Cellulose Products Manufacturing: National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

Read the National Emission Standards for Hazardous Air Pollutants (NESHAP) for Cellulose Products Manufacturing, see the rule history for this Maximum Achievable Control Technology (MACT), and find Compliance help for this source.

Fact Sheet for Friction Materials Manufacturing Facilities Residual Risk and Technology Review

Science.gov (United States)

proposed amendments to the National Emission Standards for Hazardous Air Pollutants (NESHAP) for Friction Materials Manufacturing Facilities to address the results of the residual risk and technology review

Facility Effluent Monitoring Plan for the 3720 Building

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

Ross In Situ Uranium Recovery Project NESHAP Subpart W Construction Approval

Science.gov (United States)

On May 5, 2015, EPA issued a Construction Approval under the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at 40 CFR Part 61, subpart W, to Strata Energy, Inc., for their Ross In Situ Recovery (ISR) Uranium Project in Crook County, WY.

Brick and Structural Clay Products: National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

Learn about the NESHAP regulation for brick and structural clay products by reading the rule summary, rule history, code of federal regulations, and the additional resources like fact sheets and background information documents

Pesticide Active Ingredient Production Industry: National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

This action promulgates national emission standards for hazardous air pollutants (NESHAP) for the pesticide active ingredient (PAI) production source category under section 112 of the Clean Air Act as amended (CAA or Act).

Surface Coating of Wood Building Products: National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

Learn about the NESHAP for surface coating of wood building products by reading the rule summary and history, with links to the federal register notices, additional documents, related rules and compliance information

Ethylene Oxide Commerical Sterilization and Fumigation Operations National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

The purpose of this document is to provide implementation materials to assist in conducting complete and efficient inspections at ethylene oxide commercial sterilization and fumigation operations to determine compliance with the NESHAP

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

International Nuclear Information System (INIS)

Shields, K.D.; Ballinger, M.Y.

1999-03-01

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

Energy Technology Data Exchange (ETDEWEB)

Shields, K.D.; Ballinger, M.Y.

1999-04-02

This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

77 FR 2535 - Agency Information Collection Activities; Proposed Collection; Comment Request; NESHAP for...

Science.gov (United States)

2012-01-18

... listing of the contents of the docket, and to access those documents in the public docket that are... respond, including through the use of appropriate automated electronic, mechanical, or other technological... for-profit, and State, Local, or Tribal governments. Title: NESHAP for Hazardous Waste Combustors (40...

1996 Idaho National Engineering and Environmental Laboratory (INEEL) National Emissions Standards for Hazardous Air Pollutants (NESHAPs) -- Radionuclides. Annual report

International Nuclear Information System (INIS)

1997-06-01

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1996. The Idaho Operations Office of the DOE is the primary contact concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For calendar year 1996, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 3.14E-02 mrem (3.14E-07 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

78 FR 54892 - Information Collection Request Submitted to OMB for Review and Approval; Comment Request; NESHAP...

Science.gov (United States)

2013-09-06

...: Catalytic Cracking Units, Catalytic Reforming Units, and Sulfur Recovery Units (Renewal) AGENCY... submitted an information collection request (ICR), ``NESHAP for Petroleum Refineries: Catalytic Cracking Units, Catalytic Reforming Units, and Sulfur Recovery Units (40 CFR Part 63, Subpart UUU) (Renewal...

National Emission Standards for Hazardous Air Pollutants (NESHAP) for the Portland Cement Manufacturing Industry Subpart LLL Rule Guidance

Science.gov (United States)

This Spring 2016 document is intended for the use of EPA staff, State and Local regulatory agencies and their staff, and industry plant managers for the NESHAP for the Portland Cement Manufacturing Industry.

Petroleum Refineries (Catalytic Cracking, Catalytic Reforming and Sulfur Recovery Units): National Emission Standards for Hazardous Air Pollutants (NESHAP)

Science.gov (United States)

learn more about the NESHAP for catalytic cracking and reforming units, as well as sulfur recovery units in petroleum refineries by reading the rule history, rule summary, background information documents, and compliance information

Performance Testing of Tracer Gas and Tracer Aerosol Detectors for use in Radionuclide NESHAP Compliance Testing

Energy Technology Data Exchange (ETDEWEB)

Fuehne, David Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lattin, Rebecca Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-06-28

The Rad-NESHAP program, part of the Air Quality Compliance team of LANL’s Compliance Programs group (EPC-CP), and the Radiation Instrumentation & Calibration team, part of the Radiation Protection Services group (RP-SVS), frequently partner on issues relating to characterizing air flow streams. This memo documents the most recent example of this partnership, involving performance testing of sulfur hexafluoride detectors for use in stack gas mixing tests. Additionally, members of the Rad-NESHAP program performed a functional trending test on a pair of optical particle counters, comparing results from a non-calibrated instrument to a calibrated instrument. Prior to commissioning a new stack sampling system, the ANSI Standard for stack sampling requires that the stack sample location must meet several criteria, including uniformity of tracer gas and aerosol mixing in the air stream. For these mix tests, tracer media (sulfur hexafluoride gas or liquid oil aerosol particles) are injected into the stack air stream and the resulting air concentrations are measured across the plane of the stack at the proposed sampling location. The coefficient of variation of these media concentrations must be under 20% when evaluated over the central 2/3 area of the stack or duct. The instruments which measure these air concentrations must be tested prior to the stack tests in order to ensure their linear response to varying air concentrations of either tracer gas or tracer aerosol. The instruments used in tracer gas and aerosol mix testing cannot be calibrated by the LANL Standards and Calibration Laboratory, so they would normally be sent off-site for factory calibration by the vendor. Operational requirements can prevent formal factory calibration of some instruments after they have been used in hazardous settings, e.g., within a radiological facility with potential airborne contamination. The performance tests described in this document are intended to demonstrate the reliable

NESHAP Area-Specific Dose-Release Factors for Potential Onsite Member-of-the-Public Locations at SRS using CAP88-PC Version 4.0

Energy Technology Data Exchange (ETDEWEB)

Trimor, P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-09

The Environmental Protection Agency (EPA) requires the use of the computer model CAP88-PC to estimate the total effective doses (TED) for demonstrating compliance with 40 CFR 61, Subpart H (EPA 2006), the National Emission Standards for Hazardous Air Pollutants (NESHAP) regulations. As such, CAP88 Version 4.0 was used to calculate the receptor dose due to routine atmospheric releases at the Savannah River Site (SRS). For estimation, NESHAP dose-release factors (DRFs) have been supplied to Environmental Compliance and Area Closure Projects (EC&ACP) for many years. DRFs represent the dose to a maximum receptor exposed to 1 Ci of a specified radionuclide being released into the atmosphere. They are periodically updated to include changes in the CAP88 version, input parameter values, site meteorology, and location of the maximally exposed individual (MEI). In this report, the DRFs were calculated for potential radionuclide atmospheric releases from 13 SRS release points. The three potential onsite MEI locations to be evaluated are B-Area, Three Rivers Landfill (TRL), and Savannah River Ecology Lab Conference Center (SRELCC) with TRL’s onsite workers considered as members-of-the-public, and the potential future constructions of dormitories at SRELCC and Barracks at B-Area. Each MEI location was evaluated at a specified compass sector with different area to receptor distances and was conducted for both ground-level and elevated release points. The analysis makes use of area-specific meteorological data (Viner 2014). The resulting DRFs are compared to the 2014 NESHAP offsite MEI DRFs for three operational areas; A-Area, H-Area, and COS for a release rate of 1 Ci of tritium oxide at 0 ft. elevation. CAP88 was executed again using the 2016 NESHAP MEI release rates for 0 and 61 m stack heights to determine the radionuclide dose at TRL from the center-of-site (COS).

Area Source Boiler National Emission Standards for Hazardous Air Pollutants (NESHAP), 40 CFR Part 63, Subpart JJJJJJ: Questions and Answers

Science.gov (United States)

This October 2016 question and answer (Q&A) document is in response to a number of questions the EPA has received from delegated state and local agencies and the regulated community regarding the NESHAP for Area source boilers. Document updates 4/2014 PDF.

Secondary limits of exposure in facilities handling uranium

International Nuclear Information System (INIS)

Raghavayya, M.

1999-08-01

Annual limits of exposure and intake for radiation workers in nuclear installations have been recommended by the International Commission on Radiological Protection and the same have been adopted by the Indian Atomic Energy Regulatory Board for all the radionuclides of interest. The prescribed limits cannot be directly used for day to day radiation protection work. Hence secondary limits have to be derived for routine applications. The modeling steps may be simple in some situations and more complicated in some others. The limits recommended are for individual radionuclides. But in facilities handling natural or enriched uranium the radionuclides (isotopes of uranium and its decay products) generally occur together in specific ratios. Derivation of secondary limits has to take this into consideration. The present document is an attempt at deriving the secondary limits required for routine application in facilities handling uranium (Mine, mill, refineries and fuel fabrication etc.). Secondary limits of exposure have been derived in this document for air borne activity, activity in water, surface contamination and internal exposures. (author)

77 FR 14777 - Agency Information Collection Activities OMB Responses

Science.gov (United States)

2012-03-13

...; Approved without change. EPA ICR Number 1712.08; NESHAP for Shipbuilding and Ship Repair Facilities... filed comment on 02/03/2012. EPA ICR Number 2028.07; NESHAP for Industrial, Commercial, and...

U.S. DOE 2004 LANL Radionuclide Air Emissions

International Nuclear Information System (INIS)

K.W. Jacobson

2005-01-01

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2004

U.S. Department of Energy Report, 2005 LANL Radionuclide Air Emissions

Energy Technology Data Exchange (ETDEWEB)

Keith W. Jacobson, David P. Fuehne

2006-09-01

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2006.

Background information document to support NESHAPS rulemaking on nuclear power reactors. Draft report

International Nuclear Information System (INIS)

Colli, A.; Conklin, C.; Hoffmeyer, D.

1991-08-01

The purpose of this Background Information Document (BID) is to present information relevant to the Administrator of the Environmental Protection Agency's (EPA) reconsideration of the need for a NESHAP to control radionuclides emitted to the air from commercial nuclear power reactors. The BID presents information on the relevant portions of the regulatory framework that NRC has implemented for nuclear power plant licensees, under the authority of the Atomic Energy Act, as amended, to protect the public's health and safety. To provide context, it summarizes the rulemaking history for Subpart I. It then describes NRC's regulatory program for routine atmospheric emissions of radionuclides and evaluates the doses caused by actual airborne emissions from nuclear power plants, including releases resulting from anticipated operational occurrences

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

International Nuclear Information System (INIS)

Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

2009-01-01

Battelle-Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy's Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

Energy Technology Data Exchange (ETDEWEB)

Barfuss, Brad C.; Barnett, J. Matthew; Ballinger, Marcel Y.

2009-04-08

Battelle—Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy’s Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

76 FR 26899 - Agency Information Collection Activities: Request for Comments on Sixty-Four Proposed Information...

Science.gov (United States)

2011-05-09

.... Title: NESHAP for Integrated Iron and Steel Manufacturing (40 CFR Part 63, Subpart FFFFF). ICR Numbers... 31, 2012. (60) NESHAP for Integrated Iron and Steel Manufacturing (40 CFR Part 63, Subpart FFFFF... for the Friction Materials Manufacturing Facilities (40 CFR Part 63, Subpart QQQQQ). ICR Numbers: EPA...

Heat generation and heating limits for the IRUS LLRW disposal facility

International Nuclear Information System (INIS)

Donders, R.E.; Caron, F.

