Powered by Deep Web Technologies
Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Energy Facility Evaluation, Siting, Construction and Operation (New Hampshire)  

Broader source: Energy.gov [DOE]

The statute establishes a procedure for the review, approval, monitoring, and enforcement of compliance in the planning, siting, construction, and operation of energy facilities, including...

2

Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3  

SciTech Connect (OSTI)

This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-09-01T23:59:59.000Z

3

Removal site evaluation report for the Isotope Facilities at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This removal site evaluation (RmSE) report of the Isotope Facilities at Oak Ridge National Laboratory (ORNL) was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Isotopes Facility pose a substantial risk to human health or the environment and if remedial site evaluations (RSEs) or removal actions are required. The scope of the project included: (1) a review of historical evidence regarding operations and use of the facility; (2) interviews with facility personnel concerning current and past operating practices; (3) a site inspection; and (4) identification of hazard areas requiring maintenance, removal, or remedial actions. The results of RmSE indicate that no substantial risks exist from contaminants present in the Isotope Facilities because adequate controls and practices exist to protect human health and the environment. The recommended correction from the RmSE are being conducted as maintenance actions; accordingly, this RmSE is considered complete and terminated.

NONE

1996-07-01T23:59:59.000Z

4

Risk management study for the retired Hanford Site facilities. Volume 2, Risk evaluation work procedure for the retired Hanford Site facilities  

SciTech Connect (OSTI)

Risk from retired surplus facilities has always been assumed to be low at the Hanford Site as the facilities are inactive and have few potentials for causing an offsite hazardous material release. However,the fatal accident that occurred in the spring of 1992 in which an employee fell through a deteriorated roof at the 105-F Reactor Building has raised the possibility that retired facilities represent a greater risk than was originally assumed. Therefore, Westinghouse Hanford Company and the US Department of Energy management have determined that facility risk management strategies and programmatic plans should be reevaluated to assure risks are identified and appropriate corrective action plans are developed. To evaluate risk management strategies, accurate risk information about the current and projected condition of the facilities must be developed. This work procedure has been created to address the development of accurate and timely risk information. By using the evaluation results in this procedure, it will be possible to create a prioritized baseline for managing facility risk until all retired surplus facilities are demolished.

Coles, G.A.; Shultz, M.V.; Taylor, W.E.

1993-04-01T23:59:59.000Z

5

Site suitability and evaluation study for Minnegasco's proposed peat gasification facility  

SciTech Connect (OSTI)

In 1980, the Minnesota Gas Company (Minnegasco) submitted a proposal to the US Department of Energy entitled, A Feasibility Study - High BTU Gas from Peat. The proposal covered a feasibility study to assess the overall viability of designing, constructing, and operating a commercial facility for the production of high-BTU substitute natural gas (SNG) from Minnesota peat. On September 30, 1980, Minnegasco was awarded a grant by the Department of Energy to perform the proposed study. To complete the study, Minnegasco assembled a project team having a wide range of expertise. In addition, the State of Minnesota will participate in some parts of the study in an advisory capacity. The items to be investigated by the project team during the feasibility study include peat harvesting, dewatering, gasification process design, economic and risk assessment, site evaluation, environmental and socioeconomic matters. This report, the first of several to be submitted to Minnegasco by Ertec, has been prepared to outline the status of the site suitability and evaluation study. The purpose of this initial phase of the feasibility study was to identify and evaluate several potential sites in northeastern Minnesota. These sites will be studied in further detail to assess the economic and environmental feasibility of developing the proposed peat gasification facility described in Minnegasco's proposal. 33 figures, 12 tables.

Not Available

1981-03-01T23:59:59.000Z

6

Hazard ranking system evaluation of CERCLA inactive waste sites at Hanford: Volume 2: Engineered-facility sites (HISS data base)  

SciTech Connect (OSTI)

The purpose of this report is to formally document the assessment activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that address the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program for the cleanup of inactive waste sites. The DOE orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986. This methodology includes: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the Hazard Ranking System methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 13 refs.

Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.; Stenner, R.D.; Cramer, K.H.; Higley, K.A.

1988-10-01T23:59:59.000Z

7

Removal site evaluation report on the Tower Shielding Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This removal site evaluation report for the Tower Shielding Facility (TSF) at Oak Ridge National Laboratory was prepared to provide the Environmental Restoration Program with information necessary to evaluate whether hazardous and/or radiological contaminants in and around the Tower Shielding Facility pose a substantial risk to human health or the environment (i.e., a high probability of adverse effects) and if remedial site evaluations or removal actions are, therefore, required. The scope of the project included a review of historical evidence regarding operations and use of the facility; interviews with facility personnel concerning current and past operating practices; a site inspection; and identification of hazard areas requiring maintenance, removal, or remedial actions. Based an the findings of this removal site evaluation, adequate efforts are currently being made at the TSF to contain and control existing contamination and hazardous substances on site in order to protect human health and the environment No conditions requiring maintenance or removal actions to mitigate imminent or potential threats to human health and the environment were identified during this evaluation. Given the current conditions and status of the buildings associated with the TSF, this removal site evaluation is considered complete and terminated according to the requirements for removal site evaluation termination.

NONE

1996-09-01T23:59:59.000Z

8

Hazardous Waste Facilities Siting (Connecticut)  

Broader source: Energy.gov [DOE]

These regulations describe the siting and permitting process for hazardous waste facilities and reference rules for construction, operation, closure, and post-closure of these facilities.

9

Geohydrologic evaluation for the 200 Area Effluent Treatment Facility State-Approved Land Disposal Site: Addendum to WAC 173-240 Engineering Report  

SciTech Connect (OSTI)

This document provides a geohydrologic evaluation for the disposal of liquid effluent from the 200 Area Effluent Treatment Facility (ETF) at the Hanford Site. This work forms an addendum to the engineering report that supports the completion of the ETF.

Ballantyne, N.A.

1993-08-01T23:59:59.000Z

10

Evaluation of the 183-D Water Filtration Facility for Bat Roosts and Development of a Mitigation Strategy, 100-D Area, Hanford Site  

SciTech Connect (OSTI)

The 183-D Water Filtration Facility is located in the 100-D Area of the Hanford Site, north of Richland, Washington. It was used to provide filtered water for cooling the 105-D Reactor and supplying fire-protection and drinking water for all facilities in the 100-D Area. The facility has been inactive since the 1980s and is now scheduled for demolition. Therefore, an evaluation was conducted to determine if any part of the facility was being used as roosting habitat by bats.

Lindsey, C. T.; Gano, K. A.; Lucas, J. G.

2011-03-07T23:59:59.000Z

11

Montana Major Facility Siting Act (Montana)  

Broader source: Energy.gov [DOE]

The Montana Major Facility Siting Act aims to protect the environment from unreasonable degradation caused by irresponsible siting of electric transmission, pipeline, and geothermal facilities. The...

12

Canyon Facilities - Hanford Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to someone6Energy,MUSEUM DISPLAY STATUS4Tours SHARE ToursCanyon Facilities

13

Site maps and facilities listings  

SciTech Connect (OSTI)

In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities.

Not Available

1993-11-01T23:59:59.000Z

14

Hazardous Waste Facility Siting Program (Maryland)  

Broader source: Energy.gov [DOE]

The Hazardous Waste Facilities Siting Board is responsible for overseeing the siting of hazardous waste facilities in Maryland, and will treat hazardous waste facilities separately from low-level...

15

Washington Energy Facility Site Evalutation Council - Generalized...  

Open Energy Info (EERE)

Washington Energy Facility Site Evalutation Council - Generalized Siting Process Jump to: navigation, search OpenEI Reference LibraryAdd to library Chart: Washington Energy...

16

Facilities evaluation report  

SciTech Connect (OSTI)

The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities.

Sloan, P.A.; Edinborough, C.R.

1992-04-01T23:59:59.000Z

17

Management of Decommissioning on a Multi-Facility Site  

SciTech Connect (OSTI)

The management of the decommissioning of multi-facility sites may be inadequate or inappropriate if based on approaches and strategies developed for sites consisting of only a single facility. The varied nature of activities undertaken, their interfaces and their interdependencies are likely to complicate the management of decommissioning. These issues can be exacerbated where some facilities are entering the decommissioning phase while others are still operational or even new facilities are being built. Multi-facility sites are not uncommon worldwide but perhaps insufficient attention has been paid to optimizing the overall site decommissioning in the context of the entire life cycle of facilities. Decommissioning management arrangements need to be established taking a view across the whole site. A site-wide decommissioning management system is required. This should include a project evaluation and approval process and specific arrangements to manage identified interfaces and interdependencies. A group should be created to manage decommissioning across the site, ensuring adequate and consistent practices in accordance with the management system. Decommissioning management should be aimed at the entire life cycle of facilities. In the case of multi facility sites, the process becomes more complex and decommissioning management arrangements need to be established with a view to the whole site. A site decommissioning management system, a group that is responsible for decommissioning on site, a site project evaluation and approval process and specific arrangements to manage the identified interfaces are key areas of a site decommissioning management structure that need to be addressed to ensure adequate and consistent decommissioning practices. A decommissioning strategy based on single facilities in a sequential manner is deemed inadequate.

Laraia, Michele; McIntyre, Peter; Visagie, Abrie [IAEA, Vienna and NECSA (South Africa)

2008-01-15T23:59:59.000Z

18

Global Environment Facility Evaluation Office  

E-Print Network [OSTI]

Global Environment Facility Evaluation Office PROTECTED AREAS AND AVOIDED DEFORESTATION #12;Protected Areas and Avoided Deforestation: An Econometric Evaluation - i - TABLE OF CONTENTS 1................................................................................4 3.3 ESTIMATED EFFECTS OF PROTECTED AREAS ON DEFORESTATION

Pfaff, Alex

19

Independent Oversight Review, Savannah River Site Tritium Facilities...  

Energy Savers [EERE]

Savannah River Site Tritium Facilities - December 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - December 2012 December 2012 Review of Site...

20

Preliminary siting characterization Salt Disposition Facility - Site B  

SciTech Connect (OSTI)

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

Wyatt, D.

2000-01-04T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Independent Oversight Review, Savannah River Site Tritium Facilities...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

June 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - June 2012 June 2012 Review of the Savannah River Site Tritium Facilities Implementation...

22

Site Visit Report, Hanford Waste Encapsulation Storage Facility...  

Office of Environmental Management (EM)

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 January 2011 Hanford...

23

Removal site evaluation report L-area rubble pile (131-3L) gas cylinder disposal facility (131-2L)  

SciTech Connect (OSTI)

This Removal Site Evaluation Report (RSER) is prepared in accordance with Sections 300.410 and 300.415 of the National Contingency Plan and Section XIV of the Savannah River Site (SRS) Federal Facility Agreement (FFA). The purpose of this investigation is to report information concerning conditions at the L-Area Rubble Pile (LRP) (131-3L) and the L-Area Gas Cylinder Disposal Facility (LGCDF) (131- 2L) sufficient to assess the threat posed to human health and the environment. This investigation also assesses the need for additional Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) actions. The scope of this investigation included a review of files, limited sampling efforts, and visits to the area. An investigation of the LRP (1131-3L) indicates the presence of semi volatile organic compounds (SVOCs), volatile organic compounds (VOCs), metals, and asbestos. Potential contaminants in the waste piles could migrate into the secondary media (soils and groundwater), and the presence of some of the contaminants in the piles poses an exposure threat to site works. The Department of Energy (DOE), United States Environmental Protection Agency (EPA) and South Carolina Department of Health and Environmental Control (SCDHEC) discussed the need for a removal action at the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation (RFI/RI) work plan scoping meetings on the waste unit, and agreed that the presence of the waste piles limits the access to secondary media for sampling, and the removal of the piles would support future characterization of the waste unit. In addition, the DOE, EPA, and SCDHEC agreed that the proposed removal action for the LRP (131-3L) would be documented in the RFI/RI work plan. The LGCDF (131-2L) consists of a backfilled pit containing approximately 28 gas cylinders. The gas cylinders were supposed to have been vented prior to burial; however, there is a potential that a number of the cylinders are still pressurized. (Abstract Truncated)

Palmer, E.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Mason, J.T.

1997-10-01T23:59:59.000Z

24

Regional analysis of energy facility siting  

SciTech Connect (OSTI)

This paper has examined some of the regional environmental parameters of energy facility siting, with emphasis on air quality impacts. An example of a siting optimization study was presented, and it was shown how difficult it presently is to specify an environmental objective function that is universally applicable. The importance of regional background effects was discussed, and long-range transport models were used to analyze the relative importance of local and long-range impacts.

Lipfert, F W; Meier, P M; Kleinman, L I

1980-01-01T23:59:59.000Z

25

National Ignition Facility Project Site Safety Program  

SciTech Connect (OSTI)

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES&H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES&H requirements are consistent with the ''LLNL ES&H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B.

Dun, C

2003-09-30T23:59:59.000Z

26

Nuclear facility decommissioning and site remedial actions  

SciTech Connect (OSTI)

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01T23:59:59.000Z

27

Nuclear facility decommissioning and site remedial actions  

SciTech Connect (OSTI)

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01T23:59:59.000Z

28

Central Facilities Area Sewage Lagoon Evaluation  

SciTech Connect (OSTI)

The Central Facilities Area (CFA), located in Butte County, Idaho, at the Idaho National Laboratory has an existing wastewater system to collect and treat sanitary wastewater and non-contact cooling water from the facility. The existing treatment facility consists of three cells: Cell #1 has a surface area of 1.7 acres, Cell #2 has a surface area of 10.3 acres, and Cell #3 has a surface area of 0.5 acres. If flows exceed the evaporative capacity of the cells, wastewater is discharged to a 73.5-acre land application site that uses a center-pivot irrigation sprinkler system. As flows at CFA have decreased in recent years, the amount of wastewater discharged to the land application site has decreased from 13.64 million gallons in 2004 to no discharge in 2012 and 2013. In addition to the decreasing need for land application, approximately 7.7 MG of supplemental water was added to the system in 2013 to maintain a water level and prevent the clay soil liners in the cells from drying out and “cracking.” The Idaho National Laboratory is concerned that the sewage lagoons and land application site may be oversized for current and future flows. A further concern is the sustainability of the large volumes of supplemental water that are added to the system according to current operational practices. Therefore, this study was initiated to evaluate the system capacity, operational practices, and potential improvement alternatives, as warranted.

Mark R. Cole

2013-12-01T23:59:59.000Z

29

Application of the SELECS methodology to evaluate socioeconomic and environmental impacts of commercial-scale coal liquefaction plants at six potential sites in Kentucky. Final report from the study on development of environmental guidelines for the selection of sites for fossil energy conversion facilities  

SciTech Connect (OSTI)

Environmental and socioeconomic impacts likely to occur during the operational phase of two coal liquefaction processes have been evaluated with SELECS (Site Evaluation for Energy Conversion Systems) for each of six potential sites in Kentucky for commercial scale facilities capable of processing about 26,000 tons of coal per stream day. The processes considered in this evaluation are SRC-I, a direct liquefaction route with solid boiler fuel as the principal product, and Coal-to-Methanol-to-Gasoline, an indirect liquefaction route with transportation fuel as the primary product. For comparative purposes, the impacts of a 2-gigawatt coal-fired steam-electric power plant (with coal requirements comparable to the liquefaction facilities) and an automobile parts manufacturing plant (with employment requirements of 849, comparable to the liquefaction facilities) have also been evaluated at each site. At each site, impacts have been evaluated for one or two nearby cities or towns and four to six counties where significant impacts might be expected. The SELECS methodology affords a well-organized and efficient approach to collecting and assessing a large volume of data needed to comprehensively determine the potential socioeconomic and environmental impacts resulting from the implementation of commercial scale synfuel and other energy conversion facilities. This study has also shown that SELECS is equally applicable to determine the impacts of other facilities, such as automobile parts manufacturing. In brief, the SELECS methodology serves the purpose of objectively screening sites in order to choose one at which adverse impacts will be least, and/or to determine what aspect of a proposed facility might be modified to lessen impacts at a specific site.

Northrop, G. M.; D'Ambra, C. A.

1980-11-01T23:59:59.000Z

30

Method for siting detectors within a facility  

DOE Patents [OSTI]

A method, system and article of manufacture of siting one or more detectors in a facility represented with zones are provided. Signals S.sub.i,j representing an effect in zone j in response to a release of contaminant in zone i for one or more flow conditions are provided. A candidate architecture has one or more candidate zones. A limiting case signal is determined for each flow condition for multiple candidate architectures. The limiting case signal is a smallest system signal of multiple system signals associated with a release in a zone. Each system signal is a maximum one of the signals representing the effect in the candidate zones from the release in one zone for the flow condition. For each candidate architecture, a robust limiting case signal is determined based on a minimum of the limiting case signals. One candidate architecture is selected based on the robust limiting case signals.

Gleason, Nathaniel Jeremy Meyer (Livermore, CA)

2007-12-11T23:59:59.000Z

31

Independent Oversight Review, Hanford Site K-West Annex Facility...  

Office of Environmental Management (EM)

Facility - April 2014 April 2014 Review of the Hanford Site K-West Annex Facility Construction Quality The U.S. Department of Energy Office of Enforcement and Oversight...

32

Site selection for the Salt Disposition Facility at the Savannah River Site  

SciTech Connect (OSTI)

The purpose of this report is to identify, assess, and rank potential sites for the proposed Salt Disposition Facility (SDF) at the Savannah River Site.

Bowers, J.A.

2000-01-03T23:59:59.000Z

33

Sensor test facilities and capabilities at the Nevada Test Site  

SciTech Connect (OSTI)

Sandia National Laboratories has recently developed two major field test capabilities for unattended ground sensor systems at the Department of energy`s Nevada Test Site (NTS). The first capability utilizes the NTS large area, varied terrain, and intrasite communications systems for testing sensors for detecting and tracking vehicular traffic. Sensor and ground truth data can be collected at either of two secure control centers. This system also includes an automated ground truth capability that consists of differential Global Positioning Satellite (GPS) receivers on test vehicles and live TV coverage of critical road sections. Finally there is a high-speed, secure computer network link between the control centers and the Air Force`s Theater Air Command and Control Simulation Facility in Albuquerque NM. The second capability is Bunker 2-300. It is a facility for evaluating advanced sensor systems for monitoring activities in underground cut-and-cover facilities. The main part of the facility consists of an underground bunker with three large rooms for operating various types of equipment. This equipment includes simulated chemical production machinery and controlled seismic and acoustic signal sources. There has been a thorough geologic and electromagnetic characterization of the region around the bunker. Since the facility is in a remote location, it is well-isolated from seismic, acoustic, and electromagnetic interference.

Boyer, W.B.; Burke, L.J.; Gomez, B.J.; Livingston, L.; Nelson, D.S.; Smathers, D.C.

1996-12-31T23:59:59.000Z

34

Brownfields vs greenfields -- Considerations for facility siting  

SciTech Connect (OSTI)

Since the promulgation of the ``Superfund`` component of the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) in 1980, the sale and acquisition of industrial properties (brownfields) have been sluggish at best or non-existent where significant environmental contamination has been detected. As a result, many urban areas contain numerous brownfield sites that lie vacant due to the presence or the potential existence of contaminants. Wary of the potential remedial costs associated with brownfield sites, industry has focused its development on greenfield areas -- undeveloped areas where the potential for previous environmental contamination is remote. This paper evaluates the impact of the development of these brownfield areas from both an environmental and economic perspective. Critical to this evaluation is the impact of brownfield development as it relates to urban areas. Mature, heavily developed urban areas are usually unable to offer substantial greenfield areas, and as a result, have suffered a declining tax base, as employment opportunities are shifted beyond city limits. This paper also explores the advantages and disadvantages of developing brownfield versus greenfield areas, including issues such as: infrastructure, proximity to public transportation, public acceptance, and zoning and permitting. Furthermore, this paper provides an overview of current and pending legislation from both the federal government and various state agencies with regard to incentives being offered for the development of brownfield sites.

Hale, D.W.; Kaiding, D.C.; DeMaria, M.J. [Blasland, Bouck and Lee, Inc., Syracuse, NY (United States)

1995-12-31T23:59:59.000Z

35

Summary and evaluation of existing geological and geophysical data near prospective surface facilities in Midway Valley, Yucca Mountain Project, Nye County, Nevada; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

Midway Valley, located at the eastern base of the Yucca Mountain in southwestern Nevada, is the preferred location of the surface facilities for the potential high-level nuclear waste repository at Yucca Mountain. One goal in siting these surface facilities is to avoid faults that could produce relative displacements in excess of 5 cm in the foundations of the waste-handling buildings. This study reviews existing geologic and geophysical data that can be used to assess the potential for surface fault rupture within Midway Valley. Dominant tectonic features in Midway Valley are north-trending, westward-dipping normal faults along the margins of the valley: the Bow Ridge fault to the west and the Paintbrush Canyon fault to the east. Published estimates of average Quaternary slip rates for these faults are very low but the age of most recent displacement and the amount of displacement per event are largely unknown. Surface mapping and interpretive cross sections, based on limited drillhole and geophysical data, suggest that additional normal faults, including the postulated Midway Valley fault, may exist beneath the Quaternary/Tertiary fill within the valley. Existing data, however, are inadequate to determine the location, recency, and geometry of this faulting. To confidently assess the potential for significant Quaternary faulting in Midway Valley, additional data are needed that define the stratigraphy and structure of the strata beneath the valley, characterize the Quaternary soils and surfaces, and establish the age of faulting. The use of new and improved geophysical techniques, combined with a drilling program, offers the greatest potential for resolving subsurface structure in the valley. Mapping of surficial geologic units and logging of soil pits and trenches within these units must be completed, using accepted state-of-the-art practices supported by multiple quantitative numerical and relative age-dating techniques.

Gibson, J.D. [Sandia National Labs., Albuquerque, NM (United States); Swan, F.H.; Wesling, J.R.; Bullard, T.F.; Perman, R.C.; Angell, M.M.; DiSilvestro, L.A. [Geomatrix Consultants, Inc., San Francisco, CA (United States)

1992-01-01T23:59:59.000Z

36

Massachusetts Hazardous Waste Facility Siting Act (Massachusetts)  

Broader source: Energy.gov [DOE]

This Act establishes the means by which developers of proposed hazardous waste facilities will work with the community in which they wish to construct a facility. When the intent to construct,...

37

Story Road Landfill Solar Site Evaluation: San Jose  

Broader source: Energy.gov [DOE]

This report describes the findings of a solar site evaluation conducted at the Story Road Landfill (Site) in the City of San Jose, California (City). This evaluation was conducted as part of a larger study to assess solar potential at multiple public facilities within the City.

38

Water Pollution Control Plant Solar Site Evaluation: San José  

Broader source: Energy.gov [DOE]

This report describes the findings of a solar site evaluation conducted at the San Jose/Santa Clara Water Pollution Control Plant (Site) in the City of San Jose, California (City). This evaluation was conducted as part of a larger study to assess solar potential at multiple public facilities within the City.

39

City of Gainesville- Public Facilities Siting  

Broader source: Energy.gov [DOE]

The City of Gainesville requires the design process for public facilities within city limits to take into consideration current and future solar access. In addition, regulated trees may be removed...

40

Uranium Processing Facility Site Readiness Subproject Completed...  

National Nuclear Security Administration (NNSA)

(NNSA) commitment to complete UPF by 2025 and move out of the aging 9212 building facilities it is currently using for a cost not to exceed 6.5 billion. UPF is the...

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Assessor Training Evaluating OnSite Reports  

E-Print Network [OSTI]

NVLAP Assessor Training Evaluating OnSite Reports and Corrective Actions #12;Assessor Training 2009Site Report form ·NVLAP OnSite Assessment Review form #12;Assessor Training 2009: Evaluating OnSite Reports · Nonconformities cited #12;Assessor Training 2009: Evaluating OnSite Reports & Corrective Actions 44 Evaluating

42

evaluation o TAD sites p  

E-Print Network [OSTI]

% 10% 20% 30% 40% 50% D tot par T com ma T T crim com dis des 20 evaluation o ocument im TAD sites p ng, and mon ulation. Fou St. Croix trib dels: Milwau Any New Cri After TAD Di 18% Within 1 The University of Kit R. Van Stelle, http:// TAD particip minal convic mmitted a n scharge, bett scribed

Sheridan, Jennifer

43

Closure End States for Facilities, Waste Sites, and Subsurface Contamination  

SciTech Connect (OSTI)

The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE’s Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation & decommissioning (D&D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites.

Gerdes, Kurt D.; Chamberlain, Grover S.; Wellman, Dawn M.; Deeb, Rula A.; Hawley, Elizabeth L.; Whitehurst, Latrincy; Marble, Justin

2012-11-21T23:59:59.000Z

44

Quality Services: Solid Wastes, Part 361: Siting of Industrial Hazardous Waste Facilities (New York)  

Broader source: Energy.gov [DOE]

These regulations describe the siting of new industrial hazardous waste facilities located wholly or partially within the State. Industrial hazardous waste facilities are defined as facilities used...

45

On-Site Disposal Facility Inspection Report  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawandaUniversity21 theB29.1y8947.1 09/13

46

On-Site Disposal Facility Inspection Report  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawandaUniversity21 theB29.1y8947.1

47

Federal Facilities Compliance Act, Draft Site Treatment Plan: Background Volume, Part 2, Volume 1  

SciTech Connect (OSTI)

This Draft Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed include: purpose and scope of the plan; site history and mission; draft plant organization; waste minimization; waste characterization; preferred option selection process; technology for treating low-level radioactive wastes and TRU wastes; future generation of mixed waste streams; funding; and process for evaluating disposal issues in support of the site treatment plan.

NONE

1994-08-31T23:59:59.000Z

48

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31T23:59:59.000Z

49

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01T23:59:59.000Z

50

ANNUAL COMPREHENSIVE SITE COMPLIANCE EVALUATION  

E-Print Network [OSTI]

...........................................................................................................12 3.1 REVIEW OF EXISTING BEST MANAGEMENT PRACTICES of Best Management Practices LIST OF FIGURES Figure 1-1 Facility Location Map Figure 1-2 Facility Plan ........................................................................................................................2 2.3 STORM WATER SAMPLING

51

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SURFACE EXPLORATORY STUDIES FACILITY  

SciTech Connect (OSTI)

This DIE applies to the surface facilities component of the Yucca Mountain Site Characterization Project (W) ESF. The ESF complex-including surface and subsurface accommodations--encompasses an area that is approximately six miles wide and nine miles long (approximately 30,000 acres total) (United States Department of Energy [DOE] 1997, p. 9.04). It is located on federally withdrawn lands, near the southwest border of the Nevada Test Site (NTS) in southern Nevada (DOE 1997, p. 9.04). Site characterization activities are conducted within the subsurface ESF to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. Most ESF surface facilities are located within the Conceptual Controlled Area Boundary (CCAB) (DOE 1997, p. 9.04), with the exception of the southeastern most portions of the H-Road and the Water Supply System. Various SBT activities are also conducted throughout the Yucca Mountain region as a part of the overall site-characterization effort. In general, the DIE for SBT Activities (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 1998a) evaluates activities associated with SBT. Potential test-to-test interference and waste isolation impacts associated with SBT activities are also evaluated in CRWMS M&O (1998a).

C.J. Byrne

2000-07-25T23:59:59.000Z

52

Guidelines for Evaluation of Nuclear Facility Training Programs  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Guidelines for Evaluation of Nuclear Facility Training Programs establish objectives and criteria for evaluating nuclear facility training programs. The guidance in this standard provides a framework for the systematic evaluation of training programs at nuclear facilities and is based, in part, on established criteria for Technical Safety Appraisals, Tiger Team Assessments, commercial nuclear industry evaluations, and the DOE Training Accreditation Program.

1995-11-22T23:59:59.000Z

53

Site Selection for the Salt Disposition Facility at the Savannah River Site  

SciTech Connect (OSTI)

A site selection study was conducted to identify a suitable location for the construction and operation of a new Salt Disposition Facility (SDF) at the Savannah River Site (SRS). The facility to be sited is a single processing facility and support buildings that could house either of three technology alternatives being developed by the High Level Waste Systems Engineering Team: Small Tank Tetraphenylborate Precipitation, Crystalline Silicotitanate Non-Elutable Ion Exchange or Caustic Side Solvent Extraction. A fourth alternative, Direct Disposal in grout, is not part of the site selection study because a location has been identified that is unique to this technology (i.e., Z-Area). Facility site selection at SRS is a formal, documented process that seeks to optimize siting of new facilities with respect to facility-specific engineering requirements, sensitive environmental resources, and applicable regulatory requirements. In this manner, the prime objectives of cost minimization, environmental protection, and regulatory compliance are achieved. The results from this geotechnical characterization indicated that continued consideration be given to Site B for the proposed SDF. Suitable topography, the lack of surface hydrology and floodplain issues, no significant groundwater contamination, the presence of minor soft zones along the northeast portion of footprint, and no apparent geological structure in the Gordon Aquitard support this recommendation.

Gladden, J.B.; Rueter, K.J.; Morin, J.P.

2000-11-15T23:59:59.000Z

54

Lessons learned -- a comparison of the proposed on-site waste management facilities at the various Department of Energy sites  

SciTech Connect (OSTI)

The Department of Energy Sites (DOE) are faced with the challenge of managing several categories of waste generated from past or future cleanup activities, such as 11(e)2 byproduct material, low-level radioactive (LL), low-level radioactive mixed (LLM), transuranic (TRU), high level radioactive (HL), and hazardous waste (HW). DOE must ensure safe and efficient management of these wastes while complying with all applicable federal and state laws. Proposed waste management strategies for the EM-40 Environmental Restoration (ER) program at these sites indicate that on-site disposal is becoming a viable option. For purposes of this paper, on-site disposal cells managed by the EM-40 program at Hanford, Weldon Spring, Fernald Environmental Management Project (FEMP) and Rocky Flats were compared. Programmatic aspects and design features were evaluated to determine what comparisons can be made, and to identify benefits lessons learned that may be applicable to other sites. Based on comparative analysis, it can be concluded that the DOE EM-40 disposal cells are very unique. Stakeholders played a major role in the decision to locate the various DOE on-site disposal facilities. The disposal cells will be used to manage 11(e)2 by-product materials, LL, LLM, and/or HLW. The analysis further suggests that the design criteria are comparable. Lessons learned relative to the public involvement activities at Weldon Spring, and the design approach at Hanford should be considered when planning future on-site disposal facilities at DOE sites. Further, a detailed analysis of progress made at Hanford should be evaluated for application at sites such as Rocky Flats that are currently planning on-site disposal facilities.

Ciocco, J. [Dept. of Energy, Germantown, MD (United States); Singh, D. [Booz Allen and Hamilton, Germantown, MD (United States); Survochak, S. [DOE RFETS, Golden, CO (United States); Elo, M. [Burns and Roe, Germantown, MD (United States)

1996-12-31T23:59:59.000Z

55

EIS-0089: PUREX Plant and Uranium Oxide Plant Facilities, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of resumption of operations of the PUREX/Uranium Oxide facilities at the Hanford Site to produce plutonium and other special nuclear materials for national defense needs.

56

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities  

SciTech Connect (OSTI)

This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs.

Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

1986-01-01T23:59:59.000Z

57

Descriptions of representative contaminated sites and facilities within the DOE complex  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has initiated efforts to prepare a Programmatic Environmental Impact Statement (PEIS) that will analyze the existing environmental restoration and waste management program and evaluate alternatives for an integrated program. The alternatives being evaluated include (1) a {open_quotes}No Action{close_quotes} alternative as required by the National Environmental Policy Act (NEPA), (2) an Applicable, Relevant, and Appropriate Requirements (ARAR)-driven alternative, (3) a land-use-driven alternative, (4) a health-risk-driven alternative, and (5) a combination land-use and health-risk-driven alternative. The analytical approach being taken to evaluate each of these alternatives is to perform a remedial engineering analysis and human health and ecosystem effects analyses on every contaminated site and facility in the DOE complex. One of Pacific Northwest Laboratory`s (PNL) roles in this approach has been to compile the source term and environmental setting data needed to drive each of these analyses. To date, over 10,000 individual contaminated sites and facilities located throughout the DOE complex of installations have been identified and at least some minimal data compiled on each. The PEIS analyses have been appreciably simplified by categorizing all of these contaminated sites and facilities into six broad categories: (1) contaminated buildings, (2) contaminated soils, (3) solid waste sites (e.g., burial grounds), (4) liquid containment structures (e.g., tanks), (5) surface water sites, and (6) contaminated groundwater sites. A report containing a complete description of each of these thousands of contaminated sites and facilities would be tremendously large and unwildy, as would separate reports describing the application of the analytical methodologies to each.

Short, S.M.; Buck, J.W.; Clark, L.L.; Fletcher, J.F.; Glantz, C.S.; Holdren, G.R.; Huesties, L.R.; Williams, M.D. [Pacific Northwest Lab., Richland, WA (United States); Oates, L. [ICF, Richland, WA (United States)] [and others

1994-10-01T23:59:59.000Z

58

Federal Facilities Compliance Act, Conceptual Site Treatment Plan. Part 1  

SciTech Connect (OSTI)

This Conceptual Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed in this document include: general discussion of the plan, including the purpose and scope; technical aspects of preparing plans, including the rationale behind the treatability groupings and a discussion of characterization issues; treatment technology needs and treatment options for specific waste streams; low-level mixed waste options; TRU waste options; and future waste generation from restoration activities.

NONE

1993-10-29T23:59:59.000Z

59

DETERMINATION OF IMPORTANCE EVALUATION FOR THE SUBSURFACE EXPORATORY STUDIES FACILITY  

SciTech Connect (OSTI)

This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), the Enhanced Characterization of the Repository Block (ECRB) East-West Cross Drift Starter Tunnel (to approximate ECRB Station 0+26 m), and ancillary test and operation support areas in the TS Loop. This evaluation applies to the construction, operation, and maintenance of these excavations. A more detailed description of these items is provided in Section 6.0. Testing activities are not evaluated in this DIE. Certain construction activities with respect to testing activities are evaluated; but the testing activities themselves are not evaluated. The DIE for ESF Subsurface Testing Activities (BAJ3000000-01717-2200-00011 Rev 01) (CRWMS M&O 1998a) evaluates Subsurface ESF Testing activities. The construction, operation, and maintenance of the TS Loop niches and alcove slot cuts is evaluated herein and is also discussed in CRWMS M&O 1998a. The construction, operation, and maintenance of the Busted Butte subsurface test area in support of the Unsaturated Zone (UZ) Transport Test is evaluated in CRWMS M&O 1998a. Potential test-to-test interference and the waste isolation impacts of testing activities are evaluated in the ESF Subsurface Testing Activities DIE and other applicable evaluation(s) for the Job Package (JP), Test Planning Package (TPP), and/or Field Work Package (FWP). The objectives of this DIE are to determine whether the Subsurface ESF TS Loop and associated excavations, including activities associated with their construction and operation, potentially impact site characterization testing or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified. The validity and veracity of the individual tests, including data collection, are the responsibility of the assigned Principal Investigator(s) (PIs) and are not evaluated in this DIE.

W.J. Clark

1999-06-28T23:59:59.000Z

60

Nuclear facility decommissioning and site remedial actions: a selected bibliography  

SciTech Connect (OSTI)

This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

1982-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Comparison of Candidate Sites for installation of Landfill facility at Ignalina NPP Site Using Fuzzy Logic Approach  

SciTech Connect (OSTI)

There is only one nuclear power plant in Lithuania - Ignalina NPP (Nuclear Power Plant). Two similar units with installed capacity of 1500 MW (each) were commissioned in 1983 and 1987 respectively. But the first Unit of Ignalina NPP was finally shutdown December 31, 2004, and second Unit is planned to be shutdown before 2010. Operational radioactive waste of different activities is generated at Ignalina NPP. After closure of INPP a waste from decommissioning should be managed also. According to Lithuanian regulatory requirements (1) the waste depending on the activity must be managed in different ways. In compliance with this Regulation very low-level radioactive waste (VLLW) could be disposed of in a Landfill facility. In such case very simple engineered barriers are required. A cap on the top of the repository is necessary from long-term safety point of view. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components: the site, the disposal facility and the waste form. The basic objective of the siting process is to select a suitable site for disposal and demonstrate that this site has characteristics which provide adequate isolation of radionuclides from the biosphere for desired periods of time. The methodology and results on evaluation and comparison of two candidate sites intended for construction of Landfill facility at Ignalina NPP site are presented in the paper. Criteria for comparison are based on the IAEA (International Atomic Energy Agency) recommendations (2). Modeling of the radionuclide releases has been performed using ISAM (Improving of Safety Assessment Methodologies for Near Surface Disposal facilities) methodology (3). For generalization of the information and elaboration of the recommendations Fuzzy Logic approach was used (4). (authors)

Poskas, P.; Kilda, R. [Lithuanian Energy Institute, Kaunas (Lithuania); Poskas, G. [Vytautas Magnus University, Kaunas (Lithuania)

2008-07-01T23:59:59.000Z

62

Design and evaluation guidelines for Department of Energy facilities subjected to natural phenomena hazards  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the DOE Natural Phenomena Hazards Panel have developed uniform design and evaluation guidelines for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of the guidelines is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. The guidelines apply to both new facilities (design) and existing facilities (evaluation, modification, and upgrading). The intended audience is primarily the civil/structural or mechanical engineers conducting the design or evaluation of DOE facilities. The likelihood of occurrence of natural phenomena hazards at each DOE site has been evaluated by the DOE Natural Phenomena Hazard Program. Probabilistic hazard models are available for earthquake, extreme wind/tornado, and flood. Alternatively, site organizations are encouraged to develop site-specific hazard models utilizing the most recent information and techniques available. In this document, performance goals and natural hazard levels are expressed in probabilistic terms, and design and evaluation procedures are presented in deterministic terms. Design/evaluation procedures conform closely to common standard practices so that the procedures will be easily understood by most engineers. Performance goals are expressed in terms of structure or equipment damage to the extent that: (1) the facility cannot function; (2) the facility would need to be replaced; or (3) personnel are endangered. 82 refs., 12 figs., 18 tabs.

