This report documents the determination that the activities associated with the 100 K West fuel canister gas and liquid sampling are classified as Hazard Category Other (consequences are below criteria for Category 3).

The PFP operating organization requests that the limit set permitting 150 grams fissile be extended to the Hoods 4 and 5 of Room 187. The request for the limit change is explained in the attached request for analysis.

This document describes the training programs required to become a Phase 2 and Phase 3 certified engineer at PUREX during deactivation. With the change in mission, the PUREX engineering/certification training program is being revamped as discussed below. The revised program will be administered by PUREX Technical Training using existing courses and training materials. The program will comply with the requirements of the Department of Energy (DOE) order 5480.20A, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities.``

Dr. Matsch was born in Hungary and studied at Vienna Technical Institute, receiving degrees in physics and engineering. At the end of World War II, he was operating a krypton gas separation plant in Hungary, but left his home and personal effects and fled to Munich, Bavaria with his wife and infant son as the Russians entered the country. After the war he worked for a time with the German Linde Company and eventually came to the United States when an immigration quota was available for displaced Hungarian citizens. He went to work for the Linde Division of Union Carbide in an engineering capacity upon his arrival in the US, and he and his wife are now US citizens. He is currently Manager of the Engineering Development Division of the Linde Co., employing about 600 people including 200 engineers. His responsibilities include the design and construction of gas separation equipment and devices, improvement of their processes and economic analyses of the results. It was his group which developed the new improved distillation columns which have permitted extraordinary increases in through-put and efficiency in air separation plants, and which he would use in any purification system that he would design for …

This work plan provides the information necessary for drilling, sampling, and hydrologic testing of wells to be completed in support of a demonstration of the in-well vapor stripping system. The in-well vapor stripping system is a remediation technology designed to preferentially extract volatile organic compounds (VOCs) from contaminated groundwater by converting them to a vapor phase. Air-lift pumping is used to lift and aerate groundwater within the well. The volatiles escaping the aerated water are drawn off by a slight vacuum and treated at the surface while the water is allowed to infiltrate the vadose zone back to the watertable.

This report describes an analytical procedure for use in determining the heavy element content of a sample of HEU. Results of the analysis of a specific sample are discussed and some forensic signatures are identified. Two calibrated liquid samples were created, containing known amounts of HEU and contaminants. These samples were counted for gamma rays in the same way that an HEU sample would be treated, and results of the gamma counting are compared with the analytical results.

The attached Test Procedure provides detailed test steps to assure proper operation of the 244U DCRT instrumentation.

Double-Shell Tank 241-AP-105 is a radioactive waste tank most recently sampled in March of 1993. Sampling and characterization of the waste in Tank 241-AP-105 contributes toward the fulfillment of Milestone M-44-05 of the Hanford Federal Facility Agreement and Consent Order (Ecology, EPA, and DOE, 1993). Characterization is also needed tot evaluate the waste`s fitness for safe processing through an evaporator as part of an overall waste volume reduction program. Tank 241-AP-105, located in the 200 East Area AP Tank Farm, was constructed and went into service in 1986 as a dilute waste receiver tank; Tank 241AP-1 05 was considered as a candidate tank for the Grout Treatment Facility. With the cancellation of the Grout Program, the final disposal of the waste in will be as high- and low-level glass fractions. The tank has an operational capacity of 1,140,000 gallons, and currently contains 821,000 gallons of double-shell slurry feed. The waste is heterogeneous, although distinct layers do not exist. Waste has been removed periodically for processing and concentration through the 242-A Evaporator. The tank is not classified as a Watch List tank and is considered to be sound. There are no Unreviewed Safety Questions associated with Tank 241-AP-105 at this time. …

In the last quarterly report we presented results of coprocessing runs made with an Illinois No. 6 coal and an AMOCO VTR (as received) and after the heavy oil had been pretreated a number of different ways. Coal conversions and product yields were presented for each coprocessing experiment. We have now further analyzed results from coprocessing experiments in order to estimate the yields of coal-derived gas, asphaltenes and oil products. Although coal-derived products can not be measured directly from the coprocessing experiments, since coal and petroleum products are commingled, they can be estimated based on repeat reactions with the petroleum solvent alone. This technique assumes that the petroleum solvent reacts to yield the same products whether coal is present or not. When the coal was coprocessed with untreated heavy oil 58% of coal (MAF) was converted to gas and liquid products. We estimated that 7% of coal was converted to oils (n-pentane solubles), 28% to asphaltenes (n-pentane insolubles) and 24% to hydrocarbon gases, mostly methane. When the same coal was coprocessed with AMOCO oil that had been pretreated with 1000 ppM (metal concentration) of Mo naphthenate, 81% of coal was converted; this is an average of two runs. Coal-derived oil …

