The objectives are to: Describe the Paducah Plant Earthquake Preparedness Program, characterize the earthquake threat for the region, describe the actions which should be taken by the plant population during and after an earthquake to reduce the risk of injury, and explain the program which exists to help the plant prepare for and rapidly respond/recover from the effects of an earthquake.

The training objectives are to: Describe the responsibilities of the Plant Emergency Squad during the damage assessment/abatement process and relate its importance to the protection and recovery of plant personnel following an earthquake.

The training objectives are: Describe the Local Emergency Squad's goals and responsibilities during the damage assessment process and relate its importance to the protection and recovery of plant personnel following an earthquake.

The training objectives are: differentiate between the various levels of damage caused to buildings and structures by an earthquake and classify them as to their safety of occupancy, extent of damage, and resources needed for recovery/repair.

The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further …

This document describes the generic modeling of the total effective dose equivalent (TEDE) to an individual in a population from a unit concentration of residual radioactive contamination. Radioactive contamination inside buildings and soil contamination are considered. Unit concentration TEDE factors by radionuclide, exposure pathway, and exposure scenario are calculated. Reference radiation exposure scenarios are used to derive unit concentration TEDE factors for about 200 individual radionuclides and parent-daughter mixtures. For buildings, these unit concentration factors list the annual TEDE for volume and surface contamination situations. For soil, annual TEDE factors are presented for unit concentrations of radionuclides in soil during residential use of contaminated land and the TEDE per unit total inventory for potential use of drinking water from a ground-water source. Because of the generic treatment of potentially complex ground-water systems, the annual TEDE factors for drinking water for a given inventory may only indicate when additional site data or modeling sophistication are warranted. Descriptions are provided of the models, exposure pathways, exposure scenarios, parameter values, and assumptions used. An analysis of the potential annual TEDE resulting from reference mixtures of residual radionuclides is provided to demonstrate application of the TEDE factors. 62 refs., 5 figs., 66 tabs.

An experimental program has been conducted to investigate flow instability in circular tubes under vertical down-flow conditions. The test section L/D ratio range was 86 to 270. The maximum test section surface heat flux was one million Btu/hr-ft{sup 2}. Over 1700 data points were obtained. The effect of flowrate, inlet temperature, exit pressure, and heat flux on the initiation of flow instability was determined. In addition, the data was used to evaluate various methods of predicting the onset of flow instability. Using the measured wall temperatures, surface temperatures and heat transfer coefficients have been obtained. Correlations for the heat transfer coefficient along the tube under both single and two phase conditions were developed.

The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

The Cobra Seal System consists of a passive fiber optic seal and verification equipment which have been modified to take advantage of current technology. The seal permits on-site verification without requiring replacement of the seal. The modifications to the original Cobra Seal System extended the maximum fiber optic cable length from 1 meter to 10 meters. This improvement allowed the Cobra Seal to be considered for application on dry irradiated fuel storage canisters at two Canadian facilities. These canisters are located in an exterior environment exposed to extreme weather conditions. This paper describe the application of the Cobra Seal to these canisters, a housing for the protection of the Cobra Seal body from the environment, and some preliminary results of the IAEA field tests. 4 refs.

An automated system for formatting documents provides the technical communicator with tools to increase productivity, provide consistent document appearance, and decrease hassle and error. This paper demonstrates such a system, which uses WordPerfect's styles and macros, and illustrates the keystrokes necessary to format procedures and tables. Levels of automation will be discussed, progressing from manual application of styles, to applying styles with macros, to repeating macros with the escape key and through a parent macro. 3 refs.

A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the US NRC's Nuclear Plant aging Research (NPAR) Program. For the study, the CRD system boundary includes the power and logic cabinets associated with the manual control rod movement, and the control rod mechanism itself. The aging-related degradation of the interconnecting cables and connectors and the rod position indicating system also were considered. This paper presents the results of that study pertaining to the electrical and instrumentation portions of the CRD system including ways to detect and mitigate system degradation.

Manual tank calibrations often have variabilities of both a random and systematic nature that often affect the quality of the data collected for determining accurate calibration equations. When performing the calibration run, data omissions and transcriptions often occur (forgetting to tare weigh the prover vessel or miswriting a displayed value). A computer can be used to minimize these errors associated with the logging of data. This paper describes a IBM compatible, portable computer based system, developed at the Savannah River Site (SRS), that was used to calibrate three tanks in the second quarter 1990. It received data directly from instrumentation such as Ruska differential pressure sensors and electronic balances, while prompting the technicians to perform the various steps in the calibration procedure. This automated system greatly improved the quality of data for calculating the calibration equation for each of these tanks over previous calibration runs.

Manual tank calibrations often have variabilities of both a random and systematic nature that often affect the quality of the data collected for determining accurate calibration equations. When performing the calibration run, data omissions and transcriptions often occur (forgetting to tare weigh the prover vessel or miswriting a displayed value). A computer can be used to minimize these errors associated with the logging of data. This paper describes a IBM compatible, portable computer based system, developed at the Savannah River Site (SRS), that was used to calibrate three tanks in the second quarter 1990. It received data directly from instrumentation such as Ruska differential pressure sensors and electronic balances, while prompting the technicians to perform the various steps in the calibration procedure. This automated system greatly improved the quality of data for calculating the calibration equation for each of these tanks over previous calibration runs.

