A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO reviewed the types of activities undertaken by U.S. contractors to meet offset obligations associated with the sale of defense equipment to various foreign governments."

Quarterly publication of the Texas Comptroller's Office regarding sales and use tax in the state of Texas, including an analysis by county, analysis by industry, and related notes.

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

The acceptance test for the Westronics driver. This driver connects the Westronics Smart Multiplexer with the TMACS monitoring system.

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-T-105. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-T-105 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03, to ``issue characterization deliverables consistent with the waste information requirements documents developed for 1998``.

This report addresses Developments and Dilemmas of Algeria.

This report covers proposed and enacted legislative initiatives to change child nutrition programs (including the WIC program) during 1997 and 1998.

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The acceptance test report for the TMACS Acromag 1/0 Processor interface running under Windows NT.

The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that …

This is the final report for the polychlorinated biphenyls analysis of Tank-103 (TK-103) in the 219-S Facility at 222-S Laboratory. Twenty 1-liter bottles (Sample numbers S98SO00074 through S98SO00093) were received from TK-103 during two sampling events, on May 5 and May 7, 1998. The samples were centrifuged to separate the solids and liquids. The centrifuged sludge was analyzed for PCBs as Aroclor mixtures. The results are discussed on page 6. The sample breakdown diagram (Page 114) provides a cross-reference of sample identification of the bulk samples to the laboratory identification number for the solids. The request for sample analysis (RSA) form is provided as Page 117. The raw data is presented on Page 43. Sample Description, Handling, and Preparation Twenty samples were received in the laboratory in 1-Liter bottles. The first 8 samples were received on May 5, 1998. There were insufficient solids to perform the requested PCB analysis and 12 additional samples were collected and received on May 7, 1998. Breakdown and sub sampling was performed on May 8, 1998. Sample number S98SO00084 was lost due to a broken bottle. Nineteen samples were centrifuged and the solids were collected in 8 centrifuge cones. After the last sample was processed, …

This Enhanced Characterization of the Repository Block Requirements Document (ECRB-RD) provides applicable design and construction requirements for the Enhanced Characterization of the Repository Block (ECRB) East-West Drift and its associated equipment. This document also identifies the applicable requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) Document (YMPICM-00 19, Revision 2, ICN- 1) for design and construction of the ECRB East-West Drift, ground support, constructor support utilities and components. These requirements have been tailored specifically for the ECRB East-West Drift design and construction. The allocated requirements for the ECRB East-West Drift are in Sections III through VI. The requirements in sections III through VI contain requirement numbers from the ESFDR, Rev 2, ICN-1 for reference back to the ESFDR. Each requirement in the ECRB-RD also identifies a trace to the Site Design and Test Requirements Document (YMP/CM-0021, Rev. 2, ICN-1) and 10CFR60 similar to the style used in the ESFDR. These traces to 10CFR60 are consistent with the 1995 version of 10CFR60 used by the SD&TRD and the ESFDR. Those ESFDR requirements statements that were technically modified are identified as such and those that were derived as part of this allocation are also identified. An activity evaluation has been performed …

Simulations of the Integrated Computer Control System (ICCS) status monitor framework have been performed. The results provide confidence that the requirements related to the framework can be met. The simulation was done by using the SIMPROCESS discrete-event-modeling tool. This document describes the results of the simulations. The requirements related to the status monitor framework are the following: (1) 1 graphical user interface (GUI) per workstation supports 10 status updates per second. (2) Broad-view control system status updates can be received in less than 10 seconds in the expected configuration of the ICCS for NIF deployment.

It is widely acknowledged that Mure neutron-detection technologies will need to offer increased performance at lower cost. One clear route toward these goals is rapid and direct detection of fast neutrons prior to moderation. This report describes progress to date in an effort to achieve such neutron detection via proton recoil within plastic scintillator. Since recording proton-recoil events is of little practical use without a means to discriminate effectively against gamma-ray interactions, the present effort is concentrated on demonstrating a method that distinguishes between pulse types. The proposed method exploits the substantial difference in the speed of fission neutrons and gamma-ray photons. Should this effort ultimately prove successful, the resulting. technology would make a valuable contribution toward meeting the neutron-detection needs of the next century. This report describes the detailed investigations that have been part of Pacific Northwest National Laborato@s efforts to demonstrate direct fast-neutron detection in the laboratory. Our initial approach used a single, solid piece of scintillator along with the electronics needed for pulse-type differentiation. Work to date has led to the conclusion that faster scintillator and/or faster electronics will be necessary before satisfactory gamma-ray discrimination is achieved with this approach. Acquisition and testing of both faster scintillator …