About 128 air samplers and CAMs presently in service to detect and document potential radioactive release from `H` and `F` area tank farm ventilation stacks are scheduled for replacement and/or upgrade by Projects S-5764, S-2081, S-3603, and S-4516. The seven CAMs scheduled to be upgraded by Project S-4516 during 1995 are expected to provide valuable experience for the three remaining projects. The attached document provides design guidance for the standardized High Level Waste air sampling system.

During 1992, a series of hydrologic characterization tests were conducted at the well 4A -- 4T test facility complex. Details concerning these tests are described in Swanson (1992). Two of the tests, a constant-rate discharge test conducted on March 30, 1992 and a slug interference test performed on April 15, 1992, are the focus of this report.

For a variety of reasons, thousands of oil and gas wells have been abandoned in the Gulf Coast Region of the United States. Many of these wells penetrated geopressured zones whose resource potential for power generation was undervalued or ignored. The U.S. Department of Energy (DOE) Geopressured-Geothermal Research Program was chartered to improve geothermal technology to the point where electricity could be commercially produced from a substantial number of geopressured resource sites. This research program focused on relatively narrow technical issues that are unique to geopressured resources such as the ability to predict reservoir production capacity based on preliminary flow tests. Three well sites were selected for the research program. These are the Willis Hulin and Gladys McCall sites in Louisiana, and the Pleasant Bayou site in Texas. The final phase of this research project consists of plug and abandonment (P&A) of the wells and site restoration.

Performance Profiles of Major Energy Producers 1992 is the sixteenth annual report of the Energy Information Administration`s (EIA) Financial Reporting System (FRS). The report examines financial and operating developments, with particular reference to the 25 major energy companies (the FRS companies) required to report annually on Form EIA-28. Financial information is reported by major lines of business, including oil and gas production, petroleum refining and marketing, and other energy operations. Domestic and international operations are examined separately in this report. The data are presented in the context of key energy market developments with a view toward identifying changing strategies of corporate development and measuring the apparent success of current ongoing operations.

This report shows photos of roof deficiencies noted during roof inspections conducted since 1992 at the Hanford Site.

During the 242-A Evaporator`s 94-1 campaign, five process samples were collected from the slurry stream for waste characterization. The five samples were collected over a 36 day time span, respectively on May 4, May 9, May 16, May 23, and June 9, 1994. Sample collections were performed per the protocol described in 242-A Evaporator Waste Analysis Plan, WHC-SD-WM-EV-060, Rev. 3 and in 242-A Evaporator Quality Assurance Project Plan, WHC-SD-WM-QAPP-009, Rev. 0. Slurry waste was characterized chemically and radiochemically by the Westinghouse Hanford Company, 222-S Laboratory as directed.

The HM Process (modified PUREX) has been used in the H-Canyon since 1959 to recover uranium and byproduct neptunium. The PUREX process has been used in the Separation facilities in F and H-Area. This report analyzes both the inhalation and ingestion radionuclide dose impact of the HM and PUREX process soluble portion of their waste streams. The spent fuel assemblies analyzed are the Mark 16B, Mar 22 for the HM process, and the Mark 31A, Mark 31B for the PUREX process. The results from this analysis are combined with an analysis of the current Safety Analysis Report SAR source term to evaluate source terms for HLW supernate. Analysis of fission yield data and SAR source term values demonstrates that a limited number of radionuclides contribute 1% or more to the total dose and that cesium and plutonium isotopes are the radionuclides with major impact in the supernate source term. This report analyses both volatile and evaporative impact as recommended by DOE guidance. In reality, the only radionuclide volatilized during evaporative conditions is tritium. No evidence of selective volatility occurs during forced evaporation in HLW. The results obtained permit reducing the list of radionuclides to be considered in the development of …

This reports the results of the load test of the 3790 building roof deck and support structure.