This paper describes the development of standards for emergency operations computer systems for the US Department of Energy (DOE). The proposed DOE computer standards prescribe the necessary power and simplicity to meet the expanding needs of emergency managers. Standards include networked UNIX workstations based on the client server model and software that presents information graphically using icons and windowing technology. DOE standards are based on those of the computer industry although Proposed DOE is implementing the latest technology to ensure a solid base for future growth. A case of how these proposed standards are being implemented is also presented. The Savannah River Site (SRS), a DOE facility near Aiken, South Carolina is automating a manual information system, proven over years of development. This system is generalized as a model that can apply to most, if not all, Emergency Operations Centers. This model can provide timely and validated information to emergency managers. By automating this proven system, the system is made easier to use. As experience in the case study demonstrates, computers are only an effective information tool when used as part of a proven process.

A method to automate solution enrichment analysis by gamma-ray spectroscopy is being developed at Los Alamos National Laboratory. Both passive and x-ray fluorescence (XRF) analyses will be remotely performed to determine the amounts of {sup 235}U and total uranium in sample containers. A commercial laboratory robot will be used to process up to 40 batch and 8 priority samples in an unattended mode. Samples will be read by a bar-code reader to determine measurement requirements, then assayed by either or both of the gamma-ray and XRF instruments. The robot will be responsible for moving the sample containers and operating all shield doors and shutters. In addition to reducing hardware complexity, this feature will also allow manual operation of the instruments if the robot fails. This automated system will reduce personnel radiation exposure and increase the reliability and repeatability of the measurements.

In July 1983, the NRC ordered the shutdown of five boiling water reactors (BWR's) because of concerns about reliability of ultrasonic examination for detecting intergranular stress corrosion cracking (IGSCC). These concerns arose because of leaking piping at Niagara Mohawk's Nine Mile Point which was attributed to IGSCC. The leaks were detected shortly after completion of ultrasonic examinations of the piping. At that time, the Dupont plant manager at Savannah River (SR) directed that investigations be performed to determine if similar problems could exist in SR reactors. Investigation determined that all conditions believed necessary for the initiation and propagation of IGSCC in austenitic stainless steel exist in SR reactor process water (PW) systems. Sensitized, high carbon, austenitic stainless steel, a high purity water system with high levels of dissolved oxygen, and the residual stresses associated with welding during construction combine to provide the necessary conditions. A periodic UT inspection program is now in place to monitor the condition of the reactor PW piping systems. The program is patterned after NRC NUREG 0313, i.e., welds are placed in categories based on their history. Welds in upgraded or replacement piping are examined on a standard schedule (at least every five years) while welds …

A commercial teleoperated wheeled vehicle was fitted with a modified commercial spray/vacuum decontamination system to allow floor and wall decontamination of an existing process room in one of the chemical separations areas at the Savannah River Site (SRS). Custom end-of-arm tooling was designed to provide sufficient compliance for routine cleaning operations. An operator console was designed to allow complete control of the vehicle base and are movements as well as viewing operations via multiple television monitors. 3 refs.

This paper is a presentation to the International Professional Communication Conference on International English. Presidence is taken from the Royal Society of London in 1667 to purify and simplify the English language. Because English has become the most spoken language in the world, the case in herein made to make it plainer and more easily learned. Technical communications is stressed. (FSD).

A certification plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations has been prepared. An action matrix, checklists, a time schedule, and a resource commitment table have been included in the plan. These items identify what is required to achieve certification of the codes, the time table that this will be accomplished on, and the resources needed to support such an effort.

The Savannah River Site maintains a compilation of operating problems and equipment failures that have occurred in the fuel reprocessing and other areas in the form of computerized data banks. 14 refs., 25 figs.

Most of the progress made since September 1, 1989 is one of two types: programming or orgamzmg. In general Xpresslink has gained in a programming sense (more I/O blocks, new and revised operation screens, new key macros, broader historical trending), and the ladder has improved in an organizational sense. A database called '.CNTRL RM INFO' has been installed on the control room Mac hard disk in the Control Room folder in the Word Processors folder. This file should be updated regularly.

The National Energy Software Center (NESC) is the US Department of Energy's (DOE) software exchange and information center operated by Argonne National Laboratory for the DOE Office of Scientific and Technical Information. Software exchange and information center activities for the US Nuclear Regulatory Commission (NRC) are carried out with support from the NRC. In addition to information services, the Center offers two products--the program abstract and the program package.'' The abstract describes a computer program or data compilation, the problem it is intended to solve, the hardware required, and the material contained in the program package. The program package'' consists of the computer media containing the software and auxiliary files and machine-readable or hard-copy documentation. This paper discusses automating operations of the center.

Evidence has been found for tritium and neutron production in palladium and silicon stacks when pulsed with a high electric current. These palladium-silicon stacks consist of alternating layers of pressed palladium and silicon powder. A pulsed high electric current is thought to promote non equilibrium conditions important for tritium and neutron production. More than 2000 hours of neutron counting time has been accumulated in a underground, low background, environment with high efficiency counters (21%). Neutron emission has occurred as infrequent burst or as low level emission lasting for up to 20 hours. In eight of 30 cells, excess tritium greater than 3 sigma has been observed. In each of these measurements, with the powder system, the ratio of tritium detected to total integrated total neutrons inferred has been anomalously high. Recent cells have shown reproducible tritium generation at a level of about 0.5 nCi/hr. Several hydrogen and air control cells have been run with no anomalous excess tritium or neutron emission above background. A significant amount of the total palladium inventory (18%) has been checked for tritium contamination by three independent means. 12 refs., 6 figs., 2 tabs.

Over the last 25 years, the Savannah River Site (SRS) has developed a strong Software Quality Assurance (SQA) program. It provides the information and management controls required of a high quality auditable system. The SRS SQA program provides the framework to meet the requirements in increasing regulation.