1995-10-01

Heat generation from radioactive decay and chemical degradation must be considered when implementing low-level radioactive waste (LLRW) disposal. This is particularly important when considering the management of spent radioisotope sources. Heating considerations and temperature calculations for the proposed IRUS (Intrusion Resistant Underground Structure) near-surface disposal facility are presented. Heat transfer calculations were performed using a finite element code with realistic but somewhat conservative heat transfer parameters and environmental boundary conditions. The softening-temperature of the bitumen waste-form (38 deg C) was found to be the factor that limits the heat generation rate in the facility. This limits the IRUS heat rate, assuming a uniform source term, to 0.34 W/m 3 . If a reduced general heat-limit is considered, then some higher-heat packages can be accepted with restrictions placed on their location within the facility. For most LLRW, heat generation from radioactive decay and degradation are a small fraction of the IRUS heating limits. However, heating restrictions will impact on the disposal of higher-activity radioactive sources. High activity 60 Co sources will require decay-storage periods of about 70 years, and some 137 Cs will need to bed disposed of in facilities designed for higher-heat waste. (author). 21 refs., 8 tabs., 2 figs

Acetal Resins, Acrylic & Modacrylic Fibers, Carbon Black, Hydrogen Fluoride, Polycarbonate, Ethylene, Spandex & Cyanide Chemical Manufacturing: NESHAP for Source Categories, Generic Maximum Achievable Control Technology Standards (40 CFR 63, Subpart YY)

Science.gov (United States)

Learn about the NESHAP for GMACT for acetal resins, hydrogen fluoride, polycarbonate, ethylene production and cyanide chemicals. Find the rule history information, federal register citations, legal authority, rule summary, and additional resources

An exposure assessment of radionuclide emissions associated with potential mixed-low level waste disposal facilities at fifteen DOE sites

International Nuclear Information System (INIS)

Lombardi, D.A.; Socolof, M.L.

1996-01-01

A screening method was developed to compare the doses received via the atmospheric pathway at 15 potential DOE MLLW (mixed low-level waste) sites. Permissible waste concentrations were back calculated using the radioactivity NESHAP (National Emissions Standards for Hazardous Air Pollutants) in 40 FR 61 (DOE Order 5820.2A performance objective). Site-specific soil and meteorological data were used to determine permissible waste concentrations (PORK). For a particular radionuclide, perks for each site do not vary by more than one order of magnitude. perks of 14 C are about six orders of magnitude more restrictive than perks of 3 H because of differences in liquid/vapor partitioning, decay, and exposure dose. When comparing results from the atmospheric pathway to the water and intruder pathways, 14 C disposal concentrations were limited by the atmospheric pathway for most arid sites; for 3 H, the atmospheric pathway was not limiting at any of the sites. Results of this performance evaluation process are to be used for planning for siting of disposal facilities

National Emission Standards for Hazardous Air Pollutants Calendar Year 2005

International Nuclear Information System (INIS)

Bechtel Nevada

2006-01-01

The Nevada Test Site (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). From 1951 through 1992, the NTS was operated as the nation's site for nuclear weapons testing. The release of man-made radionuclides from the NTS as a result of testing activities has been monitored since the first decade of atmospheric testing. After 1962, when nuclear tests were conducted only underground, the radiation exposure to the public surrounding the NTS was greatly reduced. After the 1992 moratorium on nuclear testing, radiation monitoring on the NTS focused on detecting airborne radionuclides that are resuspended into the air (e.g., by winds, dust-devils) along with historically-contaminated soils on the NTS. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (40 Code of Federal Regulations 61 Subpart H) limits the release of radioactivity from a U. S. Department of Energy (DOE) facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent (EDE) to any member of the public. This is the dose limit established for someone living off of the NTS for inhaling radioactive particles that may be carried by wind off of the NTS. This limit assumes that members of the public surrounding the NTS may also inhale 'background levels' or radioactive particles unrelated to NTS activities that come from naturally-occurring elements in the environment (e.g., radon gas from the earth or natural building materials) or from other man-made sources (e.g., cigarette smoke). The U. S. Environmental Protection Agency (EPA) requires DOE facilities (e.g., the NTS) to demonstrate compliance with the NESHAP dose limit by annually estimating the dose to a hypothetical member of the public, referred to as the maximally exposed individual (MEI), or the member of the public who resides within an 80-kilometer (50-mile) radius

IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

International Nuclear Information System (INIS)

Batandjieva, B.; Warnecke, E.

2008-01-01

The number of facilities reaching their lifetime is increasing and drawing the attention of operators, regulators, public and other interested parties (potential users of the site after decommissioning) on the importance of adequate planning, funding and implementation of decommissioning activities in compliance with regulatory requirements and criteria. Specific attention is required for small facilities that have been used for research purposes and in most cases state owned by and dependent on state funding. With the current tendency for expansion of the nuclear industry such small facilities could become less of importance for the operators which can increase the probability that these facilities become abandoned, hazardous and imposing undue burden to future generations. This concern is more related to countries with limited human and financial resources at the operating organizations and the regulatory body. The International Atomic Energy Agency (IAEA) has been working on the; (i) establishment of internationally recognized safety standards on decommissioning and (ii) providing Member States with assistance on the application of these standards. The recent international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Practices (Athens, Greece, 2006) has demonstrated that the set of IAEA standards is almost complete and that the International Action Plan on Decommissioning (2004), that is addressing decommissioning of small facilities, is being successfully implemented. However the need for further assistance on decommissioning of small facilities in countries with limited resources was also recognized and the Agency is planning its future work in this field. The IAEA also addresses the needs of small nuclear countries that have only a limited number of nuclear facilities, e.g. a research reactor, in its R esearch Reactor Decommissioning Demonstration Project (R 2 D 2 P. The Philippine Research Reactor

Administrative limits for tritium concentrations found in non-potable groundwater at nuclear power facilities

International Nuclear Information System (INIS)

Parker, R.; Hart, D.; WIllert, C.

2012-01-01

Currently, there is a regulatory limit available for tritium in drinking water, but no such limit for non-potable groundwater. Voluntary administrative limits for site groundwater may be established at nuclear power facilities to ensure minimal risk to human health and the environment, and provide guidance for investigation or other actions intended to prevent exceedances of future regulatory or guideline limits. This work presents a streamlined approach for nuclear power facilities to develop three tiers of administrative limits for tritium in groundwater so that facilities can identify abnormal/uncontrolled releases of tritium at an early stage, and take appropriate actions to investigate, control, and protect groundwater. Tier 1 represents an upper limit of background, Tier 2 represents a level between background and Tier 3, and Tier 3 represents a risk-based concentration protective of down-gradient receptors. (author)

Evolution of authorised limits for environmental releases from nuclear facilities in India

International Nuclear Information System (INIS)

Subramanian, Chitra; Narayanan, K.K.; Sharma, R.M.

2002-01-01

Full text: The controlled environmental releases of radioactive effluents from any nuclear facility is primarily based on the effective dose limits for the general public, recommended by the international commission on radiation protection (ICRP). To meet the dose limit criteria for members of the public, regulatory-limits are set for the discharges of radioactive effluents from nuclear facilities, which are known as the authorised limits (ALs). The paper presents the evolution of ALs in India applicable to nuclear power plant sites, starting from Tarapur Atomic Power Station (TAPS) commissioned in 1969, when the dose limit used to be 5 mSv/yr for the public, to the present generation pressurised heavy water reactors, when the population dose limit has been revised downward to 1 mSv/yr. The paper also presents the changes in the philosophy of dose apportionment for multifacility sites like Tarapur, Rawatbhata and Kalpakkam over the years. The operating experience with respect to environmental discharges from operating nuclear power plants (NPPs) in the country was reviewed vis-a-vis the applicable discharge limits, which shows that the actual releases constitute only a small percentage of the discharge limits. A strong case for lowering the dose apportionment for NPPs is suggested on the basis of latest data on site meteorology, dosimetry of radionuclides and environmental dose assessment methodology and operating experience. It is established in the paper that there is scope for reduction in the dose apportionment of NPPs for most of the radionuclides, without major changes in the existing discharge limits. The lowering of dose apportionment will be critically important at multifacility sites like Tarapur, Rawatbhata and Kalpakkam where many new facilities are being planned. At present the dose reserve available at these sites is only 0.14 mSv/yr, 0.06 mSv/yr and 0.16 mSv/yr, respectively at Tarapur, Rawatbhata and Kalpakkam. With the programme of siting

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2009

International Nuclear Information System (INIS)

2010-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada Test Site (NTS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the NLVF, an NTS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy facility to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from sources such as medically or commercially used radionuclides. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no

Nevada Test Site National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2008

International Nuclear Information System (INIS)

Warren, Ronald; Grossman, Robert F.

2009-01-01

The Nevada Test Site (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office. From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to under-ground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by winds) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the North Las Vegas Facility (NLVF), an NTS support complex in the city of North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) (CFR, 2008a) limits the release of radioactivity from a U.S. Department of Energy facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from other man-made sources such as medical treatments. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo

Program management assessment of Federal Facility Compliance Agreement regarding CAA-40 C.F.R. Part 61, Subpart H at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

1997-01-01

An assessment of Los Alamos National Laboratory's management system related to facility compliance with an element of the Clean Air Act was performed under contract by a team from Northern Arizona University. More specifically, a Federal Facilities Compliance Agreement (FFCA) was established in 1996 to bring the Laboratory into compliance with emissions standards of radionuclides, commonly referred to as Rad/NESHAP. In the fall of 1996, the four-person team of experienced environmental managers evaluated the adequacy of relevant management systems to implement the FFCA provisions. The assessment process utilized multiple procedures including document review, personnel interviews and re-interviews, and facility observations. The management system assessment was completed with a meeting among team members, Laboratory officials and others on November 1, 1996 and preparation of an assessment report

Challenges and limitations in retrofitting facilities for low frequency noise

Energy Technology Data Exchange (ETDEWEB)

Wierzba, P. [ATCO Noise Management, Calgary, AB (Canada)

2007-07-01

The trend to revise and increase environmental regulations regarding low frequency noise emissions from oil and gas facilities was discussed. Noise related complaints can often be traced to low frequency noise, which is the unwanted sound with a frequency range falling within 31.5-Hz, 63-Hz, and 125-Hz octave bands. This paper also discussed the challenges and limitations of field retrofits of the facilities aimed at reducing low frequency noise. The main sources of low frequency noise associated with a compression facility are the radiator cooler, engine exhaust and the building envelope. Regulators are paying close attention not only to the overall noise exposure as measured by the A-weighted levels, but also to the quality of noise emitted by the particular frequency spectrum. The Alberta Energy and Utilities Board recently issued Noise Control Directive 38 and made it a requirement to perform low frequency noise impact assessment for permitting of all new energy facilities. Under Directive 38, the low frequency noise assessment is to be performed using the C-weighted scale as a measure in addition to the previously used A-weighted scale. Directive 38 recommends that in order to avoid low frequency noise problems the difference between the C-weighted and A-weighted levels at the residential locations should be lower than 20 dB. This implies that noise should be limited to 60 dBC for Category 1 residences of low dwelling density. Small upgrades and changes can be made to lower low frequency noise emissions. These may include upgrading building wall insulation, providing wall-to-skid isolation system, upgrading the fan blades, or reducing the rpm of the fans. It was concluded that these upgrades should be considered for facilities in close proximity to residential areas. 3 refs., 2 tabs., 7 figs.

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

75 FR 54869 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2010-09-09

... and Rework Facilities (Renewal), EPA ICR Number 1687.08, OMB Control Number 2060-0314 AGENCY... Manufacturing and Rework Facilities (Renewal) ICR Numbers: EPA ICR Number 1687.08, OMB Control Number 2060-0314... Standards for Hazardous Air Pollutants (NESHAP) for Aerospace Manufacturing and Rework Facilities were...

