This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for the Dukovany VVER/440 V-213 nuclear power plant, Unit 1. Section 1.1 describes the objectives of this study. Section 1.2 discusses the approach that was used for completing the Dukovany PSA. Section 1.3 summarizes the results of the PSA. Section 1.4 provides a comparison of the results of the Dukovany PSA with the results of other PSAs for different types of reactors worldwide. Section 1.5 summarizes the conclusions of the Dukovany PSA.

The DACS, which is housed in a trailer located just outside of the north fence at the SY tank farm, receives input signals from a variety of sensors located in and around the SY-101 tank. These sensors provide information such as: (1) tank vapor space and ventilation system H{sub 2} concentration; (2) tank waste temperature; (3) tank pressure; (4) waste density; (5) operating pump parameters such as speed, flow, rotational position, discharge pressure, and internal temperature; (6) strain (for major equipment); and (7) waste level. The output of these sensors is conditioned and transmitted to the DACS computers where these signals are displayed, recorded, and monitored for out-of-specification conditions. If abnormal conditions are detected, then, in certain situations, the DACS automatically generates alarms and causes the system to abort pump operations. The report documents testing performed per WHC-SD-WM-ATP-082. Rev. 0-13.

Project C-018H is one of the fourteen subprojects to the Hanford Environmental Compliance (HEC) Project. Project C-018H provides treatment and disposal for the 242-A Evaporator and PUREX plant process condensate waste streams. This project used the Integrated Management Team (IMT) approach proposed by RL. The IMT approach included all affected organizations on the project team to coordinate and execute all required project tasks, while striving to integrate and satisfy all technical, operational, functional, and organizational objectives. The HEC Projects were initiated in 1989. Project C-018H began in early 1990, with completion of construction currently targeted for mid-1995. This assessment was performed to evaluate the effectiveness of the management control on design documents and quality assurance records developed and submitted for processing, use, and retention for the Project. The assessment focused primarily on the overall adequacy and quality of the design documentation currently being submitted to the project document control function.

This document devises a method of comparing radiological and non-radiological hazard control levels. Such a comparison will be useful in determining the design control features for facilities that handle radioactive mixed waste. The design control features of interest are those that assure the protection of workers and the environment from unsafe airborne levels of radiological or non-radiological hazards.

K-Basin uses ion exchange modules and ion exchange (IX) columns for removing radionuclides from the basin water. When the columns and modules are loaded, they are removed from service, drained and stored. After a few IX columns accumulate in storage, they are moved to a burial box. One of the burial box contains 33 columns and the other, six. The radionuclides act on the liquid left within and adhering to the beads to produce hydrogen. This report describes the generation rate, accumulation rate and significance of that accumulation. This summary also highlights those major areas of concern to the external (to Westinghouse Hanford Company [WHC]) reviewers. Appendix H presents the comments made by the external reviewers and, on a separate sheet, the responses to those comments. The concerns regarding the details of the analytical approach, are addressed in Appendix H and in the appropriate section.

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This procedure will verify that the 221-B liquid effluent monitoring system, installed near the east end of the 6-in. chemical sewer header, functions as intended by design. TK-900B was installed near stairwell 3 in the 221-B electrical gallery by Project W-007H. The system is part of BAT/AKART for the BCE liquid effluent system.

This grant was awarded to provide for the scale-up of the process of production of a (1 {r_arrow})-{beta}-D-glucan which is produced by Cellulomonas flavigena. One of the goals was to provide sufficient amounts of the polysaccharide polymer to conduct a field test of its usefulness in subterranean permeability modification procedures of enhanced oil recovery. During September and October, 1994, fermentations and recoveries were done by Abbott Laboratories, to develop a process to provide at least 400 lbs of the glucan polymer for field testing. Shake flask runs and four fermentation runs were completed. A summary of the fourth fermentation run, conducted in a 40,000 liter fermentor, follows.

This is a project that sought to improve the amorphous silicon-germanium (SiGe) thin film deposition process in the production of solar cells. To accomplish this, the electron cyclotron resonance (ECR) plasma discharge, employed for the thin film deposition, was modified. Changes in the parameters of the plasma were monitored with diagnostic techniques, similar to those used in fusion plasma studies. That was the primary contribution from ORNL. Only one phase was contained in the statement of work, with the following tasks: (1) Develop a detailed program for plasma characterization. (2) Carry-out plasma modeling and analysis to support deposition systems design. (3) Operate experimental deposition systems for the purpose of plasma characterization. (4) Analyze data. (5) Modify deposition as directed by measurements. (6) This final report, which was deemed to be the only deliverable of this small project. And while the modified ECR discharge did not show measurable improvement of the conditions relevant to the deposition process, much was learned about the plasma parameters in the process. Some ideas on alternative designs are being discuss and funding options for testing such designed are being sought.

This Acceptance Test Procedure is for the 241-SY-101 Flexible Receiver System, Phase III Testing. This procedure will test the sealing integrity of the Flexible Receiver System to ensure that release of waste and aerosols will be minimized during the removal of the test mixer pump from tank SY-101.

