This note is written in response to a request from Phil Livdahl for corrections, and additions to a TM he is writing on Staffing Levels at Fermilab during Initial Construction Years and to a note that Hank Hinterberger is preparing on milestones. In my spare time over the past few years I have taken the original files of the Main Ring Section, my own notes from that period, and various other collections of relevant paper, and arranged them in a set of 44 large loose leaf binders in chronological order. I call this set of volumes the 'Main Ring Chronological Archives'. In response to Phil's request I have recently skimmed through these records of the period and extracted a small subset of documents which relate to the specific questions that Phil is addressing: staffing. administration, and milestones.

The ECRH diagnostics system monitors the net power delivered to the plasma by four 200-kW gyrotron oscillators, the frequency of each gyrotron, and some operating parameters of the gyrotron power supply system. The combination CAMAC- and GPIB-based data acquisition system is under desktop computer control that provides the capability for data conversion and display. The data acquisition system is also interfaced to the main computer system that acquires and archives the data.

The Hanford Meteorological Station (HMS), operated by Pacific Northwest Laboratory, archives wind, dry bulb temperature, and soil temperature data gathered each hour from the 410-ft meteorological tower. These data include measurements of wind speed and wind direction for seven heights, eight dry bulb temperatures, and three soil temperatures. The TOWER computer code is used to archive those measurements and apply quality assurance checks to the data. The code accesses an input file, which contains the previous archive's date and hour, and an output file, which contains tower weather observations for the current month. A data entry form consisting of 25 fields is included in the program. The fields must be filled in by the user. The information entered is appended to the monthly file, which provides an archive for the tower data gathered hourly. This volume describes the implementation and operation of the TOWER computer code at the HMS.

The health concerns of several substances likely to be encountered in the non-industrial indoor environment are discussed. Monitoring data and information on the health effects of CO, NO/sub 2/, formaldehyde, and radon are included. (JGB)

A Level II Cultural Resource Survey was completed for the Texoma Distribution Enhancements project, located in Cameron and Calcasieu Parishes, Louisiana. The 13-mile pipeline extends from Strategic Petroleum Reserve No. 3 to a terminus near Vincent Landing. Located in Louisiana's southwest coastal zone, the pipeline will traverse extensive marsh lands as well as upland prairie terrace areas. Present land use within the project area consists primarily of undeveloped marsh land and cattle range. The study methods included background research, intensive pedestrian survey with systematic shovel testing, a boat survey, and laboratory analysis of recovered artifact collections. One historic site, 16CU205, was identified during the field survey, and it was tested for National Register eligibility. The site is assignable to the Industrialization and Modernization (1890-1940) Cultural Unit. Archaeological testing indicates that it is a rural residence or farmstead, with a house and one outbuilding within the proposed right-of-way. The site lacks significant historical association and sufficient archaeological integrity to merit inclusion on the National Register of Historic Places. Four standing structures were also identified during the field survey. The structures are agricultural outbuildings, less than 40 years in age, that possess no architectural distinction or historical association. They have been documented …

Records of the Icelandic Population are being used to investigate the possible inheritance of disabilities and diseases as well as other characters and the effect of environment on man. The progress report of research covers the period 1977 to 1980. The investigation was begun in 1965 by the Genetical Committee of the University of Iceland and the materials used are demographic records from the year 1840 to present and various medical information. The records are being computerized and linked together to make them effective for use in hereditary studies.

Records of the Icelandic population are being used to investigate the possible inheritance of disabilities and diseases as well as other characteristics and the effect of environment on man. The progress report of research covers the period from 1977 to 1980. The investigation was begun in 1965 by the Genetical Committee of the University of Iceland and the materials used are demographic records from the year 1840 to present and various medical information. The records are being computerized and linked together to make them effective for use in hereditary studies.

The fact that Tritium Systems Test Assembly (TSTA) is an experimental facility makes it impossible and undesirable to try to forecast the exact software requirements. Thus the software had to be written in a manner that would allow modifications without compromising the safety requirements imposed by the handling of tritium. This suggested a multi-level approach to the software. In this approach (much like the ISO network model) each level is isolated from the level below and above by cleanly defined interfaces. For example, the subsystem support level interfaces with the subsystem hardware through the software support level. Routines in the software support level provide operations like ''OPEN VALVE'' and CLOSE VALVE'' to the subsystem level. This isolates the subsystem level from the actual hardware. This is advantageous because changes can occur in any level without the need for propagating the change to any other level. The TSTA control system consists of the hardware level, the data conversion level, the operator interface level, and the subsystem process level. These levels are described.

The performance of a pre-prototype of the SLD Warm Iron Calorimeter (WIC) build with proportional tube cathode pad readout has been studied. The calorimeter was found to have an average resolution of 36.7 +- 0.2% for muons at 2.0, 5.0 and 10.5 GeV and 81 +- 2%/..sqrt..E for pion showers at 5.0 and 10.5 GeV. The mean energy found for the pion showers was consistent with a linear dependence on energy within these standard deviations. 4 refs., 6 figs., 3 tabs.