Derivation of release limits for a typical uranium mining and milling facility

International Nuclear Information System (INIS)

1985-09-01

This report develops guidelines for calculating derived release limits (DRLs) for releases of each radionuclide belonging to the uranium-238 and thorium-232 decay chains to atmosphere, surface water and groundwater from uranium mining and milling operations in Canada. DRLs are defined as calculated limits on releases from the facility that result in radiation exposures through all environmental pathways equal to the annual effective dose equivalent limit of 0.005 Sv for stochastic effects or the annual dose equivalent limit of 0.05 Sv for non-stochastic effects in the critical group. By definition, DRLs apply to controllable radionuclide emissions which occur during the operational phase of mine/mill facilities. The report develops a steady-state environmental transfer model to determine environmental dilution and dispersion in atmosphere, surface water and groundwater between the sources at the mine and mill and the critical group receptor. Exposure pathways incorporated in the model include external exposure from immersion in the airborne plume, immersion in water, contaminated ground and contaminated shoreline sediments. Internal exposure pathways include inhalation of contaminated air and ingestion of contaminated water and terrestrial and aquatic foods

Earthquake resistant design of nuclear facilities with limited radioactive inventory

International Nuclear Information System (INIS)

1985-10-01

This document comprises the essential elements of an earthquake resistant design code for nuclear facilities with limited radioactive inventory. The purpose of the document is the enhancement of seismic safety for such facilities without the necessity to resort to complicated and sophisticated methodologies which are often associated with and borrowed from nuclear power plant analysis and design. The first two sections are concerned with the type of facility for which the document is applicable and the radiological consideration for accident conditions. The principles of facility classification and item categorization as a function of the potential radiological consequences of failure are given in section 3. The design basis ground motion is evaluated in sections 4-6 using a simplified but conservative approach which also includes considerations for the underlying soil characteristics. Sections 7 and 8 specify the principles of seismic design of building structures and equipment using two methods, called the equivalent static and simplified dynamic approach. Considerations for the detailing of equipment and piping and those other than for lateral load calculations, such as sloshing effects, are given in the subsequent sections. Several appendices are given for illustration of the principles presented in the text. Finally, a design tree diagram is included to facilitate the user's task of making the appropriate selections. (author)

Water and Sewage Utilities Sector (NAICS 2213)

Science.gov (United States)

Environmental regulation information for water utilities, including drinking and wastewater treatment facilities. Includes links to NESHAP for POTW, compliance information, and information about pretreatment programs.

2014 LANL Radionuclide Air Emissions Report

Energy Technology Data Exchange (ETDEWEB)

Fuehne, David Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-07-21

This report describes the emissions of airborne radionuclides from operations at Los Alamos National Laboratory (LANL) for calendar year 2014, and the resulting off-site dose from these emissions. This document fulfills the requirements established by the National Emissions Standards for Hazardous Air Pollutants in 40 CFR 61, Subpart H – Emissions of Radionuclides other than Radon from Department of Energy Facilities, commonly referred to as the Radionuclide NESHAP or Rad-NESHAP. Compliance with this regulation and preparation of this document is the responsibility of LANL’s RadNESHAP compliance program, which is part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being submitted to the U.S. Environmental Protection Agency (EPA) Region 6.

Preliminary data on rheological limits for grouts in the Transportable Grout Facility

International Nuclear Information System (INIS)

Gilliam, T.M.; McDaniel, E.W.; Dole, L.R.; West, G.A.

1987-04-01

This report describes a method for establishing rheological limits for grouts that can be pumped in the Hanford Transportable Grout Facility (TGF). This method is based on two models that require determining two key parameters - gel strength and density. This work also presents rheological data on grouts prepared with simulated customer phosphate wastes (CPW) and double shell slurry (DSS) from the Hanford complex. These data can be used to make preliminary estimates of operating rheological limits of the TFG grouts. The suggested design limits will include safety factors that will increase these limits significantly. 4 refs

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2012

Energy Technology Data Exchange (ETDEWEB)

Warren, R.

2013-06-10

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA for use on the NNSS in 2001 (EPA 2001a) and has

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2013

Energy Technology Data Exchange (ETDEWEB)

Warren, R.

2014-06-04

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitations to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA for use on the NNSS in 2001 (EPA 2001a) and has

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2010

International Nuclear Information System (INIS)

2011-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS, formerly the Nevada Test Site) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) (CFR, 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as those from the damaged Fukushima nuclear power plant in Japan. Because this report is intended to discuss radioactive air emissions during calendar year 2010, data on radionuclides in air from the 2011 Fukushima nuclear power plant releases are not presented but will be included in the report for calendar year 2011. The NNSS demonstrates compliance with the NESHAP

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2011

International Nuclear Information System (INIS)

2012-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan. Radionuclides from the Fukushima nuclear power plant were detected at the NNSS in March 2011 and are discussed further in Section III. The NNSS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the EPA for use on the

Pacific Northwest National Laboratory Facility Radionuclide Emissions Units and Sampling Systems

Energy Technology Data Exchange (ETDEWEB)

Barnett, J. Matthew; Brown, Jason H.; Walker, Brian A.

2012-04-01

Battelle–Pacific Northwest Division operates numerous research and development (R&D) laboratories in Richland, WA, including those associated with Pacific Northwest National Laboratory (PNNL) on the U.S. Department of Energy (DOE)’s Hanford Site and PNNL Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all emission units that have the potential for radionuclide air emissions. Potential emissions are assessed annually by PNNL staff members. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission unit system performance, operation, and design information. For sampled systems, a description of the buildings, exhaust units, control technologies, and sample extraction details is provided for each registered emission unit. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided. Deregistered emission unit details are provided as necessary for up to 5 years post closure.

Transportation and Warehousing Sector (NAICS 48-49)

Science.gov (United States)

Find EPA regulatory information for the transportation and warehousing, including NESHAPs for RICE and gasoline dispensing facilities, effluent guidelines, power wash discharges, and border and port compliance

Secondary Aluminum Production: National Emission Standards for Hazardous Air Pollutants

Science.gov (United States)

National emission standards for hazardous air pollutants (NESHAP) for new and existing sources at secondary aluminum production facilities. Includes rule history, summary, federal register citations and implementation information.

49 CFR 599.401 - Requirements and limitations for disposal facilities that receive trade-in vehicles under the...

Science.gov (United States)

2010-10-01

... facilities that receive trade-in vehicles under the CARS program. 599.401 Section 599.401 Transportation... SAVE ACT PROGRAM Disposal of Trade-in Vehicle § 599.401 Requirements and limitations for disposal facilities that receive trade-in vehicles under the CARS program. (a) The disposal facility must: (1) Not...

NESHAP Dose-Release Factor Isopleths for Five Source-to-Receptor Distances from the Center of Site and H-Area for all Compass Sectors at SRS using CAP88-PC Version 4.0

Energy Technology Data Exchange (ETDEWEB)

Trimor, P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-08-09

The Environmental Protection Agency (EPA) requires the use of the computer model CAP88-PC to estimate the total effective doses (TED) for demonstrating compliance with 40 CFR 61, Subpart H (EPA 2006), the National Emission Standards for Hazardous Air Pollutants (NESHAP) regulations. As such, CAP88 Version 4.0 was used to calculate the receptor dose due to routine atmospheric releases at the Savannah River Site (SRS). For estimation, NESHAP dose-release factors (DRFs) have been supplied to Environmental Compliance and Area Closure Projects (EC&ACP) for many years. DRFs represent the dose to a maximum receptor exposed to 1 Ci of a specified radionuclide being released into the atmosphere. They are periodically updated to include changes in the CAP88 version, input parameter values, site meteorology, and location of the maximally exposed individual (MEI). This report presents the DRFs of tritium oxide released at two onsite locations, center-of-site (COS) and H-Area, at 0 ft. elevation to maximally exposed individuals (MEIs) located 1000, 3000, 6000, 9000, and 12000 meters from the release areas for 16 compass sectors. The analysis makes use of area-specific meteorological data (Viner 2014).

Can we do it?

International Nuclear Information System (INIS)

Locheed, T.A.

1993-01-01

One wonders how a facility will cope with the new Clean Air Act Amendments (CAAA). Environmental engineers working in large companies' facilities and in corporate engineering groups already have an idea of how to comply with the regulations for chemical plant equipment leaks. (In fact, the rules will also affect process bins, wastewater, transfer and storage.) But those who work for smaller companies or who have assignments not directly tied to environmental affairs may not have access to the latest thinking on compliance. One of the first challenges in becoming aware of the CAAA regulations is learning the new language, which consists of acronyms, some containing other acronyms. NESHAP, for example, stands for national emissions standards for hazardous air pollutants. Prior to the CAAA, NESHAPs applied to a few specific chemicals, such as benzene. Now the proposed rules establish a HON, a hazardous organic NESHAP. According to David Gustafson, environmental air issues manager with Dow Chemical Company in Midland, MI, the HON mandates broader controls for a very large group of chemicals, including many of those made by the synthetic organic chemicals manufacturing industry (SOCMI)

New-doses limits introduction analysis for the design and operation of teletherapy facilities established by IAEA

International Nuclear Information System (INIS)

Castaneda M, A.; Jimenez C, I.; Ramirez M, J.C.; Sanchez V, H.F.

1996-01-01

A design of a typical teletherapy facility was made considering a Co-60 rotating unit and using critical parameters, taking into account as a design base the dose limits established in the Safety Series No. 9 (1), and Safety Series No.115-I (2), shielding thickness when the dose limits were changed. An increment in the required thickness of 1,35 CHR for controlled areas and 2,37 CHR for non-controlled areas were found. This work considered the selection of four different types of teletherapy facilities using Co-60 sources, with different design and type of used unit. An analysis of thickness was made taking into account both the original values for the design and the real operation values in each facility. In order to determine the necessary changes for the wall thicknesses when the new recommendations are applied. (authors). 4 refs., 3 tabs

Final Rule to Reduce Toxic Air Emissions from Asphalt Processing and Asphalt Roofing Manufacturing Facilities Fact Sheet

Science.gov (United States)

This page contains a February 2003 fact sheet with information regarding the National Emissions Standards for Hazardous Air Pollutants (NESHAP) for Asphalt Processing and Asphalt Roofing Manufacturing.

Recruitment of mobility limited older adults into a facility-led exercise-nutrition study: the effect of social involvement

Science.gov (United States)

Purpose of the Study: Older adults are among the most challenging population groups to enroll into health-related research. This article describes two methods used by investigators to recruit mobility limited older adults residing at assisted living or senior housing (SH) facilities into a facility-...

76 FR 76259 - National Emissions Standards for Hazardous Air Pollutants: Primary Aluminum Reduction Plants

Science.gov (United States)

2011-12-06

... Emissions From Maleic Anhydride Plants, Ethylbenzene/Styrene Plants, Benzene Storage Vessels, Benzene...). The rule is applicable to facilities with affected sources associated with the production of aluminum... are subject to the requirements of this NESHAP: 14 primary aluminum production plants and one carbon...

40 CFR 63.4881 - Am I subject to this subpart?

Science.gov (United States)

2010-07-01

... themselves: household, office, institutional, laboratory, hospital, public building, restaurant, barber and... conducted in an operation that is subject to the wood furniture manufacturing NESHAP in subpart JJ of this... janitorial, building, and facility maintenance operations. (4) Surface coating of only small items such as...

Volumetric activity of SRS mixed waste and comparison with SRS performance and commercial facility limits

International Nuclear Information System (INIS)

Ades, M.J.; Daugherty, B.A.; Cook, J.R.

1996-01-01

This paper discusses the comparative analysis performed to estimate the after-treatment volumetric activity of the radionuclides included in the Savannah River site (SRS) mixed-waste streams and its comparison with the following: (1) The performance evaluation (PE) limits established for each radionuclide for on-site disposal: These limits correspond to the permissible waste disposal limits that are the lowest limits evaluated for the most restrictive release scenarios that include the groundwater pathway, the atmospheric pathway, and the intruder scenarios. (2) The radiological performance assessment (PA) limits established for each radionuclide for disposal in the SRS disposal vaults that meet the requirements of Chap. III of the U.S. Department of Energy Order 5820.2A: The vaults considered are the low-activity waste (LAW) vaults, the intermediate-level non-tritium (ILNT) vaults. and the intermediate-level tritium (ILT) vaults. (3) The radioactive limits of a commercial mixed waste disposal facility

A comparison of radiological risk assessment models: Risk assessment models used by the BEIR V Committee, UNSCEAR, ICRP, and EPA (for NESHAP)

International Nuclear Information System (INIS)

Wahl, L.E.

1994-03-01

Radiological risk assessments and resulting risk estimates have been developed by numerous national and international organizations, including the National Research Council's fifth Committee on the Biological Effects of Ionizing Radiations (BEIR V), the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), and the International Commission on Radiological Protection (ICRP). A fourth organization, the Environmental Protection Agency (EPA), has also performed a risk assessment as a basis for the National Emission Standards for Hazardous Air Pollutants (NESHAP). This paper compares the EPA's model of risk assessment with the models used by the BEIR V Committee, UNSCEAR, and ICRP. Comparison is made of the values chosen by each organization for several model parameters: populations used in studies and population transfer coefficients, dose-response curves and dose-rate effects, risk projection methods, and risk estimates. This comparison suggests that the EPA has based its risk assessment on outdated information and that the organization should consider adopting the method used by the BEIR V Committee, UNSCEAR, or ICRP

Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

1994-01-01

Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

Adopt-A-MACT Project: A Manual of Model Documents and Guidance to Aid Compliance and Enforcement of the Nutritional Yeast MACT (Maximum Achievable Control Technology)

Science.gov (United States)

This manual provides a compliance checklist, and overview of emissions limitations, how to do performance tests, and an overview of applicability of general provisions for the Nutritional Yeast NESHAP.

