This report describes the groundwater monitoring and corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) and the Metallurgical Laboratory (Met Lab) HWMF at the Savannah River Site (SRS) during 1999.

This Acceptance for Beneficial Use documents that Pumping Instrumentation and Control (PIC) skid ''P'' is ready for field use. This document does not cover the field installation or operational testing.

Two large chemical explosions were detonated in the Dead Sea in order to calibrate seismic travel times and improve location accuracy for the International Monitoring System (IMS) to monitor a Comprehensive Nuclear Test-Ban Treaty (CTBT). These explosions provided calibration data for regional seismic networks in the Middle East. In this paper we report analysis of seismic data from these shots as recorded by two seismic networks run by King Saud University (KSU) and King Abdulaziz City for Science and Technology (KACST) in Saudi Arabia. The shots were well observed in the distance range 180-480 km mostly to the south of the Dead Sea in the Gulf of Aqaba region of northwestern Saudi Arabia. An average one-dimensional velocity model for the paths was inferred from the travel times of the regional phases Pn, Pg and Sg. Short-period Sn phases were not observed. The velocity model features a thin crust (crustal thickness 26-30 km) and low velocities (average P-wave velocity 5.8-6.0 km/s), consistent with the extensional tectonics of the region and previous studies.

The Configuration Management Plan for Project W-314 describes the systems, processes and procedures for implementation of applicable configuration management practices described in HNF-0842, Volume 111, Section 3.1, ''Configuration Management Implementation''. This plan is tailored specifically for use by Project W-314.

A near tripling in the price of crude oil from March 1999 to the first months of 2000, coupled with other developments, initially brought about sharp increases in the price of home heating oil and diesel fuel, which are essentially the same product. Gasoline prices then increased. These developments brought about discussion of what might be done to mitigate price increases and possible spot shortages, and what might be done to prevent a similar situation in the future.

A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO provided information on the Nuclear Regulatory Commission's (NRC) fire protection program, focusing on: (1) NRC's efforts to improve its oversight of fire protection at nuclear power plants; (2) any potential barriers to the successful implementation of the risk-informed oversight process for fire protection; and (3) the extent to which fire risk assessments consider the possible failure of passive fire barriers and penetration seals and whether the cumulative effect of granting exemptions has increased the risk of fire at nuclear power plants."

A hazard assessment was conducted in the parking area of the Rapaport Building in Windsor Connecticut. The site had been a processing plant for nuclear fuels for the Navy's nuclear fuel program. The subject of the study was a storm drain that showed signs of increased radiation from enriched uranium products that had been produced or used in the adjacent building. The conclusion of the assessment is that there is no public hazard from radiation from the drain.

Sawtooth phenomena have been studied on DIII-D and TFTR. In the experiments, with high power neutral beam injection the sawtooth characteristics were studied with fast electron temperature (ECE) and soft x-ray diagnostics. A strong ballistic electron heat pulse is found on DIII-D, stronger than was previously reported on TFTR. Evidence is presented in this paper that the ballistic effect is related to the sawtooth precursor. Fast, 2 msec interval, measurements on DIII-D were made of the ion temperature evolution following the sawtooth to document the ion heat pulse characteristics. It is found that the ion heat pulse does not exhibit the very fast, ''ballistic'' behavior seen for the electrons. Further, both the electron and ion heat pulses from partial sawtooth crashes and similar events are seen to propagate at speeds close to those expected from the power balance calculations of the thermal diffusivities. These results suggest that the fast sawtooth induced heat pulse propagation is not a feature of non-linear transport models, but that MHD events can have a strong effect on thermal transport.

This presentation investigates the incorporation of uncertainty and variability of drip shield and waste package degradation in analyses with the Waste Package Degradation (WAPDEG) program (CRWMS M&O 1998). This plan was developed in accordance with Development Plan TDP-EBS-MD-000020 (CRWMS M&O 1999a). Topics considered include (1) the nature of uncertainty and variability (Section 6.1), (2) incorporation of variability and uncertainty into analyses involving individual patches, waste packages, groups of waste packages, and the entire repository (Section 6.2), (3) computational strategies (Section 6.3), (4) incorporation of multiple waste package layers (i.e., drip shield, Alloy 22, and stainless steel) into an analysis (Section 6.4), (5) uncertainty in the characterization of variability (Section 6.5), and (6) Gaussian variance partitioning (Section 6.6). The presentation ends with a brief concluding discussion (Section 7).

This Interface Control Document (ICD) describes interfaces between the Double-Shell Tanks (DST) System and Waste Encapsulation and Storage Facility (WESF) (figure 1). WESF is currently operational as a storage facility for cesium and strontium capsules. This ICD covers current operational interfaces and those envisioned during Terminal Clean Out (TCO) activities in the future. WESF and the DST System do not have a direct physical interface. The waste will be moved by tank trailer to the 204-AR waste unloading facility. The purpose of the ICD process is to formalize working agreements between the River Protection Project (RPP) DST System and systems/facilities operated by organizations or companies internal and external to RPP. This ICD has been developed as part of the requirements basis for design of the DST System to support the Phase I Privatization effort.