Kennedy, R.P. (Structural Mechanics Consulting, Inc., Yorba Linda, CA (USA)); Short, S.A. (ABB Impell Corp., Mission Viejo, CA (USA)); McDonald, J.R. (Texas Tech Univ., Lubbock, TX (USA)); McCann, M.W. Jr. (Benjamin (J.R.) and Associates, Inc., Mountain View, CA (USA)); Murray, R.C. (Lawrence Livermore National Lab., CA (USA)); Hill, J.R. (USDOE Assistant Secretary for Environment, Safety, and He

1990-06-01T23:59:59.000Z

63

Planning Tool for Strategic Evaluation of Facility Plans - 13570  

SciTech Connect (OSTI)

Savannah River National Laboratory (SRNL) has developed a strategic planning tool for the evaluation of the utilization of its unique resources for processing and research and development of nuclear materials. The Planning Tool is a strategic level tool for assessing multiple missions that could be conducted utilizing the SRNL facilities and showcasing the plan. Traditional approaches using standard scheduling tools and laying out a strategy on paper tended to be labor intensive and offered either a limited or cluttered view for visualizing and communicating results. A tool that can assess the process throughput, duration, and utilization of the facility was needed. SRNL teamed with Newport News Shipbuilding (NNS), a division of Huntington Ingalls Industries, to create the next generation Planning Tool. The goal of this collaboration was to create a simulation based tool that allows for quick evaluation of strategies with respect to new or changing missions, and clearly communicates results to the decision makers. This tool has been built upon a mature modeling and simulation software previously developed by NNS. The Planning Tool provides a forum for capturing dependencies, constraints, activity flows, and variable factors. It is also a platform for quickly evaluating multiple mission scenarios, dynamically adding/updating scenarios, generating multiple views for evaluating/communicating results, and understanding where there are areas of risks and opportunities with respect to capacity. The Planning Tool that has been developed is useful in that it presents a clear visual plan for the missions at the Savannah River Site (SRS). It not only assists in communicating the plans to SRS corporate management, but also allows the area stakeholders a visual look at the future plans for SRS. The design of this tool makes it easily deployable to other facility and mission planning endeavors. (authors)

Magoulas, Virginia; Cercy, Michael [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Hall, Irin [Newport News Shipbuilding, 4101 Washington Ave., Newport News, VA 23607 (United States)] [Newport News Shipbuilding, 4101 Washington Ave., Newport News, VA 23607 (United States)

2013-07-01T23:59:59.000Z

64

Waste immobilization demonstration program for the Hanford Site`s Mixed Waste Facility  

SciTech Connect (OSTI)

This paper presents an overview of the Waste Receiving and Processing facility, Module 2A> waste immobilization demonstration program, focusing on the cooperation between Hanford Site, commercial, and international participants. Important highlights of the development and demonstration activities is discussed from the standpoint of findings that have had significant from the standpoint of findings that have had significant impact on the evolution of the facility design. A brief description of the future direction of the program is presented, with emphasis on the key aspects of the technologies that call for further detailed investigation.

Burbank, D.A.; Weingardt, K.M.

1994-05-01T23:59:59.000Z

65

Evaluating Sites for Industrial Cogeneration in Chicago  

E-Print Network [OSTI]

and hospital complexes; and new, densely populated residential developments that have large thermal and electric demands. Potential sites have been evaluated as part of a project to encourage industrial cogeneration applications in Chicago. Energy...

Fowler, G. L.; Baugher, A. H.

1982-01-01T23:59:59.000Z

66

2011 Annual Wastewater Reuse Report for the Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site's Central Facilities Area Sewage Treatment Plant from November 1, 2010, through October 31, 2011. The report contains the following information: (1) Site description; (2) Facility and system description; (3) Permit required monitoring data and loading rates; (4) Status of special compliance conditions and activities; and (5) Discussion of the facility's environmental impacts. During the 2011 permit year, approximately 1.22 million gallons of treated wastewater was land-applied to the irrigation area at Central Facilities Area Sewage Treatment plant.

Michael G. Lewis

2012-02-01T23:59:59.000Z

67

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text  

SciTech Connect (OSTI)

This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

68

Surficial geology and performance assessment for a Radioactive Waste Management Facility at the Nevada Test Site  

SciTech Connect (OSTI)

At the Nevada Test Site, one potentially disruptive scenario being evaluated for the Greater Confinement Disposal (GCD) Facility Performance Assessment is deep post-closure erosion that would expose buried radioactive waste to the accessible environment. The GCD Facility located at the Area 5 Radioactive Waste Management Site (RWMS) lies at the juncture of three alluvial fan systems. Geomorphic surface mapping in northern Frenchman Flat indicates that reaches of these fans where the RWMS is now located have been constructional since at least the middle Quaternary. Mapping indicates a regular sequence of prograding fans with entrenchment of the older fan surfaces near the mountain fronts and construction of progressively younger inset fans farther from the mountain fronts. At the facility, the oldest fan surfaces are of late Pleistocene and Holocene age. More recent geomorphic activity has been limited to erosion and deposition along small channels. Trench and pit wall mapping found maximum incision in the vicinity of the RWMS to be less than 1.5 m. Based on collected data, natural geomorphic processes are unlikely to result in erosion to a depth of more than approximately 2 m at the facility within the 10,000-year regulatory period.

Snyder, K.E. [Lockheed Environmental Systems and Technologies, Co., Las Vegas, NV (United States); Gustafson, D.L.; Huckins-Gang, H.E.; Miller, J.J.; Rawlinson, S.E. [Raytheon Services Nevada, Las Vegas, NV (United States)

1995-02-01T23:59:59.000Z

69

Criticality Safety Evaluation of Hanford Tank Farms Facility  

SciTech Connect (OSTI)

Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

WEISS, E.V.

2000-12-15T23:59:59.000Z

70

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect (OSTI)

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01T23:59:59.000Z

71

2013 Annual Wastewater Reuse Report for the Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at the Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2012, through October 31, 2013. The report contains, as applicable, the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of compliance conditions and activities • Discussion of the facility’s environmental impacts. During the 2013 permit year, no wastewater was land-applied to the irrigation area of the Central Facilities Area Sewage Treatment Plant and therefore, no effluent flow volumes or samples were collected from wastewater sampling point WW-014102. However, soil samples were collected in October from soil monitoring unit SU-014101.

Mike Lewis

2014-02-01T23:59:59.000Z

72

Site in the Sky: Climate Facility Offers New Observational Capabilities  

SciTech Connect (OSTI)

This article is intended for publication in the trade journal, Meteorological Technology International. Its purpose is to introduce the audience to the ARM Climate Research Facility by describing its key capabilities (fixed, mobile and aerial facilities) with examples of field campaigns using each. It also summarizes coming enhancements to the facility through the American Recovery and Reinvestment Act of 2009, and mentions the data archive and proposal opportunities to use the facility.

Roeder, Lynne R.

2010-06-01T23:59:59.000Z

73

RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)  

SciTech Connect (OSTI)

This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

Palmer, E.

1998-10-02T23:59:59.000Z

74

Environmental assessment for device assembly facility operations, Nevada Test Site, Nye County, Nevada. Final report  

SciTech Connect (OSTI)

The U.S. Department of Energy, Nevada Operations Office (DOE/NV), has prepared an environmental assessment (EA), (DOE/EA-0971), to evaluate the impacts of consolidating all nuclear explosive operations at the newly constructed Device Assembly Facility (DAF) in Area 6 of the Nevada Test Site. These operations generally include assembly, disassembly or modification, staging, transportation, testing, maintenance, repair, retrofit, and surveillance. Such operations have previously been conducted at the Nevada Test Site in older facilities located in Area 27. The DAF will provide enhanced capabilities in a state-of-the-art facility for the safe, secure, and efficient handling of high explosives in combination with special nuclear materials (plutonium and highly enriched uranium). Based on the information and analyses in the EA, DOE has determined that the proposed action would not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (42 U.S.C. 4321 et seq.). Therefore, an environmental impact statement is not required, and DOE is issuing this finding of no significant impact.

NONE

1995-05-01T23:59:59.000Z

75

Gasbuggy Site Assessment and Risk Evaluation  

SciTech Connect (OSTI)

This report describes the geologic and hydrologic conditions and evaluates potential health risks to workers in the natural gas industry in the vicinity of the Gasbuggy, New Mexico, site, where the U.S. Atomic Energy Commission detonated an underground nuclear device in 1967. The 29-kiloton detonation took place 4,240 feet below ground surface and was designed to evaluate the use of a nuclear detonation to enhance natural gas production from the Pictured Cliffs Formation in the San Juan Basin, Rio Arriba County, New Mexico, on land administered by Carson National Forest. A site-specific conceptual model was developed based on current understanding of the hydrologic and geologic environment. This conceptual model was used for establishing plausible contaminant exposure scenarios, which were then evaluated for human health risk potential. The most mobile and, therefore, the most probable contaminant that could result in human exposure is tritium. Natural gas production wells were identified as having the greatest potential for bringing detonation-derived contaminants (tritium) to the ground surface in the form of tritiated produced water. Three exposure scenarios addressing potential contamination from gas wells were considered in the risk evaluation: a gas well worker during gas-well-drilling operations, a gas well worker performing routine maintenance, and a residential exposure. The residential exposure scenario was evaluated only for comparison; permanent residences on national forest lands at the Gasbuggy site are prohibited

None

2011-03-01T23:59:59.000Z

76

Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities  

SciTech Connect (OSTI)

The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.

NONE

1996-01-01T23:59:59.000Z

77

Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility  

SciTech Connect (OSTI)

The deactivated 233-S Plutonium Concentration Facility (233-S Facility) is located in the 200 Area. The facility has undergone severe degradation due to exposure to extreme weather conditions. A rapid freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking to occur on portions of the building`s roof. This has resulted in significantly infiltration of water into the facility, which provides a pathway for potential release of radioactive material into the environment (air and/or ground). The weather caused several existing cracks in the concrete portions of the structure to lengthen, increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure thus creating a potential for release of radioactive material t the environment. An expedited removal action is proposed to ensure that a release from the 233-S Facility does not occur. The US Department of Energy (DOE), Richland Operations Office (RL), in cooperation with the EPA, has prepared this Engineering Evaluation/Cost Analysis (EE/CA) pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health and/or the environment, and that an expedited removal action is warranted. The purpose of the EE/CA is to provide the framework for the evaluation and selection of a technology from a viable set of alternatives for a removal action.

NONE

1997-01-01T23:59:59.000Z

78

Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site  

SciTech Connect (OSTI)

DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed.

NONE

1995-07-01T23:59:59.000Z

79

Environmental Assessment for the LGF Spill Test Facility at Frenchman Flat, Nevada Test Site  

SciTech Connect (OSTI)

The LGF Spill Test Facility at Frenchman Flat, Nevada Test Site, is being constructed by the United States Department of Energy (DOE). In this Environmental Assessment, environmental consequences of spilling hazardous materials in the Frenchman Flat basin are evaluated and mitigations and recommendations are stated in order to protect natural resources and reduce land-use impacts. Guidelines and restrictions concerning spill-test procedures will be determined by the LGF Test Facility Operations Manager and DOE based on toxicity documentation for the test material, provided by the user, and mitigations imposed by the Environmental Assessment. In addition to Spill Test Facility operational procedures, certain assumptions have been made in preparation of this document: no materials will be considered for testing that have cumulative, long-term persistence in the environment; spill tests will consist of releases of 15 min or less; and sufficient time will be allowed between tests for recovery of natural resources. Geographic limits to downwind concentrations of spill materials were primarily determined from meteorological data, human occupational exposure standards to hazardous materials and previous spill tests. These limits were established using maximum spill scenarios and environmental impacts are discussed as worst case scenarios; however, spill-test series will begin with smaller spills, gradually increasing in size after the impacts of the initial tests have been evaluated.

Patton, S.E.; Novo, M.G.; Shinn, J.H.

1986-04-01T23:59:59.000Z

80

Gasbuggy Site Assessment and Risk Evaluation  

SciTech Connect (OSTI)

The Gasbuggy site is in northern New Mexico in the San Juan Basin, Rio Arriba County (Figure 1-1). The Gasbuggy experiment was designed to evaluate the use of a nuclear detonation to enhance natural gas production from the Pictured Cliffs Formation, a tight, gas-bearing sandstone formation. The 29-kiloton-yield nuclear device was placed in a 17.5-inch wellbore at 4,240 feet (ft) below ground surface (bgs), approximately 40 ft below the Pictured Cliffs/Lewis shale contact, in an attempt to force the cavity/chimney formed by the detonation up into the Pictured Cliffs Sandstone. The test was conducted below the southwest quarter of Section 36, Township 29 North, Range 4 West, New Mexico Principal Meridian. The device was detonated on December 10, 1967, creating a 335-ft-high chimney above the detonation point and a cavity 160 ft in diameter. The gas produced from GB-ER (the emplacement and reentry well) during the post-detonation production tests was radioactive and diluted, primarily by carbon dioxide. After 2 years, the energy content of the gas had recovered to 80 percent of the value of gas in conventionally developed wells in the area. There is currently no technology capable of remediating deep underground nuclear detonation cavities and chimneys. Consequently, the U.S. Department of Energy (DOE) must continue to manage the Gasbuggy site to ensure that no inadvertent intrusion into the residual contamination occurs. DOE has complete control over the 1/4 section (160 acres) containing the shot cavity, and no drilling is permitted on that property. However, oil and gas leases are on the surrounding land. Therefore, the most likely route of intrusion and potential exposure would be through contaminated natural gas or contaminated water migrating into a producing natural gas well outside the immediate vicinity of ground zero. The purpose of this report is to describe the current site conditions and evaluate the potential health risks posed by the most plausible contaminant exposure scenario, drilling of natural gas wells near the site. The results of this risk evaluation will guide DOE's future surveillance and monitoring activities in the area to ensure that site conditions are adequately protective of human health. This evaluation is not a comprehensive risk assessment for the site; it is intended to provide assurance that DOE's monitoring approach can detect the presence of site-related contamination at levels well below those that would pose an unacceptable risk to human health.

None

2011-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes  

SciTech Connect (OSTI)

This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

NONE

1997-09-01T23:59:59.000Z

82

Utility Facility Siting and Environmental Protection Act (South Carolina)  

Broader source: Energy.gov [DOE]

This legislation applies to electric generating plants and associated facilities designed for or capable of operation at a capacity of more than 75 MW. A certificate from the Public Service...

83

Implementation of instruments and facilities at the SGP CART site  

SciTech Connect (OSTI)

This report discusses the installation of instruments and trailers at the southern Great Plains Clouds and Radiation Testbed site.

Sisterson, D.L.; Wesely, M.L.

1994-02-01T23:59:59.000Z

84

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610  

SciTech Connect (OSTI)

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling input parameters associated with the modeled features, both initial values (at the time of facility closure) and degradation rates/values. During the development of the PA, evaluations are conducted to reflect not only the results associated with the best available information at the time but also to evaluate potential uncertainties and sensitivities associated with the modeled system. While the PA will reflect the modeled system results from the best available information, it will also identify areas for future work to reduce overall PA uncertainties moving forward. DOE requires a PA Maintenance Program such that work continues to reduce model uncertainties, thus bolstering confidence in PA results that support regulatory decisions. This maintenance work may include new Research and Development activities or modeling as informed by previous PA results and other new information that becomes available. As new information becomes available, it is evaluated against previous PAs and appropriate actions are taken to ensure continued confidence in the regulatory decisions. Therefore, the PA program is a continual process that is not just the development of a PA but seeks to incorporate new information to reduce overall model uncertainty and provide continuing confidence in regulatory decisions. (author)

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

85

Nuclear power plant simulation facility evaluation methodology: handbook. Volume 1  

SciTech Connect (OSTI)

This report is Volume 1 of a two-part document which describes a project conducted to develop a methodology to evaluate the acceptability of nuclear power plant (NPP) simulation facilities for use in the simulator-based portion of NRC's operator licensing examination. The proposed methodology is to be utilized during two phases of the simulation facility life-cycle, initial simulator acceptance and recurrent analysis. The first phase is aimed at ensuring that the simulator provides an accurate representation of the reference NPP. There are two components of initial simulator evaluation: fidelity assessment and a direct determination of the simulation facility's adequacy for operator testing. The second phase is aimed at ensuring that the simulation facility continues to accurately represent the reference plant throughout the life of the simulator. Recurrent evaluation is comprised of three components: monitoring reference plant changes, monitoring the simulator's hardware, and examining the data from actual plant transients as they occur. Volume 1 is a set of guidelines which details the steps involved in the two life-cycle phases, presents an overview of the methodology and data collection requirements, and addresses the formation of the evaluation team and the preparation of the evaluation plan. 29 figs.

Laughery, K.R. Jr.; Carter, R.J.; Haas, P.M.

1986-01-01T23:59:59.000Z

86

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site  

SciTech Connect (OSTI)

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Portsmouth site in Ohio (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Portsmouth to a more stable chemical form suitable for use or disposal. The facility would also convert the DUF{sub 6} from the East Tennessee Technology Park (ETTP) site near Oak Ridge, Tennessee. In a Notice of Intent (NOI) published in the Federal Register on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (United States Code, Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (Code of Federal Regulations, Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a Federal Register Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Portsmouth site; from the transportation of all ETTP cylinders (DUF{sub 6}, low-enriched UF6 [LEU-UF{sub 6}], and empty) to Portsmouth; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). An option of shipping the ETTP cylinders to Paducah is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Portsmouth and ETTP sites. A separate EIS (DOE/EIS-0359) evaluates potential environmental impacts for the proposed Paducah conversion facility.

N /A

2003-11-28T23:59:59.000Z

87

Southwestern Power Administration - Evaluate our site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled System Highlights Power2014 Evaluate Our Site Please

88

Siting of low-level radioactive waste disposal facilities in Texas  

E-Print Network [OSTI]

University property was evaluated for suitability for disposal of low-level radioactive waste. This site was evaluated to demonstrate, briefly, the site characterization process and to determine the ability of the statewide study to accurately predict... these boreholes. Literature review was an additional method employed to characterize the site. The results of this site characterization reveal that a more extensive investigation would be necessary to completely evaluate the site and that the state- wide...

Isenhower, Daniel Bruce

1982-01-01T23:59:59.000Z

89

For National Laboratories and Major Sites/Facilities | Scientific...  

Office of Scientific and Technical Information (OSTI)

Protocols (TAP) offer automated submission. To provide STI to OSTI, follow the procedures provided by your site. For more information, contact your STI Manager. In the event...

90

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes  

SciTech Connect (OSTI)

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

91

Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...  

Office of Environmental Management (EM)

of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did...

92

EIS-0385: Ancillary Facilities for the Richton Site of the Strategic Petroleum Reserve, Mississippi  

Broader source: Energy.gov [DOE]

DOE announced the cancellation of a supplemental environmental impact statement for certain facilities associated with the 2007 selection of Richton, Mississippi, as the location of a new storage site for expanding the Strategic Petroleum Reserve.

93

Facility Siting and Layout Optimization Based on Process Safety  

E-Print Network [OSTI]

) that identifies potential layouts by minimizing overall costs. This approach gives the coordinates of each facility in a continuous plane, and estimates for the total length of pipes, the land area, and the selection of safety devices. Finally, the 3D...

Jung, Seungho

2012-02-14T23:59:59.000Z

94

EIS-0359: Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky Site  

Broader source: Energy.gov [DOE]

This site-specific EIS considers the construction, operation, maintenance, and decontamination and decommissioning of the proposed depleted uranium hexafluoride (DUF6) conversion facility at three locations within the Paducah site; transportation of depleted uranium conversion products and waste materials to a disposal facility; transportation and sale of the hydrogen fluoride (HF) produced as a conversion co-product; and neutralization of HF to calcium fluoride and its sale or disposal in the event that the HF product is not sold.

95

Preliminary site studies for critical facilities using geotechnical units derived from engineering geologic analyses  

E-Print Network [OSTI]

PRELIMINARY SITE STUDIES FOR CRITICAL FACILITIES USING GEOTECHNICAL UNITS DERIVED FROM ENGINEERING GEOLOG'C ANALYSES A Thesis DALE EVERETTE CONOVER Submitted to the Graduate College of Texas AAM University i n partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE May 1985 Major Subject: Geology PRELIMINARY SITE STUDIES FOR CRITICAL FACILITIES USING GEOTECHNICAL UNITS DERIVED FROM ENGINEERING GEOLOGIC ANALYSES A Thesis by DALE EVERETTE CONOVER Approved...

Conover, Dale Everette

2012-06-07T23:59:59.000Z

96

Closure End States for Facilities, Waste Sites, and Subsurface Contamination - 12543  

SciTech Connect (OSTI)

The United States (U.S.) Department of Energy (DOE) manages the largest groundwater and soil cleanup effort in the world. DOE's Office of Environmental Management (EM) has made significant progress in its restoration efforts at sites such as Fernald and Rocky Flats. However, remaining sites, such as Savannah River Site, Oak Ridge Site, Hanford Site, Los Alamos, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, and West Valley Demonstration Project possess the most complex challenges ever encountered by the technical community and represent a challenge that will face DOE for the next decade. Closure of the remaining 18 sites in the DOE EM Program requires remediation of 75 million cubic yards of contaminated soil and 1.7 trillion gallons of contaminated groundwater, deactivation and decommissioning (D and D) of over 3000 contaminated facilities and thousands of miles of contaminated piping, removal and disposition of millions of cubic yards of legacy materials, treatment of millions of gallons of high level tank waste and disposition of hundreds of contaminated tanks. The financial obligation required to remediate this volume of contaminated environment is estimated to cost more than 7% of the to-go life-cycle cost. Critical in meeting this goal within the current life-cycle cost projections is defining technically achievable end states that formally acknowledge that remedial goals will not be achieved for a long time and that residual contamination will be managed in the interim in ways that are protective of human health and environment. Formally acknowledging the long timeframe needed for remediation can be a basis for establishing common expectations for remedy performance, thereby minimizing the risk of re-evaluating the selected remedy at a later time. Once the expectations for long-term management are in place, remedial efforts can be directed towards near-term objectives (e.g., reducing the risk of exposure to residual contamination) instead of focusing on long-term cleanup requirements. An acknowledgement of the long timeframe for complete restoration and the need for long-term management can also help a site transition from the process of pilot testing different remedial strategies to selecting a final remedy and establishing a long-term management and monitoring approach. This approach has led to cost savings and the more efficient use of resources across the Department of Defense complex and at numerous industrial sites across the U.S. Defensible end states provide numerous benefits for the DOE environmental remediation programs including cost-effective, sustainable long-term monitoring strategies, remediation and site transition decision support, and long-term management of closure sites. (authors)

Gerdes, Kurt; Chamberlain, Grover; Whitehurst, Latrincy; Marble, Justin [Office of Groundwater and Soil Remediation, U.S. Department of Energy, Washington, DC 20585 (United States); Wellman, Dawn [Pacific Northwest National Laboratory, Richland, Washington 99352 (United States); Deeb, Rula; Hawley, Elisabeth [ARCADIS U.S., Inc., Emeryville, CA 94608 (United States)

2012-07-01T23:59:59.000Z

97

Hanford Site Near-Facility Environmental Monitoring Data Report for Calendar Year 2008  

SciTech Connect (OSTI)

Near-facility environmental monitoring is defined as monitoring near facilities that have the potential to discharge or have discharged, stored, or disposed of radioactive or hazardous materials. Monitoring locations are associated with nuclear facilities such as the Plutonium Finishing Plant, Canister Storage Building, and the K Basins; inactive nuclear facilities such as N Reactor and the Plutonium-Uranium Extraction (PUREX) Facility; and waste storage or disposal facilities such as burial grounds, cribs, ditches, ponds, tank farms, and trenches. Much of the monitoring consists of collecting and analyzing environmental samples and methodically surveying areas near facilities. The program is also designed to evaluate acquired analytical data, determine the effectiveness of facility effluent monitoring and controls, assess the adequacy of containment at waste disposal units, and detect and monitor unusual conditions.

Perkins, Craig J.; Dorsey, Michael C.; Mckinney, Stephen M.; Wilde, Justin W.; Poston, Ted M.

2009-09-15T23:59:59.000Z

98

National Ignition Facility subsystem design requirements NIF site improvements SSDR 1.2.1  

SciTech Connect (OSTI)

This Subsystem Design Requirements (SSDR) document establishes the performance, design, and verification requirements associated with the NIF Project Site at Lawrence Livermore National Laboratory (LLNL) at Livermore, California. It identifies generic design conditions for all NIF Project facilities, including siting requirements associated with natural phenomena, and contains specific requirements for furnishing site-related infrastructure utilities and services to the NIF Project conventional facilities and experimental hardware systems. Three candidate sites were identified as potential locations for the NIF Project. However, LLNL has been identified by DOE as the preferred site because of closely related laser experimentation underway at LLNL, the ability to use existing interrelated infrastructure, and other reasons. Selection of a site other than LLNL will entail the acquisition of site improvements and infrastructure additional to those described in this document. This SSDR addresses only the improvements associated with the NIF Project site located at LLNL, including new work and relocation or demolition of existing facilities that interfere with the construction of new facilities. If the Record of Decision for the PEIS on Stockpile Stewardship and Management were to select another site, this SSDR would be revised to reflect the characteristics of the selected site. Other facilities and infrastructure needed to support operation of the NIF, such as those listed below, are existing and available at the LLNL site, and are not included in this SSDR. Office Building. Target Receiving and Inspection. General Assembly Building. Electro- Mechanical Shop. Warehousing and General Storage. Shipping and Receiving. General Stores. Medical Facilities. Cafeteria services. Service Station and Garage. Fire Station. Security and Badging Services.

Kempel, P.; Hands, J.

1996-08-19T23:59:59.000Z

99

Chapter 2 Transmission Facility Siting, Route Segments and Action...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Draft EIS November 2012 BPA considers many factors when siting proposed new transmission lines. Once the need for a new line in a particular area or region is identified,...

100

Enterprise Assessments, Hanford Site K-West Annex Facility Constructio...  

Energy Savers [EERE]

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. DOE-ORP serves as DOE line management for two functions: the Tank...

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Annual report for RCRA groundwater monitoring projects at Hanford Site facilities for 1993  

SciTech Connect (OSTI)

This report presents the annual hydrogeologic evaluation of 20 Resource Conservation and Recovery Act of 1976 groundwater monitoring projects and 1 nonhazardous waste facility at the US Department of Energy`s Hanford Site. Most of the projects no longer receive dangerous waste; a few projects continue to receive dangerous waste constituents for treatment, storage, or disposal. The 20 RCRA projects comprise 30 waste management units. Ten of the units are monitored under groundwater quality assessment status because of elevated levels of indicator parameters. The impact of those units on groundwater quality, if any, is being investigated. If dangerous waste or waste constituents have entered groundwater, their concentration, distribution, and rate of migration are evaluated. Groundwater is monitored at the other 20 units to detect contamination, should it occur. This report provides an interpretation of groundwater data collected at the waste management units between October 1992 and September 1993. Recent groundwater quality is also described for the 100, 200, 300, and 600 Areas and for the entire Hanford Site. Widespread contaminants include nitrate, chromium, carbon tetrachloride, tritium, and other radionuclides.

Not Available

1994-02-01T23:59:59.000Z

102

Addressing concerns related to geologic hazards at the site of the proposed Transuranic Waste Facility , TA-63, Los Alamos National Laboratory: focus on the current Los Alamos Seismic Network earthquake catalog, proximity of identified seismic events to the proposed facility , and evaluation of prev  

SciTech Connect (OSTI)

This technical paper presents the most recent and updated catalog of earthquakes measured by the Los Alamos Seismic Network at and around Los Alamos National Laboratory (LANL), with specific focus on the site of the proposed transuranic waste facility (TWF) at Technical Area 63 (TA-63). Any questions about the data presented herein, or about the Los Alamos Seismic Network, should be directed to the authors of this technical paper. LANL and the Los Alamos townsite sit atop the Pajarito Plateau, which is bounded on its western edge by the Pajarito fault system, a 35-mile-long system locally comprised of the down-to-the-east Pajarito fault (the master fault) and subsidiary down-to-the-west Rendija Canyon, Guaje Mountain, and Sawyer Canyon faults (Figure 1). This fault system forms the local active western margin of the Rio Grande rift near Los Alamos, and is potentially seismogenic (e.g., Gardner et al., 2001; Reneau et al., 2002; Lewis et al., 2009). The proposed TWF area at TA-63 is situated on an unnamed mesa in the north-central part of LANL between Twomile Canyon to the south, Ten Site Canyon to the north, and the headwaters of Canada del Buey to the east (Figure 2). The local bedrock is the Quaternary Bandelier Tuff, formed in two eruptive pulses from nearby Valles caldera, the eastern edge of which is located approximately 6.5 miles west-northwest of the technical area. The older member (Otowi Member) of the Bandelier Tuff has been dated at 1.61 Ma (Izett and Obradovich 1994). The younger member (Tshirege Member) of the Bandelier Tuff has been dated at 1.256 Ma (age from Phillips et al. 2007) and is widely exposed as the mesa-forming unit around Los Alamos. Several discrete cooling units comprise the Tshirege Member. Commonly accepted stratigraphic nomenclature for the Tshirege Member is described in detail by Broxton and Reneau (1995), Gardner et al. (2001), and Lewis et al. (2009). The Tshirege Member cooling unit exposed at the surface at TA-63 is Qbt3. Understanding the subtle differences between Tshirege Member cooling units and the nature of the contacts between cooling units is critical to identifying the presence or absence of faults associated with the Pajarito fault system on the Pajarito Plateau. The Los Alamos Seismic Network (LASN) continuously monitors local earthquake activity in the Los Alamos area in support of LANL's Seismic Hazards program. Seismic monitoring of LANL facilities is a requirement of DOE Order 420.1B (Facility Safety). LASN currently consists of nine permanent seismic instrument field stations that telemeter real-time sensitive ground motion data to a central recording facility. Four of these stations are located on LANL property, with three of those within 2.5 miles of TA-63. The other five stations are in remote locations in the Jemez Mountains, Valles Caldera, St Peters Dome, and the Caja del Rio plateau across the Rio Grande from the Los Alamos area. Local earthquakes are defined as those with locations within roughly 100 miles of Los Alamos. Plate 1 shows the current LASN station locations and all local earthquakes recorded from 1973 through 2011. During this time period, LASN has detected and recorded over 850 local earthquakes in north-central New Mexico. Over 650 of these were located within about 50 miles of Los Alamos, and roughly 60 were within 10 miles. The apparent higher density of earthquakes close to Los Alamos, relative to the rest of north-central New Mexico, is due largely to the fact that LASN is a sensitive local seismic network, recording many very small nearby events (magnitude less than 1.0) that are undetectable at greater distances.

Roberts, Peter M. [Los Alamos National Laboratory; Schultz-Fellenz, Emily S. [Los Alamos National Laboratory; Kelley, Richard E. [Los Alamos National Laboratory

2012-04-02T23:59:59.000Z

103

Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project  

SciTech Connect (OSTI)

Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP).

NSTec Environmental Management

2009-01-31T23:59:59.000Z

104

Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1  

SciTech Connect (OSTI)

The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

Not Available

1993-01-01T23:59:59.000Z

105

EIS-0385-S1: Ancillary Facilities for the Richton Site of the Strategic Petroleum Reserve, Mississippi  

Broader source: Energy.gov [DOE]

Since selecting the Richton site, DOE has engaged in further consultations with Federal and Mississippi state agencies and is now considering different locations from those addressed in DOE/EIS–0385 for certain facilities associated with the Richton SPR expansion site.

106

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

SciTech Connect (OSTI)

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). Although not part of the proposed action, an option of shipping all cylinders (DUF{sub 6}, low-enriched UF{sub 6} [LEU-UF{sub 6}], and empty) stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Paducah rather than to Portsmouth is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Paducah site. A separate EIS (DOE/EIS-0360) evaluates the potential environmental impacts for the proposed Portsmouth conversion facility.

N /A

2003-11-28T23:59:59.000Z

107

Hanford Site near-facility environmental monitoring data report for calendar year 1998  

SciTech Connect (OSTI)

This document summarizes the results of the U.S. Department of Energy's Near-Facility Environmental Monitoring program conducted by Waste Management Federal Services of Hanford, Inc. for Fluor Daniel Hanford, Inc. for 1998 in the 100,200/600, and 300/400 Areas of the Hanford Site, in southcentral Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels are slightly elevated when compared to offsite locations, the differences are less than in previous years.

DIEDIKER, L.P.

1999-07-29T23:59:59.000Z

108

Design report for the interim waste containment facility at the Niagara Falls Storage Site. [Surplus Facilities Management Program  

SciTech Connect (OSTI)

Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection.

Not Available

1986-05-01T23:59:59.000Z

109

Physical Sciences Facility Air Emission Control Equivalency Evaluation  

SciTech Connect (OSTI)

This document presents the adequacy evaluation for the application of technology standards during design, fabrication, installation and testing of radioactive air exhaust systems at the Physical Sciences Facility (PSF), located on the Horn Rapids Triangle north of the Pacific Northwest National Laboratory (PNNL) complex. The analysis specifically covers the exhaust portion of the heating, ventilation and air conditioning (HVAC) systems associated with emission units EP-3410-01-S, EP-3420-01-S and EP 3430-01-S.

Brown, David M.; Belew, Shan T.

2008-10-17T23:59:59.000Z

110

Siting algae cultivation facilities for biofuel production in the United States: trade-offs between growth rate, site constructability, water availability, and infrastructure  

SciTech Connect (OSTI)

Locating sites for new algae cultivation facilities is a complex task. The climate must support high growth rates, and cultivation ponds require appropriate land and water resources as well as key utility and transportation infrastructure. We employ our spatiotemporal Biomass Assessment Tool (BAT) to select promising locations based on the open-pond cultivation of Arthrospira sp. and a strain of the order Desmidiales. 64,000 potential sites across the southern United States were evaluated. We progressively apply a range of screening criteria and track their impact on the number of selected sites, geographic location, and biomass productivity. Both strains demonstrate maximum productivity along the Gulf of Mexico coast, with the highest values on the Florida peninsula. In contrast, sites meeting all selection criteria for Arthrospira were located along the southern coast of Texas and for Desmidiales were located in Louisiana and southern Arkansas. Site selection was driven mainly by the lack of oil pipeline access in Florida and elevated groundwater salinity in southern Texas. The requirement for low salinity freshwater (<400 mg L-1) constrained Desmidiales locations; siting flexibility is greater for salt-tolerant species such as Arthrospira. Combined siting factors can result in significant departures from regions of maximum productivity but are within the expected range of site-specific process improvements.

Venteris, Erik R.; McBride, Robert; Coleman, Andre M.; Skaggs, Richard; Wigmosta, Mark S.

2014-02-21T23:59:59.000Z

111

Evaluation of energy system analysis techniques for identifying underground facilities  

SciTech Connect (OSTI)

This report describes the results of a study to determine the feasibility and potential usefulness of applying energy system analysis techniques to help detect and characterize underground facilities that could be used for clandestine activities. Four off-the-shelf energy system modeling tools were considered: (1) ENPEP (Energy and Power Evaluation Program) - a total energy system supply/demand model, (2) ICARUS (Investigation of Costs and Reliability in Utility Systems) - an electric utility system dispatching (or production cost and reliability) model, (3) SMN (Spot Market Network) - an aggregate electric power transmission network model, and (4) PECO/LF (Philadelphia Electric Company/Load Flow) - a detailed electricity load flow model. For the purposes of most of this work, underground facilities were assumed to consume about 500 kW to 3 MW of electricity. For some of the work, facilities as large as 10-20 MW were considered. The analysis of each model was conducted in three stages: data evaluation, base-case analysis, and comparative case analysis. For ENPEP and ICARUS, open source data from Pakistan were used for the evaluations. For SMN and PECO/LF, the country data were not readily available, so data for the state of Arizona were used to test the general concept.

VanKuiken, J.C.; Kavicky, J.A.; Portante, E.C. [and others

1996-03-01T23:59:59.000Z

112

File:07TXAEnergyFacilitySiting.pdf | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublicIDAPowerPlantSitingConstruction.pdf Jump to: navigation, search File File historysource History

113

2010 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central Facilities Area Sewage Treatment Plant  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2009, through October 31, 2010. The report contains the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of special compliance conditions • Discussion of the facility’s environmental impacts. During the 2010 permit year, approximately 2.2 million gallons of treated wastewater was land-applied to the irrigation area at Central Facilities Area Sewage Treatment plant.

Mike lewis

2011-02-01T23:59:59.000Z

114

2012 Annual Wastewater Reuse Report for the Idaho National Laboratory Site's Central facilities Area Sewage Treatment Plant  

SciTech Connect (OSTI)

This report describes conditions, as required by the state of Idaho Wastewater Reuse Permit (#LA-000141-03), for the wastewater land application site at Idaho National Laboratory Site’s Central Facilities Area Sewage Treatment Plant from November 1, 2011, through October 31, 2012. The report contains the following information: • Site description • Facility and system description • Permit required monitoring data and loading rates • Status of compliance conditions and activities • Discussion of the facility’s environmental impacts. During the 2012 permit year, no wastewater was land-applied to the irrigation area of the Central Facilities Area Sewage Treatment Plant.

Mike Lewis

2013-02-01T23:59:59.000Z

115

TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS  

SciTech Connect (OSTI)

The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-26T23:59:59.000Z

116

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01T23:59:59.000Z

117

Chapter 2 Transmission Facility Siting, Route Segments and Action Alternatives  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation SitesStanding FriedelIron-Sulfur3-1 November 2012 Words2-1 November

118

Savannah River Site Federal Facility Agreement, January 15, 1993 Summary  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-W StateSite

119

Major Facility Siting Program - Circular 2 | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 - 429Lacey,(MonasterLowell Point,ECO Auger11.Spain:&Maitland, Florida:°Siting

120

Comparative approaches to siting low-level radioactive waste disposal facilities  

SciTech Connect (OSTI)

This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

Newberry, W.F.