Recruitment of Mobility Limited Older Adults Into a Facility-Led Exercise-Nutrition Study: The Effect of Social Involvement.

Science.gov (United States)

Corcoran, Michael P; Nelson, Miriam E; Sacheck, Jennifer M; Reid, Kieran F; Kirn, Dylan; Fielding, Roger A; Folta, Sara C

2016-08-01

Older adults are among the most challenging population groups to enroll into health-related research. This article describes two methods used by investigators to recruit mobility limited older adults residing at assisted living or senior housing (SH) facilities into a facility-led exercise-nutrition research study. Sedentary older adults were recruited from 42 different assisted living facilities (ALFs) or SH communities. Two different recruitment approaches were used: At 22 sites, investigators conducted heavily advertised informational sessions to recruit participants (Info only). At 20 locations, these sessions were preceded by attendance of a study team member at various activities offered by the facility over the preceding 2 weeks (activity attendance). Population reach, enrollment, personnel cost, and time required to recruit at least five participants at each facility was measured. Reasons for declining participation and withdrawal rate were also measured. Sixty percent more residents elected to be screened for eligibility when study personnel attended an activity offered by the facility. Activity attendance resulted in significantly less time, costs, and participant withdrawals compared with facilities with no activity attendance. Study team member attendance at activities offered by senior living facilities reduces cost and duration of recruitment and improves study retention. Interventions targeting this demographic are likely to benefit from deliberately building trust and familiarity among the resident population at senior living communities as part of the recruitment process. © The Author 2015. Published by Oxford University Press on behalf of The Gerontological Society of America. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

Ureterolithiasis: Management in an environment with limited facilities

African Journals Online (AJOL)

Background: In the past 2–3 decades, there has been a dramatic development in the techniques of stone removal. This study highlights the management of symptomatic ureteral stones in an environment without such facilities. Materials and Methods: Sixty‑nine patients, comprising 53 (76.8%) males and 16 (23.2%) females ...

75 FR 39244 - Agency Information Collection Activities OMB Responses

Science.gov (United States)

2010-07-08

.... EPA ICR Number 1801.08; NESHAP for the Portland Cement Manufacturing Industry; 40 CFR part 63.... EPA ICR Number 1790.05; NESHAP for Phosphoric Acid Manufacturing and Phosphate Fertilizers Production... with change. EPA ICR Number 1160.09; NSPS/NESHAP for Wool Fiberglass Insulation Manufacturing Plants...

78 FR 3893 - Agency Information Collection Activities OMB Responses

Science.gov (United States)

2013-01-17

...; NESHAP for Aluminum, Copper, and Other Non- Ferrous Foundries; 40 CFR part 63 subparts A and ZZZZZZ; was... ICR Number 1894.07; NESHAP for Secondary Aluminum Production; 40 CFR part 63 subparts A and RRR; was...; NESHAP for Chromium Emissions from Hard and Decorative Chromium Electroplating and Chromium Anodizing...

EPA perspective on radionuclide aerosol sampling

Energy Technology Data Exchange (ETDEWEB)

Karhnak, J.M. [Environmental Protection Agency, Washington, DC (United States)

1995-02-01

The Environmental Protection Agency (EPA) is concerned with radionuclide aerosol sampling primarily at Department of Energy (DOE) facilities in order to insure compliance with national air emission standards, known as NESHAPs. Sampling procedures are specified in {open_quotes}National Emission Standards for Emissions of Radionuclides other than Radon from Department of Energy Sites{close_quotes} (Subpart H). Subpart H also allows alternate procedures to be used if they meet certain requirements. This paper discusses some of the mission differences between EPA and Doe and how these differences are reflected in decisions that are made. It then describes how the EPA develops standards, considers alternate sampling procedures, and lists suggestions to speed up the review and acceptance process for alternate procedures. The paper concludes with a discussion of the process for delegation of Radionuclide NESHAPs responsibilities to the States, and responsibilities that could be retained by EPA.

26 CFR 1.141-8 - $15 million limitation for output facilities.

Science.gov (United States)

2010-04-01

... defined in § 1.148-1(b) is disregarded for this purpose. (b) Definition of project—(1) General rule. For... other output facility that is part of the same project. (ii) Bonds taken into account. For purposes of... of the same project as the output facility that is financed by 5 percent or more of the sale proceeds...

75 FR 68354 - Agency Information Collection Activities OMB Responses

Science.gov (United States)

2010-11-05

... 1801.09; NESHAP for the Portland Cement Manufacturing Industry; 40 CFR part 63, subparts A and LLL; was....04; NESHAP for Metal Can Manufacturing Surface Coating; 40 CFR part 63, subparts A and KKKK; was... Number 1966.04; NESHAP for Boat Manufacturing; 40 CFR part 63, subparts A and VVVV; was approved on 10/01...

Experimental Fuels Facility Re-categorization Based on Facility Segmentation

Energy Technology Data Exchange (ETDEWEB)

Reiss, Troy P.; Andrus, Jason

2016-07-01

The Experimental Fuels Facility (EFF) (MFC-794) at the Materials and Fuels Complex (MFC) located on the Idaho National Laboratory (INL) Site was originally constructed to provide controlled-access, indoor storage for radiological contaminated equipment. Use of the facility was expanded to provide a controlled environment for repairing contaminated equipment and characterizing, repackaging, and treating waste. The EFF facility is also used for research and development services, including fuel fabrication. EFF was originally categorized as a LTHC-3 radiological facility based on facility operations and facility radiological inventories. Newly planned program activities identified the need to receive quantities of fissionable materials in excess of the single parameter subcritical limit in ANSI/ANS-8.1, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (identified as “criticality list” quantities in DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,” Attachment 1, Table A.1). Since the proposed inventory of fissionable materials inside EFF may be greater than the single parameter sub-critical limit of 700 g of U-235 equivalent, the initial re-categorization is Hazard Category (HC) 2 based upon a potential criticality hazard. This paper details the facility hazard categorization performed for the EFF. The categorization was necessary to determine (a) the need for further safety analysis in accordance with LWP-10802, “INL Facility Categorization,” and (b) compliance with 10 Code of Federal Regulations (CFR) 830, Subpart B, “Safety Basis Requirements.” Based on the segmentation argument presented in this paper, the final hazard categorization for the facility is LTHC-3. Department of Energy Idaho (DOE-ID) approval of the final hazard categorization determined by this hazard assessment document (HAD) was required per the

Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Cook, J.R.

2001-01-01

This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

Radioactive facilities classification criteria

International Nuclear Information System (INIS)

Briso C, H.A.; Riesle W, J.

1992-01-01

Appropriate classification of radioactive facilities into groups of comparable risk constitutes one of the problems faced by most Regulatory Bodies. Regarding the radiological risk, the main facts to be considered are the radioactive inventory and the processes to which these radionuclides are subjected. Normally, operations are ruled by strict safety procedures. Thus, the total activity of the radionuclides existing in a given facility is the varying feature that defines its risk. In order to rely on a quantitative criterion and, considering that the Annual Limits of Intake are widely accepted references, an index based on these limits, to support decisions related to radioactive facilities, is proposed. (author)

New experimental limits on heavy neutrino mixing in 8B decay obtained with the BOREXINO counting test facility

International Nuclear Information System (INIS)

Back, H.O.; Hagner, C.; Vogelaar, R.B.

2003-01-01

If heavy neutrinos with mass m νH ≥2m e are emitted in the decays of 8 B in the Sun, then decays ν H →ν L +e + +e - should be observed. The results of background measurements with the BOREXINO Counting Test Facility have been used to obtain bounds on the number of these decays. As a result, new limits on the coupling |U eH | 2 of a massive neutrino in the range of 1.1 to 12 MeV have been derived (|U eH | 2 ≤10 -3 -10 -5 ). The obtained limits on the mixing parameter are stronger than those obtained in the previous experiments using nuclear reactors and accelerators

50 CFR 260.100 - Facilities.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Facilities. 260.100 Section 260.100... Basis 1 § 260.100 Facilities. Each official establishment shall be equipped with adequate sanitary facilities and accommodations, including, but not being limited to, the following: (a) Containers approved...

1990 INEL national emission standards for hazardous air pollutants

International Nuclear Information System (INIS)

1990-05-01

The Environmental Protection Agency issued on December 15, 1989 final rules governing air emissions of radionuclides. Requirements concerning radionuclide emissions from Department of Energy Facilities are addressed under Title 40, Code Federal Regulations (CFR) 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides other Than Radon From Department of Energy Facilities.'' Section 61.94 of the regulations require that each DOE facility submit on an annual basis a report documenting compliance with the Subpart H requirements. This report addresses the section 61.94 reporting requirements for operations at the Idaho National Engineering Laboratory (INEL) for calendar year 1990. The Idaho Operations Office of the Department of Energy is the primary contact concerning NESHAPs compliance at the INEL

Assessment of wastewater treatment facility compliance with decreasing ammonia discharge limits using a regression tree model.

Science.gov (United States)

Suchetana, Bihu; Rajagopalan, Balaji; Silverstein, JoAnn

2017-11-15

A regression tree-based diagnostic approach is developed to evaluate factors affecting US wastewater treatment plant compliance with ammonia discharge permit limits using Discharge Monthly Report (DMR) data from a sample of 106 municipal treatment plants for the period of 2004-2008. Predictor variables used to fit the regression tree are selected using random forests, and consist of the previous month's effluent ammonia, influent flow rates and plant capacity utilization. The tree models are first used to evaluate compliance with existing ammonia discharge standards at each facility and then applied assuming more stringent discharge limits, under consideration in many states. The model predicts that the ability to meet both current and future limits depends primarily on the previous month's treatment performance. With more stringent discharge limits predicted ammonia concentration relative to the discharge limit, increases. In-sample validation shows that the regression trees can provide a median classification accuracy of >70%. The regression tree model is validated using ammonia discharge data from an operating wastewater treatment plant and is able to accurately predict the observed ammonia discharge category approximately 80% of the time, indicating that the regression tree model can be applied to predict compliance for individual treatment plants providing practical guidance for utilities and regulators with an interest in controlling ammonia discharges. The proposed methodology is also used to demonstrate how to delineate reliable sources of demand and supply in a point source-to-point source nutrient credit trading scheme, as well as how planners and decision makers can set reasonable discharge limits in future. Copyright © 2017 Elsevier B.V. All rights reserved.

SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility

International Nuclear Information System (INIS)

Rathbun, R.

1993-01-01

Separate review of NMP-NCS-930058, open-quotes Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility (U), August 17, 1993,close quotes was requested of SRTC Applied Physics Group. The NCSE is a criticality assessment to determine waste container uranium limits in the Uranium Solidification Facility's Waste Handling Facility. The NCSE under review concludes that the NDA room remains in a critically safe configuration for all normal and single credible abnormal conditions. The ability to make this conclusion is highly dependent on array limitation and inclusion of physical barriers between 2x2x1 arrays of boxes containing materials contaminated with uranium. After a thorough review of the NCSE and independent calculations, this reviewer agrees with that conclusion

Risk based limits for Operational Safety Requirements

International Nuclear Information System (INIS)

Cappucci, A.J. Jr.

1993-01-01

OSR limits are designed to protect the assumptions made in the facility safety analysis in order to preserve the safety envelope during facility operation. Normally, limits are set based on ''worst case conditions'' without regard to the likelihood (frequency) of a credible event occurring. In special cases where the accident analyses are based on ''time at risk'' arguments, it may be desirable to control the time at which the facility is at risk. A methodology has been developed to use OSR limits to control the source terms and the times these source terms would be available, thus controlling the acceptable risk to a nuclear process facility. The methodology defines a new term ''gram-days''. This term represents the area under a source term (inventory) vs time curve which represents the risk to the facility. Using the concept of gram-days (normalized to one year) allows the use of an accounting scheme to control the risk under the inventory vs time curve. The methodology results in at least three OSR limits: (1) control of the maximum inventory or source term, (2) control of the maximum gram-days for the period based on a source term weighted average, and (3) control of the maximum gram-days at the individual source term levels. Basing OSR limits on risk based safety analysis is feasible, and a basis for development of risk based limits is defensible. However, monitoring inventories and the frequencies required to maintain facility operation within the safety envelope may be complex and time consuming

10 CFR 503.33 - Site limitations.

Science.gov (United States)

2010-01-01

... OF ENERGY (CONTINUED) ALTERNATE FUELS NEW FACILITIES Permanent Exemptions for New Facilities § 503.33... include: (i) Inaccessibility of alternate fuels as a result of a specific physical limitation; (ii) Unavailability of transportation facilities for alternate fuels; (iii) Unavailability of adequate land or...

