kentucky has recently been defined as: A Study of Novel Approaches for Destabilization of Flotation Froth. Accomplishments to date of these three projects are presented in this report.

In the dewatering project, two different approaches are taken. One approach involves displacing the water on the surface of coal by a hydrophobic substance that can be readily recovered and recycled. This novel concept, referred to as the Hydrophobic Dewatering (HD) process, is based on improved understanding of the surface chemistry of dewatering. The other approach is to use disposable dewatering substances in mechanical dewatering. The objectives of the proposed work are (1) to test the HD process on a variety of coals from the Appalachian coal fields, and (2) to identify suitable dewatering reagents that would enable mechanical dewatering to reduce the moisture to the levels satisfactory to electrical utilities and other coal users. The objective of the spiral separation project is to use computer modeling to develop better, more efficient spiral designs for coal cleaning. The fully-developed model will predict spiral performance based on variations in spiral profile, flow rate, and pitch. Specific goals are to: (1) design spirals capable of making separations at a specific gravity of 1.5, and (2) broaden the size range at which spirals make effective separations.

The Oxy West Welch project is designed to demonstrate how the use of advanced technology can improve the economics of miscible CO{sub 2} injection projects in lower quality shallow shelf carbonate reservoirs. The research and design phase primarily involves advanced reservoir characterization and the demonstration phase will implement the reservoir management plan based on an optimum miscible CO{sub 2} flood as designed in the initial phase. The reservoir characterization phase is near completion with the tomography currently being integrated into the petrophysical and 3-D seismic interpretations. The petrophysical analysis has yielded both an improved net pay criteria and a method of calculating permeability from log response. The 3-D seismic has enhanced the ability to distribute the reservoir properties between wellbore control points. During the reporting period, work was completed on the CO{sub 2}, stimulation treatments and the hydraulic fracture design. Analysis of the CO{sub 2} stimulation treatment provided a methodology for predicting results. The hydraulic fracture treatment proved up both the fracture design approach and the use of passive seismic for mapping the fracture wing orientation.

An asymmetric muon-proton collider is proposed as an instrument for possible quark structure search. Energy of proton beam is supposed to be some 5-6 times of muon energy. Estimated luminosity of the collider with two rings-the Tevatron accelerator and {mu}-ring-is found to be of the order of 10{sup 33} s{sup {minus}1} cm{sup {minus}2}.

The Department of Energy`s (Department) Albuquerque Operations Office (Albuquerque) and Los Alamos National Laboratory (Los Alamos) are responsible for acquiring consulting services in a manner most advantageous to the Government by ensuring adequate competition. Although the Department prefers competitively awarding subcontracts, including consultant agreements, to ensure the lowest possible cost, it allows sole sourcing a subcontract if the sole source is fully justified. The objective of the audit was to determine whether Los Alamos` consultant agreements contained adequate sole source justifications. The audit showed that Los Alamos may not have acquired some of its consultant agreements at the lowest possible cost because it did not prepare adequate sole source justifications for 17 sole source consultant agreements valued at $842,900. This condition existed because: (1) requesters did not follow policies and procedures when preparing sole source justifications, (2) Los Alamos did not have an internal mechanism to reject consultant agreements that were not adequately justified, and (3) the Department did not review consultant agreements to evaluate the adequacy of sole source justifications. Without adequate justifications, the Department cannot be assured that consultant services were obtained at the lowest possible cost. We therefore recommended that the Manager, Albuquerque Operations Office require Los …

To address disposition of special nuclear material taken from dismantled nuclear weapons, DOE in Nov. 1994 agreed to provide financial assistance to the State of Texas to establish the Amarillo National Resource Center for Plutonium. The Center sponsored research on storage, disposition, potential utilization, and transportation of Pu, high explosives, and other materials generated from nuclear weapons disassembly. Objective of the audit was to determine if DOE provided adequate management, direction, and control to ensure that the Center`s activities are beneficial to DOE and do not duplicate the work at DOE`s national laboratories. DOE has had limited involvement in the Center. The Center`s projects identified by the Office of Fissile Materials Disposition as supporting Defense Programs activities have not been reviewed. Review revealed that DOE funded about $1.8 million during the first two years of Center`s operation for research which duplicated research conducted by DOE`s national laboratories. This duplication occurred because responsibility for technical review was assigned at a level without authority to fully coordinate review of the Center`s research projects with DOE`s national laboratories. Recommendations are given.

The Department of Energy (Department) restructured its work force at the Fernald Environmental Management Project (Fernald Project) to reduce staffing levels and to modify the mix of workers` skills in response to budget cuts, facility closures, and changes in the Fernald Project`s mission. The objective of this audit was to determine whether the work force restructurings were effective in reducing staffing levels and in changing the mix of workers` skills. As of September 30, 1995, the restructurings were not effective in reducing staffing levels or in improving the mix of workers` skills. The Fernald Environmental Restoration Management Corporation (FERMCO) spent $2.9 million to separate 255 employees in October 1993. However, by September 30, 1994, all but 14 of the employees separated were either rehired or replaced by new employees with similar skills. The second restructuring began in October 1994 and is not expected to be completed until May 1996. The Department expects the second restructuring to reduce FERMCO`s work force by 476 employees at a cost of $12.9 million. However, since the second restructuring began, FERMCO has hired 265 new employees and at September 30, 1995, had open job announcements seeking 82 additional employees. Many of these new employees have …

This report summarizes the results of qualification testing of the B Plant D-Filter Detector System. The purpose of this test was to verify that the system meets the performance requirements and that the unit is ready for field deployment. Testing was performed in the test pit in the 306E Facility. This detector system will be deployed in the B Plant D-Filter to measure beta/gamma dose rates from the filter bank.