1994-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program  

SciTech Connect (OSTI)

This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

122

Environmental Assessment for the new Whole Body Counter facility at the Savannah River Site  

SciTech Connect (OSTI)

The U.S. Department of Energy proposes to construct and operate a new in-vivo counting facility at the Savannah River Site for the monitoring of employees for internal radionuclides. The proposed facility, titled the new Whole Body Counter (WBC) facility, would house both the existing and additional new invivo counting equipment and facility support operations. The proposed facility would be sited and located in an area of the SRS in which background radiation levels are sufficiently low to assure accurate in-vivo counts and a location that would assure ease of access for occupational workers. This Environmental Assessment has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council on Environmental Quality Regulations for Implementing NEPA (40 CPR Parts 1500-1508). NEPA requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. The proposed action has independent utility to the Savannah River operations and will be necessary to support plant activities regardless of the makeup of the future mission at the site. As such, the proposed new WBC facility is treated as part of the preliminary Reconfiguration Programmatic Environmental Impact Statement ``No Action`` alternative.

Not Available

1993-01-01T23:59:59.000Z

123

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

SciTech Connect (OSTI)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

West, K.A.

1988-11-01T23:59:59.000Z

124

RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY  

SciTech Connect (OSTI)

The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

Sexton, L.; Fuller, Kenneth

2013-07-09T23:59:59.000Z

125

Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility  

SciTech Connect (OSTI)

The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

2003-02-26T23:59:59.000Z

126

Calendar Year 2004 annual site environmental report : Tonopah Test Range, Nevada & Kauai Test Facility, Hawaii.  

SciTech Connect (OSTI)

Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, manages TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2004. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 450.1, Environmental Protection Program (DOE 2005) and DOE Order 231.1A, Environment, Safety, and Health Reporting (DOE 2004b).

Montoya, Amber L.; Wagner, Katrina; Goering, Teresa Lynn; Koss, Susan I.; Salinas, Stephanie A.

2005-09-01T23:59:59.000Z

127

Health-hazard evaluation report HETA 89-270-2080, Harrisburg Steam Generation Facility, Harrisburg, Pennsylvania  

SciTech Connect (OSTI)

In response to a request from the City of Harrisburg, Pennsylvania, a health hazard evaluation was conducted at the Harrisburg Steam Generation Facility (HSGF)(SIC-4953) concerning possible exposure to fly ash, combustion products and asbestos (1332214). The facility was a waste to energy site where municipal refuse was incinerated at approximately 1400 degrees-F. The steam generated was either sold directly or converted to electricity via an on site turbine. Employees used hard hats, safety shoes and glasses, work clothes and single use disposable dust and mist respirators. There was a potential for exposure to fly ash for employees working in the boiler and basement areas. Total particulate exposures ranged from 5 to llmg/m3 for laborers. The concentration of lead (7439921) exceeded the standards set by OSHA permissible exposure level of 0.05mg/kg in three of the personal breathing zone air samples. Amosite (12172735) and chrysotile (12001295) asbestos were identified in bulk samples of insulation and asbestos taken from a settled dust sample in the boiler area. Surface wipe samples indicated the possibility of hand to mouth contact with fly ash, particularly in the break and locker rooms. The author concludes that there is a need for reducing worker exposure to fly ash particulate. The author recommends engineering and work practice controls to reduce particulate exposures, increased cleaning and maintenance activities; and further evaluation of asbestos contamination at the facility.

Seitz, T.A.

1990-11-01T23:59:59.000Z

128

RESRAD Computer Code- Evaluation of Radioactively Contaminated Sites  

Broader source: Energy.gov [DOE]

The evaluation of sites with radioactive contamination was a problem until the RESidual RADioactivity (RESRAD) Computer Code was first released in 1989.

129

AQUIFER STORAGE SITE EVALUATION AND MONITORING  

E-Print Network [OSTI]

on the market sectors of electricity transmission, gas transmission, storage and distribution and process science information and expertise. It is responsible for advising the UK government on all aspects research and has extensive state of the art facilities for geomechanics, geochemistry and enhanced oil

Edwards, Mike

130

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites  

SciTech Connect (OSTI)

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01T23:59:59.000Z

131

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility  

SciTech Connect (OSTI)

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes.

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01T23:59:59.000Z

132

Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8  

SciTech Connect (OSTI)

The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1987-09-01T23:59:59.000Z

133

EIS-0364: Decommissioning of the Fast Flux Test Facility, Hanford Site, Richland, WA  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy (DOE) announces its intent to prepare an Environmental Impact Statement (EIS), pursuant to the National Environmental Policy Act of 1969 (NEPA), on proposed decommissioning of the Fast Flux Test Facility (FFTF) at the Hanford Site, Richland, Washington.

134

Optimal Siting of Regional Fecal Sludge Treatment Facilities: St. Elizabeth, Jamaica  

E-Print Network [OSTI]

for rural wastewater treatment. However, there are serious environmental and human health effects associ for wastewater treatment. Fecal sludge FS is defined as the sludge of variable consistency collected from onOptimal Siting of Regional Fecal Sludge Treatment Facilities: St. Elizabeth, Jamaica Ana Martha

Vogel, Richard M.

135

Sociopolitical Challenges to the Siting of Facilities with Perceived Environmental Risks Gemma Aymonne Heddle  

E-Print Network [OSTI]

recently, can also be attributed to minority and low-income communities' pursuit of environmental justice the possibility nor effectiveness of opposition based on NIMBY syndrome or environmental justice concernsSociopolitical Challenges to the Siting of Facilities with Perceived Environmental Risks by Gemma

136

Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography  

SciTech Connect (OSTI)

This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

Owen, P.T.; Michelson, D.C.; Knox, N.P.

1985-09-01T23:59:59.000Z

137

Pollution Prevention Plan for the Y-12 Analytical Chemistry Organization Off-Site Union Valley Facility  

SciTech Connect (OSTI)

The Y-12 Analytical Chemistry Organization (ACO) Off-Site Union Valley Facility (Union Valley Facility) is managed by Babcock and Wilcox Technical Services Y-12, L.L.C. (B and W Y-12) through the Y-12 National Security Complex organization. Accordingly, the Y-12 Pollution Prevention Program encompasses the operations conducted at the Union Valley Facility. The Y-12 Program is designed to fully comply with state, federal and U.S. Department of Energy (DOE) requirements concerning waste minimization/pollution prevention as documented in the Y-12 Pollution Prevention Program Plan. The Program is formulated to reduce the generation and toxicity of all Y-12 wastes in all media, including those wastes generated by the Union Valley Facility operations. All regulatory and DOE requirements are met by the Y-12 Program Plan.

Jackson, J. G.

2010-03-01T23:59:59.000Z

138

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-01-01T23:59:59.000Z

139

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-12-31T23:59:59.000Z

140

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16  

SciTech Connect (OSTI)

This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

NONE

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1A: Citations with abstracts, sections 1 through 9  

SciTech Connect (OSTI)

This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

NONE

1997-09-01T23:59:59.000Z

142

Washington State Energy Facility Site Evaluation Council | Open Energy  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov PtyInformationSEDS dataIndiana:Coop Inc Place:Existing Water

143

Evaluation of Aqua-Ammonia Chiller Technologies and Field Site Installation  

SciTech Connect (OSTI)

The Naval Facilities Engineering Service Center (NFESC) has sponsored Oak Ridge National Laboratory (ORNL) to review, select, and evaluate advanced, gas-fired, 5-ton, aqua-ammonia, chiller technologies. The selection criteria was that units have COP values of 0.67 or better at Air-conditioning and Refrigeration Institute (ARI) 95 F outdoor rating conditions, an active refrigerant flow control, and a variable-speed condenser fan. These features are expected to allow these units to operate at higher ambient temperatures (up to the maximum operating temperature of 110 F) with minimal degradation in performance. ORNL evaluated three potential manufacturers of advanced, gas-fired, 5-ton, aqua-ammonia chillers-Robur, Ambian, and Cooling Technologies. Unfortunately, Robur did not meet the COP requirements and Cooling Technologies could not deliver a unit to be tested at the U.S. Department of Energy (DOE)-ORNL environmental chamber testing facility for thermally activated heat pumps. This eliminated these two technologies from further consideration, leaving only the Ambian chillers for evaluation. Two Ambian chillers were evaluated at the DOE-ORNL test facility. Overall these chillers operated well over a wide range of ambient conditions with minimal degradation in performance due to several control strategies used such as a variable speed condenser fan, a modulating burner, and active refrigerant flow control. These Ambian pre-commercial units were selected for installation and field testing at three federal facilities. NFESC worked with ORNL to assist with the site selection for installation and evaluation of these chillers. Two sites (ORNL and Naval Surface Warfare Center [NSWC] Corona) had a single chiller unit installed; and at one site (Naval Amphibious Base [NAB] Little Creek), two 5-ton chillers linked together were installed to provide 10 tons of cooling. A chiller link controller developed under this project was evaluated in the field test at Little Creek.

Zaltash, Abdolreza [ORNL

2007-09-01T23:59:59.000Z

144

Corrective Action Decision Document for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Corrective Action Decision Document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 254, R-MAD Decontamination Facility, under the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 254 is comprised of Corrective Action Site (CAS) 25-23-06, Decontamination Facility. A corrective action investigation for this CAS as conducted in January 2000 as set forth in the related Corrective Action Investigation Plan. Samples were collected from various media throughout the CAS and sent to an off-site laboratory for analysis. The laboratory results indicated the following: radiation dose rates inside the Decontamination Facility, Building 3126, and in the storage yard exceeded the average general dose rate; scanning and static total surface contamination surveys indicated that portions of the locker and shower room floor, decontamination bay floor, loft floor, east and west decon pads, north and south decontamination bay interior walls, exterior west and south walls, and loft walls were above preliminary action levels (PALs). The investigation-derived contaminants of concern (COCs) included: polychlorinated biphenyls, radionuclides (strontium-90, niobium-94, cesium-137, uranium-234 and -235), total volatile and semivolatile organic compounds, total petroleum hydrocarbons, and total Resource Conservation and Recovery Act (Metals). During the investigation, two corrective action objectives (CAOs) were identified to prevent or mitigate human exposure to COCs. Based on these CAOs, a review of existing data, future use, and current operations at the Nevada Test Site, three CAAs were developed for consideration: Alternative 1 - No Further Action; Alternative 2 - Unrestricted Release Decontamination and Verification Survey; and Alternative 3 - Unrestricted Release Decontamination and Verification Survey and Dismantling of Building 3126. These alternatives were evaluated based on four general corrective action standards and five remedy selection decision factors, and the preferred CAA chosen on technical merit was Alternative 2. This CAA was judged to meet all requirements for the technical components evaluated and applicable state and federal regulations for closure of the site, and reduce the potential for future exposure pathways.

U.S. Department of Energy, Nevada Operations Office

2000-06-01T23:59:59.000Z

145

Facility Closure Report for T-Tunnel (U12t), Area 12, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This Facility Closure Report (FCR) has been prepared to document the actions taken to permanently close the remaining accessible areas of U12t-Tunnel (T-Tunnel) in Area 12 of the Nevada Test Site (NTS). The closure of T-Tunnel was a prerequisite to transfer facility ownership from the Defense Threat Reduction Agency (DTRA) to the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Closure of the facility was accomplished with the cooperation and concurrence of both NNSA/NSO and the Nevada Division of Environmental Protection (NDEP). The purpose of this FCR is to document that the closure of T-Tunnel complied with the closure requirements specified in the Facility Closure Plan for N- and T-Tunnels Area 12, Nevada Test Site (Appendix D) and that the facility is ready for transfer to NNSA/NSO. The Facility Closure Plan (FCP) is provided in Appendix D. T-Tunnel is located approximately 42 miles north of Mercury in Area 12 of the NTS (Figure 1). Between 1970 and 1987, T-Tunnel was used for six Nuclear Weapons Effects Tests (NWETs). The tunnel was excavated horizontally into the volcanic tuffs of Rainier Mesa. The T-Tunnel complex consists of a main access drift with two NWET containment structures, a Gas Seal Plug (GSP), and a Gas Seal Door (GSD) (Figure 2). The T-Tunnel complex was mothballed in 1993 to preserve the tunnel for resumption of testing, should it happen in the future, to stop the discharge of tunnel effluent, and to prevent unauthorized access. This was accomplished by sealing the main drift GSD.

NSTec Environmental Restoration

2008-08-01T23:59:59.000Z

146

Plutonium production story at the Hanford site: processes and facilities history  

SciTech Connect (OSTI)

This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

Gerber, M.S., Westinghouse Hanford

1996-06-20T23:59:59.000Z

147

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 5  

SciTech Connect (OSTI)

This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

1984-09-01T23:59:59.000Z

148

Hanford site near-facility environmental monitoring annual report, calendar year 1996  

SciTech Connect (OSTI)

This document summarizes the results of the near-facility environmental monitoring results for 1996 in the 100, 200/600, and 300/400 areas of the Hanford Site in south-central Washington State. Surveillance activities included sampling and analyses of ambient air, surface water, groundwater, soil, sediments, and biota. Also, external radiation measurements and radiological surveys were taken at waste disposal sites, radiologically controlled areas, and roads. These activities were conducted to assess and control the effects of nuclear facilities and waste sites on the local environment. The monitoring implements applicable portions of DOE Orders 5400.1 (DOE 1988a), 5400.5 (DOE 1990), and 5820.2A (DOE 1988b); Washington Administrative Code (WAC) 246-247; and Title 40 Code of Federal Regulations (CFR) Part 61, Subpart H (EPA 1989). In addition, diffuse sources were monitored to determine compliance with federal, state, and/or local regulations. In general, although effects from nuclear facilities can still be observed on the Hanford Site and radiation levels were slightly elevated when compared to offsite locations, the differences are less than in previous years.

Perkins, C.J.

1997-08-05T23:59:59.000Z

149

Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary  

SciTech Connect (OSTI)

This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

1995-05-01T23:59:59.000Z

150

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites  

SciTech Connect (OSTI)

This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

Maheras, Steven J. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Best, Ralph E.; Ross, Steven B. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River National Laboratory, Aiken, SC (United States); McConnell, Paul E. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2013-09-30T23:59:59.000Z

151

Does your facility have CHP potential? Ideal sites will fit the following profile, but sites meeting only a few of these  

E-Print Network [OSTI]

Does your facility have CHP potential? Ideal sites will fit the following profile, but sites meeting only a few of these characteristics may also have a cost-effective CHP opportunity: high upgrades are planned. CHP Potential at Federal Sites Combined heat and power (CHP) systems provide thermal

Oak Ridge National Laboratory

152

Decommissioning of facilities and encapsulation of wastes for an uranium mill site in Spain  

SciTech Connect (OSTI)

In the south of Spain on the outskirts of the town of Andujar an inactive uranium mill tailings site is being remediated in place. Mill equipment, buildings and process facilities have been dismantled and demolished and the resulting metal wastes and debris have been placed in the tailings pile. The tailings mass has been reshaped by flattening the sideslopes to improve stability and a cover system has been placed over the pile. Remedial action works started in February 1991 and will be completed by March 1994. This paper describes the progress of the remediation works for the closure of the Andujar mill site and in particular discusses the approaches used for the dismantling and demolition of the processing facilities and the stabilization of the tailings pile.

Santiago, J.L. [Enresa, Madrid (Spain); Sanchez, M. [Initec, Madrid (Spain)

1994-12-31T23:59:59.000Z

153

Federal Facility Compliance Act: Conceptual Site Treatment Plan for Lawrence Livermore National Laboratory, Livermore, California  

SciTech Connect (OSTI)

The Department of Energy (DOE) is required by section 3021(b) of the Resource Conservation and Recovery Act (RCRA), as amended by the Federal Facility Compliance Act (the Act), to prepare plans describing the development of treatment capacities and technologies for treating mixed waste. The Act requires site treatment plans (STPs or plans) to be developed for each site at which DOE generates or stores mixed waste and submitted to the State or EPA for approval, approval with modification, or disapproval. The Lawrence Livermore National Laboratory (LLNL) Conceptual Site Treatment Plan (CSTP) is the preliminary version of the plan required by the Act and is being provided to California, the US Environmental Protection Agency (EPA), and others for review. A list of the other DOE sites preparing CSTPs is included in Appendix 1.1 of this document. Please note that Appendix 1.1 appears as Appendix A, pages A-1 and A-2 in this document.

Not Available

1993-10-01T23:59:59.000Z

154

Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography  

SciTech Connect (OSTI)

This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

Faust, R.A.; Fore, C.S.; Knox, N.P.

1980-09-01T23:59:59.000Z

155

Comprehensive evaluation of future site alternatives  

SciTech Connect (OSTI)

Due to rapid changes occurring within the Nuclear Weapons complex, the need for integrated planning designed to combine multiple program needs into one strategic plan has become a necessity. This is more apparent as diverse DOE programs compete for dwindling resources. These programs range from traditional production operations, environmental and waste management, to facility transition, economic development, decontamination and decommissioning, and environmental restoration activities. Each program can influence another, thus increasing the difficulty of distinguishing program elements. The method in developing comprehensive plans becomes even more complicated when environmental compliance issues, regulatory agreements and stakeholder values are considered. AT the Department of Energy`s (DOE) Rocky Flats Plant (RFP), all of these program conditions exist. This paper addresses a set of tools which are being developed at RFP that provides key planning elements and alternatives assessment for the DOE`s Office of Planning and Integration (OPI) and National Environmental Policy Act (NEPA) Compliance Officer at RFP. This set of tools is referred to as the Systems Engineering Analysis (SEA).

Shain, D.I.; Jones, M.E.; Ryan, K.

1994-04-01T23:59:59.000Z

156

Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9  

SciTech Connect (OSTI)

The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

1988-09-01T23:59:59.000Z

157

Analysis of 2011 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities  

SciTech Connect (OSTI)

Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, NY and the Kesselring Site Operations (KSO) facility near Ballston Spa, NY are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the US Environmental Protection Agency (EPA), which regulates these facilities. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted by KAPL to process the on-site data for the calendar year 2011. The purpose of this document is to: (1) summarize the procedures used in the preparation/analysis of the 2011 meteorological data; and (2) document adherence of these procedures to the guidance set forth in 'Meteorological Monitoring Guidance for Regulatory Modeling Applications', EPA document - EPA-454/R-99-005 (EPA-454). This document outlines the steps in analyzing and processing meteorological data from the Knolls Atomic Power Laboratory and Kesselring Site Operations facilities into a format that is compatible with the steady state dispersion model CAP88. This process is based on guidance from the EPA regarding the preparation of meteorological data for use in regulatory dispersion models. The analysis steps outlined in this document can be easily adapted to process data sets covering time period other than one year. The procedures will need to be modified should the guidance in EPA-454 be updated or revised.

Aluzzi, F J

2012-02-27T23:59:59.000Z

158

Performance Evaluation Of An Irradiation Facility Using An Electron Accelerator  

SciTech Connect (OSTI)

Irradiation parameters over a period of seven years have been evaluated for a radiation processing electron accelerator facility. The parameters monitored during this time were the electron beam energy, linearity of beam current, linearity of dose with the reciprocal value of the samples speed, and dose uniformity along the scanning area after a maintenance audit performed by the electron accelerator manufacturer. The electron energy was determined from the depth-dose curve by using a two piece aluminum wedge and measuring the practical range from the obtained curves. The linearity of dose with beam current, and reciprocal value of the speed and dose uniformity along the scanning area of the electron beam were determined by measuring the dose under different beam current and cart conveyor speed conditions using film dosimetry. The results of the experiments have shown that the energy in the range from 1 to 5 MeV has not changed by more than 15% from the High Voltage setting of the machine over the evaluation period, and dose linearity with beam current and cart conveyor speed has not changed. The dose uniformity along the scanning direction of the beam showed a dose uniformity of 90% or better for energies between 2 and 5 MeV, however for 1 MeV electrons this value was reduced to 80%. This parameter can be improved by changing the beam optics settings in the control console of the accelerator though.

Uribe, R. M.; Hullihen, K. [Kent State University, Kent, Ohio (United States); Filppi, E. [Case Western Reserve University, Cleveland OH (United States)

2011-06-01T23:59:59.000Z

159

Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A  

SciTech Connect (OSTI)

This report was prepared to evaluate the compliance of Cask Transportation Facility Modifications (CTFM) to DOE Order 6430.1A.

ARD, K.E.

1999-07-14T23:59:59.000Z

160

Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input  

Broader source: Energy.gov [DOE]

The study entitled, “Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries: Evaluation for Regulatory Input,” focuses on the issue of showing compliance with given...

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Site selection and preliminary evaluation of potential solar-industrial-process-heat applications for federal buildings in Texas  

SciTech Connect (OSTI)

The potential for solr process heat applications for federal buildings in Texas is assessed. The three sites considered are Reese Air Force Base, Lubbock; Fort Bliss, El Paso; and Dyess Air Force Base, Abilene. The application at Lubbock is an electroplating and descaling facility for aircraft maintenance. The one at El Paso is a laundry facility. The Abilene system would use solar heat to preheat boiler feedwater makeup for the base hospital boiler plant. The Lubbock site is found to be the most appropriate one for a demonstration plant, with the Abilene site as an alternate. The processes at each site are described. A preliminary evaluation of the potential contribution by solar energy to the electroplating facility at Reese AFB is included. (LEW)

Branz, M A

1980-09-30T23:59:59.000Z

162

Technical assistance to Ohio closure sites; Technologies to address leachate from the on-site disposal facility at Fernald Environmental Management Project, Ohio  

SciTech Connect (OSTI)

On August 6-7, 2002, a Technical Assistance Team (''Team'') from the U.S. Department of Energy (DOE) Subsurface Contaminants Focus Area (SCFA) met with Fernald Environmental Management Project (FEMP) personnel in Ohio to assess approaches to remediating uranium-contaminated leachate from the On-Site Disposal Facility (OSDF). The Team was composed of technical experts from national labs, technology centers, and industry and was assembled in response to a request from the FEMP Aquifer Restoration Project. Dave Brettschneider of Fluor Fernald, Inc., requested that a Team of experts be convened to review technologies for the removal of uranium in both brine ion exchange regeneration solution from the Advanced Wastewater Treatment facility and in the leachate from the OSDF. The Team was asked to identify one or more technologies for bench-scale testing as a cost effective alternative to remove uranium so that the brine regeneration solution from the Advanced Waste Water Treatment facility and the leachate from the OSDF can be discharged without further treatment. The Team was also requested to prepare a recommended development and demonstration plan for the alternative technologies. Finally, the Team was asked to make recommendations on the optimal technical solution for field implementation. The Site's expected outcomes for this effort are schedule acceleration, cost reduction, and better long-term stewardship implementation. To facilitate consideration of the most appropriate technologies, the Team was divided into two groups to consider the brine and the leachate separately, since they represent different sources with different constraints on solutions, e.g., short-term versus very long-term and concentrated versus dilute contaminant matrices. This report focuses on the technologies that are most appropriate for the leachate from the OSDF. Upon arriving at FEMP, project personnel asked the Team to concentrate its efforts on evaluating potential technologies and strategies to reduce uranium concentration in the leachate.

Hazen, Terry

2002-08-26T23:59:59.000Z

163

CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I  

SciTech Connect (OSTI)

The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP.

Denney, R.D.

1995-10-01T23:59:59.000Z

164

Siting the International Linear Collider at Hanford  

SciTech Connect (OSTI)

Review of the proposed International Linear Collider, applications in high energy physics, and evaluation of the Hanford Site as a possible location for siting the facility.

Kouzes, Richard T.; Asner, David M.; Brodzinski, Ronald L.; Fast, James E.; Miley, Harry S.

2012-05-01T23:59:59.000Z

165

Preliminary evaluation of VTA effectiveness to protect runoff water quality on small pork production facilities in Texas  

E-Print Network [OSTI]

/or Robertson County sites on the following dates: • January 9, 2013 • February 10, 2013 • March 10, 2013 • April 3, 2013 • May 9, 2013 • May 16, 2013 • May 21, 2013 • June 3, 2013 • June 10, 2013 • July 15, 2013 Results from the analysis... Research Service Texas Water Resources Institute TR-452 November 2013 Preliminary evaluation of VTA effectiveness to protect runoff water quality on small pork production facilities in Texas STATE NONPOINT SOURCE GRANT PROGRAM TSSWCB PROJECT...

Wagner, K.; Harmel, D.; Higgs, K.

2013-01-01T23:59:59.000Z

166

Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)  

SciTech Connect (OSTI)

During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

Not Available

1987-06-01T23:59:59.000Z

167

ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY  

SciTech Connect (OSTI)

A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the Berea sandstone aquiver over time and does not conform to standard private water well construction practices. The bottom-line is that all predicted doses from the base case and five sensitivity cases fall well below the DOE all-pathways 25 mrem/yr Performance Objective.

Smith, F.; Phifer, M.

2014-04-10T23:59:59.000Z

168

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program  

SciTech Connect (OSTI)

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Not Available

1991-09-01T23:59:59.000Z

169

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12  

SciTech Connect (OSTI)

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

1991-09-01T23:59:59.000Z

170

Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities  

SciTech Connect (OSTI)

This DOE standard gives design and evaluation criteria for natural phenomena hazards (NPH) effects as guidance for implementing the NPH mitigation requirements of DOE 5480.28. Goal of the criteria is to assure that DOE facilities can withstand the effects of earthquakes, extreme winds, tornadoes, flooding, etc. They apply to the design of new facilities and the evaluation of existing facilities; they may also be used for modification and upgrading of the latter.

Not Available

1994-04-01T23:59:59.000Z

171

Closure Report for Corrective Action Unit 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. Corrective Action Unit 117 comprises Corrective Action Site (CAS) 26-41-01, Pluto Disassembly Facility, located in Area 26 of the Nevada Test Site. The purpose of this CR is to provide documentation supporting the completed corrective actions and provide data confirming that the closure objectives for CAU 117 were met. To achieve this, the following actions were performed: • Review the current site conditions, including the concentration and extent of contamination. • Implement any corrective actions necessary to protect human health and the environment. • Properly dispose of corrective action and investigation wastes. • Document Notice of Completion and closure of CAU 117 issued by the Nevada Division of Environmental Protection. From May 2008 through February 2009, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 117, Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada. The purpose of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, and properly dispose of wastes. Analytes detected during the closure activities were evaluated against final action levels to determine COCs for CAU 117. Assessment of the data generated from closure activities indicated that the final action levels were exceeded for polychlorinated biphenyls (PCBs) reported as total Aroclor and radium-226. A corrective action was implemented to remove approximately 50 cubic yards of PCB-contaminated soil, approximately 1 cubic foot of radium-226 contaminated soil (and scabbled asphalt), and a high-efficiency particulate air filter that was determined to meet the criteria of a potential source material (PSM). Electrical and lighting components (i.e., PCB-containing ballasts and capacitors) and other materials (e.g., mercury-containing thermostats and switches, lead plugs and bricks) assumed to be PSM were also removed from Building 2201, as practical, without the need for sampling. Because the COC contamination and PSMs have been removed, clean closure of CAS 26-41-01 is recommended, and no use restrictions are required to be placed on this CAU. No further action is necessary because no other contaminants of potential concern were found above preliminary action levels. The physical end state for Building 2201 is expected to be eventual demolition to slab. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • Clean closure is the recommended corrective action for CAS 26-41-01 in CAU 117. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 117. • Corrective Action Unit 117 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

Mark Burmeister

2009-06-01T23:59:59.000Z

172

Stress evaluation of the primary tank of a double-shell underground storage tank facility  

SciTech Connect (OSTI)

A facility called the Multi-Function Waste Tank Facility (MWTF) is being designed at the Department of Energy`s Hanford site. The MWTF is expected to be completed in 1998 and will consist of six underground double-shell waste storage tanks and associated systems. These tanks will provide safe and environmentally acceptable storage capacity to handle waste generated during single-shell and double-shell tank safety mitigation and remediation activities. This paper summarizes the analysis and qualification of the primary tank structure of the MWTF, as performed by ICF Kaiser Hanford during the latter phase of Title 1 (Preliminary) design. Both computer finite element analysis (FEA) and hand calculations methods based on the so-called Tank Seismic Experts Panel (TSEP) Guidelines were used to perform the analysis and evaluation. Based on the evaluations summarized in this paper, it is concluded that the primary tank structure of the MWTF satisfies the project design requirements. In addition, the hand calculations performed using the methodologies provided in the TSEP Guidelines demonstrate that, except for slosh height, the capacities exceed the demand. The design accounts for the adverse effect of the excessive slosh height demand, i.e., inadequate freeboard, by increasing the hydrodynamic wall and roof pressures appropriately, and designing the tank for such increased pressures.

Atalay, M.B. [ICF Kaiser Engineers, Inc., Oakland, CA (United States); Stine, M.D. [ICF Kaiser Hanford Co., Richland, WA (United States); Farnworth, S.K. [Westinghouse Hanford Co., Richland, WA (United States)

1994-12-01T23:59:59.000Z

173

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program  

SciTech Connect (OSTI)

This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01T23:59:59.000Z

174

Groundwater Monitoring Plan for the Hanford Site 216-B-3 Pond RCRA Facility  

SciTech Connect (OSTI)

The 216-B-3 Pond system was a series of ponds used for disposal of liquid effluent from past Hanford production facilities. In operation from 1945 to 1997, the B Pond System has been a Resource Conservation and Recovery Act (RCRA) facility since 1986, with RCRA interim-status groundwater monitoring in place since 1988. In 1994 the expansion ponds of the facility were clean closed, leaving only the main pond and a portion of the 216-B-3-3 ditch as the currently regulated facility. In 2001, the Washington State Department of Ecology (Ecology) issued a letter providing guidance for a two-year, trial evaluation of an alternate, intrawell statistical approach to contaminant detection monitoring at the B Pond system. This temporary variance was allowed because the standard indicator-parameters evaluation (pH, specific conductance, total organic carbon, and total organic halides) and accompanying interim status statistical approach is ineffective for detecting potential B-Pond-derived contaminants in groundwater, primarily because this method fails to account for variability in the background data and because B Pond leachate is not expected to affect the indicator parameters. In July 2003, the final samples were collected for the two-year variance period. An evaluation of the results of the alternate statistical approach is currently in progress. While Ecology evaluates the efficacy of the alternate approach (and/or until B Pond is incorporated into the Hanford Facility RCRA Permit), the B Pond system will return to contamination-indicator detection monitoring. Total organic carbon and total organic halides were added to the constituent list beginning with the January 2004 samples. Under this plan, the following wells will be monitored for B Pond: 699-42-42B, 699-43-44, 699-43-45, and 699-44-39B. The wells will be sampled semi-annually for the contamination indicator parameters (pH, specific conductance, total organic carbon, and total organic halides) and annually for water quality parameters (chloride, iron, manganese, phenols, sodium, and sulfate). This plan will remain in effect until superseded by another plan or until B Pond is incorporated into the Hanford Facility RCRA Permit.

Barnett, D BRENT.; Smith, Ronald M.; Chou, Charissa J.; McDonald, John P.

2005-11-01T23:59:59.000Z

175

Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4  

SciTech Connect (OSTI)

This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

1983-09-01T23:59:59.000Z

176

Siting Evaluation for Biomass-Ethanol Production in Hawaii  

SciTech Connect (OSTI)

This report examines four Hawaiian islands, Oahu, Hawaii, Maui, and Kauai, to identify three best combinations of potential sites and crops for producing dedicated supplies of biomass for conversion to ethanol. Key technical and economic factors considered in the siting evaluation include land availability (zoning and use), land suitability (agronomic conditions), potential quantities and costs of producing biomass feedstocks, infrastructure (including water and power supplies), transportation, and potential bioresidues to supplement dedicated energy crops.

Kinoshita, C.M.; Zhou, J.

2000-10-15T23:59:59.000Z

177

Emergency and backup power supplies at Department of Energy facilities: Augmented Evaluation Team -- Final report  

SciTech Connect (OSTI)

This report documents the results of the Defense Programs (DP) Augmented Evaluation Team (AET) review of emergency and backup power supplies (i.e., generator, uninterruptible power supply, and battery systems) at DP facilities. The review was conducted in response to concerns expressed by former Secretary of Energy James D. Watkins over the number of incidents where backup power sources failed to provide electrical power during tests or actual demands. The AET conducted a series of on-site reviews for the purpose of understanding the design, operation, maintenance, and safety significance of emergency and backup power (E&BP) supplies. The AET found that the quality of programs related to maintenance of backup power systems varies greatly among the sites visited, and often among facilities at the same site. No major safety issues were identified. However, there are areas where the AET believes the reliability of emergency and backup power systems can and should be improved. Recommendations for improving the performance of E&BP systems are provided in this report. The report also discusses progress made by Management and Operating (M&O) contractors to improve the reliability of backup sources used in safety significant applications. One area that requires further attention is the analysis and understanding of the safety implications of backup power equipment. This understanding is needed for proper graded-approach implementation of Department of Energy (DOE) Orders, and to help ensure that equipment important to the safety of DOE workers, the public, and the environment is identified, classified, recognized, and treated as such by designers, users, and maintainers. Another area considered important for improving E&BP system performance is the assignment of overall ownership responsibility and authority for ensuring that E&BP equipment performs adequately and that reliability and availability are maintained at acceptable levels.

Not Available

1993-11-01T23:59:59.000Z

178

Facility Closure Report for Tunnel U16a, Area 16, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

U16a is not listed in the Federal Facility Agreement and Consent Order. The closure of U16a was sponsored by the Defense Threat Reduction Agency (DTRA) and performed with the cooperation of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office and the Nevada Division of Environmental Protection. This report documents closure of this site as identified in the DTRA Fiscal Year 2008 Statement of Work, Task 6.3. Closure activities included: · Removing and disposing of a shack and its contents · Disposing of debris from within the shack and in the vicinity of the tunnel entrance · Verifying that the tunnel is empty · Welding screened covers over tunnel vent holes to limit access and allow ventilation · Constructing a full-tunnel cross-section fibercrete bulkhead to prevent access to the tunnel Field activities were conducted from July to August 2008.

NSTec Environmental Restoration

2009-07-01T23:59:59.000Z

179

Interaction of Sr-90 with site candidate soil for demonstration disposal facility at Serpong  

SciTech Connect (OSTI)

Interaction of radiostrontium (Sr-90) with site candidate soil for demonstration disposal facility to be constructed in the near future at Serpong has been done. This activity is to anticipate the interim storage facility at Serpong nuclear area becomes full off condition, and show to the public how radioactive waste can be well managed with the existing technology. To ensure that the location is save, a reliability study of site candidate soil becomes very importance to be conducted through some experiments consisted some affected parameters such as contact time, effect of ionic strength, and effect of Sr{sup +} ion in solution. Radiostrontium was used as a tracer on the experiments and has role as radionuclide reference in low-level radioactive waste due to its long half-live and it's easy to associate with organism in nature. So, interaction of radiostrontium and soil samples from site becomes important to be studied. Experiment was performed in batch method, and soil sample-solution containing radionuclide was mixed in a 20 ml of PE vial. Ratio of solid: liquid was 10{sup ?2} g/ml. Objective of the experiment is to collect the specific characteristics data of radionuclide sorption onto soil from site candidate. Distribution coefficient value was used as indicator where the amount of initial and final activities of radiostrontium in solution was compared. Result showed that equilibrium condition was reached after contact time 10 days with Kd values ranged from 1600-2350 ml/g. Increased in ionic strength in solution made decreased of Kd value into soil sample due to competition of background salt and radiostrontium into soil samples, and increased in Sr ion in solution caused decreased of Kd value in soil sample due to limitation of sorption capacity in soil samples. Fast condition in saturated of metal ion into soil samples was reached due to a simple reaction was occurred.

Setiawan, Budi, E-mail: bravo@batan.go.id [Radwaste Technology Center-National Nuclear Energy Agency, PUSPIPTEK, Serpong-Tangerang 15310 (Indonesia); Mila, Oktri; Safni [Dept. of Chemistry, Fac. of Math. and Nat. Sci., Andalas University, Kampus Limau Manis, Padang-West Sumatra 25163 (Indonesia)

2014-03-24T23:59:59.000Z

180

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2003  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP - U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection - Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods and provides the results for the assessment performed in 2003.

Ballinger, Marcel Y.; Sula, Monte J.; Gervais, Todd L.; Edwards, Daniel L.

2003-12-05T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2001  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP - U.S. Code of Federal Regulations, Title 40 Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection - Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods, and provides the results, for the assessment performed in 2001.

Ballinger, Marcel Y.; Sula, Monte J.; Gervais, Todd L.; Shields, Keith D.; Edwards, Daniel R.

2001-09-28T23:59:59.000Z

182

Allowable residual-contamination levels for decommissioning facilities in the 100 areas of the Hanford Site  

SciTech Connect (OSTI)

This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for five generic categories of facilities in the 100 Areas of the Hanford Site. The purpose of this study is to provide ARCL data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use provided by this report is intended to permit a full consideration of decommissioning alternatives. ARCL results are presented both for surface contamination remaining in facilities (in dpm/100 cm/sup 2/), and for unconfined surface and confined subsurface soil conditions (in pCi/g). Two confined soil conditions are considered: contamination at depths between 1 and 4 m, and contamination at depths greater than or equal to 5 m. A set of worksheets are presented in an appendix for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations, to consider the impacts of radioactive decay, and to predict instrument responses. Finally, a comparison is made between the unrestricted release ARCL values for the 100 Area facilities and existing decommissioning and land disposal regulations. For surface contamination, the comparison shows good agreement. For soil contamination, the comparison shows good agreement if reasonable modification factors are applied to account for the differences in modeling soil contamination and licensed low-level waste.

Kennedy, W.E. Jr.; Napier, B.A.

1983-07-01T23:59:59.000Z

183

Statistical evaluation of effluent monitoring data for the 200 Area Treated Effluent Disposal Facility  

SciTech Connect (OSTI)

The 200 Area Treated Effluent Disposal Facility (TEDF) consists of a pair of infiltration basins that receive wastewater originating from the 200 West and 200 East Areas of the Hanford Site. TEDF has been in operation since 1995 and is regulated by State Waste Discharge Permit ST 4502 (Ecology 1995) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216. The permit stipulates monitoring requirements for effluent (or end-of-pipe) discharges and groundwater monitoring for TEDF. Groundwater monitoring began in 1992 prior to TEDF construction. Routine effluent monitoring in accordance with the permit requirements began in late April 1995 when the facility began operations. The State Waste Discharge Permit ST 4502 included a special permit condition (S.6). This condition specified a statistical study of the variability of permitted constituents in the effluent from TEDF during its first year of operation. The study was designed to (1) demonstrate compliance with the waste discharge permit; (2) determine the variability of all constituents in the effluent that have enforcement limits, early warning values, and monitoring requirements (WHC 1995); and (3) determine if concentrations of permitted constituents vary with season. Additional and more frequent sampling was conducted for the effluent variability study. Statistical evaluation results were provided in Chou and Johnson (1996). Parts of the original first year sampling and analysis plan (WHC 1995) were continued with routine monitoring required up to the present time.