77 FR 71323 - Reconsideration of Certain New Source and Startup/Shutdown Issues: National Emission Standards...

Science.gov (United States)

2012-11-30

... INFORMATION CONTACT: For the NESHAP action: Mr. William Maxwell, Energy Strategies Group, Sector Policies and... Strategies Group, Sector Policies and Programs Division, (D243-01), Office of Air Quality Planning and... revisions to the Hg limit applicable to low rank virgin coal-fired EGUs based on additional data in the...

Particle size distributions of lead measured in battery manufacturing and secondary smelter facilities and implications in setting workplace lead exposure limits.

Science.gov (United States)

Petito Boyce, Catherine; Sax, Sonja N; Cohen, Joel M

2017-08-01

Inhalation plays an important role in exposures to lead in airborne particulate matter in occupational settings, and particle size determines where and how much of airborne lead is deposited in the respiratory tract and how much is subsequently absorbed into the body. Although some occupational airborne lead particle size data have been published, limited information is available reflecting current workplace conditions in the U.S. To address this data gap, the Battery Council International (BCI) conducted workplace monitoring studies at nine lead acid battery manufacturing facilities (BMFs) and five secondary smelter facilities (SSFs) across the U.S. This article presents the results of the BCI studies focusing on the particle size distributions calculated from Personal Marple Impactor sampling data and particle deposition estimates in each of the three major respiratory tract regions derived using the Multiple-Path Particle Dosimetry model. The BCI data showed the presence of predominantly larger-sized particles in the work environments evaluated, with average mass median aerodynamic diameters (MMADs) ranging from 21-32 µm for the three BMF job categories and from 15-25 µm for the five SSF job categories tested. The BCI data also indicated that the percentage of lead mass measured at the sampled facilities in the submicron range (i.e., lead) was generally small. The estimated average percentages of lead mass in the submicron range for the tested job categories ranged from 0.8-3.3% at the BMFs and from 0.44-6.1% at the SSFs. Variability was observed in the particle size distributions across job categories and facilities, and sensitivity analyses were conducted to explore this variability. The BCI results were compared with results reported in the scientific literature. Screening-level analyses were also conducted to explore the overall degree of lead absorption potentially associated with the observed particle size distributions and to identify key issues

Petroleum Sector (NAICS 324)

Science.gov (United States)

Find relevant environmental regulations for the petroleum industry (NAICS 324), including National Emission Standards for Hazardous Air Pollutants (NESHAP)s for petroleum refineries and gasoline dispensing & effluent guidelines for oil and gas extraction

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Final Rule to Reduce Hazardous Air Emissions from Newly Built Stationary Combustion Turbines: Fact Sheet

Science.gov (United States)

This page contains an August 2003 fact sheet with information regarding the National Emissions Standards for Hazardous Air Pollutants (NESHAP) for Stationary Combustion Turbines. This document provides a summary of the information for this NESHAP.

Fact Sheets: Air Toxics Rules for the Manufacture of Amino/Phenolic Resins

Science.gov (United States)

This page contains a December 1999 fact sheet for the proposed National Emission Standards for Hazardous Air Pollutants (NESHAP): Manufacture of Amino/Phenolic Resins and a September 2014 fact sheet with information regarding the final NESHAP

33-GVA interrupter test facility

International Nuclear Information System (INIS)

Parsons, W.M.; Honig, E.M.; Warren, R.W.

1979-01-01

The use of commercial ac circuit breakers for dc switching operations requires that they be evaluated to determine their dc limitations. Two 2.4-GVA facilities have been constructed and used for this purpose at LASL during the last several years. In response to the increased demand on switching technology, a 33-GVA facility has been constructed. Novel features incorporated into this facility include (1) separate capacitive and cryogenic inductive energy storage systems, (2) fiber-optic controls and optically-coupled data links, and (3) digital data acquisition systems. Facility details and planned tests on an experimental rod-array vacuum interrupter are presented

Realities of proximity facility siting

International Nuclear Information System (INIS)

DeMott, D.L.

1981-01-01

Numerous commercial nuclear power plant sites have 2 to 3 reactors located together, and a group of Facilities with capabilities for fuel fabrication, a nuclear reactor, a storage area for spent fuel, and a maintenance area for contaminated equipment and radioactive waste storage are being designed and constructed in the US. The proximity of these facilities to each other provides that the ordinary flow of materials remain within a limited area. Interactions between the various facilities include shared resources such as communication, fire protection, security, medical services, transportation, water, electrical, personnel, emergency planning, transport of hazardous material between facilities, and common safety and radiological requirements between facilities. This paper will explore the advantages and disadvantages of multiple facilities at one site. Problem areas are identified, and recommendations for planning and coordination are discussed

Empowering Facilities Teams through Technology

Science.gov (United States)

Cormier, Scott

2013-01-01

Facilities departments at colleges and universities are facing the same challenge: how not to do just the most projects, but also the right projects with the limited funds they are given. In order to make the best decisions, they need more control over the capital planning process, which requires accurate, current facility condition data. Each…

Identifying and Funding the Greatest Needs in School Facilities

Science.gov (United States)

Gorrell, Bob; Salamone, Frank

2012-01-01

How should public school facilities programs allocate limited resources to school facilities needs fairly, cost-effectively, and efficiently while taking into account facility condition, educational adequacy, and other priorities? New Mexico has developed a solution that overcomes key challenges that are common to school facilities programs across…

Radionuclide limits for vault disposal at the Savannah River Site

International Nuclear Information System (INIS)

Cook, James R.

1992-01-01

The Savannah River Site is developing a facility called the E-Area Vaults which will serve as the new radioactive waste disposal facility beginning early in 1992. The facility will employ engineered below-grade concrete vaults for disposal and above grade storage for certain long-lived mobile radionuclides. This report documents the determination of interim upper limits for radionuclide inventories and concentrations which should be allowed in the disposal structures. The work presented here will aid in the development of both waste acceptance criteria and operating limits for the E-Area Vaults. Disposal limits for forty isotopes which comprise the SRS waste streams were determined. The limits are based on total facility and vault inventories for those radionuclides which impact groundwater) and on waste package concentrations for those radionuclides which could affect intruders. (author)

77 FR 65314 - Missouri: Final Authorization of State Hazardous Waste Management Program Revisions

Science.gov (United States)

2012-10-26

... application, subject to the limitations of the Hazardous and Solid Waste Amendments of 1984 (HSWA). New... RCRA Cluster XI NESHAPS: Final Standards for 65 FR 42292, 07/10/ 10 CSR 25- Hazardous Air Pollutants 00... 66 FR 35087, 7/ *10 CSR 25- Checklist 188. 03/01. 7.7270(2)(D)6 is excluded from the authorization...

75 FR 20838 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2010-04-21

... Collection Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Wood Furniture... electronic docket, go to http://www.regulations.gov . Title: NESHAP for Wood Furniture Manufacturing..., install, and utilize technology and systems for the purposes of collecting, validating, and verifying...

STAR facility tritium accountancy

International Nuclear Information System (INIS)

Pawelko, R. J.; Sharpe, J. P.; Denny, B. J.

2008-01-01

The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the development of safe fusion energy and other technologies. STAR is a radiological facility with an administrative total tritium inventory limit of 1.5 g (14,429 Ci) [1]. Research studies with moderate tritium quantities and various radionuclides are performed in STAR. Successful operation of the STAR facility requires the ability to receive, inventory, store, dispense tritium to experiments, and to dispose of tritiated waste while accurately monitoring the tritium inventory in the facility. This paper describes tritium accountancy in the STAR facility. A primary accountancy instrument is the tritium Storage and Assay System (SAS): a system designed to receive, assay, store, and dispense tritium to experiments. Presented are the methods used to calibrate and operate the SAS. Accountancy processes utilizing the Tritium Cleanup System (TCS), and the Stack Tritium Monitoring System (STMS) are also discussed. Also presented are the equations used to quantify the amount of tritium being received into the facility, transferred to experiments, and removed from the facility. Finally, the STAR tritium accountability database is discussed. (authors)

Study of physical resistance of the disposal facility for accidental artificial event in LLW disposal facility

International Nuclear Information System (INIS)

Ogawa, Suihei; Irie, Masaaki; Uchida, Masahiro

2013-11-01

This report refer to results of examine what follows for structural stability evaluation for the LLW disposal facility in depth over general human activity in underground. Study of physically resistance on the facility for accidental artificial event, namely tunneling an operation facing the disposal facility in future. Physically resistance to excavation of tunneling etc. in disposal facility is studied based on supposing of Tunnel Boring Machine as an excavator, paying attention to reinforcement bar in concrete and steel plate of waste package, as feature of strength in these material differs from rock strength. And it is examined not only resistibility on excavation but also about hard situations of excavation in tunneling works, and namely give thorough consideration to critical quantity of cutting to reinforcement bar and steel plate that could keep resistibility on excavation based on tunneling velocity and limits time furthermore. It requests necessity of evaluation in consider with metal corrosion that status alteration on disposal facility is considered with on timescale. Period of keep on the physically resistance is estimated by velocity of metal corrosion consequently. The physically resistance is kept until metal corrosion reach remaining its material, giving a limits of the physically resistance on inside of facility. Main point of physically resistance in the report will be made the good use of a practice to physically resistance evaluation of in safety assessment. (author)

Shielding design for positron emission tomography facility

International Nuclear Information System (INIS)

Abdallah, I.I.

2007-01-01

With the recent advent of readily available tracer isotopes, there has been marked increase in the number of hospital-based and free-standing positron emission tomography (PET) clinics. PET facilities employ relatively large activities of high-energy photon emitting isotopes, which can be dangerous to the health of humans and animals. This coupled with the current dose limits for radiation worker and members of the public can result in shielding requirements. This research contributes to the calculation of the appropriate shielding to keep the level of radiation within an acceptable recommended limit. Two different methods were used including measurements made at selected points of an operating PET facility and computer simulations by using Monte Carlo Transport Code. The measurements mainly concerned the radiation exposure at different points around facility using the survey meter detectors and Thermoluminescent Dosimeters (TLD). Then the set of manual calculation procedures were used to estimate the shielding requirements for a newly built PEF facility. The results from the measurement and the computer simulation were compared to the results obtained from the set manual calculation procedure. In general, the estimated weekly dose at the points of interest is lower than the regulatory limits for the little company of Mary Hospital. Furthermore, the density and the HVL for normal strength concrete and clay bricks are almost similar. In conclusion, PET facilities present somewhat different design requirements and are more likely to require additional radiation shielding. Therefore, existing shields at the little Company of Mary Hospital are in general found to be adequate and satisfactory and additional shielding was found necessary at the new PET facility in the department of Nuclear Medicine of the Dr. George Mukhari Hospital. By use of appropriate design, by implying specific shielding requirements and by maintaining good operating practices, radiation doses to

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

International Nuclear Information System (INIS)

Coenenberg, J.G.

1997-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

Energy Technology Data Exchange (ETDEWEB)

Coenenberg, J.G.

1997-08-15

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

Radiological NESHAP Annual Report CY 2015 Sandia National Laboratories New Mexico

Energy Technology Data Exchange (ETDEWEB)

Evelo, Stacie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-05-01

This report provides a summary of the radionuclide releases from the United States (U.S.) Department of Energy (DOE) National Nuclear Security Administration facilities at Sandia National Laboratories, New Mexico (SNL/NM) during Calendar Year (CY) 2015, including the data, calculations, and supporting documentation for demonstrating compliance with 40 Code of Federal Regulation (CFR) 61.

