The 244-CR Vault is a two-level, multi-cell structure of reinforced concrete constructed below grade. The lower cell contains four individual compartments, each containing a steel process storage tank and equipped with a concrete sump. The upper cell contains the piping and support equipment, and has two compartments for each of the tanks. The ''pump pit'' is accessed by the removal of concrete cover blocks, while the smaller ''riser pit'' is accessed by steel cover plates. The facility most recently was used as a double-contained receiver tank (DCRT). A DCRT is a type of waste transfer tank that together with its related equipment constitutes a short-term storage area for liquid waste and has a pump pit for waste transfer operations. This vault most recently was used for short-term storage and waste routing for saltwell liquid pumped from the 241-C Tank Farm in the 200 East Area. Waste transfer lines are connected inside the pump pit by a jumper installed between connecting nozzles. An active ventilation system is in operation at the 244-CR vault. Ventilation supply air enters the upper vault section through an inlet header with some leakage through the spaces between the cell cover blocks. The upper and lower vaults …

DWPF Engineering requested that the Savannah River Technology Center (SRTC) provide a demonstration of the DWPF flowsheet on sludge from Tank 42H in the Shielded Cell facility. A 5 liter sample of the Tank 42H sludge (ESP-200), obtained with the tank contents fully mixed, arrived at SRTC on January 20, 1998. This report details receipt of the 5 liter sample at SRTC, the decant of the sample, and the characterization of the pre- and post-decant Tank 42H sludge. Evaluation of the measured composition of the supernate indicates Sample ESP-200 became diluted approximately 20 percent by volume prior to receipt. This dilution complicates the relationship of the characterization of Post-Decant ESP-200 to the current contents of Tank 42H. For the purposes of modeling the current tank contents of Tank 42H, this report provides an estimated composition based on analytical data of recent samples from Tank 42H.

This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Fire Protection and Detection System installed by Project W-441 (Cold Vacuum Drying Facility and Diesel Generator Building) functions as required by project specifications.

This report documents a statistical data analysis of radiological data obtained to characterize the 324 Facility B-Cell decontamination and decommissioning waste stream.

This report defines the Double-Shell Tank (DST) Process Waste Sampling Subsystem (PWSS). This subsystem definition report fully describes and identifies the system boundaries of the PWSS. This definition provides a basis for developing functional, performance, and test requirements (i.e., subsystem specification), as necessary, for the PWSS. The resultant PWSS specification will include the sampling requirements to support the transfer of waste from the DSTs to the Privatization Contractor during Phase 1 of Waste Feed Delivery.

The purpose of this analysis is to evaluate potential effects of fault displacement on emplacement drifts, including drip shields and waste packages emplaced in emplacement drifts. The output from this analysis not only provides data for the evaluation of long-term drift stability but also supports the Engineered Barrier System (EBS) process model report (PMR) and Disruptive Events Report currently under development. The primary scope of this analysis includes (1) examining fault displacement effects in terms of induced stresses and displacements in the rock mass surrounding an emplacement drift and (2 ) predicting fault displacement effects on the drip shield and waste package. The magnitude of the fault displacement analyzed in this analysis bounds the mean fault displacement corresponding to an annual frequency of exceedance of 10{sup -5} adopted for the preclosure period of the repository and also supports the postclosure performance assessment. This analysis is performed following the development plan prepared for analyzing effects of fault displacement on emplacement drifts (CRWMS M&O 2000). The analysis will begin with the identification and preparation of requirements, criteria, and inputs. A literature survey on accommodating fault displacements encountered in underground structures such as buried oil and gas pipelines will be conducted. For a …

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The scope of this environmental assessment (EA) is to analyze the potential consequences of the Proposed Action on human health and the environment. Accordingly, this EA contains an introduction to the site and the history of the Grand Junction Office (Chapter One), a description of the Purpose and Need for Agency Action (Chapter Two), a description of the Proposed Action and Alternatives (Chapter Three), and the description of the Affected Environment and the Environmental Consequences (Chapter Four). Resource categories addressed in this EA include geology, soils and topography, groundwater and surface water, floodplains and wetlands, land use and infrastructure, human health, ecological resources, cultural resources, air quality, noise, visual resources, solid and hazardous waste management, transportation, and socioeconomic and environmental justice.

This report reviews progress within NATO to develop a European Security and Defense Identity (ESDI), and the initiative within the European Union to create a common European Security and Defense Policy (ESDP). The report considers both European and U.S. perspectives on these developments. It will be updated as events warrant.

A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO provided information on the Department of Energy's (DOE) merit review practices, focusing on: (1) what procedures DOE has established for performing merit reviews; and (2) whether DOE could document that it has followed the merit review procedures it has established."