CJ Chou; VG Johnson

2000-04-04T23:59:59.000Z

184

Early Site Permit Demonstration Program: Siting Guide, Site selection and evaluation criteria for an early site permit application. Revision 1  

SciTech Connect (OSTI)

In August 1991, the Joint Contractors came to agreement with Sandia National Laboratories (SNL) and the Department of Energy (DOE) on a workscope for the cost-shared Early Site Permit Demonstration Program. One task within the scope was the development of a guide for site selection criteria and procedures. A generic Siting Guide his been prepared that is a roadmap and tool for applicants to use developing detailed siting plans for their specific region of the country. The guide presents three fundamental principles that, if used, ensure a high degree of success for an ESP applicant. First, the site selection process should take into consideration environmentally diverse site locations within a given region of interest. Second, the process should contain appropriate opportunities for input from the public. Third, the process should be applied so that it is clearly reasonable to an impartial observer, based on appropriately selected criteria, including criteria which demonstrate that the site can host an advanced light water reactor (ALWR). The Siting Guide provides for a systematic, comprehensive site selection process in which three basic types of criteria (exclusionary, avoidance, and suitability) are presented via a four-step procedure. It provides a check list of the criteria for each one of these steps. Criteria are applied qualitatively, as well as presented numerically, within the guide. The applicant should use the generic guide as an exhaustive checklist, customizing the guide to his individual situation.

Not Available

1993-03-24T23:59:59.000Z

185

Survey of computer codes applicable to waste facility performance evaluations  

SciTech Connect (OSTI)

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs.

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01T23:59:59.000Z

186

General Engineer / Physical Scientist (Facility Representative)  

Broader source: Energy.gov [DOE]

Facility Representatives (FRs) are line management's on-site technical representative with responsibility for identifying and evaluating environmental, safety and health issues and concerns,...

187

Hanford performance evaluation program for Hanford site analytical services  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Order 5700.6C, Quality Assurance, and Title 10 of the Code of Federal Regulations, Part 830.120, Quality Assurance Requirements, states that it is the responsibility of DOE contractors to ensure that ``quality is achieved and maintained by those who have been assigned the responsibility for performing the work.`` Hanford Analytical Services Quality Assurance Plan (HASQAP) is designed to meet the needs of the Richland Operations Office (RL) for maintaining a consistent level of quality for the analytical chemistry services provided by contractor and commmercial analytical laboratory operations. Therefore, services supporting Hanford environmental monitoring, environmental restoration, and waste management analytical services shall meet appropriate quality standards. This performance evaluation program will monitor the quality standards of all analytical laboratories supporting the Hanforad Site including on-site and off-site laboratories. The monitoring and evaluation of laboratory performance can be completed by the use of several tools. This program will discuss the tools that will be utilized for laboratory performance evaluations. Revision 0 will primarily focus on presently available programs using readily available performance evaluation materials provided by DOE, EPA or commercial sources. Discussion of project specific PE materials and evaluations will be described in section 9.0 and Appendix A.

Markel, L.P.

1995-09-01T23:59:59.000Z

188

A method for the assessment of site-specific economic impacts of commercial and industrial biomass energy facilities. A handbook and computer model  

SciTech Connect (OSTI)

A handbook on ``A Method for the Assessment of Site-specific Econoomic Impacts of Industrial and Commercial Biomass Energy Facilities`` has been prepared by Resource Systems Group Inc. under contract to the Southeastern Regional Biomass Energy Program (SERBEP). The handbook includes a user-friendly Lotus 123 spreadsheet which calculates the economic impacts of biomass energy facilities. The analysis uses a hybrid approach, combining direct site-specific data provided by the user, with indirect impact multipliers from the US Forest Service IMPLAN input/output model for each state. Direct economic impacts are determined primarily from site-specific data and indirect impacts are determined from the IMPLAN multipliers. The economic impacts are given in terms of income, employment, and state and federal taxes generated directly by the specific facility and by the indirect economic activity associated with each project. A worksheet is provided which guides the user in identifying and entering the appropriate financial data on the plant to be evaluated. The WLAN multipliers for each state are included in a database within the program. The multipliers are applied automatically after the user has entered the site-specific data and the state in which the facility is located. Output from the analysis includes a summary of direct and indirect income, employment and taxes. Case studies of large and small wood energy facilities and an ethanol plant are provided as examples to demonstrate the method. Although the handbook and program are intended for use by those with no previous experience in economic impact analysis, suggestions are given for the more experienced user who may wish to modify the analysis techniques.

Not Available

1994-10-01T23:59:59.000Z

189

Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This standard provides a framework for generating Criticality Safety Evaluations (CSE) supporting fissionable material operations at Department of Energy (DOE) nonreactor nuclear facilities. This standard imposes no new criticality safety analysis requirements.

2007-02-07T23:59:59.000Z

190

EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to build, permit, and operate the Explosive Waste Treatment Facility to treat explosive waste at the U.S. Department of Energy's Lawrence...

191

The development and evaluation of a neutron window filter facility utilizing the TAMU NSC TRIGA reactor  

E-Print Network [OSTI]

THE DEVELOPMENT AND EVALUATION OF A NEUTRON WINDOW FILTER FACILITY UTILIZING THE TAMU NSC TRIGA REACTOR A Thesis by PATRICIA COLLEEN HARDING Submitted to the Graduate College of Texas AAM University in partial fulfillment of the requirement... for the degree of MASTER OF SCIENCE December 1982 Major Subject: Nuclear Engineering THE DEVELOPMENT AND EVALUATION OF A NEUTRON WINDOW FILTER FACILITY UTILIZING THE TAMU NSC TRIGA REACTOR A Thesis by PATRICIA COLLEEN HARDING Approved as to style...

Harding, Patricia Colleen

2012-06-07T23:59:59.000Z

192

From Legislation to Implementation: An Evaluation of the Instructional Facilities Allotment Policy  

E-Print Network [OSTI]

FROM LEGISLATION TO IMPLEMENTATION: AN EVALUATION OF THE INSTRUCTIONAL FACILITIES ALLOTMENT POLICY A Dissertation by BRANDON HEATH CORE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment...: Educational Administration Copyright 2013 Brandon Heath Core ii ABSTRACT The purpose of this study was to advance our understanding of the original legislative intents of the Instructional Facilities Allotment (IFA) and to evaluate the IFA policy...

Core, Brandon Heath

2013-04-24T23:59:59.000Z

193

Multiattribute utility analysis as a framework for public participation siting a hazardous waste facility  

SciTech Connect (OSTI)

How can the public play a role in decisions involving complicated scientific arguments? This paper describes a public participation exercise in which stakeholders used multiattribute utility analysis to select a site for a hazardous waste facility. Key to success was the ability to separate and address the two types of judgements inherent in environmental decisions: technical judgements on the likely consequences of alternative choices and value judgements on the importance or seriousness of those consequences. This enabled technical specialists to communicate the essential technical considerations and allowed stakeholders to establish the value judgements for the decision. Although rarely used in public participation, the multiattribute utility approach appears to provide a useful framework for the collaborative resolution of many complex environmental decision problems.

Merkhofer, M.W. [Applied Decision Analysis, Inc., Menlo Park, CA (United States); Conway, R. [Sandia National Labs., Albuquerque, NM (United States); Anderson, R.G. [Los Alamos National Lab., NM (United States)

1996-05-01T23:59:59.000Z

194

North Dakota Energy Conversion and Transmission Facility Siting Act (North Dakota)  

Broader source: Energy.gov [DOE]

This chapter aims to ensure that the location, construction, and operation of energy conversion facilities and transmission facilities will produce minimal adverse effects on the environment and...

195

SAVANNAH RIVER SITE'S H-CANYON FACILITY: RECOVERY AND DOWN BLEND URANIUM FOR BENEFICIAL USE  

SciTech Connect (OSTI)

For over fifty years, the H Canyon facility at the Savannah River Site (SRS) has performed remotely operated radiochemical separations of irradiated targets to produce materials for national defense. Although the materials production mission has ended, the facility continues to play an important role in the stabilization and safe disposition of proliferable nuclear materials. As part of the US HEU Disposition Program, SRS has been down blending off-specification (off-spec) HEU to produce LEU since 2003. Off-spec HEU contains fission products not amenable to meeting the American Society for Testing and Material (ASTM) commercial fuel standards prior to purification. This down blended HEU material produced 301 MT of ~5% enriched LEU which has been fabricated into light water reactor fuel being utilized in Tennessee Valley Authority (TVA) reactors in Tennessee and Alabama producing economic power. There is still in excess of ~10 MT of off-spec HEU throughout the DOE complex or future foreign and domestic research reactor returns that could be recovered and down blended for beneficial use as either ~5% enriched LEU, or for use in subsequent LEU reactors requiring ~19.75% enriched LEU fuel.

Magoulas, V.

2013-05-27T23:59:59.000Z

196

INSTALLATION OF BUBBLERS IN THE SAVANNAH RIVER SITED DEFENSE WASTE PROCESSING FACILITY MELTER  

SciTech Connect (OSTI)

Savannah River Remediation (SRR) LLC assumed the liquid waste contract at the Savannah River Site (SRS) in the summer of 2009. The main contractual agreement was to close 22 High Level Waste (HLW) tanks in eight years. To achieve this aggressive commitment, faster waste processing throughout the SRS liquid waste facilities will be required. Part of the approach to achieve faster waste processing is to increase the canister production rate of the Defense Waste Processing Facility (DWPF) from approximately 200 canisters filled with radioactive waste glass per year to 400 canisters per year. To reach this rate for melter throughput, four bubblers were installed in the DWPF Melter in the late summer of 2010. This effort required collaboration between SRR, SRR critical subcontractor EnergySolutions, and Savannah River Nuclear Solutions, including the Savannah River National Laboratory (SRNL). The tasks included design and fabrication of the bubblers and related equipment, testing of the bubblers for various technical issues, the actual installation of the bubblers and related equipment, and the initial successful operation of the bubblers in the DWPF Melter.

Smith, M.; Iverson, D.

2010-12-08T23:59:59.000Z

197

Type B Investigation Board Report on the April 2, 2002, Worker Fall from Shoring/Scaffolding Structure at the Savannah River Site Tritium Extraction Facility Construction Site  

Broader source: Energy.gov [DOE]

On April 2, 2002, a carpenter helping to erect shoring/scaffolding fell about 52” and struck his head. He sustained head injuries requiring hospitalization that exceeded the threshold for a Type B investigation in accordance with Department of Energy (DOE) Order 225.1A, Accident Investigation. The accident occurred at the DOE’s Savannah River Site (SRS) at the Tritium Extraction Facility (TEF) construction site.

198

Evaluation of the location and recency of faulting near prospective surface facilities in Midway Valley, Nye County, Nevada  

SciTech Connect (OSTI)

Evaluation of surface faulting that may pose a hazard to prospective surface facilities is an important element of the tectonic studies for the potential Yucca Mountain high-level radioactive waste repository in southwestern Nevada. For this purpose, a program of detailed geologic mapping and trenching was done to obtain surface and near-surface geologic data that are essential for determining the location and recency of faults at a prospective surface-facilities site located east of Exile Hill in Midway Valley, near the eastern base of Yucca Mountain. The dominant tectonic features in the Midway Valley area are the north- to northeast-trending, west-dipping normal faults that bound the Midway Valley structural block-the Bow Ridge fault on the west side of Exile Hill and the Paint-brush Canyon fault on the east side of the valley. Trenching of Quaternary sediments has exposed evidence of displacements, which demonstrate that these block-bounding faults repeatedly ruptured the surface during the middle to late Quaternary. Geologic mapping, subsurface borehole and geophysical data, and the results of trenching activities indicate the presence of north- to northeast-trending faults and northwest-trending faults in Tertiary volcanic rocks beneath alluvial and colluvial sediments near the prospective surface-facilities site. North to northeast-trending faults include the Exile Hill fault along the eastern base of Exile Hill and faults to the east beneath the surficial deposits of Midway Valley. These faults have no geomorphic expression, but two north- to northeast-trending zones of fractures exposed in excavated profiles of middle to late Pleistocene deposits at the prospective surface-facilities site appear to be associated with these faults. Northwest-trending faults include the West Portal and East Portal faults, but no disruption of Quaternary deposits by these faults is evident. The western zone of fractures is associated with the Exile Hill fault. The eastern zone of fractures is within Quaternary alluvial sediments, but no bedrock was encountered in trenches and soil pits in this part of the prospective surface facilities site; thus, the direct association of this zone with one or more bedrock faults is uncertain. No displacement of lithologic contacts and soil horizons could be detected in the fractured Quaternary deposits. The results of these investigations imply the absence of any appreciable late Quaternary faulting activity at the prospective surface-facilities site.

Swan, F.H.; Wesling, J.R.; Angell, M.M.; Thomas, A.P.; Whitney, J.W.; Gibson, J.D.

2002-01-17T23:59:59.000Z

199

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations  

SciTech Connect (OSTI)

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Waters, R.D.; Gruebel, M.M. [eds.] [eds.

1996-03-01T23:59:59.000Z

200

Implementation of DOE/NFDI D&D Cost Estimating Tool (POWERtool) for Initiative Facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has embarked on an aggressive D&D program to reduce the footprint of excess facilities. Key to the success of this effort is the preparation of accurate cost estimates for decommissioning. SRS traditionally uses ''top-down'' rough order-of-magnitude (ROM) estimating for decommissioning cost estimates. A second cost estimating method (POWERtool) using a ''bottoms-up'' approach has been applied to many of the SRS excess facilities in the T and D-area. This paper describes the use of both estimating methods and compares the estimated costs to actual costs of 5 facilities that were decommissioned in 2002.

Austin, W. E.; WSRC; Baker, S. B. III, Cutshall, C. M.; Crouse, J. L.

2003-02-26T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Environmental Management Waste Management Facility (EMWMF) Site-Specific Health and Safety Plan, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Bechtel Jacobs Company LLC (BJC) policy is to provide a safe and healthy workplace for all employees and subcontractors. The implementation of this policy requires that operations of the Environmental Management Waste Management Facility (EMWMF), located one-half mile west of the U.S. Department of Energy (DOE) Y-12 National Security Complex, be guided by an overall plan and consistent proactive approach to environment, safety and health (ES&H) issues. The BJC governing document for worker safety and health, BJC/OR-1745, 'Worker Safety and Health Program', describes the key elements of the BJC Safety and Industrial Hygiene (IH) programs, which includes the requirement for development and implementation of a site-specific Health and Safety Plan (HASP) where required by regulation (refer also to BJC-EH-1012, 'Development and Approval of Safety and Health Plans'). BJC/OR-1745, 'Worker Safety and Health Program', implements the requirements for worker protection contained in Title 10 Code of Federal Regulations (CFR) Part 851. The EMWMF site-specific HASP requirements identifies safe operating procedures, work controls, personal protective equipment, roles and responsibilities, potential site hazards and control measures, site access requirements, frequency and types of monitoring, site work areas, decontamination procedures, and outlines emergency response actions. This HASP will be available on site for use by all workers, management and supervisors, oversight personnel and visitors. All EMWMF assigned personnel will be briefed on the contents of this HASP and will be required to follow the procedures and protocols as specified. The policies and procedures referenced in this HASP apply to all EMWMF operations activities. In addition the HASP establishes ES&H criteria for the day-to-day activities to prevent or minimize any adverse effect on the environment and personnel safety and health and to meet standards that define acceptable waste management practices. The HASP is written to make use of past experience and best management practices to eliminate or minimize hazards to workers or the environment from events such as fires, falls, mechanical hazards, or any unplanned release to the environment.

Flynn, N.C. Bechtel Jacobs

2008-04-21T23:59:59.000Z

202

Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)  

SciTech Connect (OSTI)

The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory constraints based on the intruder analysis are well above conservative estimates of the OSWDF inventory and, based on intruder disposal limits; about 7% of the disposal capacity is reached with the estimated OSWDF inventory.

Smith, Frank G.; Phifer, Mark A.

2014-01-22T23:59:59.000Z

203

HOLDUP MEASUREMENTS FOR THREE VISUAL EXAMINATION AND TRU REMEDIATION GLOVEBOX FACILITIES AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Visual Examination (VE) gloveboxes are used to remediate transuranic waste (TRU) drums at three separate facilities at the Savannah River Site. Noncompliant items are removed before the drums undergo further characterization in preparation for shipment to the Waste Isolation Pilot Plant (WIPP). Maintaining the flow of drums through the remediation process is critical to the program's seven-days-per-week operation. Conservative assumptions are used to ensure that glovebox contamination from this continual operation is below acceptable limits. Holdup measurements using cooled HPGe spectrometers are performed in order to confirm that these assumptions are conservative. {sup 239}Pu is the main nuclide of interest; however, {sup 241}Pu, equilibrium {sup 237}Np/{sup 233}Pa and {sup 238}Pu (if detected) are typically assayed. At the Savannah River National Laboratory (SRNL) facility {sup 243,244,245}Cm are also generally observed and are always reported at either finite levels or at limits of detection. A complete assay at each of the three facilities includes a measure of TRU content in the gloveboxes and HEPA filters in the glovebox exhaust. This paper includes a description of the {gamma}-PHA acquisitions, of the modeling, and of the calculations of nuclide content. Because each of the remediation facilities is unique and ergonomically unfavorable to {gamma}-ray acquisitions, we have constructed custom detector support devices specific to each set of acquisitions. This paper includes a description and photographs of these custom devices. The description of modeling and calculations include determination and application of container and matrix photon energy dependent absorption factors and also determination and application of geometry factors relative to our detector calibration geometry. The paper also includes a discussion of our measurements accuracy using off-line assays of two SRNL HEPA filters. The comparison includes assay of the filters inside of 55-gallon drums using the SRNL Q{sup 2} assay system and separately using off-line assay with an acquisition configuration unique from the original in-situ acquisitions.

Dewberry, R; Donald Pak, D

2007-05-04T23:59:59.000Z

204

An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System  

SciTech Connect (OSTI)

An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control & Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

Martyn, Rose [Global Nuclear Fuels; Fitzgerald, Peter [Global Nuclear Fuels; Stehle, Nicholas D [ORNL; Rowe, Nathan C [ORNL; Younkin, James R [ORNL

2011-01-01T23:59:59.000Z

205

Evaluation of the Drum Tipper Mechanism for the WRAP Facility  

SciTech Connect (OSTI)

The drum tipper assembly has had numerous problems and has recently failed. ARES Corporation was asked to evaluate the existing system and provide recommendations for a replacement system.

LEIST, K.J.

1999-12-07T23:59:59.000Z

206

Non-Operational Property Evaluation for the Hanford Site River Corridor - 12409  

SciTech Connect (OSTI)

The Hanford Site River Corridor consists of the former reactor areas of the 100 Areas and the former industrial (fuel processing) area in the 300 Area. Most of the waste sites are located close to the decommissioned reactors or former industrial facilities along the Columbia River. Most of the surface area of the River Corridor consists of land with little or no subsurface infrastructure or indication of past or present releases of hazardous constituents, and is referred to as non-operational property or non-operational area. Multiple lines of evidence have been developed to assess identified fate and transport mechanisms and to evaluate the potential magnitude and significance of waste site-related contaminants in the non-operational area. Predictive modeling was used for determining the likelihood of locating waste sites and evaluating the distribution of radionuclides in soil based on available soil concentration data and aerial radiological surveys. The results of this evaluation indicated: 1) With the exception of stack emissions, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas, 2) Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides, and (3) the likelihood of detecting elevated radionuclide concentrations or other waste sites in non-operational area soils is very small. The overall conclusions from the NPE evaluation of the River Corridor are: - With the exception of stack emissions to the air, transport pathways associated with waste site contaminants are unlikely to result in dispersion of contaminants in soil away from operational areas. While pathways such as windblown dust, overland transport and biointrusion have the potential for dispersing waste site contaminants, the resulting transport is unlikely to result in substantial contamination in non-operational areas. - Stack emissions that may have been associated with Hanford Site operations generally emitted short-lived and/or gaseous radionuclides; these radionuclides either would have decayed and would be undetectable in soil, or likely would not have deposited onto Hanford Site soils. A small fraction of the total historical emissions consisted of long-lived particulate radionuclides, which could have deposited onto the soil. Soil monitoring studies conducted as part of surveillance and monitoring programs do not indicate a build-up of radionuclide concentrations in soil, which might indicate potential deposition impacts from stack emissions. Aerial radiological surveys of the Hanford Site, while effective in detecting gamma-emitting nuclides, also do not indicate deposition patterns in soil from stack emissions. - The surveillance and monitoring programs also have verified that the limited occurrence of biointrusion observed in the River Corridor has not resulted in a spread of contamination into the non-operational areas. - Monitoring of radionuclides in ambient air conducted as part of the surveillance and monitoring programs generally show a low and declining trend of detected concentrations in air. Monitoring of radionuclides in soil and vegetation correspondingly show declining trends in concentrations, particularly for nuclides with short half lives (Cs-137, Co-60 and Sr-90). - Statistical analysis of the geographical distribution of waste sites based on man -made features and topography describes the likely locations of waste sites in the River Corridor. The results from this analysis reinforce the findings from the Orphan Site Evaluation program, which has systematically identified any remaining waste sites within the River Corridor. - Statistical analysis of the distribution of radionuclide concentrations observable from aerial surveys has confirmed that the likelihood of detecting elevated radionuclide concentrations in non-operational area soils is very small; the occurrences and locations where potentially elevated concentrations may be found are discussed below. In

Lowe, John [CH2M HILL, Richland, Washington 99354 (United States); Aly, Alaa [CH2M HILL Plateau Remediation Company and INTERA Incorporated, Richland, Washington 99354 (United States)

2012-07-01T23:59:59.000Z

207

A successful effort to involve stakeholders in a facility siting decision using LIPS with stakeholder involvement  

SciTech Connect (OSTI)

Local public opposition to federal bureaucratic decisions has resulted in public agencies rethinking the role of stakeholders in decision making. Efforts to include stakeholders directly in the decision-making process are on the increase. Unfortunately, many attempts to involve members of the public in decisions involving complex technical issues have failed. A key problem has been defining a meaningful role for the public in the process of arriving at a technical decision. This paper describes a successful effort by Sandia National Laboratories (SNL) in New Mexico to involve stakeholders in an important technical decision associated with its Environmental Restoration (ER) Project. The decision was where to locate a Corrective Action Management Unit (CAMU), a facility intended to consolidate and store wastes generated from the cleanup of hazardous waste sites. A formal priority setting process known as the Laboratory Integration Prioritization System (LIPS) was adapted to provide an approach for involving the public. Although rarely applied to stakeholder participation, the LIPS process proved surprisingly effective. It produced a consensus over a selected site and enhanced public trust and understanding of Project activities.

Merkhofer, L. [Applied Decision Analysis, Inc., Menlo Park, CA (United States); Conway, R. [Sandia National Labs., Albuquerque, NM (United States); Anderson, B. [Los Alamos National Lab., NM (United States)

1995-12-31T23:59:59.000Z

208

Idaho Waste Treatment Facility Startup Testing Suspended To Evaluate System  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinementEtching. | EMSLtheIndustry |MentoringFacilityIdaho Waste

209

Calendar year 2002 annual site environmental report for Tonopah Test Range, Nevada and Kauai Test Facility, Hawaii.  

SciTech Connect (OSTI)

Tonopah Test Range (TTR) in Nevada and Kauai Test Facility (KTF) in Hawaii are government-owned, contractor-operated facilities operated by Sandia Corporation, a subsidiary of Lockheed Martin Corporation. The U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA), through the Sandia Site Office (SSO), in Albuquerque, NM, oversees TTR and KTF's operations. Sandia Corporation conducts operations at TTR in support of DOE/NNSA's Weapons Ordnance Program and has operated the site since 1957. Westinghouse Government Services subcontracts to Sandia Corporation in administering most of the environmental programs at TTR. Sandia Corporation operates KTF as a rocket preparation launching and tracking facility. This Annual Site Environmental Report (ASER) summarizes data and the compliance status of the environmental protection and monitoring program at TTR and KTF through Calendar Year (CY) 2002. The compliance status of environmental regulations applicable at these sites include state and federal regulations governing air emissions, wastewater effluent, waste management, terrestrial surveillance, and Environmental Restoration (ER) cleanup activities. Sandia Corporation is responsible only for those environmental program activities related to its operations. The DOE/NNSA, Nevada Site Office (NSO) retains responsibility for the cleanup and management of ER TTR sites. Currently, there are no ER Sites at KTF. Environmental monitoring and surveillance programs are required by DOE Order 5400.1, General Environmental Protection Program (DOE 1990) and DOE Order 231.1, Environment, Safety, and Health Reporting (DOE 1996).

Wagner, Katrina; Sanchez, Rebecca V.; Mayeux, Lucie; Koss, Susan I.; Salinas, Stephanie A.

2003-09-01T23:59:59.000Z

210

Energy infrastructure of the United States and projected siting needs: Scoping ideas, identifying issues and options. Draft report of the Department of Energy Working Group on Energy Facility Siting to the Secretary  

SciTech Connect (OSTI)

A Department of Energy (DOE) Working Group on Energy Facility Siting, chaired by the Policy Office with membership from the major program and staff offices of the Department, reviewed data regarding energy service needs, infrastructure requirements, and constraints to siting. The Working Group found that the expeditious siting of energy facilities has important economic, energy, and environmental implications for key Administration priorities.

Not Available

1993-12-01T23:59:59.000Z

211

Development of technology for the design of shallow land burial facilities at arid sites  

SciTech Connect (OSTI)

The Los Alamos field research program involving technology development for arid shallow land burial (SLB) sites is described. Field data are presented for an integrated field experiment, which was designed to test individual SLB component experiments related to erosion control, biobarriers, and subsurface capillary and migration barriers. Field tests of biointrusion barriers at waste disposal sites and in experimental plots are reported. The results of a joint DOE/NRC experiment to evaluate leaching and transport of sorbing (Cs, Sr, Li) and nonsorbing (I, Br) solutes in sandy silt backfill are presented for steady-state and unsteady-state flow conditions. A capillary barrier experiment performed in a large caisson (3-m diameter, 6.1 m deep) is described and a year's worth of field data is presented.

Nyhan, J.W.; Abeele, W.V.; Drennon, B.J.; Herrera, W.J.; Lopez, E.A.; Langhorst, G.J.; Stallings, E.A.; Walker, R.D.; Martinez, J.L.

1985-01-01T23:59:59.000Z

212

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities  

SciTech Connect (OSTI)

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24.

Not Available

1993-11-01T23:59:59.000Z

213

Hanford Site Annual Report Radiological Dose Calculation Upgrade Evaluation  

SciTech Connect (OSTI)

Operations at the Hanford Site, Richland, Washington, result in the release of radioactive materials to offsite residents. Site authorities are required to estimate the dose to the maximally exposed offsite resident. Due to the very low levels of exposure at the residence, computer models, rather than environmental samples, are used to estimate exposure, intake, and dose. A DOS-based model has been used in the past (GENII version 1.485). GENII v1.485 has been updated to a Windows®-based software (GENII version 2.08). Use of the updated software will facilitate future dose evaluations, but must be demonstrated to provide results comparable to those of GENII v1.485. This report describes the GENII v1.485 and GENII v2.08 dose exposure, intake, and dose estimates for the maximally exposed offsite resident reported for calendar year 2008. The GENII v2.08 results reflect updates to implemented algorithms. No two environmental models produce the same results, as was again demonstrated in this report. The aggregated dose results from 2008 Hanford Site airborne and surface water exposure scenarios provide comparable dose results. Therefore, the GENII v2.08 software is recommended for future offsite resident dose evaluations.

Snyder, Sandra F.

2010-02-28T23:59:59.000Z

214

Establishment of a facility for intrusive characterization of transuranic waste at the Nevada Test Site  

SciTech Connect (OSTI)

This paper describes design and construction, project management, and testing results associated with the Waste Examination Facility (WEF) recently constructed at the Nevada Test Site (NTS). The WEF and associated systems were designed, procured, and constructed on an extremely tight budget and within a fast track schedule. Part 1 of this paper focuses on design and construction activities, Part 2 discusses project management of WEF design and construction activities, and Part 3 describes the results of the transuranic (TRU) waste examination pilot project conducted at the WEF. In Part 1, the waste examination process is described within the context of Waste Isolation Pilot Plant (WIPP) characterization requirements. Design criteria are described from operational and radiological protection considerations. The WEF engineered systems are described. These systems include isolation barriers using a glove box and secondary containment structure, high efficiency particulate air (HEPA) filtration and ventilation systems, differential pressure monitoring systems, and fire protection systems. In Part 2, the project management techniques used for ensuring that stringent cost/schedule requirements were met are described. The critical attributes of these management systems are described with an emphasis on team work. In Part 3, the results of a pilot project directed at performing intrusive characterization (i.e., examination) of TRU waste at the WEF are described. Project activities included cold and hot operations. Cold operations included operator training, facility systems walk down, and operational procedures validation. Hot operations included working with plutonium contaminated TRU waste and consisted of waste container breaching, waste examination, waste segregation, data collection, and waste repackaging.

Foster, B.D.; Musick, R.G.; Pedalino, J.P.; Cowley, J.L. [Bechtel Nevada Corp., Las Vegas, NV (United States); Karney, C.C. [Dept. of Energy, Las Vegas, NV (United States); Kremer, J.L.

1998-01-01T23:59:59.000Z

215

Decommissioning an Active Historical Reactor Facility at the Savannah River Site - 13453  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is an 802 square-kilometer United States Department of Energy (US DOE) nuclear facility located along the Savannah River near Aiken, South Carolina, where Management and Operations are performed by Savannah River Nuclear Solutions (SRNS). In 2004, DOE recognized SRS as structure within the Cold War Historic District of national, state and local significance composed of the first generation of facilities constructed and operated from 1950 through 1989 to produce plutonium and tritium for our nation's defense. DOE agreed to manage the SRS 105-C Reactor Facility as a potentially historic property due to its significance in supporting the U.S. Cold War Mission and for potential for future interpretation. This reactor has five primary areas within it, including a Disassembly Basin (DB) that received irradiated materials from the reactor, cooled them and prepared the components for loading and transport to a Separation Canyon for processing. The 6,317 square meter area was divided into numerous work/storage areas. The walls between the individual basin compartments have narrow vertical openings called 'slots' that permit the transfer of material from one section to another. Data indicated there was over 830 curies of radioactivity associated with the basin sediments and approximately 9.1 M liters of contaminated water, not including a large quantity of activated reactor equipment, scrap metal, and debris on the basin floor. The need for an action was identified in 2010 to reduce risks to personnel in the facility and to eliminate the possible release of contaminants into the environment. The release of DB water could potentially migrate to the aquifer and contaminate groundwater. DOE, its regulators [U. S. Environmental Protection Agency (USEPA)-Region 4 and the South Carolina Department of Health and Environmental Control (SCDHEC)] and the SC Historical Preservation Office (SHPO) agreed/concurred to perform a non-time critical removal action for the In Situ Decommissioning (ISD) of the 105-C Disassembly Basin. ISD consisted of stabilization/isolation of remaining contaminated water, sediment, activated reactor equipment, and scrap metal by filling the DB with underwater non-structural grout to the appropriate (-4.877 meter) grade-level, thence with dry area non-structural grout to the final -10 centimeter level. The roof over the DB was preserved due to its potential historical significance and to prevent the infiltration of precipitation. Forced evaporation was the form of treatment implemented to remove the approximately 9.1 M liters of contaminated basin water. Using specially formulated grouts, irradiated materials and sediment were treated by solidification/isolation thus reducing their mobility, reducing radiation exposure and creating an engineered barrier thereby preventing access to the contaminants. Grouting provided a low permeability barrier to minimize any potential transport of contaminants to the aquifer. Efforts were made to preserve the historical significance of the Reactor in accordance with the National Historic Preservation Act. ISD provides a cost effective means to isolate and contain residual radioactivity from past nuclear operations allowing natural radioactive decay to reduce hazards to manageable levels. This method limits release of radiological contamination to the environment, minimizes radiation exposure to workers, prevents human/animal access to the hazardous substances, and allows for ongoing monitoring of the decommissioned facility. Field construction was initiated in August 2011; evaporator operations commenced January 2012 and ended July 2012 with over 9 M liters of water treated/removed. Over 8,525 cubic meters of grout were placed, completing in August 2012. The project completed with an excellent safety record, on schedule and under budget. (authors)

Bergren, Christopher L.; Long, J. Tony; Blankenship, John K. [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, LLC, Bldg. 730-4B, Aiken, SC 29808 (United States); Adams, Karen M. [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)] [United States Department of Energy, Bldg. 730-B, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

216

Closure Report for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 [as amended March 2010]). CAU 116 consists of the following two Corrective Action Sites (CASs), located in Area 25 of the Nevada National Security Site: (1) CAS 25-23-20, Nuclear Furnace Piping and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 consisted of Building 3210 and the attached concrete shield wall. CAS 25-23-20 consisted of the nuclear furnace piping and tanks. Closure activities began in January 2007 and were completed in August 2011. Activities were conducted according to Revision 1 of the Streamlined Approach for Environmental Restoration Plan for CAU 116 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2008). This CR provides documentation supporting the completed corrective actions and provides data confirming that closure objectives for CAU 116 were met. Site characterization data and process knowledge indicated that surface areas were radiologically contaminated above release limits and that regulated and/or hazardous wastes were present in the facility.

NSTec Environmental Restoration

2011-09-29T23:59:59.000Z

217

Evaluation of a Fish Passage Site in the Walla Walla River Basin, 2009 Annual Report : September 2008 - August 2009.  

SciTech Connect (OSTI)

In 2009, Pacific Northwest National Laboratory (PNNL) evaluated the Touchet Consolidated Facility to determine if it is designed, constructed, operated, and maintained to effectively provide juvenile salmonids with safe passage past the diversion and back to the Touchet River. Completed in 2008, the Touchet Consolidated Facility combined two irrigation diversions with an existing intake for the Touchet Acclimation Facility. The consolidated facility includes a separate fish screen and intake for each user, a pool and chute fishway, and an adult fish trap. The fish screens portions of the facility were evaluated on April 20, 2009, using underwater videography, acoustic Doppler velocimeter measurements, and visual observations while water was diverted to the acclimation facility alone and again as water was diverted to the irrigation system and pond together. The facility is in good condition and is well maintained, although water velocities within the site do not meet the criteria set by the National Marine Fisheries Service (NMFS). Approach velocities above 0.4 ft/s at the upstream end of the facility and decreases in sweep velocity toward the bypass are likely caused by the proximity of the upstream screen to the spill over stoplogs that control flow at the upstream end of the forebay. We recommend working with Touchet Acclimation Facility staff to try different configurations and heights of forebay stoplogs while PNNL staff measure water velocities, allowing real-time monitoring of changes in approach and sweep velocities resulting from the configuration changes. It may be possible to bring approach and sweep velocities more in line with the NMFS criteria for juvenile fish screens. We also recommend evaluating the facility later in the year when river levels are low and the irrigation district is the only water user. During the site visit, it was noted that the upstream end of the fishway has relatively closely spaced louvers that point downstream. During higher river levels such as on April 20, the orientation of the louvers causes a headloss of up to 1 ft or more. Fish must maneuver through this hydraulic jump and between the louvers. The Washington Department of Fish and Wildlife is considering alternatives to this configuration; if needed, we would be available to offer technical assistance.

Chamness, Mickie A. [Pacific Northwest National Laboratory

2009-08-20T23:59:59.000Z

218

REGULATION AND SYSTEM INTERDEPENDENCE: EFFECTS ON THE SITING OF CALIFORNIA ELECTRICAL ENERGY FACILITIES  

E-Print Network [OSTI]

electricity, regardless of the ownership of the facilities, is public in the sense that it is a government

Kooser, J.C.

2013-01-01T23:59:59.000Z

219

A Model Evaluation Data Set for the Tropical ARM Sites  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

This data set has been derived from various ARM and external data sources with the main aim of providing modelers easy access to quality controlled data for model evaluation. The data set contains highly aggregated (in time) data from a number of sources at the tropical ARM sites at Manus and Nauru. It spans the years of 1999 and 2000. The data set contains information on downward surface radiation; surface meteorology, including precipitation; atmospheric water vapor and cloud liquid water content; hydrometeor cover as a function of height; and cloud cover, cloud optical thickness and cloud top pressure information provided by the International Satellite Cloud Climatology Project (ISCCP).

Jakob, Christian

220

Criteria for Evaluation of Nuclear Facility Training Programs  

Broader source: Energy.gov (indexed) [DOE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTS AVAILABLEReport 2009Site | Department of Energy Bryan Harting,8

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Criteria for Evaluation of Nuclear Facility Training Programs  

Broader source: Energy.gov (indexed) [DOE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana. DOCUMENTS AVAILABLEReport 2009Site | Department of Energy Bryan Harting,8

222

Report on the emergency response to the event on May 14, 1997, at the plutonuim reclamation facility, Hanford Site, Richland,Washington  

SciTech Connect (OSTI)

On the evening of May 14,1997, a chemical explosion Occurred at the Plutonium Reclamation Facility (PRF) in the 200 West Area(200-W) of the Hanford Site. The event warranted the declaration of an Alert emergency, activation of the Hanford Emergency Response Organization (BRO), and notification of offsite agencies. As a result of the emergency declaration, a subsequent evaluation was conducted to assess: 9 the performance of the emergency response organization o the occupational health response related to emergency activities o event notifications to offsite and environmental agencies. Additionally, the evaluation was designed to: 9 document the chronology of emergency and occupational health responses and environmental notifications connected with the explosion at the facility 0 assess the adequacy of the Hanford Site emergency preparedness activities; response readiness; and emergency management actions, occupational health, and environmental actions 0 provide an analysis of the causes of the deficiencies and weaknesses in the preparedness and response system that have been identified in the evaluation of the response a assign organizational responsibility to correct deficiencies and weaknesses a improve future performance 0 adjust elements of emergency implementing procedures and emergency preparedness activities.

Shoop, D.S.

1997-08-20T23:59:59.000Z

223

2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report  

SciTech Connect (OSTI)

This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation.