Radioactive material inventory control at a waste characterization facility

International Nuclear Information System (INIS)

Yong, L.K.; Chapman, J.A.; Schultz, F.J.

1996-01-01

Due to the recent introduction of more stringent Department of Energy (DOE) regulations and requirements pertaining to nuclear and criticality safety, the control of radioactive material inventory has emerged as an important facet of operations at DOE nuclear facilities. In order to comply with nuclear safety regulations and nuclear criticality requirements, radioactive material inventories at each nuclear facility have to be maintained below limits specified for the facility in its safety authorization basis documentation. Exceeding these radioactive material limits constitutes a breach of the facility's nuclear and criticality safety envelope and could potentially result in an accident, cause a shut-down of the facility, and bring about imminent regulatory repercussions. The practice of maintaining control of radioactive material, especially sealed and unsealed sources, is commonplace and widely implemented; however, the requirement to track the entire radioactivity inventory at each nuclear facility for the purpose of ensuring nuclear safety is a new development. To meet the new requirements, the Applied Radiation Measurements Department at Oak Ridge National Laboratory (ORNL) has developed an information system, called the open-quotes Radioactive Material Inventory Systemclose quotes (RMIS), to track the radioactive material inventory at an ORNL facility, the Waste Examination and Assay Facility (WEAF). The operations at WEAF, which revolve around the nondestructive assay and nondestructive examination of waste and related research and development activities, results in an ever-changing radioactive material inventory. Waste packages and radioactive sources are constantly being brought in or taken out of the facility; hence, use of the RMIS is necessary to ensure that the radioactive material inventory limits are not exceeded

Safeguards implementation at US facilities during 1986 and 1987

International Nuclear Information System (INIS)

Wredberg, L.

1987-01-01

Safeguards procedures were implemented at three nuclear facilities in the United States during 1986 and 1987, namely, the Westinghouse fuel fabrication plant in Columbia, South Carolina; the Salem No. 1 light water reactor (LWR) in New Jersey; and the Turkey Point No. 4 LWR in Florida. These three facilities have been under International Atomic Energy Agency (IAEA) safeguards since early 1986 in accordance with the voluntary offer agreement between the IAEA and the United States, which went into force in 1980. Because of limited manpower and budget resources allocated to safeguards in nuclear weapon states, only a limited number of facilities can be under IAEA safeguards inspections at a time. Facilities are, therefore, subject to inspection only during a 2-yr period in the case of the United States. After that period other facilities are selected for another 2-yr period from the list of facilities subject to safeguards under the agreement. The facilities have been selected so that they form a fuel cycle, i.e., the inspected reactors are fueled with fuel assemblies manufactured by the inspected fabrication plant. The IAEA applies full scope safeguards at the selected facilities based upon established implementation practice for the facility types

Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

International Nuclear Information System (INIS)

Sula, M.J.; Jette, S.J.

1994-09-01

Assessments for evaluating compliance with airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAPs - U.S. Code of Federal Regulations, Title 40 Part 61, Subparts H and I) were performed for 33 buildings at the U.S. Department of Energy's (DOE) Pacific Northwest Laboratory on the Hanford Site, and for five buildings owned and operated by Battelle, Pacific Northwest Laboratories in Richland, Washington. The assessments were performed using building radionuclide inventory data obtained in 1992 and 1993. Results of the assessments are summarized in Table S.1 for DOE-PNL buildings and in Table S.2 for Battelle-owned buildings. Based on the radionuclide inventory assessments, four DOE-PNL buildings (one with two emission points) require continuous sampling for radionuclides per 40 CFR 61. None of the Battelle-owned buildings require continuous emission sampling

Environmental Protection Agency (EPA) Facility Registry Service (FRS) Emergency Response (ER) Toxic Substances Control Act (TSCA) Facilities - Oil and Hazardous Materials

Data.gov (United States)

Department of Homeland Security — The purpose of this web feature service is to provide users with access to integrated facility information from FRS, limited to the subset of facilities that link to...

77 FR 37904 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2012-06-25

... Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Reinforced Plastic... compliance with the Paperwork Reduction Act (44 U.S.C. 3501 et seq.), this document announces that an...: NESHAP for Reinforced Plastic Composites Production (Renewal) ICR Numbers: EPA ICR Number 1976.05, OMB...

76 FR 76401 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2011-12-07

... Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Cellulose Products... in paper, will be made available for public viewing at http://www.regulations.gov as EPA receives... information about the electronic docket, go to http://www.regulations.gov . Title: NESHAP for Cellulose...

Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range

Energy Technology Data Exchange (ETDEWEB)

Michael Sandvig

2011-01-01

The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, “National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities,” (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

76 FR 19771 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2011-04-08

... Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Vinyl Chloride (Renewal... . Title: NESHAP for Vinyl Chloride (Renewal). ICR Numbers: EPA ICR Number 0186.12, OMB Control Number 2060... performance tests, and periodic reports and results. Owners or operators are also required to maintain records...

75 FR 16458 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2010-04-01

... Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Plastic Parts and Products... Protection Agency (EPA). ACTION: Notice. SUMMARY: In compliance with the Paperwork Reduction Act (44 U.S.C... . Title: NESHAP for Plastic Parts and Products Surface Coating (Renewal). ICR Numbers: EPA ICR Number 2044...

78 FR 20630 - Agency Information Collection Activities; Submission to OMB for Review and Approval; Comment...

Science.gov (United States)

2013-04-05

... Activities; Submission to OMB for Review and Approval; Comment Request; NESHAP for Plastic Parts and Products... compliance with the Paperwork Reduction Act (44 U.S.C. 3501 et seq.), this document announces that an... www.regulations.gov . Title: NESHAP for Plastic Parts and Products Surface Coating (Renewal). ICR...

7 CFR 205.271 - Facility pest management practice standard.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Facility pest management practice standard. 205.271... Requirements § 205.271 Facility pest management practice standard. (a) The producer or handler of an organic facility must use management practices to prevent pests, including but not limited to: (1) Removal of pest...

76 FR 67728 - Proposed Settlement Agreement

Science.gov (United States)

2011-11-02

...). The RICE NESHAP requires certain subcategories of four-stroke rich burn spark-ignition RICE to meet an... provisions to allow owners and operators of spark-ignition four-stroke rich burn engines that meet an... to revise the RICE NESHAP to allow owners and operators of spark-ignition 4-stroke rich burn engines...

Hanford Waste Vitrification Project Building limited scope risk assessment

International Nuclear Information System (INIS)

Braun, D.J.; Lindberg, S.E.; Reardon, M.F.; Wilson, G.P.

1992-10-01

A limited scope risk assessment was performed on the preliminary design of a high-level waste interim storage facility. The Canister Storage Building (CSB) facility will be built to support remediation at the US Department of Energy Hanford Site in Washington State. The CSB will be part of the support facilities for a high level Hanford Waste Vitrification Plant (HWVP). The limited scope risk assessment is based on a preliminary design which uses forced air circulation systems to move air through the building vault. The current building design calls for natural circulation to move air through the building vault

Detailed description of an SSAC at the facility level for research laboratory facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-08-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Preliminary disposal limits, plume interaction factors, and final disposal limits

Energy Technology Data Exchange (ETDEWEB)

Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2018-01-11

In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1984-05-25

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

340 Waste Handling Facility interim safety basis

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

Sandia National Laboratories/New Mexico existing environmental analyses bounding environmental test facilities.

Energy Technology Data Exchange (ETDEWEB)

May, Rodney A.; Bailey-White, Brenda E. (Sandia Staffing Alliance, LLC, Albuquerque, NM); Cantwell, Amber (Sandia Staffing Alliance, LLC, Albuquerque, NM)

2009-06-01

This report identifies current environmental operating parameters for the various test and support facilities at SNL/NM. The intent of this report is solely to provide the limits which bound the facilities' operations. Understanding environmental limits is important to maximizing the capabilities and working within the existing constraints of each facility, and supports the decision-making process in meeting customer requests, cost and schedule planning, modifications to processes, future commitments, and use of resources. Working within environmental limits ensures that mission objectives will be met in a manner that protects human health and the environment. It should be noted that, in addition to adhering to the established limits, other approvals and permits may be required for specific projects.

Dose apportionment for BARC facilities

International Nuclear Information System (INIS)

Preetha, J.; Sundar, D.; Munshi, S.K.; Pradeepkumar, K.S.

2017-01-01

One of the important responsibilities of BARC Safety Council (BSC) is to ensure that appropriate measures are in place to protect the members of the public and the environment from the undue effects of radioactive releases from the facilities regulated by BSC. It is with this aim in mind that a Standing Committee for Dose Apportionment (DAC) was constituted by BSC in 2005, to ensure that the limits are set by the regulatory body for release of low-level gaseous and liquid effluents into the environment from BARC facilities. There are three Committees for dose apportionment constituted by the Chairman, BSC, viz, DAC-TK for Tarapur and Kalpakkam facilities, DAC-TV for Trombay and DACSF for specific faculties

Environmental monitoring of nuclear facilities

International Nuclear Information System (INIS)

Winter, M.

1983-01-01

The objectives of one environmental monitoring program for nuclear facilities, are presented. The program in Federal Republic of Germany, its goals, its basic conditions, its regulations, and its dose limits are emphasized. (E.G.) [pt

78 FR 68054 - Information Collection Request Submitted to OMB for Review and Approval; Comment Request; NESHAP...

Science.gov (United States)

2013-11-13

... Rework Facilities (Renewal) AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The... Manufacturing and Rework Facilities (40 CFR Part 63, Subpart GG) (Renewal)'' (EPA ICR No. 1687.09, OMB Control... are owners or operators of aerospace manufacturing and rework operations. Respondents must submit one...

Regional energy facility siting analysis

International Nuclear Information System (INIS)

Eberhart, R.C.; Eagles, T.W.

1976-01-01

Results of the energy facility siting analysis portion of a regional pilot study performed for the anticipated National Energy Siting and Facility Report are presented. The question of cell analysis versus site-specific analysis is explored, including an evaluation of the difference in depth between the two approaches. A discussion of the possible accomplishments of regional analysis is presented. It is concluded that regional sitting analysis could be of use in a national siting study, if its inherent limits are recognized

Race, ethnicity, and noxious facilities: Environmental racism re- examined

Energy Technology Data Exchange (ETDEWEB)

Nieves, A.L. [Wheaton Coll., IL (United States)]|[Argonne National Lab., IL (United States); Nieves, L.A. [Argonne National Lab., IL (United States)

1992-10-01

The charge has been made that hazardous facilities tend to be located in proximity to minority populations. This study uses a facility density measure for three categories of noxious facilities to examine the relationship between facilities and minority population concentrations. County-level data are used in a correlation analysis for African Americans, Hispanics, and Asians in the four major regions of the US. Even controlling for income and housing value, and limiting the data set to urban areas, consistent patterns of moderate to strong association of facility densities with minority population percentages are found.

CSER 94-012: Criticality safety evaluation report for 340 Facility

International Nuclear Information System (INIS)

Altschuler, S.J.

1995-01-01

This Criticality Safety Evaluation Report (CSER) covers the 340 Facility which acts as a collecting point for liquid and solid waste from various facilities in the 300 Area. Criticality safety is achieved by controlling the amount and concentration of the fissionable material sent to the 340 Facility from the originating facilities in the 300 Area, a method similar to that used elsewhere at Hanford for the waste tank farms. Unlike those, however, the waste received at the 340 Facility will be far less radioactive. It is concluded that present operations meet the two contingency criterion. The facility will still be safely subcritical even after two independent and concurrent failures (either of equipment or administrative controls). The solid waste storage and liquid waste will be managed separately. The solid waste storage area is classified as exempt because it contains less than 15 grams of fissionable materials. The Radioactive Liquid Waste System is classified as isolated because it contains less than one third of a minimum critical mass. The criticality safety of the 340 Facility devoted to the Radioactive Liquid Waste System (RLWS) is assured by the form and concentration of the fissile material and could also be classified as a limited control facility. However, the 340 Facility has been operated as an isolated facility which results in a more conservative limit

Fire detection in warehouse facilities

CERN Document Server

Dinaburg, Joshua

2013-01-01

Automatic sprinklers systems are the primary fire protection system in warehouse and storage facilities. The effectiveness of this strategy has come into question due to the challenges presented by modern warehouse facilities, including increased storage heights and areas, automated storage retrieval systems (ASRS), limitations on water supplies, and changes in firefighting strategies. The application of fire detection devices used to provide early warning and notification of incipient warehouse fire events is being considered as a component of modern warehouse fire protection.Fire Detection i

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Larson, H L

2007-09-07

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Evaluation of concentration limits of radionuclides produced by accelerators

International Nuclear Information System (INIS)

Shibata, Tokushi; Ohkubo, Tohru; Uwamino, Yoshitomo; Iwai, Satoshi; Satoh, Osamu; Rintsu, Yukoh; Fukumoto, Toshiharu.

