National Pollutant Discharge Elimination System (NPDES) Permit TN0002968, issued April 28, 1995, requires that the Y-12 Plant Radiological Monitoring Plan for surface water be modified (Part 111-H). These modifications shall consist of expanding the plan to include storm water monitoring and an assessment of alpha, beta, and gamma emitters. In addition, a meeting was held with personnel from the Tennessee Department of Environment and Conservation (TDEC) on May 4, 1995. In this meeting, TDEC personnel provided guidance to Y-12 Plant personnel in regard to the contents of the modified plan. This report contains a revised plan incorporating the permit requirements and guidance provided by TDEC personnel. In addition, modifications were made to address future requirements of the new regulation for radiation protection of the public and the environment in regards to surface water monitoring.

Automatic control of fine coal cleaning circuits has traditionally been limited by the lack of sensors for on-line ash analysis. Although several nuclear-based analyzers are available, none have seen widespread acceptance. This is largely due to the fact that nuclear sensors are expensive and tend to be influenced by changes in seam type and pyrite content Recently, researchers at VPI&SU have developed an optical sensor for phosphate analysis. The sensor uses image processing technology to analyze video images of phosphate ore. It is currently being used by Texas gulf for off-line analysis of dry flotation concentrates. The primary advantages of optical sensors over nuclear sensors are that they are significantly cheaper, are not subject to measurement variations due to changes in high atomic number minerals, are inherently safer and require no special radiation permitting. The purpose of this work is to apply the knowledge gained in the development of an optical phosphate analyzer to the development of an on-line ash analyzer for fine coal slurries. During the past quarter, a new prototype sample presentation system for the optical analyzer has been developed. This new approach appears to solve the problems encountered with previous prototypes. A qualitative comparison of the images …

Navigation systems have been vital to transportation ever since man took to the air and sea. Early navigation systems utilized the sextant to navigate by starlight as well as the magnetic needle compass. As electronics and communication technologies improved, inertial navigation systems were developed for use in ships and missile delivery. These systems consisted of electronic compasses, gyro-compasses, accelerometers, and various other sensors. Recently, systems such as LORAN and the Global Positioning System (GPS) have utilized the properties of radio wave propagation to triangulate position. The Local Positioning System (LPS), described in this paper, is an implementation of a limited inertial navigation system designed to be used on a bicycle. LPS displays a cyclist`s current position relative to a starting location. This information is displayed in Cartesian-like coordinates. To accomplish this, LPS relies upon two sensors, an electronic compass sensor and a distance sensor. The compass sensor provides directional information while the distance sensor provides the distance traveled. This information yields a distance vector for each point in time which when summed produces the cyclist`s current position. LPS is microprocessor controlled and is designed for a range of less than 90 miles.

While substantial work has been performed in the Russian MPC&A Program, much more needs to be done at Russian nuclear facilities to complete four necessary steps. These are (1) periodically measuring the physical inventory of nuclear material, (2) continuously measuring the flows of nuclear material, (3) using the results to close the material balance, particularly at bulk processing facilities, and (4) statistically evaluating any apparent loss of nuclear material. The periodic closing of material balances provides an objective test of the facility's system of nuclear material protection, control and accounting. The statistical evaluation using the uncertainties associated with individual measurement systems involved in the calculation of the material balance provides a fair standard for concluding whether the apparent loss of nuclear material means a diversion or whether the facility's accounting system needs improvement. In particular, if unattractive flow material at a facility is not measured well, the accounting system cannot readily detect the loss of attractive material if the latter substantially derives from the former.

The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk form, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing, and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; Information about measurement methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological and instrumentation support of accounting measurements for all types of materials were formulated. The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear and radiation safety control. Requirements for these applications are lower than requirements for MC and A applications. To improve the state of MC and A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials.

The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan and the US Department of Energy (DOE) are cooperating on the development of a remote monitoring system for nuclear nonproliferation efforts. This cooperation is part of a broader safeguards agreement between PNC and DOE. A remote monitoring system is being installed in a spent fuel storage area at PNC`s experimental reactor facility Joyo in Oarai. The system has been designed by Sandia National Laboratories (SNL) and is closely related to those used in other SNL remote monitoring projects. The Joyo project will particularly study the unique aspects of remote monitoring in contribution to nuclear nonproliferation. The project will also test and evaluate the fundamental design and implementation of the remote monitoring system in its application to regional and international safeguards efficiency. This paper will present a short history of the cooperation, the details of the monitoring system and a general schedule of activities.

This document defines functional requirements for portable exhausters used to ventilate primary tanks during saltwell pumping, and provide back-up to primary and annulus ventilation systems at C-106 and AY-102.

