This analysis defines and evaluates the surface water supply system from the existing J-13 well to the North Portal. This system includes the pipe running from J-13 to a proposed Booster Pump Station at the intersection of H Road and the North Portal access road. Contained herein is an analysis of the proposed Booster Pump Station with a brief description of the system that could be installed to the South Portal and the optional shaft. The tanks that supply the water to the North Portal are sized, and the supply system to the North Portal facilities and up to Topopah Spring North Ramp is defined.

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document.

This study provides a preliminary design for a RCRA mixed waste landfill final closure cover. The cover design was developed by a senior class design team from Seattle University. The design incorporates a layered design of indigenous soils and geosynthetics in a layered system to meet final closure cover requirements for a landfill as imposed by the Washington Administrative Code WAC-173-303 implementation of the Resource Conservation and Recovery Act.

This System Design Description provides: (1) statements of the Spent Nuclear Fuel Projects (SNFP) needs requiring sampling of canister sludge in the K East and K West Basins, (2) the sampling equipment system functions and requirements, (3) a general work plan and the design logic being followed to develop the equipment, and (4) a summary description of the design for the sampling equipment.

Highly alkaline radioactive waste solutions originating from production of plutonium for military purposes are stored in underground tanks at the U.S. Department of Energy Hanford Site. The purification of alkaline solutions from neptunium and plutonium is important in the treatment and disposal of these wastes. This report describes scoping tests with sodium hydroxide solutions, where precipitation techniques were investigated to perform the separation. Hydroxides of iron (III), manganese (II), cobalt (II, III), and chromium (III); manganese (IV) oxide, and sodium uranate were investigated as carriers. The report describes the optimum conditions that were identified to precipitate these carriers homogeneously throughout the solution by reductive, hydrolytic, or catalytic decomposition of alkali-soluble precursor compounds by a technique called the Method of Appearing Reagents. The coprecipitation of pentavalent and hexavalent neptunium and plutonium was investigated for the candidate agents under optimum conditions and is described in this report along with the following results. Plutonium coprecipitated well with all tested materials except manganese (IV) oxide. Neptunium only coprecipitated well with uranate. The report presents a hypothesis to explain these behaviors. Further tests with more complex solution matrices must be performed.

The overall objective of this two phase program is to investigate the use of dry carbon-based sorbents for mercury control. This information is important to the utility industry in anticipation of pending regulations. During Phase I, a bench-scale field test device that can be configured as an electrostatic precipitator, a pulse-jet baghouse, or a reverse-gas baghouse has been designed, built and integrated with an existing pilot-scale facility at PSCo`s Comanche Station. Up to three candidate sorbents will be injected into the flue gas stream upstream of the test device to and mercury concentration measurements will be made to determine the mercury removal efficiency for each sorbent. During the Phase II effort, component integration for the most promising dry sorbent technology shall be tested at the 5000 acfm pilot-scale.

This Systems Engineering Management Plan (SEMP) describes the Tank Waste Remediation Systems (TWRS) implementation of U.S. Department of Energy (DOE) Systems Engineering (SE) policy provided in Tank Waste Remediation System Systems Engineering Management Policy, DOE/RL letter, 95-RTI-107, Oct. 31, 1995. This SEMP defines the products, process, organization, and procedures used by the TWRS Program to accomplish SE objectives. This TWRS SEMP is applicable to all aspects of the TWRS Program and will be used as the basis for tailoring SE to apply necessary concepts and principles to develop and mature the processes and physical systems necessary to achieve the desired end states of the program.

The mission of the B Plant Transition Project is to place B Plant and its ancillary facilities (refeffed to as B Plant throughout this document) in a safe and stable condition which requires minimal long term surveillance and maintenance (S&M), thereby reducing the risks associated with the current radiological and chemical inventory and the costs for S&M until disposition. Transition may include activities such as removal of stored radioactive and hazardous materials, safe shutdown of support systems such as electrical circuits and ventilation, and installation of new or modified systems required to support S&M for a 10 year period. The goal of this Project is to complete B Plant transition activities by September 30, 1998. During transition, the Waste Encapsulation and Storage Facility will be isolated from B Plant for stand alone operation. Upon completion of transition, B Plant will be turned over to the Office of Environmental Restoration (EM-40) for the S&M phase of B Plant decommissioning.

A set of tank-by-tank waste inventories is derived from historical waste models, flowsheet records, and analytical data to support the Tank Waste Remediation System flowsheet and retrieval sequence studies. Enabling assumptions and methodologies used to develop the inventories are discussed. These provisional inventories conform to previously established baseline inventories and are meant to serve as an interim basis until standardized inventory estimates are made available.

This report documents the conceptual design of the Hot Conditioning System Equipment. The Hot conditioning System will consist of two separate designs: the Hot Conditioning System Equipment; and the Hot Conditioning System Annex. The Hot Conditioning System Equipment Design includes the equipment such as ovens, vacuum pumps, inert gas delivery systems, etc.necessary to condition spent nuclear fuel currently in storage in the K Basins of the Hanford Site. The Hot Conditioning System Annex consists of the facility of house the Hot Conditioning System. The Hot Conditioning System will be housed in an annex to the Canister Storage Building. The Hot Conditioning System will consist of pits in the floor which contain ovens in which the spent nuclear will be conditioned prior to interim storage.