1992-01-01

This report describes the evaluation of concentration limits of 78 radionuclides typically produced by accelerator facilities and not listed in ICRP Pub. 30. The evaluation method and system have been developed in the present study. The evaluated values were compared with tremendously severe concentration limits given in the Annex Table 2 of the Science and Technology Agency Notification No. 15 which describes the concentration limits of the nuclides of which concentration limits are not given in the Annex Table 1 of the Agency Notification No. 15. The results show that two to nine order larger limits should be used. The new limits rationalize greatly the internal exposure control and the design of accelerator facilities. Simple and convenient techniques are also discussed for finding concentration limits of very-short-lived nuclides without knowing detail information about the nuclides such as decay scheme and metabolic data. (author)

Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Otis, P.T.

1985-10-01

A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

Intra-facility linkage of HIV-positive mothers and HIV-exposed babies into HIV chronic care: rural and urban experience in a resource limited setting.

Directory of Open Access Journals (Sweden)

Christine Mugasha

Full Text Available INTRODUCTION: Linkage of HIV-infected pregnant women to HIV care remains critical for improvement of maternal and child outcomes through prevention of maternal-to-child transmission of HIV (PMTCT and subsequent chronic HIV care. This study determined proportions and factors associated with intra-facility linkage to HIV care and Early Infant Diagnosis care (EID to inform strategic scale up of PMTCT programs. METHODS: A cross-sectional review of records was done at 2 urban and 3 rural public health care facilities supported by the Infectious Diseases Institute (IDI. HIV-infected pregnant mothers, identified through routine antenatal care (ANC and HIV-exposed babies were evaluated for enrollment in HIV clinics by 6 weeks post-delivery. RESULTS: Overall, 1,025 HIV-infected pregnant mothers were identified during ANC between January and June, 2012; 267/1,025 (26% in rural and 743/1,025 (74% in urban facilities. Of these 375/1,025 (37% were linked to HIV clinics [67/267(25% rural and 308/758(41% urban]. Of 636 HIV-exposed babies, 193 (30% were linked to EID. Linkage of mother-baby pairs to HIV chronic care and EID was 16% (101/636; 8/179 (4.5%] in rural and 93/457(20.3% in urban health facilities. Within rural facilities, ANC registration <28 weeks-of-gestation was associated with mothers' linkage to HIV chronic care [AoR, 2.0 95% CI, 1.1-3.7, p = 0.019] and mothers' multi-parity was associated with baby's linkage to EID; AoR 4.4 (1.3-15.1, p = 0.023. Stigma, long distance to health facilities and vertical PMTCT services affected linkage in rural facilities, while peer mothers, infant feeding services, long patient queues and limited privacy hindered linkage to HIV care in urban settings. CONCLUSION: Post-natal linkage of HIV-infected mothers to chronic HIV care and HIV-exposed babies to EID programs was low. Barriers to linkage to HIV care vary in urban and rural settings. We recommend targeted interventions to rapidly improve linkage to

Waste Sampling and Characterization Facility (WSCF) Complex Safety Analysis

International Nuclear Information System (INIS)

MELOY, R.T.

2003-01-01

The Waste Sampling and Characterization Facility (WSCF) is an analytical laboratory complex on the Hanford Site that was constructed to perform chemical and low-level radiological analyses on a variety of sample media in support of Hanford Site customer needs. The complex is located in the 600 area of the Hanford Site, east of the 200 West Area. Customers include effluent treatment facilities, waste disposal and storage facilities, and remediation projects. Customers primarily need analysis results for process control and to comply with federal, Washington State, and US. Department of Energy (DOE) environmental or industrial hygiene requirements. This document was prepared to analyze the facility for safety consequences and includes the following steps: Determine radionuclide and highly hazardous chemical inventories; Compare these inventories to the appropriate regulatory limits; Document the compliance status with respect to these limits; and Identify the administrative controls necessary to maintain this status

Challenges of ICRP 60 for uranium refining and conversion facilities

International Nuclear Information System (INIS)

Takala, J.M.

1998-01-01

Cameco Corporation operates high-grade uranium mines in northern Saskatchewan and uranium refining and conversion facilities in Ontario. The dose limits for these and all other nuclear facilities in Canada are 50 mSv per year and 4 WLM per year, which are applied separately. However, the upcoming incorporation of the recommendations in ICRP 60 into the Canadian regulations will result in several important changes. In addition to a more restrictive dose limit, the new regulations will require that all radiation exposures be combined into a single index of exposure. Meeting the new lower dose limits of 50 mSv per year and 100 mSv per 5 years will not be a major problem at Cameco facilities. However, the incorporation of long-lived radioactive dust exposures into the dose calculation will be a major challenge. This will cause the most difficulty at the uranium refining and conversion facilities where much of the process involves handling a variety of uranium compounds in the form of a dry powder. At the uranium conversion facilities the control of exposure to airborne uranium is achieved through a combination of lung counting, urinalysis, and fixed area monitors. To progress from a system of exposure control to dose estimation to individual workers will require some major changes. (author)

Current limiters

Energy Technology Data Exchange (ETDEWEB)

Loescher, D.H. [Sandia National Labs., Albuquerque, NM (United States). Systems Surety Assessment Dept.; Noren, K. [Univ. of Idaho, Moscow, ID (United States). Dept. of Electrical Engineering

1996-09-01

The current that flows between the electrical test equipment and the nuclear explosive must be limited to safe levels during electrical tests conducted on nuclear explosives at the DOE Pantex facility. The safest way to limit the current is to use batteries that can provide only acceptably low current into a short circuit; unfortunately this is not always possible. When it is not possible, current limiters, along with other design features, are used to limit the current. Three types of current limiters, the fuse blower, the resistor limiter, and the MOSFET-pass-transistor limiters, are used extensively in Pantex test equipment. Detailed failure mode and effects analyses were conducted on these limiters. Two other types of limiters were also analyzed. It was found that there is no best type of limiter that should be used in all applications. The fuse blower has advantages when many circuits must be monitored, a low insertion voltage drop is important, and size and weight must be kept low. However, this limiter has many failure modes that can lead to the loss of over current protection. The resistor limiter is simple and inexpensive, but is normally usable only on circuits for which the nominal current is less than a few tens of milliamperes. The MOSFET limiter can be used on high current circuits, but it has a number of single point failure modes that can lead to a loss of protective action. Because bad component placement or poor wire routing can defeat any limiter, placement and routing must be designed carefully and documented thoroughly.

Waste-clearance strategy for DOE waste processed at commercial facilities

International Nuclear Information System (INIS)

Chen, S.Y.; Pfingston, M.; LePoire, D.

1996-01-01

In May 1991, a moratorium was issued on shipping potentially mixed waste from DOE facilities nationwide to commercial treatment, storage, and disposal facilities. A potential waste-clearance strategy was developed to address the DOE mixed-waste moratorium issues, which had resulted from a lack of exisitng volume contamination regulations. This strategy also has important potential applications for establishing site clearance limits that ensure worker and public risks remain well below regulatory limits

Detailed description of an SSAC at the facility level for mixed oxide fuel fabrication facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-09-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a mixed oxide fuel fabrication facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Fuel conditioning facility material accountancy

International Nuclear Information System (INIS)

Yacout, A.M.; Bucher, R.G.; Orechwa, Y.

1995-01-01

The operation of the Fuel conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. It differs significantly, therefore, from traditional PUREX process facilities in both processing technology and safeguards implications. For example, the fissile material is processed in FCF only in batches and is transferred within the facility only as solid, well-characterized items; there are no liquid steams containing fissile material within the facility, nor entering or leaving the facility. The analysis of a single batch lends itself also to an analytical relationship between the safeguards criteria, such as alarm limit, detection probability, and maximum significant amount of fissile material, and the accounting system's performance, as it is reflected in the variance associated with the estimate of the inventory difference. This relation, together with the sensitivity of the inventory difference to the uncertainties in the measurements, allows a thorough evaluation of the power of the accounting system. The system for the accountancy of the fissile material in the FCF has two main components: a system to gather and store information during the operation of the facility, and a system to interpret this information with regard to meeting safeguards criteria. These are described and the precision of the inventory closure over one batch evaluated

CRITICALITY SAFETY LIMIT EVALUATION PROGRAM (CSLEP's) AND QUICK SCREENS: ANSWERS TO EXPEDITED PROCESSING LEGACY CRITICALITY SAFETY LIMITS AND EVALUATIONS

International Nuclear Information System (INIS)

TOFFER, H.

2006-01-01

Since the end of the cold war, the need for operating weapons production facilities has faded. Criticality Safety Limits and controls supporting production modes in these facilities became outdated and furthermore lacked the procedure based rigor dictated by present day requirements. In the past, in many instances, the formalism of present day criticality safety evaluations was not applied. Some of the safety evaluations amounted to a paragraph in a notebook with no safety basis and questionable arguments with respect to double contingency criteria. When material stabilization, clean out, and deactivation activities commenced, large numbers of these older criticality safety evaluations were uncovered with limits and controls backed up by tenuous arguments. A dilemma developed: on the one hand, cleanup activities were placed on very aggressive schedules; on the other hand, a highly structured approach to limits development was required and applied to the cleanup operations. Some creative approaches were needed to cope with the limits development process

Gaseous radioactive effluent restrictions, measurement, and minimization at a PET/cyclotron facility

International Nuclear Information System (INIS)

Plascjak, P.S.; Kim, K.K.; Googins, S.W.; Meyer, W.C. Jr.

1993-01-01

In the US, restrictions on the release of radioactive effluents from PET (positron emission tomography)/cyclotron facilities are typically imposed by State regulatory agencies and may be based on various methodologies and limits published by numerous agencies. This work presents suitable effluent concentration limits for various chemical forms of radioisotopes routinely produced in PET/cyclotron facilities. They were determined by application of metabolic models defined by ICRP 53 and ICRP 26/30 which will result in compliance with effective dose equivalent limits of 100 mrem per year at the release point. The NIH Cyclotron Facility effluent air monitoring system, environmental dosimetry program, and simple, effective systems for radioactive effluent minimization are also described. (orig.)

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, M.; Kus, J.P.

2009-01-01

Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

UTN's gamma irradiation facility: design and concept

International Nuclear Information System (INIS)

Mohamad Noor Mohamad Yunus

1986-01-01

UTN is building a multipurpose gamma irradiation facility which compromises of research and pilot scale irradiation cells in The Fifth Malaysia Plan. The paper high-lights the basic futures of the facility in terms of its design and selection including layout sketches. Plant performances and limitations are discussed. Plants safety is briefly highlighted in block diagrams. Lastly, a typical specification brief is tabled in appendix for reference purposes. (author)

Safety of magnetic fusion facilities: Requirements

International Nuclear Information System (INIS)

1996-05-01

This Standard identifies safety requirements for magnetic fusion facilities. Safety functions are used to define outcomes that must be achieved to ensure that exposures to radiation, hazardous materials, or other hazards are maintained within acceptable limits. Requirements applicable to magnetic fusion facilities have been derived from Federal law, policy, and other documents. In addition to specific safety requirements, broad direction is given in the form of safety principles that are to be implemented and within which safety can be achieved

Criticality Safety Evaluation of Hanford Tank Farms Facility

Energy Technology Data Exchange (ETDEWEB)

WEISS, E.V.

2000-12-15

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.

Criticality Safety Evaluation of Hanford Tank Farms Facility

International Nuclear Information System (INIS)

WEISS, E.V.

