The following major pieces of work were completed under the sponsorship of this grant: (1) singular perturbation theory for dynamical systems; (2) homoclinic orbits and chaotic dynamics in second-harmonic generating, optically pumped, passive optical cavities; (3) chaotic dynamics in short ring-laser cavities; (4) homoclinic orbits in moderately-long ring-laser cavities; (5) finite-dimensional attractor in ring-laser cavities; (6) turbulent dynamics in long ring-laser cavities; (7) bifurcations in a model for a free-boundary problem for the heat equation; (8) weakly nonlinear dynamics of interface propagation; (9) slowly periodically forced planar Hamiltonian systems; and (10) soliton spectrum of the solutions of the nonlinear Schroedinger equation. A brief summary of the research is given for each project.

This plan describes the configuration management for the Light Duty Utility Arm robotic manipulation arm control software. It identifies the requirement, associated documents, and the software control methodology. The Light Duty Utility Ann (LDUA) System is a multi-axis robotic manipulator arm and deployment vehicle, used to perform surveillance and characterization operations in support of remediation of defense nuclear wastes currently stored in the Hanford Underground Storage Tanks (USTs) through the available 30.5 cm (12 in.) risers. This plan describes the configuration management of the LDUA software.

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

This Source Guide will assist those working with the National Environmental Policy Act (NEPA) of 1969 to become more familiar with the environmental assessments (EA) and environmental impact statements (EIS) that apply to specific activities and facilities on the Hanford Site. This document should help answer questions concerning NEPA coverage, history, processes, and the status of many of the buildings and units on and related to the Hanford Site. This document summarizes relevant EAs and EISs by briefly outlining the proposed action of each document and the decision made by the US Department of Energy (DOE) or its predecessor agencies, the US Atomic Energy Commission (AEC) and the US Energy Research and Development Administration (ERDA). The summary includes the proposed action alternatives and current status of the proposed action. If a decision officially was stated by the DOE, as in a finding of no significant impact (FONSI) or a record of decision (ROD), and the decision was located, a summary is provided. Not all federal decisions, such as FONSIs and RODS, can be found in the Federal Register (FR). For example, although significant large-action FONSIs can be found in the FR, some low-interest FONSIs might have been published elsewhere (i.e., …

An overall systems approach has been applied to develop action plans to support the retrieval and immobilization waste disposal mission. The review concluded that the systems and infrastructure required to support the mission are known. Required systems are either in place or plans have been developed. An analysis of the programmatic, management and technical activities necessary to declare Readiness to Proceed with execution of the mission demonstrates that the system, people, and hardware will be on line and ready to support the private contractors. The systems approach included defining the retrieval and immobilized waste disposal mission requirements and evaluating the readiness of the TWRS contractor to supply waste feed to the private contractors in June 2002. The Phase 1 feed delivery requirements from the Private Contractor Request for Proposals were reviewed, transfer piping routes were mapped on it, existing systems were evaluated, and upgrade requirements were defined. Technical Basis Reviews were completed to define work scope in greater detail, cost estimates and associated year by year financial analyses were completed. Personnel training, qualifications, management systems and procedures were reviewed and shown to be in place and ready to support the Phase 1B mission. Key assumptions and risks that could negatively …

This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

This Quality Assurance Program plan (QAPP) describes how the Fuel Supply Shutdown (FSS) project organization implements the quality assurance requirements of HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) and the B and W Hanford Company Quality Assurance Program Plan (QAPP), FSP-MP-004. The QAPP applies to facility structures, systems, and components and to activities (e.g., design, procurement, testing, operations, maintenance, etc.) that could affect structures, systems, and components. This QAPP also provides a roadmap of applicable Project Hanford Policies and Procedures (PHPP) which may be utilized by the FSS project organization to implement the requirements of this QAPP.

On February 11, 1998, the AY-1 02, Riser 15E ENRAF Densitometer was acceptance tested per HNF-SD-WM-ATP-077. The test was performed at the Department of Energy`s Hanford Site, 200 East Area, building MO-407. The test validated the functionality of the Densitometer for use by project W-320, C-1 06 Retrieval. The purpose of the test procedure was to verify the functionality of the ENRAF Series 854 ATG densitometer. Typically, all ENRAF Series 854 ATGs are acceptance tested before transport to the field. The ATP, as performed for level gauges, sets default program values within the gauge and verifies the gauge`s force transducer calibration.

This document describes the formal documentation for maintaining the control system associated with the 1,000 CFM portable exhauster`s. The objective of the software configuration control plan is to provide assurances that the portable exhauster`s control system will be operable for the duration of 241-C-106 and 241-AY-102 operations (project 320). The design was based upon the criteria documented in the portable exhauster functional design criteria (HNF-SD-WM-DB-035) and procurement specification (HNF-S-0490) for the exhauster interlock systems.