Luke, S.N.

1994-07-14T23:59:59.000Z

224

Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning  

E-Print Network [OSTI]

1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

American Society for Testing and Materials. Philadelphia

2002-01-01T23:59:59.000Z

225

Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities  

SciTech Connect (OSTI)

This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

NONE

1994-12-01T23:59:59.000Z

226

Review of project definition studies of possible on-site uses of superconducting super collider assets and facilities. Final report  

SciTech Connect (OSTI)

This document reports on the results of a peer review and evaluation of studies made of potential uses of assets from the terminated Superconducting Super Collider (SSC) project. These project definition studies focused on nine areas of use of major assets and facilities at the SSC site near Waxahachie, Texas. The studies were undertaken as part of the effort to maximize the value of the investment made in the SSC and were supported by two sets of grants, one to the Texas National Research Laboratory Commission (TNRLC) and the second to various universities and other institutions for studies of ideas raised by a public call for expressions of interest. The Settlement Agreement, recently signed by the Department of Energy (DOE) and TNRLC, provides for a division of SSC property. As part of the goal of maximizing the value of the SSC investment, the findings contained in this report are thus addressed to officials in both the Department and TNRLC. In addition, this review had several other goals: to provide constructive feedback to those doing the studies; to judge the benefits and feasibility (including funding prospects) of the projects studied; and to help worthy projects become reality by matching projects with possible funding sources.

NONE

1994-12-01T23:59:59.000Z

227

CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL  

SciTech Connect (OSTI)

RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

Farfan, E.; Coleman, R.

2011-03-31T23:59:59.000Z

228

Summary environmental site assessment report for the U.S. Department of Energy Oxnard Facility, Oxnard, California  

SciTech Connect (OSTI)

This report summarizes the investigations conducted by Rust Geotech at the U.S. Department of Energy (DOE) Oxnard facility, 1235 East Wooley Road, Oxnard, California. These investigations were designed to locate, identify, and characterize any regulated contaminated media on the site. The effort included site visits; research of ownership, historical uses of the Oxnard facility and adjacent properties, incidences of and investigations for contaminants on adjacent properties, and the physical setting of the site; sampling and analysis; and reporting. These investigations identified two friable asbestos gaskets on the site, which were removed, and nonfriable asbestos, which will be managed through the implementation of an asbestos management plan. The California primary drinking water standards were exceeded for aluminum on two groundwater samples and for lead in one sample collected from the shallow aquifer underlying the site; remediation of the groundwater in this aquifer is not warranted because it is not used. Treated water is available from a municipal water system. Three sludge samples indicated elevated heavy metals concentrations; the sludge must be handled as a hazardous waste if disposed. Polychlorinated biphenyls (PCBs) were detected at concentrations below remediation criteria in facility soils at two locations. In accordance with U.S. Environmental Protection Agency (EPA) and State of California guidance, remediation of the PCBs is not required. No other hazardous substances were detected in concentrations exceeding regulatory limits.

NONE

1996-02-01T23:59:59.000Z

229

Early Site Permit Demonstration Program: Regulatory criteria evaluation report  

SciTech Connect (OSTI)

The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

Not Available

1993-03-01T23:59:59.000Z

230

The National Criticality Experiments Research Center at the Device Assembly Facility, Nevada National Security Site: Status and Capabilities, Summary Report  

SciTech Connect (OSTI)

The National Criticality Experiments Research Center (NCERC) was officially opened on August 29, 2011. Located within the Device Assembly Facility (DAF) at the Nevada National Security Site (NNSS), the NCERC has become a consolidation facility within the United States for critical configuration testing, particularly those involving highly enriched uranium (HEU). The DAF is a Department of Energy (DOE) owned facility that is operated by the National Nuclear Security Agency/Nevada Site Office (NNSA/NSO). User laboratories include the Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). Personnel bring their home lab qualifications and procedures with them to the DAF, such that non-site specific training need not be repeated to conduct work at DAF. The NNSS Management and Operating contractor is National Security Technologies, LLC (NSTec) and the NNSS Safeguards and Security contractor is Wackenhut Services. The complete report provides an overview and status of the available laboratories and test bays at NCERC, available test materials and test support configurations, and test requirements and limitations for performing sub-critical and critical tests. The current summary provides a brief summary of the facility status and the method by which experiments may be introduced to NCERC.

S. Bragg-Sitton; J. Bess; J. Werner

2011-09-01T23:59:59.000Z

231

Evaluation of inherent distortions in the IIST facility using the RELAP5/MOD3 code  

SciTech Connect (OSTI)

The Institute of Nuclear Energy Research (INER) integral system test (IIST) facility is a reduced-height, reduced-pressure test facility constructed at INER that is used to simulate the thermal hydraulics of the Maanshan nuclear power plant (NPP). A small-scaled facility is not capable of simulating all the physical phenomena of an NPP because the behavior of an NPP during accidents is very complicated. Proper scaling then plays an important role in the design of a test facility to ensure the usefulness and applicability of experimental data obtained from a small-scaled facility. However, distortions caused by necessary compromises in the design and construction of a small-scaled test facility exist. The analysis here evaluates whether the inherent distortions in the IIST facility will distort the thermal-hydraulic behaviors of a natural-circulation experiment and influence the usefulness and applicability of the experimental data. Based on the current calculations, the IIST experimental results are found to be partially distorted. Appropriate consideration of and correction for these distortion effects are needed before the results of the IIST natural-circulation experiments can be used to reliably investigate the Maanshan NPP behavior expected by way of an appropriate scale-up procedure.

Ferng, Y.M. [Inst. of Nuclear Energy Research, Lung-Tan (Taiwan, Province of China)

1996-06-01T23:59:59.000Z

232

Umatilla Satellite and Release Sites Project : Final Siting Report.  

SciTech Connect (OSTI)

This report presents the results of site analysis for the Umatilla Satellite and Release Sites Project. The purpose of this project is to provide engineering services for the siting and conceptual design of satellite and release facilities for the Umatilla Basin hatchery program. The Umatilla Basin hatchery program consists of artificial production facilities for salmon and steelhead to enhance production in the Umatilla River as defined in the Umatilla master plan approved in 1989 by the Northwest Power Planning Council. Facilities identified in the master plan include adult salmon broodstock holding and spawning facilities, facilities for recovery, acclimation, and/or extended rearing of salmon juveniles, and development of river sites for release of hatchery salmon and steelhead. The historic and current distribution of fall chinook, summer chinook, and coho salmon and steelhead trout was summarized for the Umatilla River basin. Current and future production and release objectives were reviewed. Twenty seven sites were evaluated for the potential and development of facilities. Engineering and environmental attributes of the sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

Montgomery, James M.

1992-04-01T23:59:59.000Z

233

Development and evaluation of fully automated demand response in large facilities  

SciTech Connect (OSTI)

This report describes the results of a research project to develop and evaluate the performance of new Automated Demand Response (Auto-DR) hardware and software technology in large facilities. Demand Response (DR) is a set of activities to reduce or shift electricity use to improve electric grid reliability, manage electricity costs, and ensure that customers receive signals that encourage load reduction during times when the electric grid is near its capacity. The two main drivers for widespread demand responsiveness are the prevention of future electricity crises and the reduction of electricity prices. Additional goals for price responsiveness include equity through cost of service pricing, and customer control of electricity usage and bills. The technology developed and evaluated in this report could be used to support numerous forms of DR programs and tariffs. For the purpose of this report, we have defined three levels of Demand Response automation. Manual Demand Response involves manually turning off lights or equipment; this can be a labor-intensive approach. Semi-Automated Response involves the use of building energy management control systems for load shedding, where a preprogrammed load shedding strategy is initiated by facilities staff. Fully-Automated Demand Response is initiated at a building or facility through receipt of an external communications signal--facility staff set up a pre-programmed load shedding strategy which is automatically initiated by the system without the need for human intervention. We have defined this approach to be Auto-DR. An important concept in Auto-DR is that a facility manager is able to ''opt out'' or ''override'' an individual DR event if it occurs at a time when the reduction in end-use services is not desirable. This project sought to improve the feasibility and nature of Auto-DR strategies in large facilities. The research focused on technology development, testing, characterization, and evaluation relating to Auto-DR. This evaluation also included the related decisionmaking perspectives of the facility owners and managers. Another goal of this project was to develop and test a real-time signal for automated demand response that provided a common communication infrastructure for diverse facilities. The six facilities recruited for this project were selected from the facilities that received CEC funds for new DR technology during California's 2000-2001 electricity crises (AB970 and SB-5X).

Piette, Mary Ann; Sezgen, Osman; Watson, David S.; Motegi, Naoya; Shockman, Christine; ten Hope, Laurie

2004-03-30T23:59:59.000Z

234

Biological assessment of the effects of construction and operation of adepleted uranium hexafluoride conversion facility at the Portsmouth, Ohio,site.  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF{sub 6} inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This biological assessment (BA) has been prepared by DOE, pursuant to the National Environmental Policy Act of 1969 and the Endangered Species Act of 1974, to evaluate potential impacts to federally listed species from the construction and operation of a conversion facility at the DOE Portsmouth site. The Indiana bat is known to occur in the area of the Portsmouth site and may potentially occur on the site during spring or summer. Evaluations of the Portsmouth site indicated that most of the site was found to have poor summer habitat for the Indiana bat because of the small size, isolation, and insufficient maturity of the few woodlands on the site. Potential summer habitat for the Indiana bat was identified outside the developed area bounded by Perimeter Road, within the corridors along Little Beaver Creek, the Northwest Tributary stream, and a wooded area east of the X-100 facility. However, no Indiana bats were collected during surveys of these areas in 1994 and 1996. Locations A, B, and C do not support suitable habitat for the Indiana bat and would be unlikely to be used by Indiana bats. Indiana bat habitat also does not occur at Proposed Areas 1 and 2. Although Locations A and C contain small wooded areas, the small size and lack of suitable maturity of these areas indicate that they would provide poor habitat for Indiana bats. Trees that may be removed during construction would not be expected to be used for summer roosting by Indiana bats. Disturbance of Indiana bats potentially roosting or foraging in the vicinity of the facility during operations would be very unlikely, and any disturbance would be expected to be negligible. On the basis of these considerations, DOE concludes that the proposed action is not likely to adversely affect the Indiana bat. No critical habitat exists for this species in the action area. Although the timber rattlesnake occurs in the vicinity of the Portsmouth site, it has not been observed on the site. In addition, habitat for the timber rattlesnake is not present on the Portsmouth site. Therefore, DOE concludes that the proposed action would not affect the timber rattlesnake.

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

235

Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices  

SciTech Connect (OSTI)

This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

1995-05-01T23:59:59.000Z

236

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans  

SciTech Connect (OSTI)

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

Dwyer, P.A.

1991-10-01T23:59:59.000Z

237

General Engineer/Physical Scientist (Senior Facility Representative)  

Broader source: Energy.gov [DOE]

A successful candidate in this position will serve as the Site Managers Senior Facility Representative, and responsible for program management, technical monitoring, advising and evaluating all...

238

The 1993 baseline biological studies and proposed monitoring plan for the Device Assembly Facility at the Nevada Test Site  

SciTech Connect (OSTI)

This report contains baseline data and recommendations for future monitoring of plants and animals near the new Device Assembly Facility (DAF) on the Nevada Test Site (NTS). The facility is a large structure designed for safely assembling nuclear weapons. Baseline data was collected in 1993, prior to the scheduled beginning of DAF operations in early 1995. Studies were not performed prior to construction and part of the task of monitoring operational effects will be to distinguish those effects from the extensive disturbance effects resulting from construction. Baseline information on species abundances and distributions was collected on ephemeral and perennial plants, mammals, reptiles, and birds in the desert ecosystems within three kilometers (km) of the DAF. Particular attention was paid to effects of selected disturbances, such as the paved road, sewage pond, and the flood-control dike, associated with the facility. Radiological monitoring of areas surrounding the DAF is not included in this report.

Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

1995-02-01T23:59:59.000Z

239

The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility  

SciTech Connect (OSTI)

Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs.

Malenfant, R.E.

1991-12-01T23:59:59.000Z

240

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect (OSTI)

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

G. N. Doyle

2002-02-01T23:59:59.000Z

242

Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada  

SciTech Connect (OSTI)

The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document.

C. M. Obi

2000-12-01T23:59:59.000Z

243

Final Status Survey Report for Corrective Action Unit 117 - Pluto Disassembly Facility, Building 2201, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This document contains the process knowledge, radiological data and subsequent statistical methodology and analysis to support approval for the radiological release of Corrective Action Unit (CAU) 117 – Pluto Disassembly Facility, Building 2201 located in Area 26 of the Nevada National Security Site (NNSS). Preparations for release of the building began in 2009 and followed the methodology described in the Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM is the DOE approved process for release of Real Property (buildings and landmasses) to a set of established criteria or authorized limits. The pre-approved authorized limits for surface contamination values and corresponding assumptions were established by DOE O 5400.5. The release criteria coincide with the acceptance criteria of the U10C landfill permit. The U10C landfill is the proposed location to dispose of the radiologically non-impacted, or “clean,” building rubble following demolition. However, other disposition options that include the building and/or waste remaining at the NNSS may be considered providing that the same release limits apply. The Final Status Survey was designed following MARSSIM guidance by reviewing historical documentation and radiological survey data. Following this review a formal radiological characterization survey was performed in two phases. The characterization revealed multiple areas of residual radioactivity above the release criteria. These locations were remediated (decontaminated) and then the surface activity was verified to be less than the release criteria. Once remediation efforts had been successfully completed, a Final Status Survey Plan (10-015, “Final Status Survey Plan for Corrective Action Unit 117 – Pluto Disassembly Facility, Building 2201”) was developed and implemented to complete the final step in the MARSSIM process, the Final Status Survey. The Final Status Survey Plan consisted of categorizing each individual room into one of three categories: Class 1, Class 2 or Class 3 (a fourth category is a “Non-Impacted Class” which in the case of Building 2201 only pertained to exterior surfaces of the building.) The majority of the rooms were determined to fall in the less restrictive Class 3 category, however, Rooms 102, 104, 106, and 107 were identified as containing Class 1 and 2 areas. Building 2201 was divided into “survey units” and surveyed following the requirements of the Final Status Survey Plan for each particular class. As each survey unit was completed and documented, the survey results were evaluated. Each sample (static measurement) with units of counts per minute (cpm) was corrected for the appropriate background and converted to a value with units of dpm/100 cm2. With a surface contamination value in the appropriate units, it was compared to the surface contamination limits, or in this case the derived concentration guideline level (DCGLw). The appropriate statistical test (sign test) was then performed. If the survey unit was statistically determined to be below the DCGLw, then the survey unit passed and the null hypothesis (that the survey unit is above limits) was rejected. If the survey unit was equal to or below the critical value in the sign test, the null hypothesis was not rejected. This process was performed for all survey units within Building 2201. A total of thirty-three “Class 1,” four “Class 2,” and one “Class 3” survey units were developed, surveyed, and evaluated. All survey units successfully passed the statistical test. Building 2201 meets the release criteria commensurate with the Waste Acceptance Criteria (for radiological purposes) of the U10C landfill permit residing within NNSS boundaries. Based on the thorough statistical sampling and scanning of the building’s interior, Building 2201 may be considered radiologically “clean,” or free of contamination.

Jeremy Gwin and Douglas Frenette

2010-09-30T23:59:59.000Z

244

Evaluation of syngas production unit cost of bio-gasification facility using regression analysis techniques  

SciTech Connect (OSTI)

Evaluation of economic feasibility of a bio-gasification facility needs understanding of its unit cost under different production capacities. The objective of this study was to evaluate the unit cost of syngas production at capacities from 60 through 1800Nm 3/h using an economic model with three regression analysis techniques (simple regression, reciprocal regression, and log-log regression). The preliminary result of this study showed that reciprocal regression analysis technique had the best fit curve between per unit cost and production capacity, with sum of error squares (SES) lower than 0.001 and coefficient of determination of (R 2) 0.996. The regression analysis techniques determined the minimum unit cost of syngas production for micro-scale bio-gasification facilities of $0.052/Nm 3, under the capacity of 2,880 Nm 3/h. The results of this study suggest that to reduce cost, facilities should run at a high production capacity. In addition, the contribution of this technique could be the new categorical criterion to evaluate micro-scale bio-gasification facility from the perspective of economic analysis.

Deng, Yangyang; Parajuli, Prem B.

2011-08-10T23:59:59.000Z

245

GIS-based wind farm site selection: Evaluating the case for New York State  

E-Print Network [OSTI]

GIS-based wind farm site selection: Evaluating the case for New York State E-mail: rv2216@columbia Conference, Saratoga Springs, NY, November 15, 2011 #12;Where to build a 50 MW wind farm? 1. What sites.clca.columbia.edu GIS-based wind farm site selection: evaluating the case for New York State ­ NEARC GIS conference 2011

246

Evolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1  

E-Print Network [OSTI]

Evolution of a Visual Impact Model to Evaluate Nuclear Plant Siting and Design Option1 2/ Brian A and economic options for the analysis of nuclear plant siting possibilities (Burnham 1974; Jones, April 1975 of nuclear plant siting options for the AEC. BNWL's multi-disciplinary impact evaluation pro- cedure required

Standiford, Richard B.

247

Manhattan Project buildings and facilities at the Hanford Site: A construction history  

SciTech Connect (OSTI)

This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures.

Gerber, M.S.

1993-09-01T23:59:59.000Z

248

Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1  

SciTech Connect (OSTI)

The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

King, J.W.

1993-08-01T23:59:59.000Z

249

Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites. [Metal smelting facility  

SciTech Connect (OSTI)

Capabilities exist for reducing all the contaminated nickel, aluminum, and copper scrap to ingot form by smelting. Processing these metals at existing facilities could be completed in about 5 or 6 years. However, these metals represent only about 20% of the total metal inventories currently on hand at the DOE/ORO-managed sites. No provisions have been made for the ferrous scrap. Most of the ferrous scrap is unclassified and does not require secured storage. Also, the potential resale value of the ferrous scrap at about $100 per ton is very low in comparison. Consequently, this scrap has been allowed to accumulate. With several modifications and equipment additions, the induction melter at PGDP could begin processing ferrous scrap after its commitment to nickel and aluminum. The PGDP smelter is a retrofit installation, and annual throughput capabilities are limited. Processing of the existing ferrous scrap inventories would not be completed until the FY 1995-2000 time frame. An alternative proposal has been the installation of induction melters at the other two enrichment facilities. Conceptual design of a generic metal smelting facility is under way. The design study includes capital and operating costs for scrap preparation through ingot storage at an annual throughput of 10,000 tons per year. Facility design includes an induction melter with the capability of melting both ferrous and nonferrous metals. After three years of operation with scrapyard feed, the smelter would have excess capacity to support on-site decontamination and decomissioning projects or upgrading programs. The metal smelting facility has been proposed for FY 1984 line item funding with start-up operations in FY 1986.

Mack, J.E.; Williams, L.C.

1982-01-01T23:59:59.000Z

250

State waste discharge permit application for the 200 Area Effluent Treatment Facility and the State-Approved Land Disposal Site  

SciTech Connect (OSTI)

Application is being made for a permit pursuant to Chapter 173--216 of the Washington Administrative Code (WAC), to discharge treated waste water and cooling tower blowdown from the 200 Area Effluent Treatment Facility (ETF) to land at the State-Approved Land Disposal Site (SALDS). The ETF is located in the 200 East Area and the SALDS is located north of the 200 West Area. The ETF is an industrial waste water treatment plant that will initially receive waste water from the following two sources, both located in the 200 Area on the Hanford Site: (1) the Liquid Effluent Retention Facility (LERF) and (2) the 242-A Evaporator. The waste water discharged from these two facilities is process condensate (PC), a by-product of the concentration of waste from DSTs that is performed in the 242-A Evaporator. Because the ETF is designed as a flexible treatment system, other aqueous waste streams generated at the Hanford Site may be considered for treatment at the ETF. The origin of the waste currently contained in the DSTs is explained in Section 2.0. An overview of the concentration of these waste in the 242-A Evaporator is provided in Section 3.0. Section 4.0 describes the LERF, a storage facility for process condensate. Attachment A responds to Section B of the permit application and provides an overview of the processes that generated the wastes, storage of the wastes in double-shell tanks (DST), preliminary treatment in the 242-A Evaporator, and storage at the LERF. Attachment B addresses waste water treatment at the ETF (under construction) and the addition of cooling tower blowdown to the treated waste water prior to disposal at SALDS. Attachment C describes treated waste water disposal at the proposed SALDS.

Not Available

1993-08-01T23:59:59.000Z

251

Niagara falls storage site: Annual site environmental report, Lewiston, New York, Calendar Year 1988: Surplus Facilities Management Program (SFMP)  

SciTech Connect (OSTI)

The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during two round-trip flights from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1988 monitoring show that the NFSS is in compliance with applicable DOE radiation protection standards. 17 refs., 31 figs., 20 tabs.

Not Available

1989-04-01T23:59:59.000Z

252

EVALUATION OF MERCURY EMISSIONS FROM COAL-FIRED FACILITIES WITH SCR AND FGD SYSTEMS  

SciTech Connect (OSTI)

CONSOL Energy Inc., Research & Development (CONSOL), with support from the U.S. Department of Energy, National Energy Technology Laboratory (DOE) and the Electric Power Research Institute (EPRI), evaluated the effects of selective catalytic reduction (SCR) on mercury (Hg) capture in coal-fired plants equipped with an electrostatic precipitator (ESP)-wet flue gas desulfurization (FGD) combination or a spray dyer absorber-fabric filter (SDA-FF) combination. In this program CONSOL determined mercury speciation and removal at 10 bituminous coal-fired facilities; at four of these facilities, additional tests were performed on units without SCR, or with the existing SCR bypassed. This project final report summarizes the results and discusses the findings of the body of work as a whole. Eleven Topical Reports were issued (prior to this report) that describe in great detail the sampling results at each of the ten power plants individually. The results showed that the SCR-FGD combination removed a substantial fraction of mercury from flue gas. The coal-to-stack mercury removals ranged from 65% to 97% for the units with SCR and from 53% to 87% for the units without SCR. There was no indication that any type of FGD system was more effective at mercury removal than others. The coal-to-stack mercury removal and the removal in the wet scrubber were both negatively correlated with the elemental mercury content of the flue gas and positively correlated with the scrubber liquid chloride concentration. The coal chlorine content was not a statistically significant factor in either case. Mercury removal in the ESP was positively correlated with the fly ash carbon content and negatively correlated with the flue gas temperature. At most of the units, a substantial fraction (>35%) of the flue gas mercury was in the elemental form at the boiler economizer outlet. After passing through the SCR-air heater combination very little of the total mercury (<10%) remained in the elemental form in the flue gas; this was true for all SCR catalyst types and sources. Although chlorine has been suggested as a factor affecting the mercury speciation in flue gas, coal chlorine was not a statistically significant factor affecting mercury speciation at the economizer exit or at the air heater exit. The only statistically significant factors were the coal ash CaO content and the fly ash carbon content; the fraction of mercury in the elemental form at the economizer exit was positively correlated with both factors. In a direct comparison at four SCR-equipped units vs. similar units at the same sites without SCR (or with the SCR bypassed), the elemental mercury fractions (measured at the ESP outlet) were lower, and the coal-to-stack mercury removals were higher, when the SCR was present and operating. The average coal-to-stack mercury removal at the four units without an operating SCR was 72%, whereas the average removal at the same sites with operating SCRs was 88%. The unit mercury mass balance (a gauge of the overall quality of the tests) at all of the units ranged from 81% to 113%, which were within our QA/QC criterion of 80-120%.

J.A. Withum

2006-03-07T23:59:59.000Z

253

Use of DOE-2 to Evaluate Evaporative Cooling in Texas Correctional Facilities  

E-Print Network [OSTI]

, W.K., "Fundamental Concepts Integrating Evaporative Techniques in HVAC Systems," ASHRAE TRANSACTIONS, V. 96, Pt. 1, 1990. 3. McDonald, G.W., M.H. Turietta and R.E. Foster, "Modeling Evaporative Cooling Systems with DOE- 2. ID," ASHRAE...USE OF DOE-2 TO EVALUATE EVAPORATIVE COOLING IN TEXAS CORRECTIONAL FACILITIES Namir Saman, Ph.D., P.E. Tarek Bou-Saada Tia Heneghan Visiting Assistant Professor Research Associate Energy Manager Energy Systems Laboratory Energy Systems...

Saman, N.; Heneghan, T.; Bou-Saada, T. E.

1996-01-01T23:59:59.000Z

254

Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah...  

Office of Environmental Management (EM)

site considerations such as seismic and brown versus green field, (3) the public communication plan, (4) future public use options, and (5) the baseline schedule. What the ETR...

255

Facility Utilization and Risk Analysis for Remediation of Legacy Transuranic Waste at the Savannah River Site - 13572  

SciTech Connect (OSTI)

Savannah River Nuclear Solutions (SRNS) completed the Accelerated TRU Project for remediating legacy waste at the Savannah River Site with significant cost and schedule efficiencies due to early identification of resources and utilization of risk matrices. Initial project planning included identification of existing facilities that could be modified to meet the technical requirements needed for repackaging and remediating the waste. The project schedule was then optimized by utilization of risk matrices that identified alternate strategies and parallel processing paths which drove the overall success of the project. Early completion of the Accelerated TRU Project allowed SRNS to pursue stretch goals associated with remediating very difficult TRU waste such as concrete casks from the hot cells in the Savannah River National Laboratory. Project planning for stretch goals also utilized existing facilities and the risk matrices. The Accelerated TRU project and stretch goals were funded under the American Recovery and Reinvestment Act (ARRA). (authors)

Gilles, Michael L.; Gilmour, John C. [Savannah River Nuclear Solutions, LLC (United States)] [Savannah River Nuclear Solutions, LLC (United States)

2013-07-01T23:59:59.000Z

256

Estimate of Legacy Tritium in Building 232-H Tritium Facility, Savannah River Site  

SciTech Connect (OSTI)

This report describes an estimate of how much tritium will be held up in those parts of the 232-H process that will remain in the building after deactivation The anticipated state of this tritium is also discussed. This information will be used to assess the radiological status of the deactivated facility.

Clark, E.A.

2003-01-07T23:59:59.000Z

257

Grout Isolation and Stabilization of Structures and Materials within Nuclear Facilities at the U.S. Department of Energy, Hanford Site, Summary - 12309  

SciTech Connect (OSTI)

Per regulatory agreement and facility closure design, U.S. Department of Energy Hanford Site nuclear fuel cycle structures and materials require in situ isolation in perpetuity and/or interim physicochemical stabilization as a part of final disposal or interim waste removal, respectively. To this end, grout materials are being used to encase facilities structures or are being incorporated within structures containing hazardous and radioactive contaminants. Facilities where grout materials have been recently used for isolation and stabilization include: (1) spent fuel separations, (2) uranium trioxide calcining, (3) reactor fuel storage basin, (4) reactor fuel cooling basin transport rail tanker cars and casks, (5) cold vacuum drying and reactor fuel load-out, and (6) plutonium fuel metal finishing. Grout components primarily include: (1) portland cement, (2) fly ash, (3) aggregate, and (4) chemical admixtures. Mix designs for these typically include aggregate and non aggregate slurries and bulk powders. Placement equipment includes: (1) concrete piston line pump or boom pump truck for grout slurry, (2) progressive cavity and shearing vortex pump systems, and (3) extendable boom fork lift for bulk powder dry grout mix. Grout slurries placed within the interior of facilities were typically conveyed utilizing large diameter slick line and the equivalent diameter flexible high pressure concrete conveyance hose. Other facilities requirements dictated use of much smaller diameter flexible grout conveyance hose. Placement required direct operator location within facilities structures in most cases, whereas due to radiological dose concerns, placement has also been completed remotely with significant standoff distances. Grout performance during placement and subsequent to placement often required unique design. For example, grout placed in fuel basin structures to serve as interim stabilization materials required sufficient bearing i.e., unconfined compressive strength, to sustain heavy equipment yet, low breakout force to permit efficient removal by track hoe bucket or equivalent construction equipment. Further, flow of slurries through small orifice geometries of moderate head pressures was another typical design requirement. Phase separation of less than 1 percent was a typical design requirement for slurries. On the order of 30,000 cubic meters of cementitious grout have recently been placed in the above noted U.S. Department of Energy Hanford Site facilities or structures. Each has presented a unique challenge in mix design, equipment, grout injection or placement, and ultimate facility or structure performance. Unconfined compressive and shear strength, flow, density, mass attenuation coefficient, phase separation, air content, wash-out, parameters and others, unique to each facility or structure, dictate the grout mix design for each. Each mix design was tested under laboratory and scaled field conditions as a precursor to field deployment. Further, after injection or placement of each grout formulation, the material was field inspected either by standard laboratory testing protocols, direct physical evaluation, or both. (authors)

Phillips, S.J.; Phillips, M.; Etheridge, D. [Applied Geotechnical Engineering and Construction, Incorporated, Richland, Washington (United States); Chojnacki, D.W.; Herzog, C.B.; Matosich, B.J.; Steffen, J.M.; Sterling, R.T. [CH2M HILL Plateau Remediation Company, Richland, Washington (United States); Flaucher, R.H.; Lloyd, E.R. [Fluor Federal Services, Incorporated, Richland, Washington (United States)

2012-07-01T23:59:59.000Z

258

Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year  

SciTech Connect (OSTI)

This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

1985-06-01T23:59:59.000Z

259

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 116: Area 25 Test Cell C Facility, Nevada Test Site, Nevada, Revision 1  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 116, Area 25 Test Cell C Facility. The Test Cell C (TCC) Facility is located in Area 25 of the Nevada Test Site (NTS) approximately 25 miles northwest of Mercury, Nevada (Figure 1). CAU 116 is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) of 1996 (as amended February 2008) and consists of two Corrective Action Sites (CASs): (1) CAS 25-23-20, Nuclear Furnace Piping; and (2) CAS 25-41-05, Test Cell C Facility. CAS 25-41-05 is described in the FFACO as the TCC Facility but actually includes Building 3210 and attached concrete shield wall only. CAU 116 will be closed by demolishing Building 3210, the attached concrete shield wall, and the nuclear furnace piping. In addition, as a best management practice (BMP), Building 3211 (moveable shed) will be demolished due to its close proximity to Building 3210. This will aid in demolition and disposal operations. Radiological surveys will be performed on the demolition debris to determine the proper disposal pathway. As much of the demolition debris as space allows will be placed into the Building 3210 basement structure. After filling to capacity with demolition debris, the basement structure will be mounded or capped and closed with administrative controls. Prior to beginning demolition activities and according to an approved Sampling and Analysis Plan (SAP), representative sampling of surface areas that are known, suspected, or have the potential to contain hazardous constituents such as lead or polychlorinated biphenyls (PCBs) will be performed throughout all buildings and structures. Sections 2.3.2, 4.2.2.2, 4.2.2.3, 4.3, and 6.2.6.1 address the methodologies employed that assure the solid debris placed in the basement structure will not contain contaminants of concern (COCs) above hazardous waste levels. The anticipated post-closure-posting requirements for the mounded/capped basement structure, as well as for the entire CAU, are addressed in Section 4.2.10. The site contains radiologically impacted surfaces and hazardous materials. Based on review of the historical information for CAU 116 and recent site inspections, there is sufficient process knowledge to close CAU 116 using the SAFER process. CAUs that may be closed using the SAFER process have conceptual corrective actions that are clearly identified. Consequently, corrective action alternatives can be chosen prior to completing a corrective action investigation, given anticipated investigation results. The SAFER process combines elements of the data quality objective (DQO) process and the observational approach to plan and conduct closure activities. The DQOs are used to identify the problem and define the type and quality of data needed to complete the investigation phase of the SAFER process. The purpose of the investigation phase is to verify the adequacy of existing information used to determine the chosen corrective action. The observational approach provides a framework for managing uncertainty during the planning and decision-making phases of the project. The SAFER process allows for technical decisions to be made based on information gathered during site visits, interviews, meetings, research, and a consensus of opinion by the decontamination and decommissioning (D&D) team members. Any uncertainties are addressed by documented assumptions that are verified by sampling and analysis, data evaluation, onsite observations, and contingency plans, as necessary. Closure activities may proceed simultaneously with site characterization as sufficient data are gathered to confirm or disprove the assumptions made during selection of the corrective action. If, at any time during the closure process, new information is discovered that indicates that closure activities should be revised, closure activities will be reevaluated as appropriate. Based on a detailed review of historical documentation, there is sufficient process know

NSTec Environmental Restoration

2008-12-01T23:59:59.000Z

260

Evaluation of the Deployable Seismic Verification System at the Pinedale Seismic Research Facility  

SciTech Connect (OSTI)

The intent of this report is to examine the performance of the Deployable Seismic Verification System (DSVS) developed by the Department of Energy (DOE) through its national laboratories to support monitoring of underground nuclear test treaties. A DSVS was installed at the Pinedale Seismic Research Facility (PSRF) near Boulder, Wyoming during 1991 and 1992. This includes a description of the system and the deployment site. System performance was studied by looking at four areas: system noise, seismic response, state of health (SOH) and operational capabilities.

Carr, D.B.

1993-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Natural phenomena hazards evaluation of equipment and piping of Gaseous Diffusion Plant Uranium Enrichment Facility  

SciTech Connect (OSTI)

In support of the Gaseous Diffusion Plant Safety Analysis Report Upgrade program (GDP SARUP), a natural phenomena hazards evaluation was performed for the main process equipment and piping in the uranium enrichment buildings at Paducah and Portsmouth gaseous diffusion plants. In order to reduce the cost of rigorous analyses, the evaluation methodology utilized a graded approach based on an experience data base collected by SQUG/EPRI that contains information on the performance of industrial equipment and piping during past earthquakes. This method consisted of a screening walkthrough of the facility in combination with the use of engineering judgment and simple calculations. By using these screenings combined with evaluations that contain decreasing conservatism, reductions in the time and cost of the analyses were significant. A team of experienced seismic engineers who were trained in the use of the DOE SQUG/EPRI Walkdown Screening Material was essential to the success of this natural phenomena hazards evaluation.

Singhal, M.K.; Kincaid, J.H.; Hammond, C.R.; Stockdale, B.I.; Walls, J.C. [Oak Ridge National Lab., TN (United States). Technical Programs and Services; Brock, W.R.; Denton, D.R. [Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

1995-12-31T23:59:59.000Z

262

Savannah River Site’s H Canyon Begins 2012 with New and Continuing Missions- Transuranic waste remediation, new mission work are the focus of the nation’s only active nuclear chemical separations facility in 2012  

Broader source: Energy.gov [DOE]

AIKEN, S.C. – The Savannah River Site (SRS) is breathing new life into the H Canyon, the only active nuclear chemical separations facility still operating in the U.S.

263

Finding of no significant impact for the tritium facility modernization and consolidation project at the Savannah River Site  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1222) for the proposed modernization and consolidation of the existing tritium facilities at the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an environmental impact statement (EIS) is not required, and DOE is issueing this Finding of No Significant Impact (FONSI).

NONE

1998-01-01T23:59:59.000Z

264

Environmental Evaluation of the NSLS-II Construction Site  

E-Print Network [OSTI]

pumps Coal storage and later fuel oil Boiler facilities Former Landfill Vehicle Repair Area to the east storage Scrap metal storage Warehouse row ­ ca 1952 #12;Preconstruction Planning (Path forward) Demolition;Preconstruction Planning (Path forward) Collected soil and ground water samples near Bldg. 208 to ensure

Homes, Christopher C.

265

OMEGA: A NEW COLD X-RAY SIMULATION FACILITY FOR THE EVALUATION OF OPTICAL COATINGS  

SciTech Connect (OSTI)

We report on recent progress for the development of a new cold X-ray optical test capability using the Omega Facility located at the Laboratory for Laser Energetics (LLE) at the University of Rochester. These tests were done on the 30 kJ OMEGA laser at the Laboratory for Laser Energetics (LLE) at the University of Rochester, Rochester, NY. We conducted a six-shot series called OMEGA II on 14 July 2006 in one eight-hour day (supported by the Defense Threat Reduction Agency). The initial testing was performed using simple protected gold optical coatings on fused silica substrates. PUFFTFT analyses were completed and the specimen's thermal lateral stress and transverse stress conditions were calculated and interpreted. No major anomalies were detected. Comparison of the pre- and posttest reflective measurements coupled with the TFCALC analyses proved invaluable in guiding the analyses and interpreting the observed damage. The Omega facility is a high quality facility for performing evaluation of optical coatings and coupons and provides experience for the development of future National Ignition Facility (NIF) testing.

Fisher, J H; Newlander, C D; Fournier, K B; Beutler, D E; Coverdale, C A; May, M J; Tobin, M; Davis, J F; Shiekh, D

2007-04-27T23:59:59.000Z

266

Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.

NONE

1992-01-01T23:59:59.000Z

267

Biological assessment of the effects of construction and operation of a depleted uranium hexafluoride conversion facility at the Paducah, Kentucky, site.  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF6 inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This biological assessment (BA) has been prepared by DOE, pursuant to the National Environmental Policy Act of 1969 (NEPA) and the Endangered Species Act of 1974, to evaluate potential impacts to federally listed species from the construction and operation of a conversion facility at the DOE Paducah site.

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

268

Federal Facilities Liaison Weighs in on EM Achievements, Challenges at Savannah River Site  

Broader source: Energy.gov [DOE]

AIKEN, S.C. – For more than two decades, Shelly Wilson has been working with the Savannah River Site (SRS) as an employee of South Carolina Department of Health and Environmental Control (SCDHEC)....

269

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste.

NONE

1994-12-31T23:59:59.000Z

270

Recommended Method To Account For Daughter Ingrowth For The Portsmouth On-Site Waste Disposal Facility Performance Assessment Modeling  

SciTech Connect (OSTI)

A 3-D STOMP model has been developed for the Portsmouth On-Site Waste Disposal Facility (OSWDF) at Site D as outlined in Appendix K of FBP 2013. This model projects the flow and transport of the following radionuclides to various points of assessments: Tc-99, U-234, U-235, U-236, U-238, Am-241, Np-237, Pu-238, Pu-239, Pu-240, Th-228, and Th-230. The model includes the radioactive decay of these parents, but does not include the associated daughter ingrowth because the STOMP model does not have the capability to model daughter ingrowth. The Savannah River National Laboratory (SRNL) provides herein a recommended method to account for daughter ingrowth in association with the Portsmouth OSWDF Performance Assessment (PA) modeling.