The purpose of this Safety Evaluation for Packaging (SEP) is to authorize the ChemNuclear CNS 1-13G packaging to ship samples of irradiated fuel elements from the 100 K East and 100 K West basins to the Postirradiation Testing Laboratory (PTL) in support of the spent nuclear fuel characterization effort. It also authorizes the return of the fuel element samples to the 100 K East facility using the same packaging. The CNS 1-13G cask has been-chosen to transport the fuel because it has a Certificate of Compliance (CoC) issued by the US Nuclear Regulatory Commission (NRC) for transporting irradiated oxide and metal fuel in commerce. It is capable of being loaded and offloaded underwater and may be shipped with water in the payload compartment.

Ditch 216-B-3-1 is located within the 200-BP-11 Operable Unit, located immediately northeast of the 200 East Area. At one time, it drained into B Pond. The ditch has been filled with soil and the surrounding area reclaimed. There is no remaining physical evidence showing the original location of the ditch. Survey stakes were recently emplaced that show the documented location of the ditch from survey coordinates. The objective of this investigation was to verify the staked location of the ditch with non-intrusive geophysical methods. Ground-penetrating radar (GPR) and electromagnetic induction (EMI) were the methods selected for the investigation. GPR has been used successfully to locate similar ditches in other parts of the Hanford Reservation. EMI was used because it is much quicker to collected and interprets, and if successful, could be used to rapidly map the entire length of the ditch. Results are discussed.

This document provides the functional design criteria for the 222-S Laboratory radioactive waste drain piping and transfer pipeline replacement. The project will replace the radioactive waste drain piping from the hot cells in 222-S to the 219-S Waste Handling Facility and provide a new waste transfer route from 219-S to the 244-S Catch Station in Tank Farms.

This monitoring plan describes the activities and methods that will be employed at the 300 Area Treated Effluent Disposal Facility (TEDF) in order to ensure compliance with the National Discharge Elimination System (NPDES) permit. Included in this document are a brief description of the project, the specifics of the sampling effort, including the physical location and frequency of sampling, the support required for sampling, and the Quality Assurance (QA) protocols to be followed in the sampling procedures.

The US Department of Energy (DOE) has directed Westinghouse Hanford Company (WHC) to develop an effective strategy to minimize the generation of hazardous, radioactive, and mixed wastes at Hanford in compliance with state and federal regulations. WHC has formalized a pollution prevention program composed of management policies, management requirements and procedures. This plan addresses pollution prevention for B Plant Complex. A pollution prevention team is in place and has been assigned responsibility for implementing the plan. This plan includes actions and goals for reducing volume and toxicity of waste generated, as well as a basis for evaluation of progress. Descriptions of waste streams, current specific goals, general pollution prevention methods, and specific accomplishments are in the appendices of this plan.

Various Hanford facilities must transfer large radioactively contaminated items to burial/storage. Presently, there are eighteen Fuel Spacer Burial Boxes (FSBBs) available on the Hanford Site for transport of such items. Previously, the FSBBS were transported from a rail car to the burial trench via a drag-off operation. To allow for the lifting of the boxes into the burial trench, it will be necessary to improve the packagings lifting attachments and provide structural reinforcement. Additional safety improvements to the packaging system will be provided by the addition of a positive closure system and package ventilation. FSBBs that are modified in such a manner are referred to as Modified Fuel Spacer Burial Boxes (MFSBs). The criteria provided by this PDC will be used to demonstrate that the transfer of the MFSB will provide an equivalent degree of safety as would be provided by a package meeting offsite transportation requirements. This fulfills the onsite transportation safety requirements implemented in WHC-CM-2-14, Hazardous Material Packaging and Shipping. A Safety Analysis Report for Packaging (SARP) will be prepared to evaluate the safety of the transfer operation. Approval of the SARP is required to authorize transfer. Criteria are also established to ensure burial requirements are met.

This report describes the regional and site specific geology of the Hanford Sites low-level burial grounds in the 200 East and West Areas. The report incorporates data from boreholes across the entire 200 Areas, integrating the geology of this area into a single framework. Geologic cross-sections, isopach maps, and structure contour maps of all major geological units from the top of the Columbia River Basalt Group to the surface are included. The physical properties and characteristics of the major suprabasalt sedimentary units also are discussed.