The Uranium Mill Tailings Remedial Action (UMTRA) Project Environmental Protection Implementation Plan (EPIP) has been prepared in accordance with the requirements of the US Department of Energy (DOE) Order 5400.1. The UMTRA EPIP covers the time period of November 9, 1993, through November 8, 1994. It will be updated annually. Its purpose is to provide management direction to ensure that the UMTRA Project is operated and managed in a manner that will protect, maintain, and where necessary, restore environmental quality, minimize potential threats to public health and the environment, and comply with environmental regulations and DOE policies. Contents of this report are: (1) general description of the UMTRA project environmental protection program; (2) notifications; (3) planning and reporting; (4) special programs; (5) environmental monitoring programs; (6) quality assurance and data verification; and (7) references.

This report documents the Preliminary Hazards Analysis (PHA) for the National Ignition Facility (NIF). In summary, it provides: a general description of the facility and its operation; identification of hazards at the facility; and details of the hazards analysis, including inventories, bounding releases, consequences, and conclusions. As part of the safety analysis procedure set forth by DOE, a PHA must be performed for the NIF. The PHA characterizes the level of intrinsic potential hazard associated with a facility, and provides the basis for hazard classification. The hazard classification determines the level of safety documentation required, and the DOE Order governing the safety analysis. The hazard classification also determines the level of review and approval required for the safety analysis report. The hazards of primary concern associated with NIF are radiological and toxicological in nature. The hazard classification is determined by comparing facility inventories of radionuclides and chemicals with threshold values for the various hazard classification levels and by examining postulated bounding accidents associated with the hazards of greatest significance. Such postulated bounding accidents cannot take into account active mitigative features; they must assume the unmitigated consequences of a release, taking into account only passive safety features. In this way, the …

A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then solidified with the selected immobilization media and subjected to a battery of standard performance tests. Detailed discussion of the laboratory work and results are contained in this report.

Since mid-September we have been engaged in final revision of the data base for South and Southeast Asia. In October we revised our second chapter for the forthcoming volume Effects of Land Use Change on Atmospheric Carbon Dioxide Concentrations, edited by Virginia Dale. ``Trends in Carbon Content of Vegetation in South and Southeast Asia Associated with Changes in Land Use``, in response to a second round of reviews. Both this chapter and `` Century of Land Use Change in South and Southeast Asia`` (submitted in revised form in July) are have been accepted and are now in the hands of the technical editor. our time series of land use data and carbon content estimates for live vegetation in 93 zones comprising thirteen Asian nations at four dates was finalized in the course of manuscript revision. We sent machine-readable copies of the spreadsheets containing tabular data for Southeast Asia to CDIAC in October, and the following month delivered the South Asian data. At the same time, we sent these files to the research groups of Sandra Brown and Charlie Hall, who have entered this information in their geographic information systems, and also to Skee Houghton.

This document presents the functional performance parameters for permanent isolation surface barriers. Permanent isolation surface barriers have been proposed for use at the Hanford Site (and elsewhere) to isolate and dispose of certain types of waste in place. Much of the waste that would be disposed of using in-place isolation techniques is located in subsurface structures, such as solid waste burial grounds, tanks, vaults, and cribs. Unless protected in some way, the wastes could be transported to the accessible environment via transport pathways, such as water infiltration, biointrusion, wind and water erosion, human interference, and/or gaseous release.

AMS sensitivity arises from the direct counting of radioisotopes without interference from molecular isobars. No chemical or physical information other than a bulk isotope ratio is available from the usual AMS instrument. Chemical or biological significance of the isotope ratio depends on the definition of the sample prior to conversion to material used in the ion source. The authors use AMS to quantify biochemical interactions between labeled xenobiotics and their potential targets of toxicity. These potential target molecules are separated and defined by various types of plate and microbore separations, including thin layer chromatography (TLC), high performance liquid chromatography (HPLC) and gel electrophoresis (GE) in quantifying the binding of {sup 14}C-labeled compounds to specific DNA and protein fragments. They discuss their methods of using these microbore and plate separations of biomolecules while controlling contamination from {sup 14}C in laboratory equipment and give examples.