Phifer, Mark A.; Smith, Frank G. III

2013-06-21T23:59:59.000Z

271

DECOMMISSIONING OF THE 247-F FUEL MANUFACTURING FACILITY AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Building 247-F at SRS was a roughly 110,000 ft{sup 2} two-story facility designed and constructed during the height of the cold war naval buildup to provide additional naval nuclear fuel manufacturing capacity in early 1980s. The building layout is shown in Fig. 1. A photograph of the facility is shown in Fig. 2. The manufacturing process employed a wide variety of acids, bases, and other hazardous materials. As the cold war wound down, the need for naval fuel declined. Consequently, the facility was shut down and underwent initial deactivation. All process systems were flushed with water and drained using the existing process drain valves. However, since these drains were not always installed at the lowest point in piping and equipment systems, a significant volume of liquid remained after initial deactivation was completed in 1990. At that time, a non-destructive assay of the process area identified approximately 17 (+/- 100%) kg of uranium held up in equipment and piping.

Santos, J; Stephen Chostner, S

2007-05-22T23:59:59.000Z

272

Allowable residual contamination levels for decommissioning the 115-F and 117-F facilities at the Hanford Site  

SciTech Connect (OSTI)

This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for the 115-F and 117-F facilities at the Hanford Site. The purpose of this study is to provide data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. Information on restricted and controlled use is provided to permit a full consideration of decommissioning alternatives. Procedures are presented for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations and to determine instrument responses for various mixtures of radionuclides. Finally, a comparison is made between existing decommissioning guidance and the ARCL values calculated for unrestricted release of the 115-F and 117-F facilities. The comparison shows a good agreement.

Kennedy, W.E. Jr.; Napier, B.A.

1983-07-01T23:59:59.000Z

273

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect (OSTI)

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

NONE

1995-06-30T23:59:59.000Z

274

Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506  

SciTech Connect (OSTI)

The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

Beres, Christopher M.; Fort, E. Joseph [Cabrera Services, Inc., 473 Silver Lane, East Hartford, CT 06118 (United States)] [Cabrera Services, Inc., 473 Silver Lane, East Hartford, CT 06118 (United States); Boyle, James D. [United States Army Corps of Engineers - Buffalo, 1776 Niagara Street, Buffalo, NY 14207 (United States)] [United States Army Corps of Engineers - Buffalo, 1776 Niagara Street, Buffalo, NY 14207 (United States)

2013-07-01T23:59:59.000Z

275

FOAM FORMATION IN THE SALTSTONE PRODUCTION FACILITY: EVALUATION OF SOURCES AND MITIGATION  

SciTech Connect (OSTI)

The Saltstone Production Facility receives waste from Tank 50H for treatment. Influents into Tank 50H include the Effluent Treatment Project waste concentrate, H-Canyon low activity waste and General Purpose Evaporator bottoms, Modular Caustic Side Solvent Extraction Unit decontaminated salt solution, and salt solution from the Deliquification, Dissolution and Adjust campaign. Using the Waste Characterization System (WCS), this study tracks the relative amounts of each influent into Tank 50H, as well as the total content of Tank 50H, in an attempt to identify the source of foaming observed in the Saltstone Production Facility hopper. Saltstone has been using antifoam as part of routine processing with the restart of the facility in December 2006. It was determined that the maximum admix usage in the Saltstone Production Facility, both antifoam and set retarder, corresponded with the maximum concentration of H-Canyon low activity waste in Tank 50H. This paper also evaluates archived salt solutions from Waste Acceptance Criteria analysis for propensity to foam and the antifoam dosage required to mitigate foaming. It was determined that Effluent Treatment Project contributed to the expansion factor (foam formation) and General Purpose Evaporator contributed to foaminess (persistence). It was also determined that undissolved solids contribute to foam persistence. It was shown that additions of Dow Corning Q2-1383a antifoam reduced both the expansion factor and foaminess of salt solutions. The evaluation of foaming in the grout hopper during the transition from water to salt solution indicated that higher water-to-premix ratios tended to produce increased foaming. It was also shown that additions of Dow Corning Q2-1383a antifoam reduced foam formation and persistence.

Cozzi, A.

2011-01-18T23:59:59.000Z

276

Vegetation communities associated with the 100-Area and 200-Area facilities on the Hanford Site  

SciTech Connect (OSTI)

The Hanford Site, Benton County, Washington, lies within the broad semi-arid shrub-steppe vegetation zone of the Columbia Basin. Thirteen different habitat types on the Hanford Site have been mapped in Habitat Types on the Hanford Site: Wildlife and Plant Species of Concern (Downs et al. 1993). In a broad sense, this classification is correct. On a smaller scale, however, finer delineations are possible. This study was conducted to determine the plant communities and estimate vegetation cover in and directly adjacent to the 100 and 200 Areas, primarily in relation to waste sites, as part of a comprehensive ecological study for the Compensation Environmental Response, Compensation, and Liability Act (CERCLA) characterization of the 100 and 200 Areas. During the summer of 1993, field surveys were conducted and a map of vegetation communities in each area, including dominant species associations, was produced. The field surveys consisted of qualitative community delineations. The community delineations described were made by field reconnaissance and are qualitative in nature. The delineations were made by visually determining the dominant plant species or vegetation types and were based on the species most apparent at the time of inspection. Additionally, 38 transects were run in these plant communities to try to obtain a more accurate representation of the community. Because habitat disturbances from construction/operations activities continue to occur in these areas, users of this information should be cautious in applying these maps without a current ground survey. This work will complement large-scale habitat maps of the Hanford Site.

Stegen, J.A.

1994-01-17T23:59:59.000Z

277

Confined Spaces Assessment Plan - Developed By NNSA/Nevada Site...  

Broader source: Energy.gov (indexed) [DOE]

CONFINED SPACES Assessment Plan NNSANevada Site Office Facility Representative Division Performance Objective: This assessment provides a basis for evaluating the safety...

278

A Historical Evaluation of the U15 Complex, Nevada National Security Site, Nye County, Nevada  

SciTech Connect (OSTI)

This report presents a historical evaluation of the U15 Complex on the Nevada National Security Site (NNSS) in southern Nevada. The work was conducted by the Desert Research Institute at the request of the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office and the U.S. Department of Defense, Defense Threat Reduction Agency. Three underground nuclear tests and two underground nuclear fuel storage experiments were conducted at the complex. The nuclear tests were Hard Hat in 1962, Tiny Tot in 1965, and Pile Driver in 1966. The Hard Hat and Pile Driver nuclear tests involved different types of experiment sections in test drifts at various distances from the explosion in order to determine which sections could best survive in order to design underground command centers. The Tiny Tot nuclear test involved an underground cavity in which the nuclear test was executed. It also provided data in designing underground structures and facilities to withstand a nuclear attack. The underground nuclear fuel storage experiments were Heater Test 1 from 1977 to 1978 and Spent Fuel Test - Climax from 1978 to 1985. Heater Test 1 was used to design the later Spent Fuel Test - Climax experiment. The latter experiment was a model of a larger underground storage facility and primarily involved recording the conditions of the spent fuel and the surrounding granite medium. Fieldwork was performed intermittently in the summers of 2011 and 2013, totaling 17 days. Access to the underground tunnel complex is sealed and unavailable. Restricted to the surface, four buildings, four structures, and 92 features associated with nuclear testing and fuel storage experiment activities at the U15 Complex have been recorded. Most of these are along the west side of the complex and next to the primary access road and are characteristic of an industrial mining site, albeit one with scientific interests. The geomorphological fieldwork was conducted over three days in the summer of 2011. It was discovered that major modifications to the terrain have resulted from four principal activities. These are road construction and maintenance, mining activities related to development of the tunnel complex, site preparation for activities related to the tests and experiments, and construction of drill pads and retention ponds. Six large trenches for exploring across the Boundary geologic fault are also present. The U15 Complex, designated historic district 143 and site 26NY15177, is eligible to the National Register of Historic Places under Criteria A, C, and D of 36 CFR Part 60.4. As a historic district and archaeological site eligible to the National Register of Historic Places, the Desert Research Institute recommends that the area defined for the U15 Complex, historic district 143 and site 26NY15117, be left in place in its current condition. The U15 Complex should also be included in the NNSS cultural resources monitoring program and monitored for disturbances or alterations.

Drollinger, Harold [DRI; Holz, Barbara A [DRI; Bullard, Thomas F [DRI; Goldenberg, Nancy G [Carey & Co; Ashbaugh, Laurence J [DRI; Griffin, Wayne R [DRI

2014-01-09T23:59:59.000Z

279

Independent Assessment of the Savannah River Site High-Level Waste Salt Disposition Alternatives Evaluation  

SciTech Connect (OSTI)

This report presents the results of the Independent Project Evaluation (IPE) Team assessment of the Westinghouse Savannah River Company High-Level Waste Salt Disposition Systems Engineering (SE) Team's deliberations, evaluations, and selections. The Westinghouse Savannah River Company concluded in early 1998 that production goals and safety requirements for processing SRS HLW salt to remove Cs-137 could not be met in the existing In-Tank Precipitation Facility as currently configured for precipitation of cesium tetraphenylborate. The SE Team was chartered to evaluate and recommend an alternative(s) for processing the existing HLW salt to remove Cs-137. To replace the In-Tank Precipitation process, the Savannah River Site HLW Salt Disposition SE Team downselected (October 1998) 140 candidate separation technologies to two alternatives: Small-Tank Tetraphenylborate (TPB) Precipitation (primary alternative) and Crystalline Silicotitanate (CST) Nonelutable Ion Exchange (backup alternative). The IPE Team, commissioned by the Department of Energy, concurs that both alternatives are technically feasible and should meet all salt disposition requirements. But the IPE Team judges that the SE Team's qualitative criteria and judgments used in their downselection to a primary and a backup alternative do not clearly discriminate between the two alternatives. To properly choose between Small-Tank TPB and CST Ion Exchange for the primary alternative, the IPE Team suggests the following path forward: Complete all essential R and D activities for both alternatives and formulate an appropriate set of quantitative decision criteria that will be rigorously applied at the end of the R and D activities. Concurrent conceptual design activities should be limited to common elements of the alternatives.

J. T. Case (DOE-ID); M. L. Renfro (INEEL)

1998-12-01T23:59:59.000Z

280

1997 evaluation of tritium removal and mitigation technologies for Hanford Site wastewaters  

SciTech Connect (OSTI)

This report contains results of a biennial assessment of tritium separation technology and tritium nitration techniques for control of tritium bearing wastewaters at the Hanford Site. Tritium in wastewaters at Hanford have resulted from plutonium production, fuel reprocessing, and waste handling operations since 1944. this assessment was conducted in response to the Hanford Federal Facility Agreement and Consent Order.

Jeppson, D.W.; Biyani, R.K.; Duncan, J.B.; Flyckt, D.L.; Mohondro, P.C.; Sinton, G.L.

1997-07-24T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites  

SciTech Connect (OSTI)

The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

Maheras, Steven J. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Best, Ralph [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River National Laboratory, Aiken, SC (United States); McConnell, Paul [Sandia National Laboratories, Albuquerque, NM (United States)

2013-04-30T23:59:59.000Z

282

Monticello NPL Sites Federal Facilities Agreement Meeting Minutes & Action Items  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE Cores Tubay Long-TermGWSHP3SiteS H

283

1994 Baseline biological studies for the Device Assembly Facility at the Nevada Test Site  

SciTech Connect (OSTI)

This report describes environmental work performed at the Device Assembly Facility (DAF) in 1994 by the Basic Environmental Monitoring and Compliance Program (BECAMP). The DAF is located near the Mojave-Great Basin desert transition zone 27 km north of Mercury. The area immediately around the DAF building complex is a gentle slope cut by 1 to 3 m deep arroyos, and occupied by transitional vegetation. In 1994, construction activities were largely limited to work inside the perimeter fence. The DAF was still in a preoperational mode in 1994, and no nuclear materials were present. The DAF facilities were being occupied so there was water in the sewage settling pond, and the roads and lights were in use. Sampling activities in 1994 represent the first year in the proposed monitoring scheme. The proposed biological monitoring plan gives detailed experimental protocols. Plant, lizard, tortoise, small mammal, and bird surveys were performed in 1994. The authors briefly outline procedures employed in 1994. Studies performed on each taxon are reviewed separately then summarized in a concluding section.

Townsend, Y.E. [ed.; Woodward, B.D.; Hunter, R.B.; Greger, P.D.; Saethre, M.B.

1995-02-01T23:59:59.000Z

284

LLNL heart valve condition classification project anechoic testing results at the TRANSDEC evaluation facility  

SciTech Connect (OSTI)

This report first briefly outlines the procedures and support/activation fixture developed at LLNL to perform the heart valve tests in an anechoic-like tank at the US Navy Transducer Evaluation Facility (TransDec) located in San Diego, CA. Next they discuss the basic experiments performed and the corresponding experimental plan employed to gather meaningful data systematically. The signal processing required to extract the desired information is briefly developed along with some of the data. Finally, they show the results of the individual runs for each valve, point out any of the meaningful features and summaries.

Candy, J V

1999-10-31T23:59:59.000Z

285

Criteria for the development and use of the methodology for environmentally-acceptable fossil energy site evaluation and selection. Volume 2. Final report  

SciTech Connect (OSTI)

This report serves as a companion document to the report, Volume 1: Environmentally-Acceptable Fossil Energy Site Evaluation and Selection: Methodology and Users Guide, in which a methodology was developed which allows the siting of fossil fuel conversion facilities in areas with the least environmental impact. The methodology, known as SELECS (Site Evaluation for Energy Conversion Systems) does not replace a site specific environmental assessment, or an environmental impact statement (EIS), but does enhance the value of an EIS by thinning down the number of options to a manageable level, by doing this in an objective, open and selective manner, and by providing preliminary assessment and procedures which can be utilized during the research and writing of the actual impact statement.

Eckstein, L.; Northrop, G.; Scott, R.

1980-02-01T23:59:59.000Z

286

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility  

SciTech Connect (OSTI)

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

2013-01-11T23:59:59.000Z

287

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113  

SciTech Connect (OSTI)

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, P.O. Box 1600, MSIN R4-41, 99352 (United States)] [CH2M HILL Plateau Remediation Company, P.O. Box 1600, MSIN R4-41, 99352 (United States)

2013-07-01T23:59:59.000Z

288

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

2008-03-01T23:59:59.000Z

289

Process centrifuge operating problems and equipment failures in canyon reprocessing facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Laboratory (SRL) maintains a compilation of operating problems and equipment failures that have occurred in the fuel reprocessing areas of the Savannah River Site (SRS). At present, the data bank contains more than 230,000 entries ranging from minor equipment malfunctions to incidents with the potential for injury or contamination of personnel, or for economic loss. The data bank has been used extensively for a wide variety of purposes, such as failure analyses, trend analyses, and preparation of safety analyses. Typical of the data are problems associated with the canyon process centrifuges. This report contains a compilation of the centrifuge operating problems and equipment failures primarily as an aid to organizations with related equipment. Publication of these data was prompted by a number of requests for this information by other Department of Energy (DOE) sites. 11 refs., 2 figs., 4 tabs.

Durant, W.S.; Baughman, D.F.

1990-03-01T23:59:59.000Z

290

File:07MTAEnergyFacilitySiting (6).pdf | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublicIDAPowerPlantSitingConstruction.pdf Jump to: navigation, search File File history File

291

Evaluating suspect sites {open_quotes}to clean or not to clean?{close_quotes}  

SciTech Connect (OSTI)

Within many large government reservations are many sites that are potentially contaminated from various uses such as experiments, material storage, or material processes. There also exist many smaller areas that, by proximity to contaminated sites, or due to work contracts, are likely to be contaminated. The party responsible for such sites must evaluate if remediation is required, based on current guidelines and future uses. The Departments of Defense and Energy have many sites and properties that are suspected of being contaminated or associated with operations that could cause contamination. In some cases the contaminants may have been adequately cleaned up, then decayed away, biodegraded, or dispersed to a nondetectable level. The decision to remove these sites from any further consideration of remediation or control must be based on historical data, potential contaminants, current analytical data, future uses, and the cost associated with managing the sites. This paper deals with the methodology for evaluating small sites and gives some case studies.

Murray, M.E.; Coleman, R.L.; Tiner, P.F.

1996-04-01T23:59:59.000Z

292

Environmental Innovation Center Solar Site Evaluation: San José...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

the evaluations in partnership with, and on behalf of, the U.S. Department of Energy (DOE) as part of the Solar America Initiative, a multi-year program aimed at...

293

Voluntary Protection Program Onsite Review, Waste Sampling and Characterization Facility- May 2007  

Broader source: Energy.gov [DOE]

Evaluation of Waste Sampling and Characterization Facility to make the final decision regarding the company’s continued participation in DOE-VPP as a Star site.

294

Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells.

NONE

1995-03-01T23:59:59.000Z

295

SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION  

SciTech Connect (OSTI)

The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These “123 agreements” are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

Magoulas, V.

2013-06-03T23:59:59.000Z

296

Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September2-SCORECARD-01-24-13 Page 1 of 1Sandra L.155-WSavannah River Site

297

A brief history of the T Plant facility at the Hanford Site. Addendum 1  

SciTech Connect (OSTI)

T Plant (221-T) was the first and largest of the early chemical separations plants at the Hanford Engineer Works (HEW) (World War II name for the Hanford Site). Officially designated as a Cell Building by the Manhattan Engineer District (MED) of the Army Corps of Engineers (agency responsible for HEW), T Plant served as the headquarters of chemical processing operations at Hanford from its construction until the opening of the REDOX Plant in January 1952. Because it formed a crucial link in the first full-scale plutonium production operations in world history, it meets criteria established in the National Historic Preservation Act of 1966 as a National Historic Structure.

Gerber, M.S.

1994-05-16T23:59:59.000Z

298

Enterprise Assessments, Hanford Site K-West Annex Facility Construction Quality - January 2015  

Broader source: Energy.gov (indexed) [DOE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.Program -Department oftoTheseClickDepartmentImmobilization2014Hanford Site

299

Status, Accomplishments, and Recent Developments at the ARM Climate Research Facility Southern Great Plains Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administrationcontroller systemsBiSiteNeutron Scattering4 ByWatchingState ofDr.Quasi-Elastic

300

Weldon Spring Site Federal Facility Agreement UNITED STATES ENVIRONMENTAL PROTECTION AGENCY  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCTTO:March 20,Since dewatering atSite

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Site Characterization Plan for the Old Hydrofracture Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

The aboveground structures of the Old Hydrofracture Facility (OHF) at Oak Ridge National Laboratory (ORNL) are scheduled for decontamination and decommissioning (D&D). This Site Characterization Plan presents the strategy and techniques to be used to characterize the OHF D&D structures in support of D&D planning, design, and implementation. OHF is located approximately 1 mile southwest of the main ORNL complex. From 1964 to 1979, OHF was used in the development and full-scale application of hydrofracture operations in which 969,000 gal of liquid low-level waste (LLLW) was mixed with grout and then injected under high pressure into a low-permeability shale formation approximately 1/6 mile underground.

Not Available

1994-01-01T23:59:59.000Z

302

Better building: LEEDing new facilities  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Better building: LEEDing new facilities Better building: LEEDing new facilities We're taking big steps on-site to create energy efficient facilities and improve infrastructure....

303

Establishing nuclear facility drill programs  

SciTech Connect (OSTI)

The purpose of DOE Handbook, Establishing Nuclear Facility Drill Programs, is to provide DOE contractor organizations with guidance for development or modification of drill programs that both train on and evaluate facility training and procedures dealing with a variety of abnormal and emergency operating situations likely to occur at a facility. The handbook focuses on conducting drills as part of a training and qualification program (typically within a single facility), and is not intended to included responses of personnel beyond the site boundary, e.g. Local or State Emergency Management, Law Enforcement, etc. Each facility is expected to develop its own facility specific scenarios, and should not limit them to equipment failures but should include personnel injuries and other likely events. A well-developed and consistently administered drill program can effectively provide training and evaluation of facility operating personnel in controlling abnormal and emergency operating situations. To ensure the drills are meeting their intended purpose they should have evaluation criteria for evaluating the knowledge and skills of the facility operating personnel. Training and evaluation of staff skills and knowledge such as component and system interrelationship, reasoning and judgment, team interactions, and communications can be accomplished with drills. The appendices to this Handbook contain both models and additional guidance for establishing drill programs at the Department`s nuclear facilities.

NONE

1996-03-01T23:59:59.000Z

304

Estimating Groundwater Concentrations from Mass Releases to the Aquifer at Integrated Disposal Facility and Tank Farm Locations Within the Central Plateau of the Hanford Site  

SciTech Connect (OSTI)

This report summarizes groundwater-related numerical calculations that will support groundwater flow and transport analyses associated with the scheduled 2005 performance assessment of the Integrated Disposal Facility (IDF) at the Hanford Site. The report also provides potential supporting information to other ongoing Hanford Site risk analyses associated with the closure of single-shell tank farms and related actions. The IDF 2005 performance assessment analysis is using well intercept factors (WIFs), as outlined in the 2001 performance assessment of the IDF. The flow and transport analyses applied to these calculations use both a site-wide regional-scale model and a local-scale model of the area near the IDF. The regional-scale model is used to evaluate flow conditions, groundwater transport, and impacts from the IDF in the central part of the Hanford Site, at the core zone boundary around the 200 East and 200 West Areas, and along the Columbia River. The local-scale model is used to evaluate impacts from transport of contaminants to a hypothetical well 100 m downgradient from the IDF boundaries. Analyses similar to the regional-scale analysis of IDF releases are also provided at individual tank farm areas as additional information. To gain insight on how the WIF approach compares with other approaches for estimating groundwater concentrations from mass releases to the unconfined aquifer, groundwater concentrations were estimated with the WIF approach for two hypothetical release scenarios and compared with similar results using a calculational approach (the convolution approach). One release scenario evaluated with both approaches (WIF and convolution) involved a long-term source release from immobilized low-activity waste glass containing 25,550 Ci of technetium-99 near the IDF; another involved a hypothetical shorter-term release of {approx}0.7 Ci of technetium over 600 years from the S-SX tank farm area. In addition, direct simulation results for both release scenarios were provided to compare with the results of the WIF and convolution approaches.

Bergeron, Marcel P.; Freeman, Eugene J.

2005-06-09T23:59:59.000Z

305

Mercury contaminated sediment sites—An evaluation of remedial options  

SciTech Connect (OSTI)

Mercury (Hg) is a naturally-occurring element that is ubiquitous in the aquatic environment. Though efforts have been made in recent years to decrease Hg emissions, historically-emitted Hg can be retained in the sediments of aquatic bodies where they may be slowly converted to methylmercury (MeHg). Consequently, Hg in historically-contaminated sediments can result in high levels of significant exposure for aquatic species, wildlife and human populations consuming fish. Even if source control of contaminated wastewater is achievable, it may take a very long time, perhaps decades, for Hg-contaminated aquatic systems to reach relatively safe Hg levels in both water and surface sediment naturally. It may take even longer if Hg is present at higher concentration levels in deep sediment. Hg contaminated sediment results from previous releases or ongoing contributions from sources that are difficult to identify. Due to human activities or physical, chemical, or biological processes (e.g. hydrodynamic flows, bioturbation, molecular diffusion, and chemical transformation), the buried Hg can be remobilized into the overlying water. Hg speciation in the water column and sediments critically affect the reactivity (i.e. conversion of inorganic Hg(II) to MeHg), transport, and its exposure to living organisms. Also, geochemical conditions affect the activity of methylating bacteria and its availability for methylation. This review paper discusses remedial considerations (e.g. key chemical factors in fate and transport of Hg, source characterization and control, environmental management procedures, remediation options, modeling tools) and includes practical case studies for cleaning up Hg-contaminated sediment sites. -- Highlights: ? Managing mercury-contaminated sediment sites are challenging to remediate. ? Remediation technologies are making a difference in managing these sites. ? Partitioning plays a dominant role in the distribution of mercury species. ? Mathematical models can be used to help us understand the chemistry and processes.

Randall, Paul M., E-mail: randall.paul@epa.gov [U.S. Environmental Protection Agency, Office of Research and Development, National Risk Management Research Laboratory, 26 West Martin Luther King Drive, Cincinnati, OH 45268 (United States); Chattopadhyay, Sandip, E-mail: Sandip.Chattopadhyay@tetratech.com [Tetra Tech, Inc., 250 West Court Street, Suite 200W, Cincinnati, OH 45202 (United States)] [Tetra Tech, Inc., 250 West Court Street, Suite 200W, Cincinnati, OH 45202 (United States)

2013-08-15T23:59:59.000Z

306

Hanford Site Evaluation of Electrical Equipment for Beryllium Procedure  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2M HILL Secretary MonizSite Public ToursOfficial5

307

Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium using existing facilities at the Savannah River site: alternatives 3A/5A/6A/6B/7A/9A  

SciTech Connect (OSTI)

The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium using ceramic in a new facility at Savannah River Site (SRS).

DiSabatino, A., LLNL

1998-06-01T23:59:59.000Z

308

Resource Evaluation and Site Selection for Microalgae Production in India  

SciTech Connect (OSTI)

The study evaluates climate conditions, availability of CO2 and other nutrients, water resources, and land characteristics to identify areas in India suitable for algae production. The purpose is to provide an understanding of the resource potential in India for algae biofuels production and to assist policymakers, investors, and industry developers in their future strategic decisions.

Milbrandt, A.; Jarvis, E.

2010-09-01T23:59:59.000Z

309

Environmentally based siting assessment for synthetic-liquid-fuels facilities. Final report  

SciTech Connect (OSTI)

A detailed assessment of the major environmental constraints to siting a synthetic fuels industry and the results of that assessment are used to determine on a regional basis the potential for development of such an industry with minimal environmental conflicts. Secondly, the ability to mitigate some of the constraining impacts through alternative institutional arrangements, especially in areas that are judged to have a low development potential is also assessed. Limitations of the study are delineated, but specifically, the study is limited geographically to well-defined boundaries that include the prime coal and oil shale resource areas. The critical factors used in developing the framework are air quality, water availability, socioeconomic capacity, ecological sensitivity, environmental health, and the management of Federally owned lands. (MCW)

None

1980-01-01T23:59:59.000Z

310

Site Characterization Report ORGDP Diffusion Facilities Permanent Shutdown K-700 Power House and K-27 Switch Yard/Switch House  

SciTech Connect (OSTI)

The K-700 Power House area, initially built to supply power to the K-25 gaseous diffusion plant was shutdown and disassembled in the 1960s. This shutdown was initiated by TVA supplying economical power to the diffusion plant complex. As a result of world wide over production of enriched, reactor grade U{sup 235}, the K-27 switch yard and switch house area was placed in standby in 1985. Subsequently, as the future production requirements decreased, the cost of production increased and the separation technologies for other processes improved, the facility was permanently shutdown in December, 1987. This Site Characterization Report is a part of the FY-88 engineering Feasibility Study for placing ORGDP Gaseous Diffusion Process facilities in 'Permanent Shutdown'. It is sponsored by the Department of Energy through Virgil Lowery of Headquarters--Enrichment and through Don Cox of ORO--Enrichment Operations. The primary purpose of these building or site characterization reports is to document, quantify, and map the following potential problems: Asbestos; PCB containing fluids; Oils, coolants, and chemicals; and External contamination. With the documented quantification of the concerns (problems) the Engineering Feasibility Study will then proceed with examining the potential solutions. For this study, permanent shutdown is defined as the securing and/or conditioning of each facility to provide 20 years of safe service with minimal expenditures and, where feasible, also serving DOE's needs for long-term warehousing or other such low-risk use. The K-700 power house series of buildings were either masonry construction or a mix of masonry and wood. The power generating equipment was removed and sold as salvage in the mid 1960s but the buildings and auxiliary equipment were left intact. The nine ancillary buildings in the power house area use early in the Manhattan Project for special research projects, were left intact minus the original special equipment. During the late 1960s and 1970s, some of the abandoned buildings were used for offices, special projects, and storage. Some of the remaining electrical transformers contain PCBs in concentrations less than 500 ppm. Many of the steam and hot water pipes in the buildings are insulated with asbestos insulation, but none of the equipment or buildings have high counts of surface radioactive contamination. The general conditions of the buildings are from fair to poor. Many should be boarded-up to prevent personnel entry and in some cases demolitions would be the safer alternative.

Thomas R.J., Blanchard R.D.

1988-06-13T23:59:59.000Z

311

Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility  

SciTech Connect (OSTI)

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

Dorr, Kent A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Freeman-Pollard, Jhivaun R. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-11-14T23:59:59.000Z

312

List of currently classified documents relative to Hanford Production Facilities Operations originated on the Hanford Site between 1961 and 1972  

SciTech Connect (OSTI)

The United States Department of Energy (DOE) has declared that all Hanford plutonium production- and operations-related information generated between 1944 and 1972 is declassified. Any documents found and deemed useful for meeting Hanford Environmental Dose Reconstruction (HEDR) objectives may be declassified with or without deletions in accordance with DOE guidance by Authorized Derivative Declassifiers. The September 1992, letter report, Declassifications Requested by the Technical Steering Panel of Hanford Documents Produced 1944--1960, (PNWD-2024 HEDR UC-707), provides an important milestone toward achieving a complete listing of documents that may be useful to the HEDR Project. The attached listing of approximately 7,000 currently classified Hanford-originated documents relative to Hanford Production Facilities Operations between 1961 and 1972 fulfills TSP Directive 89-3. This list does not include such titles as the Irradiation Processing Department, Chemical Processing Department, and Hanford Laboratory Operations monthly reports generated after 1960 which have been previously declassified with minor deletions and made publicly available. Also Kaiser Engineers Hanford (KEH) Document Control determined that no KEH documents generated between January 1, 1961 and December 31, 1972 are currently classified. Titles which address work for others have not been included because Hanford Site contractors currently having custodial responsibility for these documents do not have the authority to determine whether other than their own staff have on file an appropriate need-to-know. Furthermore, these documents do not normally contain information relative to Hanford Site operations.

Not Available

1993-04-01T23:59:59.000Z

313

Evaluation of soil radioactivity data from the Nevada Test Site  

SciTech Connect (OSTI)

Since 1951, 933 nuclear tests have been conducted at the Nevada Test Site (NTS) and test areas on the adjacent Tonopah Test Range (TTR) and Nellis Air Force Range (NAFR). Until the early 1960s. the majority of tests were atmospheric, involving detonation of nuclear explosive devices on the ground or on a tower, suspended from a balloon or dropped from an airplane. Since the signing of the Limited Test Ban Treaty in 1963, most tests have been conducted underground, although several shallow subsurface tests took place between 1962 and 1968. As a result of the aboveground and near-surface nuclear explosions, as well as ventings of underground tests, destruction of nuclear devices with conventional explosives, and nuclear-rocket engine tests, the surface soil on portions of the NTS has been contaminated with radionuclides. Relatively little consideration was given to the environmental effects of nuclear testing during the first two decades of operations at the NTS. Since the early 1970s, however, increasingly strict environmental regulations have forced greater attention to be given to contamination problems at the site and how to remediate them. One key element in the current environmental restoration program at the NTS is determining the amount and extent of radioactivity in the surface soil. The general distribution of soil radioactivity on the NTS is already well known as a result of several programs carried out in the 1970s and 1980s. However, questions have been raised as to whether the data from those earlier studies are suitable for use in the current environmental assessments and risk analyses. The primary purpose of this preliminary data review is to determine to what extent the historical data collected at the NTS can be used in the characterization/remediation process.

NONE

1995-03-01T23:59:59.000Z

314

A Fisheries Evaluation of the Dryden Fish Screening Facility : Annual Report 1994.  

SciTech Connect (OSTI)

Effectivness was evaluated of the Dryden Fish Screening Facility in the Wenatchee Reclamation District Canal near Dryden in north central Washington State. In situ tests were conducted by releasing groups of hatchery reared salmonids of different ages and sizes. Spring chinook salmon smolts (110-165 mm) were not injured or descaled in passing through the canal forebay. Smolts were not delayed as they migrated in the canal. Most fish released at the canal headworks exited the screening facility in <4 h, with >99% of the test fish captured in the fish bypass in <24 h. Steelhead subyearlings 65-125 mm were not injured or descaled in traveling through the bypass flume and fish return pipe. Average time for steelhead subyearlings to travel through thebypass structure was 70 seconds. Small rainbow trout fry 23-27mm could pass through the 0.125-in. profile bar screen openings and were entrained in the irrigation canal; about 38% was lost to the canal within 48 h of release. Some fry stayed in the forebay and did not migrate during the tests. Wild chinook fry 36-42mm were also entrained. Estimated 34% of emergent wild chinook salmon fry passed through the profile bar screens and were entrained in the canal. Approach velocity at the Dryden screens was {ge}0.4 ft/s; low velocities through the first two screen panels indicated that vertical louvers installed behind each screen panel to balance flow were not totally effective.

Mueller, Robert P.; Abernethy, C.Scott; Neitzel, Duane A.

1995-04-01T23:59:59.000Z

315

AN EVALUATION OF HANFORD SITE TANK FARM SUBSURFACE CONTAMINATION FY2007  

SciTech Connect (OSTI)

The Tank Farm Vadose Zone (TFVZ) Project conducts activities to characterize and analyze the long-term environmental and human health impacts from tank waste releases to the vadose zone. The project also implements interim measures to mitigate impacts, and plans the remediation of waste releases from tank farms and associated facilities. The scope of this document is to report data needs that are important to estimating long-term human health and environmental risks. The scope does not include technologies needed to remediate contaminated soils and facilities, technologies needed to close tank farms, or management and regulatory decisions that will impact remediation and closure. This document is an update of ''A Summary and Evaluation of Hanford Site Tank Farm Subsurface Contamination''. That 1998 document summarized knowledge of subsurface contamination beneath the tank farms at the time. It included a preliminary conceptual model for migration of tank wastes through the vadose zone and an assessment of data and analysis gaps needed to update the conceptual model. This document provides a status of the data and analysis gaps previously defined and discussion of the gaps and needs that currently exist to support the stated mission of the TFVZ Project. The first data-gaps document provided the basis for TFVZ Project activities over the previous eight years. Fourteen of the nineteen knowledge gaps identified in the previous document have been investigated to the point that the project defines the current status as acceptable. In the process of filling these gaps, significant accomplishments were made in field work and characterization, laboratory investigations, modeling, and implementation of interim measures. The current data gaps are organized in groups that reflect Components of the tank farm vadose zone conceptual model: inventory, release, recharge, geohydrology, geochemistry, and modeling. The inventory and release components address residual wastes that will remain in the tanks and tank-farm infrastructure after closure and potential losses from leaks during waste retrieval. Recharge addresses the impacts of current conditions in the tank farms (i.e. gravel covers that affect infiltration and recharge) as well as the impacts of surface barriers. The geohydrology and geochemistry components address the extent of the existing subsurface contaminant inventory and drivers and pathways for contaminants to be transported through the vadose zone and groundwater. Geochemistry addresses the mobility of key reactive contaminants such as uranium. Modeling addresses conceptual models and how they are simulated in computers. The data gaps will be used to provide input to planning (including the upcoming C Farm Data Quality Objective meetings scheduled this year).

MANN, F.M.

2007-07-10T23:59:59.000Z

316

EERC pilot-scale CFBC evaluation facility Project CFB test results  

SciTech Connect (OSTI)

Project CFB was initiated at the University of North Dakota Energy and Environmental Research Center (EERC) in May 1988. Specific goals of the project were to (1) construct a circulating fluidized-bed combustor (CFBC) facility representative of the major boiler vendors' designs with the capability of producing scalable data, (2) develop a database for use in making future evaluations of CFBC technology, and (3) provide a facility for evaluating fuels, free of vendor bias for use in the - energy industry. Five coals were test-burned in the 1-MWth unit: North Dakota and Asian lignites, a Wyoming subbituminous, and Colorado and Pennsylvania bituminous coats. A total of 54 steady-state test periods were conducted, with the key test parameters being the average combustor temperature, excess air, superficial gas velocity, calcium-to-sulfur molar ratio, and the primary air-to-secondary air split. The capture for a coal fired in a CFBC is primarily dependent upon the total alkali-to-sulfur ratio. The required alkali-to ratio for 90% sulfur retention ranged from 1.4 to 4.9, depending upon coal type. While an alkali-to-ratio of 4.9 was required to meet 90% sulfur retention for the Salt Creek coal versus 1.4 for the Asian lignite, the total amount of sorbent addition required is much less for the Salt Creek coal, 4.2 pound sorbent per million Btu coal input, versus 62 pound/million Btu for the Asian lignite. The bituminous coals tested show optimal capture at combustor temperatures of approximately 1550[degree]F, with low-rank coals having optimal sulfur capture approximately 100[degree]F lower.

Mann, M.D.; Hajicek, D.R.; Henderson, A.K.; Moe, T.A.

1992-09-01T23:59:59.000Z

317

A framework for nuclear facility safeguard evaluation using probabilistic methods and expert elicitation  

E-Print Network [OSTI]

With the advancement of the next generation of nuclear fuel cycle facilities, concerns of the effectiveness of nuclear facility safeguards have been increasing due to the inclusion of highly enriched material and reprocessing ...

Iamsumang, Chonlagarn

2010-01-01T23:59:59.000Z

318

A manual for applying the allowable residual contamination level method for decommissioning facilities on the Hanford Site  

SciTech Connect (OSTI)

This report describes the modifications that have been made to enhance the original Allowable Residual Contamination Level (ARCL) method to make it more applicable to site-specific analyses. This version considers the mixture of radionuclides present at the time of site characterization, the elapsed time after decommissioning when exposure to people could occur, and includes a calculation of the upper confidence limit of the potential dose based on sampling statistics that are developed during the site characterization efforts. The upper confidence limit of potential exposure can now be used for comparison against applicable radiation dose limits (i.e., 25 mrem/yr at Hanford). The level of confidence can be selected by the user. A wide range of exposure scenarios were evaluated; the rationale used to select the most limiting scenarios is explained. The radiation dose factors used for the inhalation and ingestion pathways were also updated to correspond with the radiation dosimetry methods utilized in the International Commission of Radiological Protection Publications 26 and 30 (ICRP 1977; 1979a,b, 1980, 1981, 1982a,b). This simplifies the calculations, since ''effective whole body'' doses are now calculated, and also brings the dosimetry methods used in the ARCL method in conformance with the rationale used by DOE in developing the 25 mrem/yr limit at Hanford. 46 refs., 21 figs., 15 tabs.