Uncertainties in estimating the potential health impact of a given radiation exposure include instrument measurement error in determining exposure and difficulty in relating this exposure to an effective dose value. Instrument error can be due to design or manufacturing deficiencies, limitations of the sensing element used, and calibration and maintenance of the instrument. This paper evaluates the errors which can be introduced by design deficiencies and limitations of the sensing element for a wide variety of commonly used survey instruments. The results indicate little difference among sensing element choice for general survey work, with variations among specific instrument designs being the major factor. Ion chamber instruments tend to be the best for all around use, while scintillator-based units should not be used where accurate measurements are required. The need to properly calibrate and maintain an instrument appears to be the most important factor in instrument accuracy. 8 references, 6 tables.

To use data on {sup 129}I in human tissue to estimate an individual's past exposure to that radionuclide, it is necessary to know when and how the exposure occurred, and to know about any other prior and/or ongoing exposures. Moreover, to use {sup 129}I data to estimate past exposure to {sup 131}I, it is also necessary to know the relationship of the two radionuclides at the time of exposure. The relative quantities of {sup 131}I and {sup 129}I in gaseous effluents from Hanford Site facilities varied significantly because of the large variations in elapsed time between discharge of irradiated fuel from Hanford production reactors and initiation of chemical processing. The relationship of the two radionuclides also varied in the environment because the shorter-lived {sup 131}I decayed and the longer-lived {sup 129}I accumulated. Because of its extremely long half-life, {sup 129}I from both Hanford and non-Hanford sources (such as fallout from weapons testing) has accumulated in the environment. Without an associated exposure to {sup 131}I, chronic exposure to {sup 129}I deposited in the environment has contributed and continues to contribute to thyroid burdens. Based on investigations conducted to date, measured levels of {sup 129}I in human tissue will not provide a …

None

Environmental effluents that may be associated with the fusion fuel cycle are identified. Existing standards for controlling their release are summarized and anticipated regulatory changes are identified. The ability of existing and planned environmental control technology to limit effluent releases to acceptable levels is evaluated. Reference tokamak fusion system concepts are described and the principal materials required of the associated fuel cycle are analyzed. These materials include the fusion fuels deuterium and tritium; helium, which is used as a coolant for both the blanket and superconducting magnets; lithium and beryllium used in the blanket; and niobium used in the magnets. The chemical and physical processes used to prepare these materials are also described.

The Geothermal Site Development Forecasting System (FORSITE) is a computer-based multiproject monitoring, scheduling, and forecasting system. Its main purpose is to assist DOE geothermal program managers in monitoring the progress of multiple geothermal electric exploration and construction projects. The system actively combines conceptual project development schedules with site-specific status data to predict a time-phased sequence of development likely to occur at multiple specific geothermal sites. The forecasting capabilities of the model include estimation of industry costs and federal manpower requirements across sites on a year-by-year basis.

This report concerns the development of a marking system for a nuclear waste repository which is very likely to survive for 10,000 years. In order to provide a background on the subject, and for the preliminary design presented in this report, a discussion is presented about the issues involved in human interference with the repository system and the communication of information. A separate chapter summarizes six ancient man-made monuments including: materials, effects of associated textual information on our understanding of the monument, and other features of the ancient monument relevant to marking a repository site. The information presented in the two chapters is used to provide the basis and rationale for a preliminary marker system design presented in a final chapter. 86 refs., 22 figs., 1 tab.

An extensive program of characterization of several inactive uranium tailings piles has been carried out in the past year. The geotechnical engineering program conducted a drilling program at the Salt Lake City and Grand Junction sites. The locations of slimes and sands in these sites hve been characterized. In general, it was found that slimes exist in the impoundments in lower percentages than normally produced from mill tailings. Permeability tests were conducted yielding values ranging from 10/sup -3/ cm/sec to 10/sup -6/cm/sec. The geochemical studies made considerable progress in the past year. Extensive sampling of several sites was conducted. Sampling programs have been completed for seven sites and are underway for nine other sites. The work to date has indicated the importance of salts in controlling the direction and rate of movement of contaminants. The work has also indicated that a number of non-radioactive elements such as As are of environmental importance. The work also indicates the importance of the fact that the tailings piles are out of chemical equilibrium with their environment. Computer software was developed and implemented for data storage and retrieval. Automation hardware was installed and tested for the Inductively Coupled Plasma Emission Spectrometer. A number of …

It is proposed to build a regional outpatient medical clinic at the Fermi National Accelerator Laboratory (Fermilab), Batavia, Illinois, to exploit the unique therapeutic characteristics of high energy proton beams. The Fermilab location for a proton therapy facility (PTF) is being chosen for reasons ranging from lower total construction and operating costs and the availability of sophisticated technical support to a location with good access to patients from the Chicago area and from the entire nation. 9 refs., 4 figs., 26 tabs.