We describe the three dimensional global stratospheric chemistry model developed under the NASA Global Modeling Initiative (GMI) to assess the possible environmental consequences from the emissions of a fleet of proposed high speed civil transport aircraft. This model was developed through a unique collaboration of the members of the GMI team. Team members provided computational modules representing various physical and chemical processes, and analysis of simulation results through extensive comparison to observation. The team members' modules were integrated within a computational framework that allowed transportability and simulations on massively parallel computers. A unique aspect of this model framework is the ability to interchange and intercompare different submodules to assess the sensitivity of numerical algorithms and model assumptions to simulation results. In this paper, we discuss the important attributes of the GMI effort, describe the GMI model computational framework and the numerical modules representing physical and chemical processes. As an application of the concept, we illustrate an analysis of the impact of advection algorithms on the dispersion of a NO{sub y}-like source in the stratosphere which mimics that of a fleet of commercial supersonic transports (High-Speed Civil Transport (HSCT)) flying between 17 and 20 kilometers.

This report is a summary of the following topics of the first quarter of 2000: (1) Han Padron Associates (HPA) provided conceptual structural design of the mooring buoy; and (2) they completed partial review of the HPA design and designed the sealing elements.

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A chapter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO provided information on Soviet-designed nuclear power reactors, focusing on: (1) how much money has been spent by the United States and other countries for assistance to improve the safety of Soviet-designed nuclear power reactors--and the types of assistance being provided--as well as planned U.S. expenditures; (2) experts' views on the impact of the assistance; (3) the status of efforts to close high-risk Soviet-designed reactors; and (4) the management of the Department of Energy's (DOE) and the Nuclear Regulatory Commission's (NRC) safety assistance activities."

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A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO reviewed the Small Business Administration's (SBA) progress in performing planning actions for its loan monitoring system."

The goal of the National Ignition Facility (NIF) project is to provide an aboveground experimental capability for maintaining nuclear competence and weapons effects simulation and to provide a facility capable of achieving fusion ignition using solid-state lasers as the energy driver. The facility will incorporate 192 laser beams, which will be focused onto a small target located at the center of a spherical target chamber--the energy from the laser beams will be deposited in a few billionths of a second. The target will then implode, forcing atomic nuclei to sufficiently high temperatures and densities necessary to achieve a miniature fusion reaction. The NIF is under construction, at Livermore, California, located approximately 50 miles southeast of San Francisco, California.

The Energy Policy and Conservation Act (EPCA) as amended by the Energy Policy Act of 1992 (EPACT) establishes that the U.S. Department of Energy (DOE) regulate efficiency levels of certain categories of commercial heating, cooling, and water-heating equip-ment. EPACT establishes the initial minimum efficiency levels for products falling under these categories, based on ASHRAE/IES Standard 90.1-1989 requirements. EPCA states that, if ASHRAE amends Standard 90.1-1989 efficiency levels, then DOE must establish an amended uniform national manufacturing standard at the minimum level specified in the amended Standard 90.1 and that it can establish higher efficiency levels if they would result in significant additional energy savings. Standard 90.1-1999 increases minimum efficiency levels for some of the equipment categories covered by EPCA 92. DOE conducted a screening analysis to determine the energy-savings potential for EPACT-covered products meet and exceeding these levels. This paper describes the methodology, data assumptions, and results of the analysis.

The Energy Policy and Conservation Act (EPCA) as amended by the Energy Policy Act of 1992 (EPACT) establishes that the U.S. Department of Energy (DOE) regulate efficiency levels of certain categories of commercial heating, cooling, and water-heating equipment. EPACT establishes the initial minimum efficiency levels for products falling under these categories, based on ASHRAE/IES Standard 90.1-1989 requirements. EPCA states that, if ASHRAE amends Standard 90.1-1989 efficiency levels, then DOE must establish an amended uniform national manufacturing standard at the minimum level specified in the amended Standard 90.1 and that it can establish higher efficiency levels if they would result in significant additional energy savings. 011Standard 90.1-1999 increases minimum efficiency levels for some of the equipment categories covered by EPCA 92. DOE conducted a screening analysis to determine the energy-savings potential for EPACT-covered products meet and exceeding these levels. This paper describes the methodology, data assumptions, and results of the analysis.

The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures.

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The purpose of this calculation is to evaluate the thermal performance of the naval long spent nuclear fuel (SNF) waste package (WP) under multiple disposal conditions in a monitored geologic repository (MGR). The scope of this calculation is limited to determination of thermal temperature profiles upon the surface of, and within, the naval long SNF WP. The objective is to develop a temperature profile history within the WP, at time increments up to 10,000 years of emplacement. The results of this calculation are intended to support the Naval SNF WP Analysis and Model Report (AMR) for Site Recommendation (SR). This calculation was performed to the specifications within its Technical Development Plan (TDP) (Ref. 8.16). This calculation is developed and documented in accordance with the AP-3.12Q/REV. 0IICN. 0 procedure, Calculations.

A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a legislative requirement, GAO reviewed the Global Hawk Advanced Concept Technology Demonstration, focusing on: (1) whether the average unit flyaway price for the 10 Global Hawk production aircraft numbered 11 through 20 will be within the Department of Defense's (DOD) price goal of $10 million each in fiscal year 1994 dollars; (2) the status of the military user demonstration, including the extent to which Global Hawk has demonstrated reconnaissance capabilities; and (3) DOD and Air Force plans to transition to a formal acquisition program."