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Japan-U.S. relations are more uncertain and subject to greater strain today than at any time since World War II. Longstanding military allies and increasingly interdependent economic partners, Japan and the United States have worked closely together to build a strong, multifaceted relationship based on democratic values and interests in world stability and development. But Japan today is our foremost economic and technological competitor.

The purpose of this operability test procedure (OTP) is to verify the 211-BA flow proportional sampler system and components function correctly as intended by design. System test will include the sampling system, all associated instrumentation, and Facility Process Monitor and Control System (FPMCS). The combined chemical sewer stream from B Plant flows through sump 211BA-SMP-01 located in 211-BA and is continuously monitored for gamma and beta radiation and pH. 211-BA has been upgraded to include a flow proportional sampler. A specified sample volume will be withdrawn at programmed intervals from the 211BA sump and deposited in a 19 liter plastic carboy. The sampler will be programmed per the vendor installation and operations manual by B Plant instrument maintenance personnel. Samples will be taken during five consecutive sample cycles with the sample volumes and sample frequencies recorded for comparison purposes. Additional tests related to the sampler include the alarm circuitry for loss of power and failure to obtain sample.

This project specific quality assurance program plan establishes the responsibility for the implementation of QA requirements, defines and documents the QA requirements associated with design, procurement, and construction, and defines and documents the degree of QA reviews and verifications on the design and construction necessary to assure compliance to project and DOE requirements. Revision 2 updates the QAPP to provide concurrence with approved work scope deletion. In addition, the Quality Assurance Program Index is being updated to reflect the current Quality Assurance Program requirements per DOE Order 5700.6C.

In wall construction, highly conductive members spaced along the wall, which allow higher heat transfer than that through less conductive areas, are referred to as thermal bridges. Thermal bridges in walls tend to increase heat loss and, under certain adverse conditions, can cause dust streaking (``ghosting``) on interior walls over studs due to temperature differentials, as well as condensation in and on walls. Although such adverse conditions can be easily avoided by proper thermal design of wall systems, these effects have not been well understood and thermal data has been lacking. Therefore, the present study was initiated to provide (1) a better understanding of the thermal behavior of steel-framed walls, (2) a set of R-values for typical wall constructions, and (3) information that could be used to develop improved methods of predicting R-values. An improved method for estimating R-value would allow an equitable comparison of thermal performance with other construction types and materials. This would increase the number of alternative materials for walls available to designers, thus allowing them to choose the optimum choice for construction. Twenty-three wall samples were tested in a calibrated hot box (ASTM C9761) to measure the thermal performance of steel-framed wall systems. The tests included …

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The Advisory Committee on Human Radiation Experiments was created by President Clinton to advise the Human Radiation Interagency Working Group on the ethical and scientific criteria applicable to human radiation experiments carried out or sponsored by the U.S. Government. The Committee seeks to answer several fundamental question: What ethics criteria should be used to evaluate human radiation experiments? What was the Federal Government`s role in human radiation experiments? What are the criteria for determining appropriate Federal responses where wrongs or harms have occurred? What lessons learned from studying past and present research standards and practices should be applied to the future? The Committee has been gathering vast amounts of information and working to render it orderly and accessible. In the next six months, the Committee will continue with the tasks of data gathering and organizing. The focus of the work, however, will be developing criteria for judging historical and contemporary experiments, policies, and procedures, as well as criteria for remedies that may be appropriate where harms or wrongs have ocurred. Based on findings, the Committee will make specific recommendations regarding policies for the future.

A computer model of a Kearney and Tracker (K and T) Milwaukee Matic 600 (MM600) with a Gemini controller for use under the Deneb Robotics, Inc. simulation environment has been constructed. The simulation uses the K and T controller and standard MM600 machine geometry. Both the machine geometry and the controller are provided. The machine has been constructed using K and T`s standard machine dimensions and setup. The controller simulation addresses the most typically used NC codes, but may not be setup for extremely specialized functions. The machine geometry has been reduced to simulate only those components and surfaces which could possibly interfere or collide with other machine components or the workpiece envelope. The level of detail has been reduced to a functional level to enhance computational performance during simulation. The model may be directly used in the Virtual-NC environment for a complete machining simulator, or the model with kinematics may be used in IGRIP. The geometry is suitable for translation into standard file formats for importation into other systems.

This talk is about how to avoid turning swords into Superfund sites. The problem we address is the potential conflict between the desire to take advantage of the greater international security brought by the end of the Cold War by entering arms control agreements requiring various military weapons to be dismantled, and the desire to avoid further degrading the environment in the process of destroying them. We will use as an illustration of these issues the Chemical Weapons Convention (CWC), which is intended to cause the destruction of all chemical weapons in the world. First, we will provide a brief overview of the CWC, then we will focus in on its environmental provisions, and, finally, we will discuss potential conflicts with United States law and how they might be resolved.

The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality.

This analysis examines activities associated with the installation of isolation barriers in the K Basins at the Hanford Reservation. This revision adds evaluation of barrier drops on stored fuel and basin floor, identifies fuel which will be moved and addresses criticality issues with sludge. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications.

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, Oak Ridge National Laboratory, and PNL 329 Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of vapor samples from tank 241-BY-103.

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