This manual assumes a knowledge of (terminology used and a working familiarity with) the windowing system and mouse of the Sun computer workstation. See the appropriate Sun manuals for additional information. ALDO, the alpha detector control program, is used to control, monitor, and edit log information associated with the collection of alpha spectra. Actual data collection and control functions are performed by Mizar Real-Time computers for which ALDO acts as a friendly user command interface and status display. It is normally started as part of your login procedure, but may also be started from the ``NETSPEC Utilities`` submenu of the root menu. The root menu is obtained by pushing the right mouse button when the cursor is over the root window (background picture). To become a user of ALDO and the other programs in the NETSPEC system, contact the person who performs systems administration tasks for the Sun computers. Most user interaction with ALDO is by means of mouse manipulation of screen items such as buttons, checkboxes, and sliders. The action of pushing the left mouse button when the cursor is over an item is called selecting that item. The left mouse button is therefore called the select button. The …

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

Biological effects occur in natural systems at chemical concentrations of parts per billion (1:10{sup 9}) or less. Affected biomolecules may be separable in only milligram or microgram quantities. Quantification at attomole sensitivity is needed to study these interactions. AMS measures isotope concentrations to parts per 10{sup 13--15} on milligram-sized samples and is ideal for quantifying long-lived radioisotopic labels that are commonly used to trace biochemical pathways in natural systems. {sup 14}C-AMS has now been coupled to a variety of organic separation and definition technologies. The primary research investigates pharmacokinetics and genotoxicities of toxins and drugs at very low doses. Human subject research using AMS includes nutrition, toxicity and elemental balance studies. {sup 3} H, {sup 41}Ca and {sup 26}Al are also traced by AMS for fundamental biochemical kinetic research. Expansion of biomedical AMS awaits further development of biochemical and accelerator technologies designed specifically for these applications.

Santiago, Chile has a serious air pollution problem. Aerosols reach very high levels and ozone exceeds US ambient standards on over 100 days a year. Chileans are very concerned about the poor air quality of Santiago and the effect of emissions from their copper smelters both near Santiago and at other sites. Officials from both the Santiago metropolitan air quality commission (La Comision Especial de Descontaminacion de le Region Metropolitana) and a government owned copper development company (La Empress Nacional de Mineria (ENAMI)) have asked for assistance to deal with the air quality problems in the city and associated with smelter emissions. This report describes the first steps in that effort. Santiago lies in a valley between a small coastal range to the west and the towering Andes to the cast. Air motion is greatly affected by the major topographical features which include the Pacific Ocean, the coastal range, and the Andes. In this first year of work the authors concentrated on gathering information on the meteorology, topography, and air quality of the metropolitan region. They examined two smelter sites and applied models to them to help their understanding and to provide assistance to ENAMI. One smelter, Ventanas, was located …

A study was undertaken to evaluate the irradiation damage response of several different types of low alloy steel: vintage type ASTM A302 Grade B (A302B) plates and welds containing different Ni and Cu concentrations, 3.5% Ni steels similar to ASTM A508 Class 4, welds containing about 1% Ni (similar to type 105S), and 3.5% Ni steels with ``superclean`` composition. All materials were irradiated at several different irradiation damage levels ranging from 0.0003 to 0.06 dpa at 232C (450F). Complete Charpy V-notch impact energy transition temperature curves were generated for all materials before and after irradiation to determine transition temperature at 4IJ (30 ft-lb) or 47J (35 ft-lb) and the upper shelf energy. Irradiation damage behavior was measured by shift in Charpy 41J or 47J transition temperature ({Delta}TT4{sub 41J} or {Delta}TT{sub 47J}) and lowering of upper shelf Charpy energy at a given irradiation damage level. It was found that chemical composition greatly influenced irradiation damage behavior; highest irradiation damage (greatest {Delta}TT) was found in an A302B type weld containing 1.28% Ni and 0.20% Cu while the least damage was found in 3.5% Ni, 0.05% Cu, superclean wrought materials. Combination of Ni and Cu was found to affect irradiation damage behavior at …

Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with long-term regulations of the United States Environmental Protection Agency (EPA), specifically the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), and the Land Disposal Restrictions (40 CFR 268) of the Hazardous and Solid Waste Amendments to the Resource Conservation and Recovery Act (RCRA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper provides background information on the regulations, describes the SNL WIPP PA Departments approach to developing a defensible technical basis for consistent compliance evaluations, and summarizes the major observations and conclusions drawn from the 1991 and 1992 PAs.