This document is the final report deliverable for tank 241-A- 101 grab samples. Three grab samples (IA-96-1, IA-96-2 and IA-96-3) were taken from riser 4 of tank 241-A-101. Samples were collected on April 3, 1996 and received by the 222-S Laboratory on April 4, 1996. Analyses were performed in accordance with the Compatibility Grab Sampling and Analysis Plan (TSAP) and the Data Quality Objectives for Tank Farms Waste Compatibility Program (DQO). The samples were subsampled and analyzed in accordance with the TSAP. Two of the three grab samples contained a significant amount of solids and special analyses were requested. None of the samples exceeded notification limits. No similarities in sample appearance were noted; this could be an explanation for the varying analytical results. Quality control issues are discussed in each analytical subheading. The raw data for all analyses are included in this report.

On May 14, 1997, at 7:53 p.m. (PDT), a chemical explosion occur-red in Tank A- 109 in Room 40 of the Plutonium Reclamation Facility (Facility) located in the 200 West Area of the Hanford Site, approximately 30 miles north of Richland, Washington. The inactive processing Facility is part of the Plutonium Finishing Plant (PFP). On May 16, 1997, Lloyd L. Piper, Deputy Manager, acting for John D. Wagoner, Manager, U.S. Department of Energy (DOE), Richland Operations Office (RL), formally established an Accident Investigation Board (Board) to investigate the explosion in accordance with DOE Order 225. 1, Accident Investigations. The Board commenced its investigation on May 15, 1997, completed the investigation on July 2, 1997, and submitted its findings to the RL Manager on July 26, 1997. The scope of the Board`s investigation was to review and analyze the circumstances of the events that led to the explosion; to analyze facts and to determine the causes of the accident; and to develop conclusions and judgments of need that may help prevent a recurrence of the accident. The scope also included the application of lessons learned from similar accidents within DOE. In addition to this detailed report, a companion document has also …

This document summarizes the test result information for the Data Management System (DMS). Appendix A contains test result information for all Functional Test cases and Appendix B contains the results for all the Performance Test cases.

This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable. The objectives of this calculation are (1) To perform static and Safety Class 2 dynamic stress analysis of the Slurry and Supernate Process (inner) piping connecting Tanks 241-C-106 and 241-AY-102 in order to be in compliance with the Code requirements; (2) To assure the thermal expansion of the process pipe not be strained by the outer encasement pipe; and (3) To furnish process pipe support to the Civil Engineering group.

Project W-320 has installed the Waste Retrieval Sluicing System at the 200 East Area on the Hanford Site to retrieve the sludge from single-shell tank 241-C-106 and transfer it into double-shell tank 241-AY-102. Operation of the WRSS process will resolve the high-heat safety issue for tank 241-C-106 and demonstrate a technology for the retrieval of single-shell tank wastes. This process control plan coordinates the technical operating requirements (primarily mass transfer, temperature, and flammable gas) for the sluicing operation and provides overall technical guidance for the retrieval activity.

A series of CuMgCeO{sub x} catalysts have been prepared by coprecipitating the corresponding metal nitrates with a mixed solution of potassium carbonate and potassium hydroxide. Kinetic studies of methanol and ethanol coupling reactions on K-Cu/MgO/CeO{sub 2} and MgO/CeO{sub 2} catalysts indicate that Cu enhances the rates of alcohol dehydrogenation. The cross-coupling reactions of acetaldehyde and {sup 13}C-labeled methanol produce singly-labeled propionaldehyde, suggesting that it forms by the condensation of acetaldehyde and a reactive intermediate derived from methanol. Isobutyraldehyde, a precursor to isobutanol, forms via the condensation of propionaldehyde and a reactive C{sub 1} intermediate resulting from methanol. CO{sub 2}, one of the reaction products, poisons both basic and metal sites on Ce-containing CuMgO{sub x} catalysts, resulting in decreases in the rates of both alcohol dehydrogenation (Cu sites) and chain-growth condensation reactions (basic sites). CO{sub 2} inhibits ethanol dehydrogenation on both low-Cu and high-Cu CuMgCeO{sub x} catalysts; however, CO{sub 2} has no effect on the activity of low-Cu Ce-free Cu-MgO{sub x} catalysts, suggesting that the Cu on CuMgCeO{sub x} catalysts is more likely to be oxidized by CO{sub 2} to Cu{sup +} species that can be subsequently stabilized by CeO{sub 2}. CO{sub 2} effects on high-pressure isobutanol synthesis from CO/H{sub 2} …

This plan details the sequence of activities and identifies the organizational roles and responsibilities to ensure a safe startup of the Waste Retrieval Sluicing System (WRSS). This start up plan identifies the activities which must be performed during the initial startup as well as the document which directs each step. This startup plan does not authorize or direct any specific field activities or authorize a change of configuration. As such, this plan does not require a USQ screening.

