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. It consistently runs the largest annual international trade surplus with the U.S. ($59 billion in 1993). The end of the Cold War, lackluster international economic conditions, and the focus on economic issues in U.S. politics have raised new questions about the appropriate U.S. policy toward this Asian ally.

This document presents the details of the implementation of the Site Treatment Plan developed by Ames Laboratory in compliance with the Federal Facilities Compliance Act. Topics discussed in this document include: implementation of the plan; milestones; annual updates to the plan; inclusion of new waste streams; modifications of the plan; funding considerations; low-level mixed waste treatment plan and schedules; and TRU mixed waste streams.

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

This report summarizes the results of the off-line testing the Integrated DWPF Melter System (IDMS) ammonia scrubbers using ammonia supplied from cylinders. Three additional tests with ammonia are planned to verify the data collected during off-line testing. Operation of the ammonia scrubber during IDMS SRAT and SME processing will be completed during the next IDMS run. The Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) scrubbers were successful in removing ammonia from the vapor stream to achieve ammonia vapor concentrations far below the 10 ppM vapor exit design basis. In most of the tests, the ammonia concentration in the vapor exit was lower than the detection limit of the analyzers so results are generally reported as <0.05 parts per million (ppM). During SRAT scrubber testing, the ammonia concentration was no higher than 2 ppM and during SME testing the ammonia concentration was no higher than 0.05 m.

An archaeological evaluation survey report for the proposed site of the Municipal Golf Course in Plano, Texas to determine whether any cultural resource were present in the area.

The mixed phase of a substance undergoing a first order phase transition has entirely different behavior according as the substance has more than one conserved charge or only one, as in the text book examples. In the latter case the pressure and nature of the phases are constants throughout the coexistence phase. For systems with more than one conserved charge (or independent component) we prove two theorems: (1) The pressure and the nature of the phases in equilibrium change continuously as the proportion of the phases varies from one pure phase to the other. (2) If one of the conserved charges is the Coulomb force, an intermediate-range order will be created by the competition between Coulomb and surface interface energy. Their sum is minimized when the coexistence phase assumes a Coulomb lattice of one phase immersed in the other. The geometry will vary continuously as the proportion of phases. We illustrate the theorems for a simple description of the hadron to quark phase transition in neutron stars and find a crystalline phase many kilometers thick. However the theorems are general and pertain to chemical mixtures, nuclear systems, either static as in stars or dynamic as in collisions, and have possible …

SRS initiated two parallel efforts to address aspects of Recommendation 90-2. An Order Compliance Program was established with initial focus on compliance with requirements contained in Environment, Safety, and Health (ES&H) related DOE Orders, both from a programmatic perspective as well as from a field adherence perspective; and a Standards/Requirements Identification Document (S/RID) development program was established to specify a ``necessary and sufficient`` set of ES&H requirements to protect the environment and public/worker safety and health. During the period while the S/RID methodology was being developed, many of the DOE ES&H Orders were revised and substantially improved. These improvements captured many of the insights gained in the developing S/RID program. As the SRS Order Compliance and S/RID programs matured and achieved major deliverables in 1993 and 1994, major overlaps between the two programs were identified. In early 1994, WSRC and DOE-SR determined that the two separate programs should be physically and organizationally integrated (and further merged with newly identified needs associated with Price-Anderson Amendments Act nuclear safety regulations) to become a single SRS Compliance Program. This document defines the program for integration of the WSRC Order Compliance, S/RID, and Price-Anderson Compliance activities. This plan supersedes the SRS ES&H Standards Compliance …

The majority of the spent fuel from the N Reactor and the single pass reactors (SPR) is presently being stored at the basins in the 100 K Area. Characterization of these fuels is essential to formulate a safe and efficient processing/disposal method for the spent fuel. Consequently, it is necessary to transport a cross section of spent fuel from the K Basins to the hot cells at the 327 Building in the 300 Area for analysis. The CNS 1-13G cask, a US Nuclear Regulatory Commission (NRC) certified cask manufactured by the ChemNuclear company, will be utilized for the transportation for irradiated fuel elements from the K Basins to the 327 Laboratories for characterization. The cask will utilize an inner container to compensate for the possibility of failed fuel cladding and to reduce the chances of contaminating the cask or the off loading facility. The Packaging Design Criteria (PDC) for these shipments establishes the acceptance criteria for the cask and for the design of an inner container that will be used in the Safety Evaluation for Packaging (SEP).

The preparation for decontamination and decommissioning (transition) of the 309 Building is projected to be completed by the end of the fiscal year (FY) 1998. The major stabilization and decontamination efforts include the Plutonium Recycle Test Reactor (PRTR), fuel storage and transfer pits, Transfer Waste (TW) tanks and the Ion Exchange Vaults. In addition to stabilizing contaminated areas, equipment, components, records, waste products, etc., will be dispositioned. All nonessential systems, i.e., heating, ventilation, and air conditioning (HVAC), electrical, monitoring, fluids, etc., will be shut down and drained/de-energized. This will allow securing of the process, laboratory, and office areas of the facility. After that, the facility will be operated at a level commensurate with its surveillance needs while awaiting D&D. The implementation costs for FY 1995 through FY 1998 for the transition activities are estimated to be $1,070K, $2,115K, $2,939K, and $4,762K, respectively. Costs include an assumed company overhead of 20% and a 30% out year contingency.