At the request of the WIPP Project Integration Office (WPIO) of the DOE, the WIPP Performance Assessment (PA) Department of Sandia National Laboratories (SNL) has completed preliminary uncertainty and sensitivity analyses of gas and brine migration away from the undisturbed repository. This paper contains descriptions of the numerical model and simulations, including model geometries and parameter values, and a summary of major conclusions from sensitivity analyses. Because significant transport of contaminants can only occur in a fluid (gas or brine) medium, two-phase flow modeling can provide an estimate of the distance to which contaminants can migrate. Migration of gas or brine beyond the RCRA ``disposal-unit boundary`` or the Standard`s accessible environment constitutes a potential, but not certain, violation and may require additional evaluations of contaminant concentrations.

Before disposing of transuranic radioactive waste at the Waste Isolation Pilot Plant (WIPP), the US Department of Energy (DOE) must evaluate compliance with long-term regulations of the US Environmental Protection Agency (EPA). Sandia National Laboratories (SNL) is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for final compliance evaluations. This paper describes the 1992 preliminary comparison with Subpart B of the Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191), which regulates long-term releases of radioactive waste. Results of the 1992 PA are preliminary, and cannot be used to determine compliance or noncompliance with EPA regulations because portions of the modeling system and data base are incomplete. Results are consistent, however, with those of previous iterations of PA, and the SNL WIPP PA Department has high confidence that compliance with 40 CFR 191B can be demonstrated. Comparison of predicted radiation doses from the disposal system also gives high confidence that the disposal system is safe for long-term isolation.

In June 1992, the Department of Energy issued DOE N 5480.6, Radiological Control Manual, which established practices for conducting radiological control activities at all DOE and DOE-funded sites that manage radiation or radioactive materials. To implement the RCM, each DOE facility was required to develop and approve their own radiological control manual, which described a phased approach to implementing the RCM over a period of time. This document, for the Hanford Site, is called the Hanford Site Radiological Control Manual. The HSRCM was issued in December 1992 (RL 1992). This project relates to Article 514 in the RCM, which discusses establishing and maintaining a comprehensive area monitoring program for minimizing the number of areas requiring the issuance of personnel dosimeters and for verifying that doses next to Radiological Buffer Areas are negligible. Three specific items in this article address the use of area monitoring dosimeters to (1) record and document radiation levels in routinely occuPied areas adjacent to areas where radiation or operations with radiation exist, (2) support dosimetry investigations, and (3) supplement the existing monitoring programs in Controlled Areas in the event of an emergency.

This paper presents an overview of MPI, a proposed standard message passing interface for MIMD distributed memory concurrent computers. The design of MPI has been a collective effort involving researchers in the United States and Europe from many organizations and institutions. MPI includes point-to-point and collective communication routines, as well as support for process groups, communication contexts, and application topologies. While making use of new ideas where appropriate, the MPI standard is based largely on current practice.

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates): Source Terms, Environmental Transport, Environmental Monitoring Data, Demography, Food Consumption, and Agriculture, and Environmental Pathways and Dose Estimates.

This report reviews those facts and issues that affect the direct disposal of spent reactor fuels. It is intended as a resource document for those impacted by the current Department of Energy (DOE) guidance that calls for the cessation of fuel reprocessing. It is not intended as a study of the specific impacts (schedules and costs) to the Savannah River Site (SRS) alone. Commercial fuels, other low enriched fuels, highly enriched defense-production, research, and naval reactor fuels are included in this survey, except as prevented by rules on classification.

Historically, tactical mission planning systems have been the primary clients of CMS data. CDPS is composed of two subsystems, the CMS Preprocessing Subsystem (CPS) and the CMS Distribution Subsystem (CDS). This guide describes the operation of CDS. References and other resources used for the preparation of this guide are listed. CDS is responsible for the management of archived CMS data, the management of production orders and the generation of theater databases. The CDS system was developed for use on a workstation running Ultrix 4.2, the X Window System Version X11R4, and Motif Version 1.1. CDS is organized into seven major functional groups: CDS Executive, Manage Processed Data, Display CMS Data, Manage Production Orders, Build Theater Databases, Administration Tools, and System Utilities.