The high heat content solids contained in Tank 241-C-106 are to be removed and transferred to Tank 241-AY-102 by sluicing operations, to be authorized under project W320. While sluicing operations are underway, the state of these tanks will be transformed from unagitated to agitated. This means that the partition fraction which describes the aerosol content of the head space will increase from IE-10 to IE-8 (see WHC-SD-WM-CN062, Rev. 2 for discussion of partition fractions). The head spare will become much more loaded with suspended material. Furthermore, the nature of this suspended material can change significantly: sluicing could bring up radioactive solids which normally would lay under many meters of liquid supernate. It is assumed that the headspace and filter aerosols in Tank 241-AY-102 are a 90/10 liquid/solid split. It is further assumed that the sluicing line, the headspace in Tank 241-C-106, and the filters on Tank 241-C-106 contain aerosols which are a 67/33 liquid/solid split. The bases of these assumptions are discussed in Section 3.0. These waste compositions (referred to as mitigated compositions) were used in Attachments 1 through 4 to calculate survey meter exposure rates per liter of inventory in the various system components. Three accident scenarios are evaluated: …

Fluor Daniel Hanford, Inc. (FDH) is currently adopting streamlined business processes through integrated software solutions. Replacing the legacy software (current/replacement systems, attached) also avoids significant maintenance required to resolve Year 2000 issues. This initiative is being referred to as `HANDI 2000`. The software being implemented in the first phase of this project includes Indus International`s PASSPORT Software, Peoplesoft and Primavera P3 Software. The project, which encompasses all the system replacements that will occur, has been named `HANDI 2000.` The PASSPORT applications being implemented are Inventory Management, Purchasing, Contract Management, Accounts Payable, and MSDS (Material Safety Data Sheets).

This report documents the testing of the Health Physics Instrumentation associated with phase 2 and 3 start-up of Project W-026, WRAP. The Health Physics Instrumentation includes: Alpha and Beta Continuous Air Monitors (CAMS), Personnel Contamination Monitors (PCMs), Gamma Area Radiation Monitors (ARMs), Criticality Monitors, Alpha and Beta Smear Sample Counters, Portable Friskers, and Operator Breathing Zone Air Samplers. This OTR will cover only the Health Physics Instrumentation that was tested under the Operational test Plan for Health Physics Instrumentation (Phase 2 and 3). That instrumentation included: Alpha CAMS, Beta CAMs and ARMs located in rooms 107 and 113 of 2336-W. The remaining Health Physics Instrumentation that will be used for phase 2 and 3 start-up is tested during calibrations. These calibrations are outside the scope of the Operational Test Plan.

The primary purpose of the two 1,000 CFM Exhauster Skids, POR-007-SKID E and POR-008-SKID F, is to provide backup to the waste tank primary ventilation systems for tanks 241-C-106 and 241-AY-102, and the AY-102 annulus in the event of a failure during the sluicing of tank 241-C-106 and subsequent transfer of sluiced waste to 241-AY-102. This redundancy is required since both of the tank ventilation systems have been declared as Safety Class systems.

This report is a compilation of the analytical results for tank 241-SX-106, cores 223 and 224.

In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report.

Incineration of applicable Department of Energy (DOE) mixed wastes has produced a secondary waste stream of radioactive and Resource Conservation and Recovery Act (RCRA) hazardous fly ash that also requires treatment before land disposal. Unlike bottom ash, fly ash usually contains constituents making efficient stabilization difficult. For example, fly ash from the DOE Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering and Environmental Laboratory (INEEL) contains volatile metals, metal salts, high concentrations of zinc, and unburned organic residues. All of these constituents can effect the stabilization process. The Department of Energy, and in particular the Mixed Waste Focus Area (MWFA) of EM-50, has stated the need for improved stabilization methods would accept a higher ash waste loading while meeting waste form disposal criteria. These alternative stabilization technologies should include delivery systems to minimize worker exposure and minimize secondary waste generation, while maximizing operational flexibility and radionuclide containment. Currently, the standard practice for stabilizing ash is mixing with Portland cement at room temperature. This standard practice produces a significant increase of waste material volume or has difficulty in adequately stabilizing the components in the fly ash to ensure regulatory requirements are consistently satisfied. To address these fly ash …

This document defines the services the Waste Sampling and Characterization Facility (WSCF) shall provide the Effluent and Environmental Monitoring Program (EEM) throughout the calendar year for analysis. The purpose of the EEM Program is to monitor liquid and gaseous effluents, and the environment immediately around the facilities which may contain radioactive and hazardous materials. Monitoring data are collected, evaluated, and reported to determine their degree of compliance with applicable federal and state regulations and permits. The Appendix identifies the samples EEM plans to submit for analysis in CY-1998. Analysis of effluent (liquid and air discharges) and environmental (air, liquid, animal, and vegetative) samples is required using standard laboratory procedures, in accordance with regulatory and control requirements cited in Quality Assurance Program Plan for Radionuclide Airborne Emissions Monitoring (especially Appendix G) (WHC 1995a), Effluent Monitoring Quality Assurance Project Plan for Radionuclide Airborne Emissions Data (WHC 1995b), Near-Facility Environmental Monitoring Quality Assurance Project Plan (WMNW 1997), and Hanford Analytical Services Quality Assurance Requirements Documents (DOE 1996). Should changes to this document be necessary, WSCF or the Waste Management Federal Services, Inc. (WMH) Air and Water Services (AWS) Organization may amend it at any time with a jointly approved internal memo.