Acoustic Resonance Spectroscopy (ARS) is a nondestructive evaluation technology developed at the Los Alamos National Laboratory. The ARS technique is a fast, safe, and nonintrusive technique that is particularly useful when a large number of objects need to be tested. Any physical object, whether solid, hollow, or fluid filled, has many modes of vibration. These modes of vibration, commonly referred to as the natural resonant modes or resonant frequencies, are determined by the object`s shape, size, and physical properties, such as elastic moduli, speed of sound, and density. If the object is mechanically excited at frequencies corresponding to its characteristic natural vibrational modes, a resonance effect can be observed when small excitation energies produce large amplitude vibrations in the object. At other excitation frequencies, i.e., vibrational response of the object is minimal.

This document provides verification that the safety related commitments specified in HNF-SD-WM-810-001, Addendum 1 for the Waste Retrieval Sluicing System, Project W-320 and Project W-320 Safety Evaluation Report (SER), have been implemented in the project hardware, procedures and administrative controls. Four appendices include matrices which show where the 810 commitments are implemented for limiting conditions of operation and surveillance requirements controls, administrative controls, defense-in-depth controls and controls discussed in 810 Addendum 1. A fifth appendix includes the implementation of Project W-320 SER issues and provisions.

This Verification and Validation (V/V) interim report summarizes to date the results of the V/V tasks performed in each of the following life cycle phases: concept, requirements, design, implementation, test, installation and checkout, and operation and maintenance. At the end of the installation and checkout phase, the V/V final report will be issued. This interim report contains or references the following for each phase: Description of V/V tasks performed; Summary of task results; Summary of anomalies and resolution; Assessment of system quality; Recommendations.

The principal objective of the Central Vacuum Unit (CVU) CO{sub 2} Huff-n-Puff (H-n-P) project is to determine the feasibility and practicality of the technology in a waterflooded shallow shelf carbonate environment. The results of parametric simulation of the CO{sub 2} H-n-P process, coupled with the CVU reservoir characterization components will determine if this process is technically and economically feasible for field implementation. The technology transfer objective of the project is to disseminate the knowledge gained through an innovative plan in support of the Department of Energy`s (DOE) objective of increasing domestic oil production and deferring the abandonment of shallow shelf carbonate (SSC) reservoirs. Tasks associated with this objective are carried out in what is considered a timely effort for near-term goals.

This document is to identify the Project W-320 1000 CFM portable exhauster documentation required to be turned over from the Projects Organization to the Tank Farm Operations as part of the acceptance of the 1000 CFM portable exhausters for beneficial use.

The objective of the 94 DOE Chemical Vapor Composites (CVC) ceramics materials grant is to develop a reliable and flexible process to produce, in a single step, ceramic composites to final shape. This report is a brief summary of activities in the development of the CVC ceramics materials. Equipment has been designed and built to fabricate CVC silicon carbides with fibers such as Nextel, Nicalon, and carbon. Materials and shapes have been fabricated and characterized as to physical and mechanical properties and microstructure. Details will be given in the final report.

This document provides storage requirements for 1,000 CFM portable exhausters POR-O07/Skid E and POR-008/Skid F. These requirements are presented in three parts: preparation for storage, storage maintenance and testing, and retrieval from storage. The exhauster component identification numbers listed in this document contain the prefix POR-007 or POR-008 depending on which exhauster is being used.

This supporting document has been prepared to make the FDNW calculations for Project W-320 readily retrievable.

Goal is engineering development of two advanced physical fine coal cleaning processes, column flotation and selective agglomeration, for premium fuel applications. Scope includes laboratory research and bench-scale testing on 6 coals to optimize these processes, followed by design/construction/operation of a 2-t/hr PDU. During this quarter, parametric testing of the 30-in. Microcel{trademark} flotation column at the Lady Dunn plant was completed and clean coal samples submitted for briquetting. A study of a novel hydrophobic dewatering process continued at Virginia Tech. Benefits of slurry PSD (particle size distribution) modification and pH adjustment were evaluated for the Taggart and Hiawatha coals; they were found to be small. Agglomeration bench-scale test results were positive, meeting product ash specifications. PDU Flotation Module operations continued; work was performed with Taggart coal to determine scaleup similitude between the 12-in. and 6-ft Microcel{trademark} columns. Construction of the PDU selective agglomeration module continued.

This document provides verification that the methodology for the safe retrieval of high-heat waste from Tank 241-C-106 as specified in the WRSS Process Control Plan HNF-SD-PCP-013, Revision 1, has been adequately implemented into the Tank Waste Remediation System (TWRS) operational procedures. Tank 241-C-106 is listed on the High Heat Load Watch List.