Surveys have confirmed the survival of both the giant Columbia River spire snail Fluminicola columbiana and the great Columbia River limpet Fisherola nuttalli in the Hanford Reach of the Columbia River, Washington State, as well as other sites in Washington, Oregon, and Idaho. A review of historical collection records suggests that both species exist in still other sites of the Columbia River Basin. At present, there is insufficient information to allow adequate appraisal of either species relative to possible federal or state listing as endangered or threatened species. The results of our studies suggest that additional undiscovered populations of both species exist. There is a relatively good chance that pristine habitat required by spire snails and limpets remains in 37 streams or portions of streams in Washington, Oregon, Idaho, and Montana (British Columbia was considered outside the project scope). For a thorough survey, visits to more than 600 sites will be required. 20 refs., 5 figs., 7 tabs.

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

The Three Mile Island (TMI) Unit 2 accident on March 28, 1979 was and is of great concern to the nuclear industry; electric power generating companies and their customers, regulatory and other government agencies, the entire nuclear community, and to the country as a whole. While the accident resulted in only limited external plant radiation exposure, the plant itself suffered extensive damage with high radiation contamination within the reactor and auxiliary system facilities. The GEND Planning Report for cleanup activities at TMI-2 covers the areas of: instrumentation and electrical equipment survivability; fission product transport; decontamination/radiation dose reduction technology; data bank organization and sample archive facility; characterization of primary system pressure boundary and mechanical components; core damage assessment; and fuel handling, removal, examination and disposal.

Non-occupational health effects associated with SRC operation will be determined by environmental factors governing the form, transport, and persistence of SRC materials and wastes - factors which also mediate exposure to man. Accordingly, the research described is an attempt to determine the fate of disposed solid wastes and spilled SRC materials, and it necessarily focuses on water soluble, persistent materials with greatest potential for mobility and incorporation into water and food supplies. Initially, aqueous equilibrations of SRC-II liquid material and SRC-I nongasified mineral residue were subjected to chemical characterization. Subsequently, laboratory studies were performed on the interaction of aqueous equilibrates of SRC-II liquid and SRC-I non-gasified mineral residue with soil materials isolated suspended sediments, and bottom sediments. These studies were designed to identify effects of specific sorption reactions ion or induced-ion exchange reactions, and toxicity of water soluble, biologically active materials derived from liquid and solid wastes. Results of these experiments have applicability to the environmental fate and effects of biologically active compounds released under different scenarios from product spills and solid waste disposal.

This is a report on the 1989 independent Criticality Safety Assessment of the Rocky Flats Plant, primarily in response to public concerns that nuclear criticality accidents involving plutonium may have occurred at this nuclear weapon component fabrication and processing plant. The report evaluates environmental issues, fissile material storage practices, ventilation system problem areas, and criticality safety practices. While no evidence of a criticality accident was found, several recommendations are made for criticality safety improvements. 9 tabs.

Reentry analyses consisting of ablation response, thermal response and thermal stress response have been conducted on the Light Weight Radioisotope Heater Unit for Galileo/VEEGA reentry conditions. Sequential ablation analyses of the LWRHU aeroshell, the fuel clad, and the fuel pellet have been conducted in reentry regimes where the aeroshell has been deemed to fail. The failure criterion for ablation is assumed to be recession corresponding to 50% of the wall thickness (the design criterion recommended in the DOE Overall Safety Manual). Although the analyses have been carried far beyond this limit (as presented and discussed herein), JHU/APL endorses the position that failure may occur at the time that this recession is achieved or at lower altitudes within the heat pulse considering the uncertainties in the aerodynamic, thermodynamic, and thermo-structural analyses and modeling. These uncertainties result mainly because of the high energies involved in the VEEGA reentries compared to orbital decay reentries. Risk evaluations should consider the fact that for shallow flight paths the unit may disassemble at high-altitude as a result of ablation or may remain intact until it impacts with a clad that had been molten. 80 refs., 46 figs., 16 tabs.

This report summarizes results of the National Bureau of Standards (NBS) evaluations of Department of Energy (DOE) activities on waste packages designed for containment of radioactive high-level nuclear waste (HLW). The waste package is a proposed engineered barrier that is part of a permanent repository for HLW. Metal alloys are the principal barriers within the engineered system. Technical discussions are given for the corrosion of metals proposed for the canister, particularly carbon and stainless steels, and copper. In the section on tuff, the current level of understanding of several canister materials is questioned. Within the Basalt Waste Isolation Project (BWIP) section, discussions are given on problems concerning groundwater, materials for use in the metallic overpack, and diffusion through the packing. For the proposed salt site, questions are raised on the work on both ASTM A216 Steel and Ti-Code 12. NBS work related to the vitrification of HLW borosilicate glass at the West Valley Demonstration Project (WVDP) and the Defense Waste Processing Facility (DWPF) is covered. NBS reviews of selected DOE technical reports and a summary of current waste-package activities of the Materials Characterization Center (MCC) is presented. Using a database management system, a computerized database for storage and retrieval of …