B and W Hanford Company have two Oak Ridge National Laboratory (ORNL) Type 4 canisters filled with cesium chloride (CsCl) originally produced at WESF (Waste Encapsulation and Storage Facility). These canisters are constructed of 304L stainless steel per drawing ORNL 970-294. Instead of removing the CsCl from the Type 4 canisters and repacking into an Inner Capsule, it is intended (for ALARA, schedule and cost purposes) that the Type 4 canisters be decontaminated (scrubbed) and placed [whole] inside a Type ``W`` overpack. The overpack is constructed from 316L stainless steel. Several tests have been run by Pacific Northwest National Laboratory (PNNL) over the. years documenting the corrosion compatibility of 316L SS with CsCl (Bryan 1989 and Fullam 1972). However, no information for 304L SS compatibility is readily available. This document estimates the corrosion resistance of 304L stainless steel in a WESF CsCl environment as it compares with that of 316L stainless steel.

This report documents the results of a performance demonstration and operational checkout of three 300 HP mixer pumps in accordance with WHC-SD-WI51-TS-001 ``Mixer Pump Test Specification for Project W-151`` and Statement of Work 8K520-EMN-95-004 ``Mixer Pump Performance Demonstration at MASF`` in the 400 Area Maintenance and Storage Facility (MASF) building. Testing of the pumps was performed by Fast Flux Test Facility (FFTF) Engineering and funded by the Tank Waste Remediation System (TWRS) Project W-151. Testing began with the first pump on 04-01-95 and ended with the third pump on 11-01-96. Prior to testing, the MASF was modified and prepared to meet the pump testing requirements set forth by the Test Specification and the Statement of Work.

This document provides estimates of the volume of sludge (1) expected from Integrated Process Strategy (IPS) processing of the fuel elements and (2) in the fuel storage canisters in K West Basin. The original estimates were based on visual observations of fuel element condition in the basin and laboratory measurements of KE canister sludge density. Revision 1 revised the volume estimates of sludge based on additional data from evaluations of material from the KW Basin fuel subsurface examinations and KW canister sludge characterization data. A nominal Working Estimate and an upper level Working Bound is developed for the canister sludge and the fuel wash sludge components in the KW Basin.

The US Department of Energy (DOE), established in the K Basin Spent Nuclear Fuel Project Regulatory Policy, dated August 4, 1995 (hereafter referred to as the Policy), the requirement for new Spent Nuclear Fuel (SNF) Project facilities to achieve nuclear safety equivalency to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. For activities other than during transport, when the Multi-Canister Overpack (MCO) is used and resides in the Canister Storage Building (CSB), Cold Vacuum Drying (CVD) facility or Hot Conditioning System, additional NRC requirements will also apply to the MCO based on the safety functions it performs and its interfaces with the SNF Project facilities. An evaluation was performed in consideration of the MCO safety functions to identify any additional NRC requirements needed, in combination with the existing and applicable DOE requirements, to establish nuclear safety equivalency for the MCO. The background, basic safety issues and general comparison of NRC and DOE requirements for the SNF Project are presented in WHC-SD-SNF-DB-002.

The high desert near Barstow, California, has witnessed the development of this country`s first two solar power towers. Solar One operated successfully from 1982 to 1988 and proved that power towers work efficiently to produce utility-scale power from sunlight. Solar Two was connected to the utility grid in 1996 and is operating today. Like its predecessor, Solar Two is rated at 10 megawatts. An upgrade of the Solar One plant, Solar Two demonstrates how solar energy can be stored in the form of heat in molten salt for power generation on demand. The experience gained with these two pilot power towers has established a foundation on which industry can develop its first commercial plants. These systems produce electricity on a large scale. They are unique among solar technologies because they can store energy efficiently and cost effectively. They can operate whenever the customer needs power, even after dark or during cloudy weather.

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal …

The Environmental Compliance Program is developing and implementing a PHMC-wide chemical management system with the goal being to: (1) manage and control chemicals from procurement through use and final disposition; (2) develop and maintain procedures for identifying and evaluating hazards and environmental impacts present in facilities, and the hazard classification of the facilities. The US Department of Energy (DOE) may promulgate the final rule, 1 0 CFR 834, Radiation Protection of the Public and the Environment in FY 1999. This rule establishes controls for the release of radioactive material and limits for the amount of radiation exposure to the public and the environment. It will be applicable to activities of DOE contractors at the Hanford site. This rule is expected to replace the bulk of DOE Orders 5400.5, Radiation Protection of the Public and the Environment and 5400. 1, General Environmental Protection Program. In doing so, these Orders will be backed by the Price-Anderson enforcement procedures and carry penalties for non-compliance.