Napier, B.A.; Piepel, G.F.; Kennedy, W.E. Jr.; Schreckhise, R.G.

1988-08-01T23:59:59.000Z

319

Geological and Geotechnical Site Investigation for the Design of a CO2 Rich Flue Gas Direct Injection and Storage Facility  

SciTech Connect (OSTI)

With international efforts to limit anthropogenic carbon in the atmosphere, various CO{sub 2} sequestration methods have been studied by various facilities worldwide. Basalt rock in general has been referred to as potential host material for mineral carbonation by various authors, without much regard for compositional variations due to depositional environment, subsequent metamorphism, or hydrothermal alteration. Since mineral carbonation relies on the presence of certain magnesium, calcium, or iron silicates, it is necessary to study the texture, mineralogy, petrology, and geochemistry of specific basalts before implying potential for mineral carbonation. The development of a methodology for the characterization of basalts with respect to their susceptibility for mineral carbonation is proposed to be developed as part of this research. The methodology will be developed based on whole rock data, petrography and microprobe analyses for samples from the Caledonia Mine in Michigan, which is the site for a proposed small-scale demonstration project on mineral carbonation in basalt. Samples from the Keweenaw Peninsula will be used to determine general compositional trends using whole rock data and petrography. Basalts in the Keweenaw Peninsula have been subjected to zeolite and prehnite-pumpellyite facies metamorphism with concurrent native copper deposition. Alteration was likely due to the circulation of CO{sub 2}-rich fluids at slightly elevated temperatures and pressures, which is the process that is attempted to be duplicated by mineral carbonation.

Metz, Paul; Bolz, Patricia

2013-03-25T23:59:59.000Z

320

20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.  

SciTech Connect (OSTI)

The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

Ramirez, Amanda Ann

2008-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Evaluation of erosion and cover re-establishment following site preparation on east Texas forest lands  

E-Print Network [OSTI]

damage following mechanical site prepara- tion. (uantitative data characterizing the rate of recovery of soi. l protective cover, used in combination with erosion data, gives planners and forest managers an indication of the total impact of mechanical...EVALUATION OF EROSION AND COVER RE-ESTABLISHMENT 1'OLLOWING SITE PREPARATION ON EAST TEXAS FOREST LANDS A Thesis by Timothy Allen Blume Submitted to the Graduate College of Texas A&M Uniuersity in partial fullfillment of the requir ment...

Blume, Timothy Allen

1979-01-01T23:59:59.000Z

322

Data evaluation technical memorandum on the K-1407C Retention Basin at the Oak Ridge K-25 Site, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The K-1407-C Retention Basin was a surface impoundment at the Oak Ridge K-25 Site. The basin was used primarily for storing potassium hydroxide scrubber sludge generated at the K-25 Site. In addition, from 1960 to 1973, metal hydroxide sludges that were removed from the K-1407-B Holding Pond were discharged to the K-1407-C Retention Basin. The sludge in the K-1407-B Pond contained discharge from the K-1420 Decontamination and Uranium Recovery, the K-1501 Steam Plant, the K-1413 Laboratory, and the K-1401 Maintenance Building. Radioactive material is also present in the K-1407-C Retention Basin, probably the result of cleaning and decontamination activities at some of the aforementioned facilities. The discharge of waste materials to K-1407-C was discontinued before November of 1988, and all sludge was removed from the retention basin. Some of the sludge was stored, and the remainder was fixed in concrete. This report is specific to the K-1407-C Retention Basin and includes information pertinent to the evaluation of soil contamination. The focus of this evaluation is the effectiveness of the Phase 1 investigation of the K-1407-C Retention Basin to define site conditions adequately to support decisions regarding appropriate closure alternatives. This includes the physical characterization of the site area and the characterization of the nature and extent of contamination at the site in relation to risk characterization and statistical evaluation.

Beal, D.; Bock, J.; Hatmaker, T.; Zolyniak, J.; Goddard, P. (Oak Ridge K-25 Site, TN (United States)); Kucsmas, D. (Oak Ridge National Lab., TN (United States))

1991-10-01T23:59:59.000Z

323

Data evaluation technical memorandum on the K-1407C Retention Basin at the Oak Ridge K-25 Site, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect (OSTI)

The K-1407-C Retention Basin was a surface impoundment at the Oak Ridge K-25 Site. The basin was used primarily for storing potassium hydroxide scrubber sludge generated at the K-25 Site. In addition, from 1960 to 1973, metal hydroxide sludges that were removed from the K-1407-B Holding Pond were discharged to the K-1407-C Retention Basin. The sludge in the K-1407-B Pond contained discharge from the K-1420 Decontamination and Uranium Recovery, the K-1501 Steam Plant, the K-1413 Laboratory, and the K-1401 Maintenance Building. Radioactive material is also present in the K-1407-C Retention Basin, probably the result of cleaning and decontamination activities at some of the aforementioned facilities. The discharge of waste materials to K-1407-C was discontinued before November of 1988, and all sludge was removed from the retention basin. Some of the sludge was stored, and the remainder was fixed in concrete. This report is specific to the K-1407-C Retention Basin and includes information pertinent to the evaluation of soil contamination. The focus of this evaluation is the effectiveness of the Phase 1 investigation of the K-1407-C Retention Basin to define site conditions adequately to support decisions regarding appropriate closure alternatives. This includes the physical characterization of the site area and the characterization of the nature and extent of contamination at the site in relation to risk characterization and statistical evaluation.

Beal, D.; Bock, J.; Hatmaker, T.; Zolyniak, J.; Goddard, P. [Oak Ridge K-25 Site, TN (United States); Kucsmas, D. [Oak Ridge National Lab., TN (United States)

1991-10-01T23:59:59.000Z

324

An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities  

SciTech Connect (OSTI)

Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

2011-03-01T23:59:59.000Z

325

Evaluation of Suitability of Selected Set of Coal Plant Sites for Repowering with Small Modular Reactors  

SciTech Connect (OSTI)

This report summarizes the approach that ORNL developed for screening a sample set of small coal stations for possible repowering with SMRs; the methodology employed, including spatial modeling; and initial results for these sample plants. The objective in conducting this type of siting evaluation is to demonstrate the capability to characterize specific sample coal plant sites to identify any particular issues associated with repowering existing coal stations with SMRs using OR-SAGE; it is not intended to be a definitive assessment per se as to the absolute suitability of any particular site.

Belles, Randy [ORNL; Copinger, Donald A [ORNL; Mays, Gary T [ORNL; Omitaomu, Olufemi A [ORNL; Poore III, Willis P [ORNL

2013-03-01T23:59:59.000Z

326

Addendum to the Closure Report for Corrective Action Unit 113: Area 25 R-MAD Facility, Nevada National Security Site, Nevada  

SciTech Connect (OSTI)

This addendum to the Closure Report for Corrective Action Unit 113: Area 25, Reactor Maintenance, Assembly, and Disassembly Facility, Building 3110, Nevada Test Site, Nevada, DOE/NV--891-VOL I-Rev. 1, dated July 2003, provides details of demolition, waste disposal, and use restriction (UR) modification for Corrective Action Unit 113, Area 25 R-MAD Facility. Demolition was completed on July 15, 2010, when the last of the building debris was disposed. Final field activities were concluded on August 30, 2010, after all equipment was demobilized and UR signs were posted. This work was funded by the American Recovery and Reinvestment Act.

NSTec Environmental Restoration

2011-02-24T23:59:59.000Z

327

Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes  

SciTech Connect (OSTI)

The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.

Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.

2003-11-15T23:59:59.000Z

328

Facility effluent monitoring plan for the tank farm facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements.

Crummel, G.M.

1998-05-18T23:59:59.000Z

329

Preliminary identification of potentially disruptive scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site  

SciTech Connect (OSTI)

The Greater Confinement Disposal location is being evaluated to determine whether defense-generated transuranic waste buried at this location complies with the Containment Requirements established by the US Environmental Protection Agency. One step in determining compliance is to identify those combinations of events and processes (scenarios) that define possible future states of the disposal system for which performance assessments must be performed. An established scenario-development procedure was used to identify a comprehensive set of mutually exclusive scenarios. To assure completeness, 761 features, events, processes, and other listings (FEPS) were compiled from 11 references. This number was reduced to 205 primarily through the elimination of duplications. The 205 FEPs were screened based on site-specific, goal-specific, and regulatory criteria. Four events survived screening and were used in preliminary scenario development: (1) exploratory drilling penetrates a GCD borehole, (2) drilling of a withdrawal/injection well penetrates a GCD borehole, (3) subsidence occurs at the RWMS, and (4) irrigation occurs at the RWMS. A logic diagram was used to develop 16 scenarios from the four events. No screening of these scenarios was attempted at this time. Additional screening of the currently retained events and processes will be based on additional data and information from site-characterization activities. When screening of the events and processes is completed, a final set of scenarios will be developed and screened based on consequence and probability of occurrence.

Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Newman, G. [GRAM, Inc., Albuquerque, NM (United States)

1993-12-01T23:59:59.000Z

330

COMPOSITE ANALYSIS OF LLW DISPOSAL FACILITIES AT THE U.S. DEPARTMENT OF ENERGY'S SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Composite Analyses (CA's) are required per DOE Order 435.1 [1], in order to provide a reasonable expectation that DOE low-level waste (LLW) disposal, high-level waste tank closure, and transuranic (TRU) waste disposal in combination with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), Resource Conservation and Recovery Act (RCRA), and deactivation and decommissioning (D&D) actions, will not result in the need for future remedial actions in order to ensure radiological protection of the public and environment. This Order requires that an accounting of all sources of DOE man-made radionuclides and DOE enhanced natural radionuclides that are projected to remain on the site after all DOE site operations have ceased. This CA updates the previous CA that was developed in 1997. As part of this CA, an inventory of expected radionuclide residuals was conducted, exposure pathways were screened and a model was developed such that a dose to the MOP at the selected points of exposure might be evaluated.

Hiergesell, R; Mark Phifer, M; Frank02 Smith, F

2009-01-08T23:59:59.000Z

331

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect (OSTI)

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

332

Engineering evaluation/cost analysis for the proposed management of 15 nonprocess buildings (15 series) at the Weldon Spring Site Chemical Plant, Weldon Spring, Missouri  

SciTech Connect (OSTI)

The US Department of Energy, under its Surplus Facilities Management Program (SFMP), is responsible for cleanup activities at the Weldon-Spring site, located near Weldon Spring, Missouri. The site consists of two noncontiguous areas: (1) a raffinate pits and chemical plant area and (2) a quarry. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support a proposed removal action to manage 15 nonprocess buildings, identified as the 15 Series buildings, at the chemical plant on the Weldon Spring site. These buildings have been nonoperational for more than 20 years, and the deterioration that has occurred during this time has resulted in a potential threat to site workers, the general public, and the environment. The EE/CA documentation of this proposed action is consistent with guidance from the US Environmental Protection Agency (EPA) that addresses removal actions at sites subject to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Actions at the Weldon Spring site are subject to CERCLA requirements because the site is on the EPA`s National Priorities List. The objectives of this report are to (1) identify alternatives for management of the nonprocess buildings; (2) document the selection of response activities that will mitigate the potential threat to workers, the public, and the environment associated with these buildings; and (3) address environmental impacts associated with the proposed action.

MacDonell, M M; Peterson, J M

1989-05-01T23:59:59.000Z

333

Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order with ROTC 1, Revision No. 0  

SciTech Connect (OSTI)

Many Federal Facility Agreement and Consent Order (FFACO) Use Restrictions (URs) have been established at various corrective action sites (CASs) as part of FFACO corrective actions (FFACO, 1996; as amended January 2007). Since the signing of the FFACO in 1996, practices and procedures relating to the implementation of risk-based corrective action (RBCA) have evolved. This document is part of an effort to re-evaluate all FFACO URs against the current RBCA criteria (referred to in this document as the Industrial Sites [IS] RBCA process) as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). Based on this evaluation, the URs were sorted into the following categories: 1. Where sufficient information exists to determine that the current UR is consistent with the RCBA criteria 2. Where sufficient information exists to determine that the current UR may be removed or downgraded based on RCBA criteria. 3. Where sufficient information does not exist to evaluate the current UR against the RCBA criteria. After reviewing all the existing FFACO URs, the 49 URs addressed in this document have sufficient information to determine that these current URs may be removed or downgraded based on RCBA criteria. This document presents recommendations on modifications to existing URs that will be consistent with the RCBA criteria.

Lynn Kidman

2008-02-01T23:59:59.000Z

334

EVALUATION OF MODELS FOR THE VERTICAL EXTRAPOLATION OF WIND SPEED MEASUREMENTS AT OFFSHORE SITES  

E-Print Network [OSTI]

EVALUATION OF MODELS FOR THE VERTICAL EXTRAPOLATION OF WIND SPEED MEASUREMENTS AT OFFSHORE SITES important for offshore wind energy utilisation are discussed and tested: Four models for the surface tested with data from the offshore field measurement Rødsand by extrapolating the measured 10 m wind

Heinemann, Detlev

335

EVALUATION OF MODELS FOR THE VERTICAL EXTRAPOLATION OF WIND SPEED MEASUREMENTS AT OFFSHORE SITES  

E-Print Network [OSTI]

EVALUATION OF MODELS FOR THE VERTICAL EXTRAPOLATION OF WIND SPEED MEASUREMENTS AT OFFSHORE SITES important for offshore wind energy utilisation are discussed and tested: Four models for the surface tested with measurements from the offshore field measurement Rødsand by extrapolating the measured 10 m

Heinemann, Detlev

336

An Initial Evaluation Of Characterization And Closure Options For Underground Pipelines Within A Hanford Site Single-Shell Tank Farm  

SciTech Connect (OSTI)

The Hanford Site includes 149 single-shell tanks, organized in 12 'tank farms,' with contents managed as high-level mixed waste. The Hanford Federal Facility Agreement and Consent Order requires that one tank farm, the Waste Management Area C, be closed by June 30, 2019. A challenge to this project is the disposition and closure of Waste Management Area C underground pipelines. Waste Management Area C contains nearly seven miles of pipelines and 200 separate pipe segments. The pipelines were taken out of service decades ago and contain unknown volumes and concentrations of tank waste residuals from past operations. To understand the scope of activities that may be required for these pipelines, an evaluation was performed. The purpose of the evaluation was to identify what, if any, characterization methods and/or closure actions may be implemented at Waste Management Area C for closure of Waste Management Area C by 2019. Physical and analytical data do not exist for Waste Management Area C pipeline waste residuals. To develop estimates of residual volumes and inventories of contamination, an extensive search of available information on pipelines was conducted. The search included evaluating historical operation and occurrence records, physical attributes, schematics and drawings, and contaminant inventories associated with the process history of plutonium separations facilities and waste separations and stabilization operations. Scoping analyses of impacts to human health and the environment using three separate methodologies were then developed based on the waste residual estimates. All analyses resulted in preliminary assessments, indicating that pipeline waste residuals presented a comparably low long-term impact to groundwater with respect to soil, tank and other ancillary equipment residuals, but exceeded Washington State cleanup requirement values. In addition to performing the impact analyses, the assessment evaluated available sampling technologies and pipeline removal or treatment technologies. The evaluation accounted for the potential high worker risk, high cost, and schedule impacts associated with characterization, removal, or treatment of pipelines within Waste Management Area C for closure. This assessment was compared to the unknown, but estimated low, long-term impacts to groundwater associated with remaining waste residuals should the pipelines be left "as is" and an engineered surface barrier or landfill cap be placed. This study also recommended that no characterization or closure actions be assumed or started for the pipelines within Waste Management Area C, likewise with the premise that a surface barrier or landfill cap be placed over the pipelines.

Badden, Janet W. [Washington River Protection Solutions, LLC, Richland, WA (United States); Connelly, Michael P. [Washington River Protection Solutions, LLC, Richland, WA (United States); Seeley, Paul N. [Cenibark International, Inc., Kennewick (United States); Hendrickson, Michelle L. [Washington State Univ., Richland (United States). Dept. of Ecology

2013-01-10T23:59:59.000Z

337

TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013 equivalency. Under the defined process conditions and associated material specifications, the high-purity PuO{sub 2} produced in HBL presents no unique safety concerns for packaging or storage in the 3013 required configuration. The PuO{sub 2} produced using the HBL flow sheet conditions will have a higher specific surface area (SSA) than PuO{sub 2} stabilized at 950 C and, consequently, under identical conditions will adsorb more water from the atmosphere. The greatest challenge to HBL operators will be controlling moisture content below 0.5 wt %. However, even at the 0.5 wt % moisture limit, the maximum acceptable pressure of a stoichiometric mixture of hydrogen and oxygen in the 3013 container is greater than the maximum possible pressure for the HBL PuO{sub 2} product.

Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

2012-07-02T23:59:59.000Z

338

Engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area: the St. Louis Downtown Site (SLDS), the St. Louis Airport Site (SLAPS) and vicinity properties, and the Latty Avenue Properties, including the Hazelwood Interim Storage Site (HISS). The general location of these properties is shown in Figure 1; the properties are referred to collectively as the St. Louis Site. None of the properties are owned by DOE, but each property contains radioactive residues from federal uranium processing activities conducted at the SLDS during and after World War 2. The activities addressed in this environmental evaluation/cost analysis (EE/CA) report are being proposed as interim components of a comprehensive cleanup strategy for the St. Louis Site. As part of the Department's Formerly Utilized Sites Remedial Action Program (FUSRAP), DOE is proposing to conduct limited decontamination in support of proprietor-initiated activities at the SLDS, commonly referred to as the Mallinckrodt Chemical Works. The primary goal of FUSRAP activity at the SLDS is to eliminate potential environmental hazards associated with residual contamination resulting from the site's use for government-funded uranium processing activities. 17 refs., 3 figs., 5 tabs.

Picel, M.H.; Hartmann, H.M.; Nimmagadda, M.R. (Argonne National Lab., IL (USA)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

339

EVALUATION OF MERCURY EMISSIONS FROM COAL-FIRED FACILITIES WITH SCR AND FGD SYSTEMS  

SciTech Connect (OSTI)

CONSOL Energy Inc., Research & Development (CONSOL), with support from the U.S. Department of Energy, National Energy Technology Laboratory (DOE) is evaluating the effects of selective catalytic reduction (SCR) on mercury (Hg) capture in coal-fired plants equipped with an electrostatic precipitator (ESP) - wet flue gas desulfurization (FGD) combination or a spray dyer absorber--fabric filter (SDA-FF) combination. In this program CONSOL is determining mercury speciation and removal at 10 coal-fired facilities. The objectives are (1) to evaluate the effect of SCR on mercury capture in the ESP-FGD and SDA-FF combinations at coal-fired power plants, (2) evaluate the effect of catalyst degradation on mercury capture; (3) evaluate the effect of low load operation on mercury capture in an SCR-FGD system, and (4) collect data that could provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on Hg speciation and the efficacy of different FGD technologies for Hg capture. This document, the second in a series of topical reports, describes the results and analysis of mercury sampling performed on a 330 MW unit burning a bituminous coal containing 1.0% sulfur. The unit is equipped with a SCR system for NOx control and a spray dryer absorber for SO{sub 2} control followed by a baghouse unit for particulate emissions control. Four sampling tests were performed in March 2003. Flue gas mercury speciation and concentrations were determined at the SCR inlet, air heater outlet (ESP inlet), and at the stack (FGD outlet) using the Ontario Hydro method. Process stream samples for a mercury balance were collected to coincide with the flue gas measurements. Due to mechanical problems with the boiler feed water pumps, the actual gross output was between 195 and 221 MW during the tests. The results showed that the SCR/air heater combination oxidized nearly 95% of the elemental mercury. Mercury removal, on a coal-to-stack basis, was 87%. The mercury material balance closures for the four tests conducted at the plant ranged from 89% to 114%, with an average of 100%. These results appear to show that the SCR had a positive effect on mercury removal. In earlier programs, CONSOL sampled mercury at six plants with wet FGDs for SO{sub 2} control without SCR catalysts. At those plants, an average of 61 {+-} 15% of the mercury was in the oxidized form at the air heater outlet. The principal purpose of this work is to develop a better understanding of the potential Hg removal ''co-benefits'' achieved by NOx, and SO{sub 2} control technologies. It is expected that this data will provide the basis for fundamental scientific insights into the nature of Hg chemistry in flue gas, the catalytic effect of SCR systems on Hg speciation and the efficacy of different FGD technologies for Hg capture. Ultimately, this insight could help to design and operate SCR and FGD systems to maximize Hg removal.

J. A. Withum; S.C. Tseng; J. E. Locke

2004-10-31T23:59:59.000Z

340

EVALUATION OF MERCURY EMISSIONS FROM COAL-FIRED FACILITIES WITH SCR AND FGD SYSTEMS  

SciTech Connect (OSTI)

CONSOL Energy Inc., Research & Development (CONSOL), with support from the U.S. Department of Energy, National Energy Technology Laboratory (DOE) and the Electric Power Research Institute (EPRI), is evaluating the effects of selective catalytic reduction (SCR) on mercury (Hg) capture in coal-fired plants equipped with an electrostatic precipitator (ESP)--wet flue gas desulfurization (FGD) combination or a spray dryer absorber--fabric filter (SDA-FF) combination. In this program CONSOL is determining mercury speciation and removal at 10 coal-fired facilities. The objectives are (1) to evaluate the effect of SCR on mercury capture in the ESP-FGD and SDA-FF combinations at coal-fired power plants, (2) evaluate the effect of catalyst degradation on mercury capture; (3) evaluate the effect of low load operation on mercury capture in an SCR-FGD system, and (4) collect data that could provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. This document, the seventh in a series of topical reports, describes the results and analysis of mercury sampling performed on a 1,300 MW unit burning a bituminous coal containing three percent sulfur. The unit was equipped with an ESP and a limestone-based wet FGD to control particulate and SO2 emissions, respectively. At the time of sampling an SCR was not installed on this unit. Four sampling tests were performed in September 2003. Flue gas mercury speciation and concentrations were determined at the ESP outlet (FGD inlet), and at the stack (FGD outlet) using the Ontario Hydro method. Process stream samples for a mercury balance were collected to coincide with the flue gas measurements. The results show that the FGD inlet flue gas oxidized:elemental mercury ratio was roughly 2:1, with 66% oxidized mercury and 34% elemental mercury. Mercury removal, on a coal-to-stack basis, was 53%. The average Hg concentration in the stack flue gas was 4.09 {micro}g/m{sup 3}. The average stack mercury emission was 3.47 Ib/TBtu. The mercury material balance closures ranged from 87% to 108%, with an average of 97%. A sampling program similar to this one was performed on a similar unit (at the same plant) that was equipped with an SCR for NOx control. Comparison of the results from the two units show that the SCR increases the percentage of mercury that is in the oxidized form, which, in turn, lends to more of the total mercury being removed in the wet scrubber. The principal purpose of this work is to develop a better understanding of the potential mercury removal ''co-benefits'' achieved by NOx, and SO{sub 2} control technologies. It is expected that this data will provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. Ultimately, this insight could help to design and operate SCR and FGD systems to maximize mercury removal.

J.A. Withum; S.C. Tseng; J.E. Locke

2005-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Evaluation of Mercury Emissions from Coal-Fired Facilities with SCR and FGD Systems  

SciTech Connect (OSTI)

CONSOL Energy Inc., Research & Development (CONSOL), with support from the U.S. Department of Energy, National Energy Technology Laboratory (DOE) and the Electric Power Research Institute (EPRI), is evaluating the effects of selective catalytic reduction (SCR) on mercury (Hg) capture in coal-fired plants equipped with an electrostatic precipitator (ESP)--wet flue gas desulfurization (FGD) combination or a spray dyer absorber--fabric filter (SDA-FF) combination. In this program CONSOL is determining mercury speciation and removal at 10 coal-fired facilities. The principal purpose of this work is to develop a better understanding of the potential mercury removal ''co-benefits'' achieved by NO{sub x}, and SO{sub 2} control technologies. It is expected that these data will provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. Ultimately, this insight could help to design and operate SCR and FGD systems to maximize mercury removal. The objectives are (1) to evaluate the effect of SCR on mercury capture in the ESP-FGD and SDA-FF combinations at coal-fired power plants, (2) evaluate the effect of SCR catalyst degradation on mercury capture; (3) evaluate the effect of low load operation on mercury capture in an SCR-FGD system, and (4) collect data that could provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. This document, the ninth in a series of topical reports, describes the results and analysis of mercury sampling performed on Unit 1 at Plant 7, a 566 MW unit burning a bituminous coal containing 3.6% sulfur. The unit is equipped with a SCR, ESP, and wet FGD to control NO{sub x}, particulate, and SO{sub 2} emissions, respectively. Four sampling tests were performed in August 2004 during ozone season with the SCR operating; flue gas mercury speciation and concentrations were determined at the SCR inlet, SCR outlet, air heater outlet (ESP inlet), ESP outlet (FGD inlet), and at the stack (FGD outlet) using the Ontario Hydro method. Three sampling tests were also performed in November 2004 during non-ozone season with the SCR bypassed; flue gas mercury speciation and concentrations were determined at the ESP outlet (FGD inlet), and at the stack (FGD outlet). Process samples for material balances were collected during the flue gas measurements. The results show that, at the point where the flue gas enters the FGD, a greater percentage of the mercury was in the oxidized form when the SCR was operating compared to when the SCR was bypassed (97% vs 91%). This higher level of oxidation resulted in higher mercury removals in the FGD because the FGD removed 90-94% of the oxidized mercury in both cases. Total coal-to-stack mercury removal was 86% with the SCR operating, and 73% with the SCR bypassed. The average mercury mass balance closure was 81% during the ozone season tests and 87% during the non-ozone season tests.

J. A. Withum; S. C. Tseng; J. E. Locke

2006-01-31T23:59:59.000Z

342

Evaluation of Mercury Emissions from Coal-Fired Facilities with SCR and FGD Systems  

SciTech Connect (OSTI)

CONSOL Energy Inc., Research & Development (CONSOL), with support from the U.S. Department of Energy, National Energy Technology Laboratory (DOE) and the Electric Power Research Institute (EPRI), is evaluating the effects of selective catalytic reduction (SCR) on mercury (Hg) capture in coal-fired plants equipped with an electrostatic precipitator (ESP)--wet flue gas desulfurization (FGD) combination or a spray dyer absorber--fabric filter (SDA-FF) combination. In this program CONSOL is determining mercury speciation and removal at 10 coal-fired facilities. The principal purpose of this work is to develop a better understanding of the potential mercury removal ''co-benefits'' achieved by NO{sub x}, and SO{sub 2} control technologies. It is expected that this data will provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. Ultimately, this insight could help to design and operate SCR and FGD systems to maximize mercury removal. The objectives are (1) to evaluate the effect of SCR on mercury capture in the ESP-FGD and SDA-FF combinations at coal-fired power plants, (2) evaluate the effect of SCR catalyst degradation on mercury capture; (3) evaluate the effect of low load operation on mercury capture in an SCR-FGD system, and (4) collect data that could provide the basis for fundamental scientific insights into the nature of mercury chemistry in flue gas, the catalytic effect of SCR systems on mercury speciation and the efficacy of different FGD technologies for mercury capture. This document, the tenth in a series of topical reports, describes the results and analysis of mercury sampling performed on two 468 MW units burning bituminous coal containing 1.3-1.7% sulfur. Unit 2 is equipped with an SCR, ESP, and wet FGD to control NO{sub x}, particulate, and SO{sub 2} emissions, respectively. Unit 1 is similar to Unit 2, except that Unit 1 has no SCR for NOx control. Four sampling tests were performed on both units in January 2005; flue gas mercury speciation and concentrations were determined at the economizer outlet, air heater outlet (ESP inlet), ESP outlet (FGD inlet), and at the stack (FGD outlet) using the Ontario Hydro method. Process samples for material balances were collected with the flue gas measurements. The results show that the SCR increased the oxidation of the mercury at the air heater outlet. At the exit of the air heater, a greater percentage of the mercury was in the oxidized and particulate forms on the unit equipped with an SCR compared to the unit without an SCR (97.4% vs 91%). This higher level of oxidation resulted in higher mercury removals in the scrubber. Total mercury removal averaged 97% on the unit with the SCR, and 87% on the unit without the SCR. The average mercury mass balance closure was 84% on Unit 1 and 103% on Unit 2.

J. A. Withum; J. E. Locke

2006-02-01T23:59:59.000Z

343

Adapting a GIS-Based Multicriteria Decision Analysis Approach for Evaluating New Power Generating Sites  

SciTech Connect (OSTI)

There is a growing need to site new power generating plants that use cleaner energy sources due to increased regulations on air and water pollution and a sociopolitical desire to develop more clean energy sources. To assist utility and energy companies as well as policy-makers in evaluating potential areas for siting new plants in the contiguous United States, a geographic information system (GIS)-based multicriteria decision analysis approach is presented in this paper. The presented approach has led to the development of the Oak Ridge Siting Analysis for power Generation Expansion (OR-SAGE) tool. The tool takes inputs such as population growth, water availability, environmental indicators, and tectonic and geological hazards to provide an in-depth analysis for siting options. To the utility and energy companies, the tool can quickly and effectively provide feedback on land suitability based on technology specific inputs. However, the tool does not replace the required detailed evaluation of candidate sites. To the policy-makers, the tool provides the ability to analyze the impacts of future energy technology while balancing competing resource use.

Omitaomu, Olufemi A [ORNL; Blevins, Brandon R [ORNL; Jochem, Warren C [ORNL; Mays, Gary T [ORNL; Belles, Randy [ORNL; Hadley, Stanton W [ORNL; Harrison, Thomas J [ORNL; Bhaduri, Budhendra L [ORNL; Neish, Bradley S [ORNL; Rose, Amy N [ORNL

2012-01-01T23:59:59.000Z

344

Design, construction and evaluation of a facility for the simulation of fast reactor blankets  

E-Print Network [OSTI]

A facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by ...

Forbes, Ian Alexander

1970-01-01T23:59:59.000Z

345

Source Characterization and Pretreatment Evaluation of Pharmaceuticals and Personal Care Products in Healthcare Facility Wastewater  

E-Print Network [OSTI]

Healthcare facility wastewaters are a potentially important and under characterized source of pharmaceuticals and personal care products to the environment. In this study the composition and magnitude of pharmaceuticals and personal care products...

Nagarnaik, Pranav Mukund

2012-07-16T23:59:59.000Z

346

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System  

SciTech Connect (OSTI)

This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

KESSLER, S.F.

2000-08-10T23:59:59.000Z

347

Ground Vibration and Siting of the Cryogenics Facility for Cornell ERL J. Welch, Cornell U., Ithaca NY  

E-Print Network [OSTI]

of extremely sensitive superconducting RF cavities and the noisy and powerful motors and compressors used, measurements at the TTF (Tesla Test Facility) on cavities very similar to those to be used in the ERL prototype

348

THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE  

SciTech Connect (OSTI)

The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent-order milestones, milestones completed to date, and the vision of bringing PFP to slab-on-grade. Innovative approaches in planning and regulatory strategies, as well new technologies from within the United States and from other countries and field decontamination techniques developed by workforce personnel, such as the ''turkey roaster'' and the ''lazy Susan'' are covered in detail in the paper. Critical information on issues and opportunities during the performance of the work such as concerns regarding the handling and storage of special nuclear material, concerns regarding criticality safety and the impact of SNM de-inventory at PFP are also provided. The continued success of the PFP D&D effort is due to the detailed, yet flexible, approach to planning that applied innovative techniques and tools, involved a team of experienced independent reviewers, and incorporated previous lessons learned at the Hanford site, Rocky Flats, and commercial nuclear D&D projects. Multi-disciplined worker involvement in the planning and the execution of the work has produced a committed workforce that has developed innovative techniques, resulting in safer and more efficient work evolutions.

CHARBONEAU, S.L.

2006-02-01T23:59:59.000Z

349

EVALUATION OF A TURBIDITY METER FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect (OSTI)

Savannah River Remediation’s (SRR’s) Defense Waste Processing Facility (DWPF) Laboratory currently tests for sludge carry-over into the Recycle Collection Tank (RCT) by evaluating the iron concentration in the Slurry Mix Evaporator Condensate Tank (SMECT) and relating this iron concentration to the amount of sludge solids present. A new method was proposed for detecting the amount of sludge in the SMECT that involves the use of an Optek turbidity sensor. Waste Services Laboratory (WSL) personnel conducted testing on two of these units following a test plan developed by Waste Solidification Engineering (WSE). Both Optek units (SN64217 and SN65164) use sensor model AF16-N and signal converter model series C4000. The sensor body of each unit was modified to hold a standard DWPF 12 cc sample vial, also known as a “peanut” vial. The purpose of this testing was to evaluate the use of this model of turbidity sensor, or meter, to provide a measurement of the sludge solids present in the SMECT based upon samples from that tank. During discussions of the results from this study by WSE, WSL, and Savannah River National Laboratory (SRNL) personnel, an upper limit on the acceptable level of solids in SMECT samples was set at 0.14 weight percent (wt%). A “go/no-go” decision criterion was to be developed for the critical turbidity response, which is expressed in concentration units (CUs), for each Optek unit based upon the 0.14 wt% solids value. An acceptable or a “go” decision for the SMECT should reflect the situation that there is an identified risk (e.g. 5%) for a CU response from the Optek unit to be less than the critical CU value when the solids content of the SMECT is actually 0.14 wt% or greater, while a “no-go” determination (i.e., an Optek CU response above the critical CU value, a conservative decision relative to risk) would lead to additional evaluations of the SMECT to better quantify the possible solids content of the tank. Subsequent to the issuance of the initial version of this report but under the scope of the original request for technical assistance, WSE asked for this report to be revised to include the “go/no-go” CU value corresponding to 0.28 wt% solids. It was this request that led to the preparation of Revision 1 of the report. The results for the 0.28 wt% solids value were developed following the same approach as that utilized for the 0.14 wt% solids value. A sludge simulant was used to develop standards for testing both Optek units and to determine the viability of a “go/no-go” CU response for each of the units. Statistical methods were used by SRNL to develop the critical CU value for the “go/no-go” decision for these standards for each Optek unit. Since only one sludge simulant was available for this testing, the sensitivity of these results to other simulants and to actual sludge material is not known. However, limited testing with samples from the actual DWPF process (both SRAT product samples and SMECT samples) demonstrated that the use of the “go/no-go” criteria developed from the sludge simulant testing was conservative for these samples taken from the sludge batch, Sludge Batch 7b, being processed at the time of this testing. While both of the Optek units performed very reliably during this testing, there were statistically significant differences (although small on a practical scale) between the two units. Thus, testing should be conducted on any new unit of this Optek model to qualify it before it is used to support the DWPF operation.

Mahannah, R.; Edwards, T.

2013-06-04T23:59:59.000Z

350

Chapter 47 Solid Waste Facilities (Kentucky)  

Broader source: Energy.gov [DOE]

This chapter establishes the permitting standards for solid waste sites or facilities, the standards applicable to all solid waste sites or facilities, and the standards for certification of...

351

Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy [DOE] Order DOE O 5400.5, “Radiation Protection of the Public and the Environment”). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the contractor. A decision was reached between the NTS regulator and NSTec, opting for alternative authorized limits from DOE Headquarters. In doing so, NSTec personnel performed a dose model using the DOE-approved modeling code RESRAD-BUILD v3.5 to evaluate scenarios. The parameters used in the dose model were conservative. NSTec’s Radiological Engineering Calculation, REC-2010-001, “Public Dose Estimate from the EMAD 25 Ton Locomotive,” concluded that the four scenarios evaluated were below the 25-millirem per year limit, the “likely” dose scenarios met the “few millirem in a year” criteria, and that the EMAD 25-ton locomotive met the radiological requirements to be released with residual radioactivity to the public.

Jeremy Gwin and Douglas Frenette

2010-04-08T23:59:59.000Z

352

Evaluation of geologic materials to limit biological intrusion into low-level radioactive waste disposal sites  

SciTech Connect (OSTI)

This report describes the results of a three-year research program to evaluate the performance of selected soil and rock trench cap designs in limiting biological intrusion into simulated waste. The report is divided into three sections including a discussion of background material on biological interactions with waste site trench caps, a presentation of experimental data from field studies conducted at several scales, and a final section on the interpretation and limitations of the data including implications for the user.

Hakonson, T.E.

1986-02-01T23:59:59.000Z

353

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments  

SciTech Connect (OSTI)

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

Doerge, D. H.; Haffner, D. R.

1988-06-01T23:59:59.000Z

354

Evaluation of chemical sensors for in situ ground-water monitoring at the Hanford Site  

SciTech Connect (OSTI)

This report documents a preliminary review and evaluation of instrument systems and sensors that may be used to detect ground-water contaminants in situ at the Hanford Site. Three topics are covered in this report: (1) identification of a group of priority contaminants at Hanford that could be monitored in situ, (2) a review of current instrument systems and sensors for environmental monitoring, and (3) an evaluation of instrument systems that could be used to monitor Hanford contaminants. Thirteen priority contaminants were identified in Hanford ground water, including carbon tetrachloride and six related chlorinated hydrocarbons, cyanide, methyl ethyl ketone, chromium (VI), fluoride, nitrate, and uranium. Based on transduction principles, chemical sensors were divided into four classes, ten specific types of instrument systems were considered: fluorescence spectroscopy, surface-enhanced Raman spectroscopy (SERS), spark excitation-fiber optic spectrochemical emission sensor (FOSES), chemical optrodes, stripping voltammetry, catalytic surface-modified ion electrode immunoassay sensors, resistance/capacitance, quartz piezobalance and surface acoustic wave devices. Because the flow of heat is difficult to control, there are currently no environmental chemical sensors based on thermal transduction. The ability of these ten instrument systems to detect the thirteen priority contaminants at the Hanford Site at the required sensitivity was evaluated. In addition, all ten instrument systems were qualitatively evaluated for general selectivity, response time, reliability, and field operability. 45 refs., 23 figs., 7 tabs.