The Consolidated Incinerator Facility (CIF) at the Savannah River Site (SRS) burns low-level radioactive wastes and mixed wastes as a method of treatment and volume reduction. The CIF generates secondary waste, which consists of ash and offgas scrubber solution. Currently the ash is stabilized/solidified in the Ashcrete process. The scrubber solution (blowdown) is sent to the SRS Effluent Treatment Facility (ETF) for treatment as wastewater. In the past, the scrubber solution was also stabilized/solidified in the Ashcrete process as blowcrete, and will continue to be treated this way for listed waste burns and scrubber solutions that do not meet the ETF Waste Acceptance Criteria (WAC). The disposal plan for Ashcrete and special case blowcrete is to bury these containerized waste forms in shallow unlined trenches in E-Area. The WAC for intimately mixed, cement-based wasteforms intended for direct disposal specifies limits on compressive strength and permeability. Simulated waste and actual CIF ash and scrubber solution were mixed in the laboratory and cast into wasteforms for testing. Test results and related waste disposal consequences are given in this report.

This is a multiyear experimental research program focused on improving relevant material properties of high-T{sub c} superconductors (HTSs) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne program. Recent results are presented on YBa{sub 2}Cu{sub 3}O{sub x} (Y-123) coated conductors, sheathed (Bi,Pb){sub 2}Sr{sub 2}Ca{sub 2}Cu{sub 3}O{sub x} (Bi-2223) tapes, and applications development.

This Project Execution Plan documents the methodology for managing Project W-211. Project W-211, Initial Tank Retrieval Systems (ITRS), is a fiscal year 1994 Major Systems Acquisition that will provide systems for retrieval of radioactive wastes from selected double-shell tanks (DST). The contents of these tanks are a combination of supernatant liquids and settled solids. To retrieve waste from the tanks, it is first necessary to mix the liquid and solids prior to transferring the slurry to alternative storage or treatment facilities. The ITRS will provide systems to mobilize the settled solids and transfer the wastes out of the tanks. In so doing, ITRS provides feed for the future waste treatment plant, allows for consolidation of tank solids to manage space within existing DST storage capacity, and supports continued safe storage of tank waste. The ITRS scope has been revised to include waste retrieval systems for tanks AP-102, AP-104, AN-102, AN-103, AN-104, AN-105, AY-102, AZ-102, and SY-102. This current tank selection and sequence provides retrieval systems supporting the River Protection Project (RF'P) Waste Treatment Facility and sustains the ability to provide final remediation of several watch list DSTs via treatment. The ITRS is configured to support changing program needs, as constrained …

The Risk Management Plan for Project W-314 describes the systems, processes and procedures for implementation of applicable risk management practices described in HNF-0842, Volume IV, Section 2.6, ''Risk Management''. This plan is tailored specifically for use by Project W-314.

Sustainable Design recognizes that products and processes are interdependent with the environmental, economic, and social systems surrounding them and implements measures to prevent an unsustainable compromise to these systems.

A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO reviewed the Social Security Administration's (SSA) final actions to ensure its year 2000 readiness, including the actions it took during the rollover period--December 30,1999, through January 3, 2000, as well as for the February 29 leap year date--to ensure a successful transition to the new century."

This report documents the results of the design verification performed on the Cask and Multiple Canister Over-pack (MCO) Helium Purge System. The helium purge system is part of the Spent Nuclear Fuel (SNF) Project Cask Loadout System (CLS) at 100K area. The design verification employed the ''Independent Review Method'' in accordance with Administrative Procedure (AP) EN-6-027-01.

The Systems Engineering Management Plan for Project W-314 has been prepared within the guidelines of HNF-SD-WM-SEMP-002, TWRS Systems Engineering Management Plan. The activities within this SEMP have been tailored, in accordance with the TWRS SEMP and DOE Order 430.1, Life Cycle Asset Management, to meet the needs of the project.

This document updates the operating scenario and plans for feed delivery to BNFL Inc. of retrieval and waste from single-shell tanks, and the overall process flowsheets for Phases 1 and 2 of the River Protection Project. The plans and flowsheets are updated with the most recent guidance from ORP and tank-by-tank inventory. The results provide the technical basis for the RTP-2 planning effort. Sensitivity cases were run to evaluate the effect of changes on key parameters.

This research project has three objectives. The first objective is to develop a capability to predict and optimize the ability of gels to reduce permeability to water more than that to oil or gas. The second objective is to develop procedures for optimizing blocking-agent placement in wells where hydraulic fractures cause channeling. The third objective is to develop procedures to optimize blocking-agent placement in naturally fractured reservoirs. This research project consists of three tasks, each of which addresses one of the above objectives. Work is directed at both injection wells and production wells and at vertical, horizontal, and highly deviated wells.