SAES metal getter material St 198 was chosen for glovebox stripper tests to evaluate its effectiveness of removing tritium from a nitrogen atmosphere. The St 198 material is unique from a number of other metal hydride-based getter materials in that it is relatively inert to nitrogen and can thus be used in nitrogen glovebox atmospheres. Six tritium stripper experiments which mock-up the use of a SAES St 198 stripper bed for a full-scale (10,500 liter) nitrogen glovebox have been completed. Experiments consisted of a release of small quantity of protium/deuterium spiked with tritium which were scaled to simulate tritium releases of 0.1 g., 1.0 g., and 10 g. into the glovebox. The tritium spike allows detection using tritium ion chambers. The St 198 stripper system produced a reduction in tritium activity of approximately two orders of magnitude in 24 hours (6--8 atmosphere turn-overs) of stripper operation.

This technical Evaluation of Equipment Maintenance (TEEM) is provided principally to document vendor suggested maintenance requirements and deviations from vendor suggested requirements, and provide documentation to support preventive maintenance procedures. As additional maintenance activities are identified, they will be documented in later revisions. The report describes daily or before use checks, weekly checks, semi-annual checks, and 5-year check procedures.

The purpose of this 291Z stack analysis is to determine the structural effects of chipping additional holes into the stacks concrete walls. The proposed holes are for new environmental monitoring sample probes to be installed at three different elevations. The approximate elevations proposed at this time are 50 ft, 135 ft and 175 ft. There will be four holes required at each of the elevations to support two sample probes extending across the diameter of the stack. A structural sensitivity study has been completed to assess the effect of the proposed holes on the baseline seismic qualification of the stack completed by URS/John A. Blume & Associates, Engineers, San Francisco, California (URS/Blume) in August, 1988. Results of the sensitivity study indicate that the stack would still have adequate structural moment capacity if the new holes were drilled cutting the vertical strength reinforcing steel, or if existing penetrations added since original construction have inadvertently cut vertical rebars. For current and future modifications, no vertical rebar should be cut. A limited number of horizontal rebar, no more than 2, may be cut at the new hole locations without significantly influencing the stack structural shear capacity. New penetrations in the 291Z stack should …

The 241-U-701 compressed air system supplies instrument quality compressed air to Tank Farm 241-U. The supply piping to the 241-U Tank Farm is not included in the modification. Modifications to the 241-U-701 compressed air system include installation of a 15 HP Reciprocating Air Compressor, Ingersoll-Rand Model 10T3NLM-E15; an air dryer, Hankinson, Model DH-45; and miscellaneous system equipment and piping (valves, filters, etc.) to meet the design. A newly installed heat pump allows the compressor to operate within an enclosed relatively dust free atmosphere and keeps the compressor room within a standard acceptable temperature range, which makes possible efficient compressor operation, reduces maintenance, and maximizes compressor operating life. This document is an Operability Test Procedure (OTP) which will further verify (in addition to the Acceptance Test Procedure) that the 241-U-701 compressed air system and heat pump operate within their intended design parameters. The activities defined in this OTP will be performed to ensure the performance of the new compressed air system will be adequate, reliable and efficient. Completion of this OTP and sign off of the OTP Acceptance of Test Results is necessary for turnover of the compressed air system from Engineering to Operations.

The initial GC/MS calibration and continuing calibration met all protocols. The calibration working standard is made from 9 separate mixes. One of the mixes (Restek semivolatile mix 3) was doubled, increasing the calibration concentration curve by a factor of two. None of the compounds of interest were affected, and all of the forms have been adjusted. All mass spectral tuning requirements were met for all standards and samples. Internal standard criteria were met for field blank R5306. Perylene-d12 was out on the low side. This sample was reanalyzed and all internal standard criteria were met. The R5302rerr was reported instead of R5302re (the original run of the re-extract) because R5302re failed its internal standard criteria. RSBLK03rr was reported instead of RSBLK03 (the original run of the method blank) because RSBLK03 failed its internal standard criteria. Internal standard criteria for all other samples in this package were met.

The purpose of this paper is to document the relocation of 105 KE basin seal conveyor that has been designed to account for normal static loading and to show that a 3 over 1 safety analysis was performed. The seal conveyor relocation is per work plan WHC-SD-SNF-WP-002, Revision 0. Calculations performed are attached in the appendices as the basis for the analysis.

First part of an annual report of the Texas Railroad Commission's Oil and Gas Division providing background on the industry and the agency's activities, information related to the production of oil and gas, and data regarding production by field.

Newsletter focusing on pecan disease and pest control in Texas, including prevention, identification, treatment, and educational opportunities.