Murphy, E.M.; Hostetler, D.D.

1989-03-01T23:59:59.000Z

355

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 117: Area 26 Pluto Disassembly Facility, Nevada Test Site, Nevada With Errata Sheets, Revision 0  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 117, Pluto Disassembly Facility, identified in the Federal Facility Agreement and Consent Order. Corrective Action Unit 117 consists of one Corrective Action Site (CAS), CAS 26-41-01, located in Area 26 of the Nevada Test Site. This plan provides the methodology for field activities needed to gather the necessary information for closing CAS 26-41-01. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 117 using the SAFER process. Additional information will be obtained by conducting a field investigation before finalizing the appropriate corrective action for this CAS. The results of the field investigation will support a defensible recommendation that no further corrective action is necessary following SAFER activities. This will be presented in a Closure Report that will be prepared and submitted to the Nevada Division of Environmental Protection (NDEP) for review and approval. The site will be investigated to meet the data quality objectives (DQOs) developed on June 27, 2007, by representatives of NDEP; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for CAS 26-41-01 in CAU 117.

Pat Matthews

2007-09-01T23:59:59.000Z

356

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada, Rev. No.: 1  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses closure for Corrective Action Unit (CAU) 118, Area 27 Super Kukla Facility, identified in the ''Federal Facility Agreement and Consent Order''. Corrective Action Unit 118 consists of one Corrective Action Site (CAS), 27-41-01, located in Area 27 of the Nevada Test Site. Corrective Action Site 27-41-01 consists of the following four structures: (1) Building 5400A, Reactor High Bay; (2) Building 5400, Reactor Building and access tunnel; (3) Building 5410, Mechanical Building; and (4) Wooden Shed, a.k.a. ''Brock House''. This plan provides the methodology for field activities needed to gather the necessary information for closing the CAS. There is sufficient information and process knowledge from historical documentation and site confirmation data collected in 2005 and 2006 to recommend closure of CAU 118 using the SAFER process. The Data Quality Objective process developed for this CAU identified the following expected closure option: closure in place with use restrictions. This expected closure option was selected based on available information including contaminants of potential concern, future land use, and assumed risks. There are two decisions that need to be answered for closure. Decision I is to determine the nature of contaminants of concern in environmental media or potential source material that could impact human health or the environment. Decision II is to determine whether or not sufficient information has been obtained to confirm that closure objectives were met. This decision includes determining whether the extent of any contamination remaining on site has been defined, and whether actions have been taken to eliminate exposure pathways.

David Strand

2006-09-01T23:59:59.000Z

357

Environmental assessment operation of the HB-Line facility and frame waste recovery process for production of Pu-238 oxide at the Savannah River Site  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0948, addressing future operations of the HB-Line facility and the Frame Waste Recovery process at the Savannah River Site (SRS), near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, DOE has concluded that, the preparation of an environmental impact statement is not required, and is issuing this Finding of No Significant Impact.

NONE

1995-04-01T23:59:59.000Z

358

Enterprise Assessments Review, Savannah River Site 2014 Site...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

More Documents & Publications Independent Oversight Inspection, Savannah River Site - January 2010 Independent Oversight Review, Savannah River Site Tritium Facilities - December...

359

Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years.

Greager, E.M.

1997-12-11T23:59:59.000Z

360

Facility effluent monitoring plan for the plutonium uranium extraction facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

Wiegand, D.L.

1994-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Safety Basis Requirements for Nonnuclear Facilities at Lawrence Livermore National Laboratory Site-Specific Work Smart Standards Revision 1  

SciTech Connect (OSTI)

This standard establishes requirements that, when coupled with Lawrence Livermore National Laboratory's (LLNL's) Integrated Safety Management System (ISMS) methods and other Work Smart Standards for assuring worker safety, assure that the impacts of nonnuclear operations authorized in LLNL facilities are well understood and controlled in a manner that protects the health of workers, the public, and the environment. All LLNL facilities shall be classified based on potential for adverse impact of operations to the health of co-located (i.e., nearby) workers and the public in accordance with this standard, Title 10 Code of Federal Regulations (10 CFR) 830, Subpart B, and Department of Energy Order (DOE O) 420.2A. This standard provides information on: Objectives; Applicability; Safety analysis requirements; Control selection and maintenance; Documentation requirements; Safety basis review, approval, and renewal; and Safety basis implementation.

Beach, R; Brereton, S; Failor, R; Hildum, S; Spagnolo, S; Van Warmerdam, C

2003-02-24T23:59:59.000Z

362

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site  

SciTech Connect (OSTI)

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

L.E. Demick

2011-10-01T23:59:59.000Z

363

Preliminary volcanic hazards evaluation for Los Alamos National Laboratory Facilities and Operations : current state of knowledge and proposed path forward  

SciTech Connect (OSTI)

The integration of available information on the volcanic history of the region surrounding Los Alamos National Laboratory indicates that the Laboratory is at risk from volcanic hazards. Volcanism in the vicinity of the Laboratory is unlikely within the lifetime of the facility (ca. 50–100 years) but cannot be ruled out. This evaluation provides a preliminary estimate of recurrence rates for volcanic activity. If further assessment of the hazard is deemed beneficial to reduce risk uncertainty, the next step would be to convene a formal probabilistic volcanic hazards assessment.

Keating, Gordon N.; Schultz-Fellenz, Emily S.; Miller, Elizabeth D.

2010-09-01T23:59:59.000Z

364

Closure Report for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada with ROTC 1, Revision 0  

SciTech Connect (OSTI)

This CR provides documentation and justification for the closure of CAU 118 without further corrective action. This justification is based on process knowledge and the results of the investigative and closure activities conducted in accordance with the CAU 118 SAFER Plan: Streamlined Approach for Environmental Restoration (SAFER) Plan for CAU 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada (NNSA/NSO, 2006). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. This CR also provides the analytical and radiological survey data to confirm that the remediation goals were met as specified in the CAU 118 SAFER Plan (NNSA/NSO, 2006). The Nevada Division of Environmental Protection (NDEP) approved the CAU 118 SAFER Plan (Murphy, 2006), which recommends closure in place with use restrictions (URs).

Mark Burmeister

2007-09-01T23:59:59.000Z

365

POST CLOSURE INSPECTION REPORT FOR CORRECTIVE ACTION UNIT 92: AREA 6 DECON POND FACILITY, NEVADA TEST SITE, NEVADA; FOR CALENDAR YEAR 2005  

SciTech Connect (OSTI)

This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility, Nevada Test Site, Nevada. CAU 92 was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection (NDEP), 1995) and the Federal Facility Agreement and Consent Order of 1996. Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by the NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs): CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period. This report covers calendar year 2005. Quarterly site inspections were performed in March, June, September, and December of 2005. All observations indicated the continued integrity of the unit. No issues or concerns were noted, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Five additional inspections were performed after precipitation events that exceeded 1.28 cm (0.50 in) within a 24-hour period during 2005. No significant changes in site conditions were noted during these inspections, and no corrective actions were necessary. Copies of the inspection checklists and field notes completed during each inspection are included in Appendix A. Precipitation records for 2005 are included in Appendix C.

NA

2006-03-01T23:59:59.000Z

366

Monitoring and Evaluation of Yearling Fall Chinook Salmon (Oncorhynchus tshawytscha) Released from Acclimation Facilities Upstream of Lower Granite Dam; 2002 Annual Report.  

SciTech Connect (OSTI)

The Nez Perce Tribe, in cooperation with the U.S. Fish and Wildlife Service and Washington Department of Fish and Wildlife, conducted monitoring and evaluation studies on Lyons Ferry Hatchery reared yearling fall Chinook salmon Oncorhynchus tshawytscha that were acclimated and released at three Fall Chinook Acclimation Project sites upstream of Lower Granite Dam in 2002. This was the seventh year of a long-term project to supplement natural spawning populations of Snake River stock fall Chinook salmon upstream of Lower Granite Dam. The 479,358 yearlings released from the Fall Chinook Acclimation Project facilities exceeded the 450,000 fish quota. We use Passive Integrated Transponder (PIT) tag technology to monitor the primary performance measures of survival to mainstem dams and migration timing. We also monitor size, condition and tag/mark retention at release. We released 7,545 PIT tagged yearlings from Pittsburg Landing, 7,482 from Big Canyon and 2,487 from Captain John Rapids. Fish health sampling indicated that, overall, bacterial kidney disease levels at the acclimation facilities could be considered medium to high with 43-62% of fish sampled rating medium to very high. Mean fork lengths (95% confidence interval) of the PIT tagged groups ranged from 146.7 mm (146.2-147.2 mm) at Captain John Rapids to 164.8 mm (163.5-166.1 mm) at Lyons Ferry Hatchery. Mean condition factors ranged from 1.06 at Lyons Ferry Hatchery to 1.14 at Pittsburg Landing and Captain John Rapids. Estimated survival (95% confidence interval) of PIT tagged yearlings from release to Lower Granite Dam ranged from 88.6% (86.0-91.1%) for Pittsburg Landing to 97.0% (92.4-101.7%) for Captain John Rapids. Estimated survival from release to McNary Dam ranged from 54.3% (50.2-58.3%) for Big Canyon to 70.5% (65.4-75.5%) for Pittsburg Landing. Median migration rates to Lower Granite Dam, based on all observations of PIT tagged yearlings from the FCAP facilities, ranged from 8.1 river kilometers per day (rkm/d) for Captain John Rapids to 14.1 rkm/d for Pittsburg Landing. Median migration rates to McNary Dam ranged from 10.9 rkm/d for Big Canyon to 15.9 rkm/d for Pittsburg Landing. Median travel times from the FCAP facilities were about 9-12 days to Lower Granite Dam and 25-30 days to McNary Dam. Median arrival dates at Lower Granite Dam, based on all observations of PIT tagged yearling groups from the FCAP facilities, ranged from April 20-28. Median arrival dates at McNary Dam for the FCAP groups were all May 11. The objectives of this project are to quantify and evaluate pre-release fish health, condition and mark retention as well as post-release survival, migration timing, migration rates, travel times and movement patterns of fall Chinook salmon from supplementation releases at the FCAP facilities, then provide feedback to co-managers for project specific and basin wide management decision-making.

Rocklage, Stephen J.; Kellar, Dale S. (Nez Perce Tribe, Department of Fisheries Resource Management, ID)

2005-07-01T23:59:59.000Z

367

Final closure plan for the high-explosives open burn treatment facility at Lawrence Livermore National Laboratory Experimental Test Site 300  

SciTech Connect (OSTI)

This document addresses the interim status closure of the HE Open Bum Treatment Facility, as detailed by Title 22, Division 4.5, Chapter 15, Article 7 of the Califonia Code of Regulations (CCR) and by Title 40, Code of Federal Regulations (CFR) Part 265, Subpart G, ``Closure and Post Closure.`` The Closure Plan (Chapter 1) and the Post- Closure Plan (Chapter 2) address the concept of long-term hazard elimination. The Closure Plan provides for capping and grading the HE Open Bum Treatment Facility and revegetating the immediate area in accordance with applicable requirements. The Closure Plan also reflects careful consideration of site location and topography, geologic and hydrologic factors, climate, cover characteristics, type and amount of wastes, and the potential for contaminant migration. The Post-Closure Plan is designed to allow LLNL to monitor the movement, if any, of pollutants from the treatment area. In addition, quarterly inspections will ensure that all surfaces of the closed facility, including the cover and diversion ditches, remain in good repair, thus precluding the potential for contaminant migration.

Mathews, S.

1997-04-01T23:59:59.000Z

368

Ground-water monitoring compliance projects for Hanford Site facilities: Progress report for the period January 1--March 31, 1988: Volume 1, Text  

SciTech Connect (OSTI)

This report describes the progress of eight Hanford Site ground-water monitoring projects for the period January 1 to March 31, 1988. The facilities represented by the eight projects are the 300 Area Process trenches, 183-H Solar Evaporation Basins, 200 Areas Low-Level Burial Grounds, Nonradioactive Dangerous Waste Landfill, 216-A-36B Crib, 1301-N Liquid Waste Disposal Facility, 1325-N Liquid Waste Disposal Facility, and 1324-N/NA Surface Impoundment and Percolation Ponds. The latter four projects are included in this series of quarterly reports for the first time. This report is the seventh in a series of periodic status reports; the first six cover the period from May 1, 1986, through December 31, 1987 (PNL 1986; 1987a, b, c, d; 1988a). This report satisfies the requirements of Section 17B(3) of the Consent Agreement and Compliance Order issued by the Washington State Department of Ecology (1986a) to the US Department of Energy-Richland Operations Office. 13 refs., 19 figs., 24 tabs.

Not Available

1988-05-01T23:59:59.000Z

369

Evaluation of Fish Passage Sites in the Walla Walla River Basin, 2008  

SciTech Connect (OSTI)

In 2008, Pacific Northwest National Laboratory evaluated the Hofer Dam fish screen and provided technical assistance at two other fish passage sites as requested by the Bonneville Power Administration, the Walla Walla Watershed Council, or the Confederated Tribes of the Umatilla Indian Reservation. Evaluation of new sites such as Hofer Dam focuses on their design, construction, operation, and maintenance to determine if they effectively provide juvenile salmonids with safe passage through irrigation diversions. There were two requests for technical assistance in 2008. In the first, the Confederated Tribes of the Umatilla Indian Reservation requested an evaluation of the Nursery Bridge fish screens associated with the fish ladder on the east side of the Walla Walla River. One set of brushes that clean the screens was broken for an extended period. Underwater videography and water velocity measurements were used to determine there were no potential adverse effects on juvenile salmonids when the west set of screens was clean enough to pass water normally. A second request, received from the National Marine Fisheries Service and the Walla Walla Watershed Council, asked for evaluation of water velocities through relatively new head gates above and adjacent to the Eastside Ditch fish screens on the Walla Walla River. Water moving through the head gates and not taken for irrigation is diverted to provide water for the Nursery Bridge fish ladder on the east side of the river. Elevations used in the design of the head gates were incorrect, causing excessive flow through the head gates that closely approached or exceeded the maximum swimming burst speed of juvenile salmonids. Hofer Dam was evaluated in June 2008. PNNL researchers found that conditions at Hofer Dam will not cause impingement or entrainment of juvenile salmonids but may provide habitat for predators and lack strong sweeping flows to encourage juvenile salmonid passage downstream. Further evaluation of velocities at the Eastside Ditch and wasteway gates should occur as changes are made to compensate for the design problems. These evaluations will help determine whether further changes are required. Hofer Dam also should be evaluated again under more normal operating conditions when the river levels are typical of those when fish are emigrating and the metal plate is not affecting flows.

Chamness, Mickie A. [Pacific Northwest National Laboratory

2008-08-29T23:59:59.000Z

370

Naval Station Newport Wind Resource Assessment. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites, and The Naval Facilities Engineering Service Center  

SciTech Connect (OSTI)

The U.S. Environmental Protection Agency (EPA) launched the RE-Powering America's Land initiative to encourage development of renewable energy (RE) on potentially contaminated land and mine sites. EPA is collaborating with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to evaluate RE options at Naval Station (NAVSTA) Newport in Newport, Rhode Island where multiple contaminated areas pose a threat to human health and the environment. Designated a superfund site on the National Priorities List in 1989, the base is committed to working toward reducing the its dependency on fossil fuels, decreasing its carbon footprint, and implementing RE projects where feasible. The Naval Facilities Engineering Service Center (NFESC) partnered with NREL in February 2009 to investigate the potential for wind energy generation at a number of Naval and Marine bases on the East Coast. NAVSTA Newport was one of several bases chosen for a detailed, site-specific wind resource investigation. NAVSTA Newport, in conjunction with NREL and NFESC, has been actively engaged in assessing the wind resource through several ongoing efforts. This report focuses on the wind resource assessment, the estimated energy production of wind turbines, and a survey of potential wind turbine options based upon the site-specific wind resource.

Robichaud, R.; Fields, J.; Roberts, J. O.

2012-02-01T23:59:59.000Z

371

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2010  

SciTech Connect (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants ([NESHAP]; U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code 246-247: Radiation Protection - Air Emissions. In these NESHAP assessments, potential unabated off-site doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campus of the Pacific Northwest National Laboratory. This report describes the inventory-based methods and provides the results for the NESHAP assessment performed in 2010.

Ballinger, Marcel Y.; Gervais, Todd L.; Barnett, J. M.

2011-05-13T23:59:59.000Z

372

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 114: Area 25 EMAD Facility Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Streamlined Approach for Environmental Restoration (SAFER) Plan addresses the actions needed to achieve closure for Corrective Action Unit (CAU) 114, Area 25 EMAD Facility, identified in the Federal Facility Agreement and Consent Order (FFACO). Corrective Action Unit 114 comprises the following corrective action sites (CASs) located in Area 25 of the Nevada Test Site: • 25-41-03, EMAD Facility • 25-99-20, EMAD Facility Exterior Releases This plan provides the methodology for field activities needed to gather the necessary information for closing each CAS. There is sufficient information and process knowledge from historical documentation and investigations of similar sites regarding the expected nature and extent of potential contaminants to recommend closure of CAU 114 using the SAFER process. Additional information will be obtained by conducting a field investigation before selecting the appropriate corrective action for each CAS. It is anticipated that the results of the field investigation and implementation of a corrective action of clean closure will support a defensible recommendation that no further corrective action is necessary. If it is determined that complete clean closure cannot be accomplished during the SAFER, then a hold point will have been reached and the Nevada Division of Environmental Protection (NDEP) will be consulted to determine whether the remaining contamination will be closed under the alternative corrective action of closure in place. This will be presented in a closure report that will be prepared and submitted to NDEP for review and approval. The sites will be investigated based on the data quality objectives (DQOs) developed on April 30, 2009, by representatives of NDEP; U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and National Security Technologies, LLC. The DQO process was used to identify and define the type, amount, and quality of data needed to determine and implement appropriate corrective actions for each CAS in CAU 114. The following text summarizes the SAFER activities that will support the closure of CAU 114: • Perform site preparation activities (e.g., utilities clearances, radiological surveys). • Collect environmental samples from designated target populations (e.g., stained soil) to confirm or disprove the presence of contaminants of concern (COCs) as necessary to supplement existing information. • Collect samples of materials to determine whether potential source material (PSM) is present that may cause the future release of a COC to environmental media. • If no COCs or PSMs are present at a CAS, establish no further action as the corrective action. • If COCs exist, collect environmental samples from designated target populations (e.g., clean soil adjacent to contaminated soil) and submit for laboratory analyses to define the extent of COC contamination. • If a COC or PSM is present at a CAS, either: - Establish clean closure as the corrective action. The material to be remediated will be removed, disposed of as waste, and verification samples will be collected from remaining soil, or - Establish closure in place as the corrective action and implement the appropriate use restrictions. • Confirm the selected closure option is sufficient to protect human health and the environment.

Mark Burmeister

2009-08-01T23:59:59.000Z

373

Facility effluent monitoring plan for 242-A evaporator facility  

SciTech Connect (OSTI)

A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years.

Crummel, G.M.; Gustavson, R.D.

1995-02-01T23:59:59.000Z

374

Summary report on reprocessing evaluation of selected inactive uranium mill tailings sites  

SciTech Connect (OSTI)

Sandia National Laboratories has been assisting the Department of Energy in the Uranium Mill Tailings Remedial Actions Program (UMTRAP) the purpose of which is to implement the provisions of Title I of Public Law 95-604, Uranium Mill Tailings Radiation Control Act of 1978.'' As part of this program, there was a need to evaluate the mineral concentration of the residual radioactive materials at some of the designated processing sites to determine whether mineral recovery would be practicable. Accordingly, Sandia contracted Mountain States Research and Development (MSRD), a division of Mountain States Mineral Enterprises, to drill, sample, and test tailings at 12 sites to evaluate the cost of and the revenue that could be derived from mineral recovery. UMTRAP related environmental and engineering sampling and support activities were performed in conjunction with the MSRD operations. This summary report presents a brief description of the various activities in the program and of the data and information obtained and summarizes the results. 8 refs., 9 tabs.

Not Available

1983-09-01T23:59:59.000Z

375

EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal for the return of all leased cesium-137 and strontium-90 leased capsules to the U.S. Department of Energy's Waste Encapsulation and...

376

Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

French, Sean B. [Los Alamos National Laboratory; Shuman, Robert [WPS: WASTE PROJECTS AND SERVICES

2012-04-17T23:59:59.000Z

377

Report for the HWMA/RCRA Post Closure Permit for the INTEC Waste Calcining Facility at the INL Site  

SciTech Connect (OSTI)

The Waste Calcining Facility (WCF) is located at the Idaho Nuclear Technology and Engineering Center. In 1998, the WCF was closed under an approved Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Closure Plan. Vessels and spaces were grouted and then covered with a concrete cap. The Idaho Department of Environmental Quality issued a final HWMA/RCRA post-closure permit on September 15, 2003, with an effective date of October 16, 2003. This permit sets forth procedural requirements for groundwater characterization and monitoring, maintenance, and inspections of the WCF to ensure continued protection of human health and the environment. The post-closure permit also includes semiannual reporting requirements under Permit Conditions III.H. and I.U. These reporting requirements have been combined into this single semiannual report.

Idaho Cleanup Project

2006-06-01T23:59:59.000Z

378

Monitoring and Evaluation of Yearling Fall Chinook Salmon (Oncorhynchus tshawytscha) Released from Acclimation Facilities Upstream of Lower Granite Dam; 1999 Annual Report.  

SciTech Connect (OSTI)

The Nez Perce Tribe, in cooperation with the U.S. Fish and Wildlife Service and Washington Department of Fish and Wildlife, conducted monitoring and evaluation studies on Lyons Ferry Hatchery reared yearling fall Chinook salmon Oncorhynchus tshawytscha that were acclimated and released at three Fall Chinook Acclimation Project (FCAP) sites upstream of Lower Granite Dam along with yearlings released on-station from Lyons Ferry Hatchery in 1999. This was the fourth year of a long-term project to supplement natural spawning populations of Snake River stock fall Chinook salmon upstream of Lower Granite Dam. The 453,117 yearlings released from the Fall Chinook Acclimation Project facilities not only slightly exceeded the 450,000 fish quota, but a second release of 76,386 yearlings (hereafter called Surplus) were acclimated at the Big Canyon facility and released about two weeks after the primary releases. We use Passive Integrated Transponder (PIT) tag technology to monitor the primary performance measures of survival to mainstem dams and migration timing. We also monitor size, condition and tag/mark retention at release. We released 9,941 PIT tagged yearlings from Pittsburg Landing, 9,583 from Big Canyon, 2,511 Big Canyon Surplus and 2,494 from Captain John Rapids. The Washington Department of Fish and Wildlife released 983 PIT tagged yearlings from Lyons Ferry Hatchery. Fish health sampling indicated that, overall, bacterial kidney disease levels could be considered relatively low and did not appear to increase after transport to the acclimation facilities. Compared to prior years, Quantitative Health Assessment Indices were relatively low at Pittsburg Landing and Lyons Ferry Hatchery and relatively high at Big Canyon and Captain John Rapids. Mean fork lengths (95% confidence interval) of the release groups ranged from 147.4 mm (146.7-148.1 mm) at Captain John Rapids to 163.7 mm (163.3-164.1 mm) at Pittsburg Landing. Mean condition factors ranged from 1.04 at Pittsburg Landing to 1.23 at Captain John Rapids. Estimated survival (95% confidence interval) of PIT tagged yearlings from release to Lower Granite Dam ranged from 87.8% (82.1-93.4%) for Big Canyon Surplus to 94.1% (90.1-98.1%) for Captain John Rapids. Estimated survival from release to McNary Dam ranged from 58.7% (49.3-68.1%) for Big Canyon Surplus to 71.3% (60.1-82.5%) for Captain John Rapids. Median migration rates to Lower Granite Dam, based on all observations of PIT tagged yearlings from the FCAP facilities, ranged from 9.3 river kilometers per day (rkm/d) for Captain John Rapids to 18.7 rkm/d for Pittsburg Landing. Median migration rates to McNary Dam ranged from 9.0 rkm/d for Lyons Ferry Hatchery to 17.3 rkm/d for Pittsburg Landing. Median travel times from the FCAP facilities were about 7-10 days to Lower Granite Dam and 21-23 days to McNary Dam. Median arrival dates at Lower Granite Dam, based on all observations of PIT tagged yearling groups from the FCAP facilities, were all from April 23-25. The median arrival date for Big Canyon Surplus was May 4. Median arrival dates at McNary Dam for Pittsburg Landing, Big Canyon and Captain John Rapids groups were all from May 7-8. Median arrival dates at McNary Dam were May 17 for Big Canyon Surplus and April 26 for Lyons Ferry Hatchery.

Rocklage, Stephen J.; Kellar, Dale S. (Nez Perce Tribe, Department of Fisheries Resource Management, ID)

2005-07-01T23:59:59.000Z

379

RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented.

Not Available

1993-06-01T23:59:59.000Z

380

Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184  

SciTech Connect (OSTI)

The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: ? Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. ? DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. ? DOE must continue to maintain constructive relationships with the U.S. Army Corps of Engineers and state and federal regulators.

Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

2012-02-26T23:59:59.000Z

Note: This page contains sample records for the topic "facility site evaluation" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Idaho Habitat Evaluation for Off-Site Mitigation Record : Annual Report 1985.  

SciTech Connect (OSTI)

Evaluation approaches to document a record of credit for mitigation were developed in 1984-1985 for most of the habitat projects. Restoration of upriver anadromous fish runs through increased passage survival at main stem Columbia and Snake River dams is essential to the establishment of an off-site mitigation record, as well as to the success of the entire Fish and Wildlife program. The mitigation record is being developed to use increased smolt production (i.e., yield) at full-seeding as the basic measure of benefit from a habitat project. The IDFG evaluation approach consists of three basic, integrated levels: general monitoring, standing crop evaluations, and intensive studies. Annual general monitoring of anadromous fish densities in a small number of sections for each project will be used to follow population trends and define full-seeding levels. For most projects, smolt production will be estimated indirectly from standing crop estimates by factoring appropriate survival rates from parr to smolt stages. Intensive studies in a few key production streams will be initiated to determine these appropriate survival rates and provide other basic biological information that is needed for evaluation of the Fish and Wildlife program. A common physical habitat and fish population data base is being developed for every BPA habitat project in Idaho to be integrated at each level of evaluation. Compatibility of data is also needed between Idaho and other agencies and tribes in the Columbia River basin. No final determination of mitigation credit for any Idaho habitat enhancement project has been attainable to date.

Petrosky, Charles E.; Holubetz, Terry B.

1986-04-01T23:59:59.000Z

382

Hanford Site Asbestos Abatement Plan. Revision 1  

SciTech Connect (OSTI)

The Hanford Site Asbestos Abatement Plan (Plan) lists priorities for asbestos abatement activities to be conducted in Hanford Site facilities. The Plan is based on asbestos assessment information gathered in fiscal year 1989 that evaluated all Hanford Site facilities for the presence and condition of asbestos. Of those facilities evaluated, 414 contain asbestos-containing materials and are classified according to the potential risk of asbestos exposure to building personnel. The Plan requires that asbestos condition update reports be prepared for all affected facilities. The reporting is completed by the asbestos coordinator for each of the 414 affected facilities and transmitted to the Plan manager annually. The Plan manager uses this information to reprioritize future project lists. Currently, five facilities are determined to be Class Al, indicating a high potential for asbestos exposure. Class Al and B1 facilities are the highest priority for asbestos abatement. Abatement of the Class A1 and Bl facilities is scheduled through fiscal year 1997. Removal of asbestos in B1 facilities will reduce the risk for further Class ``A`` conditions to arise.

Mewes, B.S.

1993-09-01T23:59:59.000Z

383

Monitoring and Evaluation of Yearling Fall Chinook Salmon Released from Acclimation Facilities Upstream of Lower Granite Dam; 1998 Annual Report.  

SciTech Connect (OSTI)

The Nez Perce Tribe, in cooperation with the U.S. Fish and Wildlife Service and Washington Department of Fish and Wildlife, conducted monitoring and evaluation studies on Lyons Ferry Hatchery (Snake River stock) yearling fall chinook salmon that were acclimated and released at three Fall Chinook Acclimation Project sites upstream of Lower Granite Dam along with yearlings released on-station from Lyons Ferry Hatchery in 1998. The three fall chinook acclimation facilities are operated by the Nez Perce Tribe and located at Pittsburg Landing and Captain John Rapids on the Snake River and at Big Canyon Creek on the Clearwater River. Yearlings at the Big Canyon facility consisted of two size classes that are referred to in this report as 9.5 fish per pound (fpp) and 30 fpp. The Big Canyon 9.5 fpp were comparable to the yearlings at Pittsburg Landing, Captain John Rapids and Lyons Ferry Hatchery. A total of 9,942 yearlings were PIT tagged and released at Pittsburg Landing. PIT tagged yearlings had a mean fork length of 159.9 mm and mean condition factor of 1.19. Of the 9,942 PIT tagged fish released, a total of 6,836 unique tags were detected at mainstem Snake and Columbia River dams (Lower Granite, Little Goose, Lower Monumental and McNary). A total of 4,926 9.5 fpp and 2,532 30 fpp yearlings were PIT tagged and released at Big Canyon. PIT tagged 9.5 fpp yearlings had a mean fork length of 156.9 mm and mean condition factor of 1.13. PIT tagged 30 fpp yearlings had a mean fork length of 113.1 mm and mean condition factor of 1.18. Of the 4,926 PIT tagged 9.5 fpp yearlings released, a total of 3,042 unique tags were detected at mainstem Snake and Columbia River dams. Of the 2,532 PIT tagged 30 fpp yearlings released, a total of 1,130 unique tags were detected at mainstem Snake and Columbia River dams. A total of 1,253 yearlings were PIT tagged and released at Captain John Rapids. PIT tagged yearlings had a mean fork length of 147.5 mm and mean condition factor of 1.09. Of the 1,253 PIT tagged fish released, a total of 719 unique tags were detected at mainstem Snake and Columbia River dams. A total of 2,420 yearlings were PIT tagged and released at Lyons Ferry Hatchery. PIT tagged yearlings had a mean fork length of 159.0 mm and mean condition factor of 1.10. Of the 2,420 PIT tagged fish released, a total of 979 unique tags were detected at mainstem Snake and Columbia River dams (Lower Monumental and McNary). Median travel times, based on all detections, of PIT tagged fish released from Pittsburg Landing were 10.5 days to Lower Granite Dam, 21.7 days to McNary Dam and 29.8 days to Bonneville Dam. Median migration rates were 16.4 rkm/d to Lower Granite Dam, 18.3 rkm/d to McNary Dam and 18.9 rkm/d to Bonneville Dam. The median arrival dates were April 25 at Lower Granite Dam, May 6 at McNary Dam and May 14 at Bonneville Dam. The 90% passage dates were May 5 at Lower Granite Dam, May 20 at McNary Dam and May 25 at Bonneville Dam. Median travel times, based on all detections, of PIT tagged 9.5 fpp yearlings released from Big Canyon were 13.3 days to Lower Granite Dam, 26.0 days to McNary Dam and 30.8 days to Bonneville Dam. Median migration rates were 13.0 rkm/d to Lower Granite Dam, 15.3 rkm/d to McNary Dam and 18.3 rkm/d to Bonneville Dam. The median arrival dates were April 27 at Lower Granite Dam, May 11 at McNary Dam and May 15 at Bonneville Dam. The 90% passage dates were May 9 at Lower Granite Dam, May 24 at McNary Dam and May 25 at Bonneville Dam. Median travel times, based on all detections, of PIT tagged 30 fpp yearlings released from Big Canyon were 20.8 days to Lower Granite Dam, 37.6 days to McNary Dam and 43.5 days to Bonneville Dam. Median migration rates were 8.3 rkm/d to Lower Granite Dam, 10.6 rkm/d to McNary Dam and 12.9 rkm/d to Bonneville Dam. The median arrival dates were May 5 at Lower Granite Dam, May 23 at McNary Dam and May 28 at Bonneville Dam. The 90% passage dates were May 22 at Lower Granite Dam, May 31 at McNary Dam and June 5 at Bonneville Dam. Median arrival dates, based on all detections, of PIT tagge

Rocklage, Stephen J. (Nez Perce Tribe, Department of Fisheries Resource Management, Lapwai, ID)

2004-01-01T23:59:59.000Z

384

Demonstration and evaluation of the pulsed ultraviolet-irradiation gas-treatment system, Savannah River Site  

SciTech Connect (OSTI)

Argonne National Laboratory was asked to demonstrate and evaluate a pulsed ultraviolet-irradiation system developed by Purus, Inc., at the Volatile Organic Compounds Non-Arid Integrated Demonstration at the Savannah River Site near aiken, South Carolina. The Purus system consists of four reactor chambers, each containing a xenon flash lamp. During the two weeks of testing, samples were taken and analyzed from the inlet and outlet sides of the Purus system. The contaminants of concern on the inlet were tetrachloroethylene (PCE), trichloroethylene (TCE), and 1,1,1-trichloroethane (TCA); the contaminants of concern on the outlet were PCE, TCE, TCA, carbon tetrachloride (CT), and chloroform. The evaluation of the Purus system included an examination of the reduction of both TCE and PCE and a search for any change in the concentrations. (Operating conditions included flow rates, ranging from 25 to 100 standard cubic feet per minute; inlet concentration of PCE, ranging from 360 to 10,700 parts per million volume; and flash lamp rates, ranging from 1 to 30 hertz.) The Purus system was quite efficient at reducing the concentrations of both PCE and TCE. The potential by-products, TCA, CT, and chloroform, showed no significant increases throughout the range of the various operating parameters. Overall, the Purus system appears to be a cost-efficient means of reducing the concentrations of PCE and TCE, while the removal of the initial photo-oxidation products and TCA is slower and needs further evaluation.

Schneider, J.; Wilkey, M.; Peters, R.; Tomczyk, N.; Friedlund, J.; Farber, P. [Argonne National Lab., IL (United States). Energy Systems Div.; Mass, B.; Haag, W. [Purus, Inc., San Jose, CA (United States)

1994-10-01T23:59:59.000Z

385

Evaluation of the Dallas Thompson Riverscreen Site on the Touchet River.  

SciTech Connect (OSTI)

Riverscreen irrigation pumps are a relatively new design in which the pump intake floats on the river surface, pulling water in only from the bottom side and surrounded by a self-cleaning screen. The Walla Walla County Conservation District recently started replacing old pump screens with the Riverscreen and was interested in whether the screens are protective of juvenile salmonids. Pacific Northwest National Laboratory evaluated approach velocities and operations at the Riverscreen installation on the Dallas Thompson property, approximately 3 mi. north of Touchet, Washington and 300 ft north of Hofer Dam, on June 18, 2007. Evaluation of this site consisted of underwater videography and water velocity measurements. The Dallas Thompson Riverscreen was pumping approximately 930 gpm during our evaluation, which is close to the maximum pumping rate for this model. Underwater videography showed only slow movement of water-borne particulates toward the pump intake, and the screen material was clean. All water velocity measurements were taken below the pump intake opening and between 3 to 6 in. from the screen face. All approach velocities (flow toward the screen and pump) were below National Marine Fisheries Service draft guidelines for juvenile fish screens.

Chamness, Mickie [Pacific Northwest National Laboratory

2007-07-25T23:59:59.000Z

386

Thesis: Modeling and Evaluation of the NIST Net Zero Energy Residential Test Facility  

E-Print Network [OSTI]

with solar thermal collectors vs. photovoltaic panels and a heat pump hot water heater ­ Enthalpy exchanger · Use model to evaluate various alternative energy system configurations ­ Heating domestic water vs. heat recovery ventilation system ­ Ground-source heat pump vs. air-source heat pump ­ Ground

Wisconsin at Madison, University of

387

Electro-Mechanical Manipulator for Use in the Remote Equipment Decontamination Cell at the Defense Waste Processing Facility, Savannah River Site - 12454  

SciTech Connect (OSTI)

One of the legacies of the cold war is millions of liters of radioactive waste. One of the locations where this waste is stored is at the Savannah River Site (SRS) in South Carolina. A major effort to clean up this waste is on-going at the defense waste processing facility (DWPF) at SRS. A piece of this effort is decontamination of the equipment used in the DWPF to process the waste. The remote equipment decontamination cell (REDC) in the DWPF uses electro-mechanical manipulators (EMM) arms manufactured and supplied by PaR Systems to decontaminate DWPF process equipment. The decontamination fluid creates a highly corrosive environment. After 25 years of operational use the original EMM arms are aging and need replacement. To support continued operation of the DWPF, two direct replacement EMM arms were delivered to the REDC in the summer of 2011. (authors)

Lambrecht, Bill; Dixon, Joe [Par Systems, Shoreview, Minnesota, 55126 (United States); Neuville, John R. [Savannah River Remediation, Savannah River Site, Aiken, South Carolina, 29808 (United States)

2012-07-01T23:59:59.000Z

388

EA-0993: Shutdown of the Fast Flux Testing Facility, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the U.S. Department of Energy's Hanford Site's proposal to place the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown...

389

Post-Closure Inspection Report for Corrective Action Unit 92: Area 6 Decon Pond Facility, Nevada Test Site, Nevada, for Calendar Year 2006  

SciTech Connect (OSTI)

This Post-Closure Inspection Report provides an analysis and summary of inspections for Corrective Action Unit (CAU) 92, Area 6 Decon Pond Facility. CAU 92 was closed according to the ''Resource Conservation and Recovery Act'' (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP], 1995) and the ''Federal Facility Agreement and Consent Order'' (FFACO) of 1996 (FFACO, 1996). Closure activities were completed on February 16, 1999, and the Closure Report (U.S. Department of Energy, Nevada Operations Office, 1999) was approved and a Notice of Completion issued by NDEP on May 11, 1999. CAU 92 consists of two Corrective Action Sites (CASs), CAS 06-04-01, Decon Pad Oil/Water Separator; and CAS 06-05-02, Decontamination Pond (RCRA). Both CASs have use restrictions; however, only CAS 06-05-02 requires post-closure inspections. Visual inspections of the cover and fencing at CAS 06-05-02 are performed quarterly. Additional inspections are conducted if precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in