We have conducted static dissolution tests to study the corrosion behavior of the Environmental Assessment (EA) glass, which is the benchmark glass for high-level waste glasses being produced at US Department of Energy facilities. These tests were conducted to evaluate the behavior of the EA glass under the same long-term and accelerated test conditions that are being used to evaluate the corrosion of waste glasses. Tests were conducted at 90 C in a tuff groundwater solution at glass surface area/solution volume (WV) ratios of about 2000 and 20,000 m{sup {minus}1}. The glass dissolved at three distinct dissolution rates in tests conducted at 2000 m{sup {minus}1}. Based on the release of boron, dissolution within the first seven days occurred at a rate of about 0.65 g/(m{sup 2} {center_dot} d). The rate between seven and 70 days decreased to 0.009 g/(m{sup 2} {center_dot} d). An increase in the dissolution rate occurred at longer times after the precipitation of zeolite phases analcime, gmelinite, and an aluminum silicate base. The dissolution rate after phase formation was about 0.18 g/(m{sup 2} {center_dot} d). The formation of the same zeolite alteration phases occurred after about 20 days in tests at 20,000 m{sup {minus}}. The average dissolution …

The objective of this report is to provide information to help DOE plan its future activities on liquid-desiccant technologies. The report meets this objective by (1) identifying commercial and residential markets where the liquid-desiccant systems will first be most successful and (2) identifying advances in the individual components of a liquid-desiccant system that will allow it to expand into new markets.

The Waste Ion Exchange Facility was free released for demolition on July 30, 1998. No surprises or unknowns were noted. The building and associated piping were demolished and removed in September, 1998. The north drain line was removed to three feet outside of the foundation of the building. The east drain line was removed to the foundation of Building 593. The piping located in the north pit drain and east pit drain (which were located under the concrete) were free released. The catch basin, which was located on the south side of the building and also connected to equalization tanks in building 592, was released for unrestricted use and was left intact.

This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division of Argonne National Laboratory in the period of October 1996 through September 1997. Studies have been performed to evaluate the behavior of nuclear waste glass and spent fuel samples under the unsaturated conditions (low-volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with actinide-doped waste glasses, in progress for over 11 years, indicate that the transuranic element release is dominated by colloids that continuously form and span from the glass surface. The nature of the colloids that form in the glass and spent fuel testing programs is being investigated by dynamic light scattering to determine the size distribution, by autoradiography to determine the chemistry, and by zeta potential to measure the electrical properties of the colloids. Tests with UO{sub 2} have been ongoing for 12 years. They show that the oxidation of UO{sub 2} occurs rapidly, and the resulting paragenetic sequence of secondary phases forming on the sample surface is similar to that observed for uranium found in natural oxidizing environments. The reaction of spent fuel …

Two-phase plumes play an important role in the more practical scenarios for ocean sequestration of CO{sub 2}--i.e. dispersing CO{sub 2} as a buoyant liquid from either a bottom-mounted or ship-towed pipeline. Despite much research on related applications, such as for reservoir destratification using bubble plumes, our understanding of these flows is incomplete, especially concerning the phenomenon of plume peeling in a stratified ambient. To address this deficiency, we have built a laboratory facility in which we can make fundamental measurements of plume behavior. Although we are using air, oil and sediments as our sources of buoyancy (rather than CO{sub 2}), by using models, our results can be directly applied to field scale CO{sub 2} releases to help us design better CO{sub 2} injection systems, as well as plan and interpret the results of our up-coming international field experiment. The experimental facility designed to study two-phase plume behavior similar to that of an ocean CO{sub 2} release includes the following components: 1.22 x 1.22 x 2.44 m tall glass walled tank; Tanks and piping for the two-tank stratification method for producing step- and linearly-stratified ambient conditions; Density profiling system using a conductivity and temperature probe mounted to an automated depth profiler; …

This evaluation examines the compatibility of coating Instacote with existing High-Level Waste facilities and safety practices. No significant incompatibilities are identified. The following actions need to be completed as indicated when applying Instacote on waste tank tops:(1) Prior to application in ITP facilities, the final product should be tested for chemical resistance to sodium tetraphenylborate solutions or sodium titanate slurries.(2) Any waste contaminated with Part A or B that can not be removed by the vendor such as for radiological contamination, HLW must hold the waste until HLW completes a formal assessment of the waste, disposal criteria, and impact.(3) Prior to the start of any application of the coating, each riser needs to be evaluated for masking and masking applied if needed.(4) At the conclusion of an application actual total weight of material applied to a waste tank needs to documented and sent to the tank top loading files for reference purposes.(5) Verify that the final product contains less than 250 ppm chloride.

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This report is a guide to appropriations of Defense for FY1999.

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