Acceptance test report for Cathodic Protection - Addition of 6 Anodes to existing Rectifier 31 for Project W-320

This document is an executive summary of the testing, adjusting and balancing completed for Project W-112 for the HVAC systems. The actual results are document in the Acceptance Test Report.

This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging.

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

This CRADA supports the objective of demonstrating feasibility and minimizing manufacturing costs associated with the use of ceramic components in a heavy duty diesel engine manufactured by Detroit Diesel Corporation (DDC). Studies were conducted to evaluate existing, known data for ceramic material, and to identify additional data needed to better characterize a valve of ceramic composition. Tests were conducted to provide important information required for redesign of existing metal valves and other engine head components. A vendor was selected by DDC to produce the valve shapes for testing and Lockheed Martin Energy Systems (LMES) provided design modeling/analysis support. The effort also included the development of a bench-test apparatus to simulate the environment of a valve in operation that provided material data and confirmation of analytical results.

This document addressed technical issues regarding the manufacturing processes involved in making plutonium pits. It addresses acceptable approaches from a technical standpoint as to how the manufacturing processes can be separated and distributed among different manufacturing sites. Site selections, costs, and intra-site transfers are not addressed in this document.

The Nevada Test Site became the nation`s continental nuclear weapons test site on January 11, 1951. Over the years, the Nevada Operations Office (Nevada) built an extensive infrastructure to support and conduct nuclear tests at the site and in Las Vegas. Roads, housing, test towers, electrical systems, and water systems are just a few of the construction projects that have been required by the Site`s nuclear testing mission. Nuclear testing continued through 1992. A presidential decision directive issued in October that year stopped testing but required Nevada to conduct and experimental program and maintain a readiness posture to resume nuclear testing within 6 months through fiscal year 1995. The directive further required that, beginning with fiscal year 1996, Nevada maintain a 2-3 year readiness posture. This change in Nevada`s mission coupled with Department downsizing requires that only cost effective projects with defined mission needs be undertaken. Although Nevada has changed and rescoped some construction projects in response to the changing Test Site mission, there are two projects, one underway and one planned, that contain unneeded overlap of capability. Specifically, the audit identified two electrical system projects that provided unnecessary duplicate capability at a cost of about $1.35 million. Management concurred …

This document provides the strength required for the energy absorption cylinder needed to prevent puncture through the AZ-101 tank resulting from a 59-ft drop of the W-151 mixer pump.

The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document.

Microbiologically influenced corrosion (MIC) is a serious concern when considering measures to guard against long-term corrosion of waste package containers at Yucca Mountain. An experimental program has been initiated to gain a better fundamental understanding of MIC in repository environments. Some engineering objectives will be achieved during the investigation: a reproducible apparatus and procedure for electrochemical monitoring of MIC will be developed; the most aggressive combinations of bacteria will be determined, and the MIC resistance of various candidate alloys for the multipurpose container (MPC) will be measured.

The diffusion equation, {phi}({rvec x}), is solved by finding the extrema of the functional, {Gamma}[{phi}] = {integral}({1/2}D{rvec {nabla}}{phi}{center_dot}{rvec {nabla}}{phi} + {1/2}{sigma}{sub a}{phi}{sup 2} - {ital Q}{phi}){ital d}{sup 3}{ital x}. A matrix is derived that is investigated for hexahedron, wedge, tetrahedron, and pyramid cells. The first term of the diffusion integration was concentrated and the others dropped; these dropped terms are also considered. Results are presented for hexahedral meshes and three weighting methods.

This document provides functions and endpoint criteria to be used for transition of the Single-Shell Tank Farms to the Controlled, Clean and Stable endstate.

A basic question was asked concerning the drill string which is used in rotary Mode coring operations: ``...what is the volume leak rate loss in a drill rod string under varying condiditons of the joint boxes and pins being either dry or coated with lubricant...``. A Variation of this was to either have an o-ring installed or absent on the drill rod that was grooved on the pin. A series of tests were run with both the o-ring grooved Longyear drill rod and the plain pin end rod manufactured by Diamond Drill. Test results show that drill rod leakage of both types is lowered dramatically when thread lubricant is applied to the threaded joints and the joints made up tight. The Diamond Drill rod with no o-ring groove has virtually no leakage when used with thread lubricant and the joints are properly tightened.

Characterizing, handling, and storing tritiated waste is challenging because of the physical and chemical properties of tritium. Tritium is soluble in many materials, including structural materials such as, stainless steel, structural steel, polymers, concrete and paints. Tritium permeates rapidly into these materials compared to other species, and so parts exposed to tritium are normally contaminated to some degree throughout the bulk. The relatively low kinetic energy of the {beta}-decay causes detecting tritium anywhere but very near the surface of materials to be impossible, because the {beta}-particle is absorbed by the material. Tritium readily exchanges with hydrogen in water vapor, and the resulting tritiated water can permeate polymers, concrete, oil, and the oxide surface films normally present on metals. Most of the tritium contamination in structural metals resides in the surface oxide film and in organic films at the surface, when metals are exposed to tritium at ambient temperature and pressure, whether the exposure is to gas or tritiated water. The most reliable method of assaying tritium is to dissolve samples in a proper liquid scintillant and use {beta}-scintillation counting. Other methods that require less time or are non-destructive (such as smear/counting) are significantly less reliable, but they can be used …