One plan for stabilization of the Solar Pond waters and sludges at Rocky Flats Plant (RFP), is evaporation and cement solidification of the salts to stabilize heavy metals and radionuclides for land disposal as low-level mixed waste. It has been reported that nitrate (NO{sub 3}{sub {minus}}) salts may interfere with cement stabilization of heavy metals and radionuclides. Therefore, biological nitrate removal (denitrification) may be an important pretreatment for the Solar Pond wastewaters at RFP, improving the stability of the cement final waste form, reducing the requirement for cement (or pozzolan) additives and reducing the volume of cemented low-level mixed waste requiring ultimate disposal. A laboratory investigation of the performance of the Sequencing Batch Reactor (SBR) activated sludge process developed for nitrate removal from a synthetic brine typical of the high-nitrate and high-salinity wastewaters in the Solar Ponds at Rocky Flats Plant was carried out at the Environmental Engineering labs at the University of Colorado, Boulder, between May 1, 1994 and October 1, 1995.

This Acceptance Test Report (ATR) documents the results of WHC-SD-WM-ATP-146 (Prototype Cone Penetrometer Moisture Probe Acceptance Test Procedure) and WHC-SD-WM-ATP-145 (Cone Penetrometer Moisture Probe Acceptance Test Procedure). The master copy of WHC-SD-WM-ATP-145 can be found in Appendix A and the master copy of WHC-SD-WM-ATP-146 can be found in Appendix B. Also included with this report is a matrix showing design criteria of the cone penetrometer moisture probe and the verification method used (Appendix C).

The crystal and molecular structures of azatranes have been extensively studied for a variety of M atoms. The crystal and molecular structures of six similar cage compounds: (t-Bu)NV(MeNCH{sub 2}CH{sub 2}){sub 3}N, HSi(OCH{sub 2}CH{sub 2}){sub 2}(HNCH{sub 2}CH{sub 2})N, O{sub 4}ClLi(HNCH{sub 2}SH{sub 2}){sub 3}N, MeP(Me{sub 3}NCH{sub 2}CH{sub 2}){sub 3}N, t-BuGe(HNCH{sub 2}CH{sub 2}){sub 3}N, and Al(Me{sub 3}SiNCH{sub 2}CH{sub 2}){sub 3}N were determined by the use of three-dimensional, single crystal x-ray diffraction.

This criticality safety evaluation allows the application of a 250 gram fissile limit to the operation of the maintenance glovebox in 236-Z at the Plutonium Finishing Plant

This report formally documents the planning assumptions for Function 4.2.4, Dispose Waste, to provide a basis for lower level Tank Waste Remediation System (TWRS) Disposal Program decisions and analyses. The TWRS Environmental Impact Statement (DOE/EIS 1996) and a supplemental Environmental Impact Statement for closure of operable units will provide the ultimate Records of Decision for the TWRS strategy at this level. However, in the interim, this decision document provides a formal basis for the TWRS Dispose Waste planning assumptions. Function 4.2.4 addresses the disposition of immobilized high-level waste (IHLW), the disposition of immobilized low-activity waste (ILAW), and closure of the tank farm operable units.

This report formally documents the planning assumptions for Function 4.2.4, {ital Dispose Waste} to provide a basis for lower level Tank Waste Remediation System (TWRS) Disposal Program decisions and analyses. The TWRS Environmental Impact Statement (DOE/EIS 1996) and a supplemental Environmental Impact Statement for closure of operable units will provide the ultimate Records of Decision for the TWRS strategy at this level. However, in the interim, this decision document provides a formal basis for the TWRS Dispose Waste planning assumptions. Function 4.2.4 addresses the disposition of immobilized high-level waste (IHLW), the disposition of immobilized low-activity waste (ILAW), and closure of the tank farm operable units.

A discussion of the reasons for the dependance of X/Q on receptor distance and compass sector is presented. In addition, X/Qs are calculated for three receptor scenarios on Highway 240 including a moving receptor. Example radiological doses and toxicological exposures at Highway 240 are calculated for two accidents already analyzed in the TWRS FSAR.

The US Department of Energy (DOE) has developed an Integrated Program Plan (IPP) to address concerns identified in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. The IPP describes the actions that DOE plans to implement at its various sites to convert excess fissile materials to forms or conditions suitable for safe interim storage. The baseline IPP was issued as DOE's DNFSB Recommendation 94-1 Implementation Plan (IP), which was transmitted to the DNFSB on February 28, 1995. The IPP was subsequently supplemented with an Integrated Facilities Plan and a Research and Development Plan, which further develop complex-wide research and development and long-range facility requirements and plans. These additions to the baseline IPP were developed based on a systems engineering approach that integrated facilities and capabilities at the various DOE sites and focused on attaining safe interim storage with minimum safety risks and environmental impacts. Each affected DOE site has developed a Site Integrated Stabilization Management Plan (SISMP) to identify individual site plans to implement the DNFSB Recommendation 94-1 IPP. The SISMPs were developed based on the objectives, requirements, and commitments identified in the DNFSB Recommendation 94-1 IP. The SISMPs supported formulation of the initial versions of the Integrated Facilities Plan …

This documents the dose rate calculations for the Strontium Fluoride and Cesium Chloride capsules and Overpacked Capsules.