This Quality Assurance Program Plan (QAPP) provides the primary requirements for the integration of quality functions into all Technical Assistance Contractor (TAC) Project organization activities. The QAPP is the written directive authorized by the TAC Program Manager to accomplish this task and to implement procedures that provide the controls and sound management practices needed to ensure TAC contractual obligations are met. The QA program is designed to use monitoring, audit, and surveillance functions as management tools to ensure that all Project organization functions are executed in a manner that will protect public health and safety, promote the success of the Project, and meet or exceed contract requirements. The key to ensuring compliance with this directive is a two-step professional approach: utilize the quality system in all areas of activity, and generate a personal commitment from all personnel to provide quality service. The quality staff will be experienced, trained professionals capable of providing maximum flexibility to Project goal attainment. Such flexibility will enable the staff to be more cost effective and to further improve communication and coordination. To provide control details, this QAPP will be supplemented by approved standard operating procedures that provide requirements for performing the various TAC quality-related activities. …

A Chemical EOR Workshop was held on June 23--24, 1993 in Houston, Texas. The objectives of this workshop were to evaluate the potential for chemical Enhanced Oil Recovery (EOR) to repower significant quantities of remaining domestic oil, to assess the role of the Department of Energy (DOE) and petroleum industry to achieve this potential, and to assess the research needs in chemical EOR. Fifty-six research engineers and scientists from major oil companies, independent oil companies, academic institutes, research institutes, and DOE attended this workshop. Opening remarks were given by Alex Crawley from DOE Bartlesville Project Office and Thomas E. Burchfield of the National Institute for Petroleum and Energy Research (NIPER). The keynote address was delivered by Donald Juckett, Acting Deputy Assistant Secretary for Gas and Petroleum Technology. Ten papers on the state-of-the-art in chemical EOR technologies and recent field test experience were presented on the first day. Two workshops, one on surfactant/alkali flooding and the other on profile modification/polymer flooding, were held on the second day. It was concluded that chemical EOR has the potential of recovering significant quantities of remaining oil, and it is the only method that has the potential of economically recovering residual oil from reservoirs of …

This document describes the activities and products of the Global Research Program in FY 1993. This publication describes all of the projects funded by the Environmental Sciences Division of DOE under annual contracts, grants, and interagency agreements in FY 1993. Each description contains the project`s title; its 3-year funding history (in thousands of dollars); the period over which the funding applies; the name(s) of the principal investigator(s); the institution(s) conducting the projects; and the project`s objectives, products, approach, and results to date (for most projects older than 1 year). Project descriptions are categorized within the report according to program areas: climate modeling, quantitative links, global carbon cycle, vegetation research, ocean research, economics of global climate change, education, information and integration, and NIGEC. Within these categories, the descriptions are grouped alphabetically by principal investigator. Each program area is preceded by a brief text that defines the program area, states its goals and objectives, lists principal research questions, and identifies program managers.

This Draft Environmental Impact Statement (DEIS) was prepared by the US Department of Energy (US DOE). The proposed action is the issuance of Presidential Permit PP-89 by DOE to Bangor Hydro-Electric Company to construct and operate a new international transmission line interconnection to New Brunswick, Canada that would consist of an 83.8 mile (US portion), 345-kilovolt (kV) alternating current transmission line from the US-Canadian border at Baileyville, Maine to an existing substation at Orrington, Maine. The principal environmental impacts of the construction and operation of the transmission line would be incremental in nature and would include the conversion of forested uplands (mostly commercial timberlands) and wetlands to right-of-way (small trees, shrubs, and herbaceous vegetation). The proposed line would also result in localized minor to moderate visual impacts and would contribute a minor incremental increase in the exposure of some individuals to electromagnetic fields. This DEIS documents the purpose and need for the proposed action, describes the proposed action and alternatives considered and provides a comparison of the proposed and alternatives routes, and provides detailed information on analyses of the environmental consequences of the proposed action and alternatives, as well as mitigative measures to minimize impacts.

This document is a compilation of nuclear regulatory legislation and other relevant material through the 102d Congress, 2d Session. This compilation has been prepared for use as a resource document, which the NRC intends to update at the end of every Congress. The contents of NUREG-0980 include: The Atomic Energy Act of 1954, as amended; Energy Reorganization Act of 1974, as amended, Uranium Mill Tailings Radiation Control Act of 1978; Low-Level Radioactive Waste Policy Act; Nuclear Waste Policy Act of 1982; and NRC Authorization and Appropriations Acts. Other materials included are statutes and treaties on export licensing, nuclear non-proliferation, and environmental protection.