2000-01-01

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

Opportunities for Automated Demand Response in California Wastewater Treatment Facilities

Energy Technology Data Exchange (ETDEWEB)

Aghajanzadeh, Arian [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Wray, Craig [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); McKane, Aimee [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2015-08-30

Previous research over a period of six years has identified wastewater treatment facilities as good candidates for demand response (DR), automated demand response (Auto-­DR), and Energy Efficiency (EE) measures. This report summarizes that work, including the characteristics of wastewater treatment facilities, the nature of the wastewater stream, energy used and demand, as well as details of the wastewater treatment process. It also discusses control systems and automated demand response opportunities. Furthermore, this report summarizes the DR potential of three wastewater treatment facilities. In particular, Lawrence Berkeley National Laboratory (LBNL) has collected data at these facilities from control systems, submetered process equipment, utility electricity demand records, and governmental weather stations. The collected data were then used to generate a summary of wastewater power demand, factors affecting that demand, and demand response capabilities. These case studies show that facilities that have implemented energy efficiency measures and that have centralized control systems are well suited to shed or shift electrical loads in response to financial incentives, utility bill savings, and/or opportunities to enhance reliability of service. In summary, municipal wastewater treatment energy demand in California is large, and energy-­intensive equipment offers significant potential for automated demand response. In particular, large load reductions were achieved by targeting effluent pumps and centrifuges. One of the limiting factors to implementing demand response is the reaction of effluent turbidity to reduced aeration at an earlier stage of the process. Another limiting factor is that cogeneration capabilities of municipal facilities, including existing power purchase agreements and utility receptiveness to purchasing electricity from cogeneration facilities, limit a facility’s potential to participate in other DR activities.

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

1994-01-01

The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

Southern Hemisphere Ice Limits, 1973-1978

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Weekly Southern Ocean ice limits, have been digitized from U.S. Navy Fleet Weather Facility ice charts, at the Max-Planck Institut fur Meteorologie, Hamburg....

Plasma-Materials Interactions Test Facility

International Nuclear Information System (INIS)

Uckan, T.

1986-11-01

The Plasma-Materials Interactions Test Facility (PMITF), recently designed and constructed at Oak Ridge National Laboratory (ORNL), is an electron cyclotron resonance microwave plasma system with densities around 10 11 cm -3 and electron temperatures of 10-20 eV. The device consists of a mirror cell with high-field-side microwave injection and a heating power of up to 0.8 kW(cw) at 2.45 GHz. The facility will be used for studies of plasma-materials interactions and of particle physics in pump limiters and for development and testing of plasma edge diagnostics

Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

Energy Technology Data Exchange (ETDEWEB)

S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

2008-04-01

A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: • Identifies pre-conceptual design requirements • Develops test loop equipment schematics and layout • Identifies space allocations for each of the facility functions, as required • Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems • Identifies pre-conceptual utility and support system needs • Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

International Nuclear Information System (INIS)

S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

2008-01-01

A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: (1) Identifies pre-conceptual design requirements; (2) Develops test loop equipment schematics and layout; (3) Identifies space allocations for each of the facility functions, as required; (4) Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems; (5) Identifies pre-conceptual utility and support system needs; and (6) Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs

Radiation protection limits and review procedure

International Nuclear Information System (INIS)

Dafauti, Sunita; Gopalakrishnan, R.K.; Pradeepkumar, K.S.

2017-01-01

The primary means of controlling radiation exposure in planned exposure situations in nuclear facilities/radiological laboratories are by good design of facilities, equipment, operating procedures and by ensuring appropriate training to all plant occupational workers. In planned exposure situations, exposure at some level can be expected to occur. For planned exposure situations, exposures are subject to control for ensuring that the specified dose limits for occupational exposure and those for public exposure are not exceeded and optimization is applied to attain the desired level of protection and safety. The person or organization responsible for any facility or activity that gives rise to radiation exposure should have the prime responsibility for protection and safety, which cannot be delegated

Proposed BISOL Facility - a Conceptual Design

Science.gov (United States)

Ye, Yanlin

2018-05-01

In China, a new large-scale nuclear-science research facility, namely the "Beijing Isotope-Separation-On-Line neutron-rich beam facility (BISOL)", has been proposed and reviewed by the governmental committees. This facility aims at both basic science and application goals, and is based on a double-driver concept. On the basic science side, the radioactive ion beams produced from the ISOL device, driven by a research reactor or by an intense deuteron-beam ac- celerator, will be used to study the new physics and technologies at the limit of the nuclear stability in the medium mass region. On the other side regarding to the applications, the facility will be devoted to the material research asso- ciated with the nuclear energy system, by using typically the intense neutron beams produced from the deuteron-accelerator driver. The initial design will be outlined in this report.

Operation of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide was prepared as part of the IAEA's programme on safety of spent fuel storage. This is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes key activities in the operation of spent fuel storage facilities. Section 3 lists the basic safety considerations for storage facility operation, the fundamental safety objectives being subcriticality, heat removal and radiation protection. Recommendations for organizing the management of a facility are contained in Section 4. Section 5 deals with aspects of training and qualification; Section 6 describes the phases of the commissioning of a spent fuel storage facility. Section 7 describes operational limits and conditions, while Section 8 deals with operating procedures and instructions. Section 9 deals with maintenance, testing, examination and inspection. Section 10 presents recommendations for radiation and environmental protection. Recommendations for the quality assurance (QA) system are presented in Section 11. Section 12 describes the aspects of safeguards and physical protection to be taken into account during operations; Section 13 gives guidance for decommissioning. 15 refs, 5 tabs

Usability Briefing - a process model for healthcare facilities

DEFF Research Database (Denmark)

Fronczek-Munter, Aneta

2014-01-01

Background: In complex buildings with many types of users it can be difficult to satisfy the numerous, often contradictory requirements. Research in usability mostly focuses on evaluating products or facilities with users, after they were built. This paper is part of a PhD project “Usability...... with various users/stakeholders, using creative boundary objects at workshops.  Practical Implications: The research results have relevance to researchers, client organisations, facility managers and architects planning new complex facilities.  Research limitations: The proposed model is theoretical and needs...... briefing for hospitals”, where methods for capturing user needs and experiences at hospital facilities are investigated in order to feed into design processes and satisfy the users’ needs and maximise the effectiveness of facilities. Purpose: This paper introduces the concept of usability briefing...

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

Facility Interface Capability Assessment (FICA) project report

International Nuclear Information System (INIS)

Pope, R.B.; MacDonald, R.R.; Viebrock, J.M.; Mote, N.

1995-09-01

The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified

Facility Interface Capability Assessment (FICA) project report

Energy Technology Data Exchange (ETDEWEB)

Pope, R.B. [ed.] [Oak Ridge National Lab., TN (United States); MacDonald, R.R. [ed.] [Civilian Radioactive Waste Management System, Vienna, VA (United States); Viebrock, J.M.; Mote, N. [Nuclear Assurance Corp., Norcross, GA (United States)

1995-09-01

The US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is to present and analyze the results of the facility assessments completed within the FICA project. During Phase 1, the data items required to complete the facility assessments were identified and the database for the project was created. During Phase 2, visits were made to 122 facilities on 76 sites to collect data and information, the database was updated, and assessments of the cask-handling capabilities at each facility were performed. Each assessment of cask-handling capability contains three parts: the current capability of the facility (planning base); the potential enhanced capability if revisions were made to the facility licensing and/or administrative controls; and the potential enhanced capability if limited physical modifications were made to the facility. The main conclusion derived from the planning base assessments is that the current facility capabilities will not allow handling of any of the FICA Casks at 49 of the 122 facilities evaluated. However, consideration of potential revisions and/or modifications showed that all but one of the 49 facilities could be adapted to handle at least one of the FICA Casks. For this to be possible, facility licensing, administrative controls, and/or physical aspects of the facility would need to be modified.

Tritium handling facility at KMS Fusion Inc

International Nuclear Information System (INIS)

Bowman, C.C.; Vis, V.A.

1990-01-01

The tritium facility at KMS Fusion, Inc. supports the inertial confinement fusion research program. The main function of the facility is to fill glass and polymer Microshell (TM) capsules (small fuel containers) to a maximum pressure of 100 atm with tritium (T 2 ) or deuterium--tritium (DT). The recent upgrade of the facility allows us to fill Microshell capsules to a maximum pressure of 200 atm. A second fill port allows us to run long term fills of Macroshell (TM) capsules (large fuel containers) concurrently. The principle processes of the system are: (1) storage of the tritium as a uranium hydride; (2) pressure intensification using cryogenics; and (3) filling of the shells by permeation at elevated temperatures. The design of the facility was centered around a NRC license limit of 6000 Ci

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

Energy Technology Data Exchange (ETDEWEB)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

Tech assist/fire safety assessment of 100K area facilities

International Nuclear Information System (INIS)

Johnson, B.H.

1994-01-01

This Tech Assist/Fire Safety Assessment provides a comprehensive assessment of the 100K Area Facilities at the U.S. Department of Energy's Hanford Site for fire protection upgrades that may be needed given the limited remaining service life of these facilities. This assessment considers the relative nature of observed fire risks and whether the installed fire protection systems adequately control this risk. The analysis is based on compliance with DOE Orders, NFPA Codes and Standards, and recognized industry practice. Limited remaining service life (i.e., 6 to 12 years), current value of each facility, comparison to the best protected class of industrial risk, and the potential for exemptions from DOE requirements are key factors for recommendations presented in this report

Integration of small computers in the low budget facility

International Nuclear Information System (INIS)

Miller, G.E.; Crofoot, T.A.

1988-01-01

Inexpensive computers (PC's) are well within the reach of low budget reactor facilities. It is possible to envisage many uses that will both improve capabilities of existing instrumentation and also assist operators and staff with certain routine tasks. Both of these opportunities are important for survival at facilities with severe budget and staffing limitations. (author)

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Analysis of occupational doses in radioactive and nuclear facilities

International Nuclear Information System (INIS)

Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

1996-01-01

Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

Operation of a low-level waste disposal facility and how to prevent problems in future facilities

International Nuclear Information System (INIS)

Di Sibio, R.

1985-01-01

Operation of a low-level waste facility is an ever increasing problem nationally, and specifically one that could grow to crisis proportion in Pennsylvania. There have been, nevertheless, a variety of changes over the years in the management of low level radioactive waste, particularly with regard to disposal facilities that can avert a crisis condition. A number of companies have been organized thru possible a broad range of services to the nuclear industry, including those that emphasize solidification of waste materials, engineering services, waste management, and transportation to disposal sites across the United States. This paper addresses one particular site and the problems which evolved at that site from an environmental perspective. It is important that it is clearly understood that, although these problems are resolvable, the lessons learned here are critical for the prevention of problems at future facilities. The focus of this paper is on the Maxey Flats, Kentucky disposal facility which was closed in 1977. It must be understood that the regulations for siting, management, burial techniques, waste classification, and the overall management of disposal sites were limited when this facility was in operation

42 CFR 57.1508 - Amount of interest subsidy payments; limitations.

Science.gov (United States)

2010-10-01

... GRANTS GRANTS FOR CONSTRUCTION OF TEACHING FACILITIES, EDUCATIONAL IMPROVEMENTS, SCHOLARSHIPS AND STUDENT LOANS Loan Guarantees and Interest Subsidies to Assist in Construction of Teaching Facilities for Health Profession Personnel § 57.1508 Amount of interest subsidy payments; limitations. The length of time for which...

33 CFR 126.15 - What conditions must a designated waterfront facility meet?

Science.gov (United States)

2010-07-01

..., access to the facility must be limited to— (i) Personnel working on the facility or vessel; (ii) Delivery... meet the requirements of NFPA 307, chapter 9. (10) Smoking. Smoking is allowed on the facility where permitted under State or local law. Signs must be posted marking authorized smoking areas. “No Smoking...

Facilities for studying the double beta decay processes

International Nuclear Information System (INIS)

Zdesenko, Yu.G.

1980-01-01

Modern state, tendencies and perspectiVes of the development of experimental installations to study double β-decay are treated. The main peculiarities of direct recognition and full experiments on the study of double β-decay are considered. A simple ratio is obtained from statistical considerations which connects the life time limits of the nuclei with the facility parameters to conduct direct recognition experiments. Possibilities of different detectors are evaluated on the basis of the ratio. Requirements for the modern technique for complete investigation of double β-decay are formulated and two designs of facilities meeting the requirements are considered. It is shown that the facility with proportional chambers is more perspective. On the basis of the analysis of the facility development to study double β-decay, conclusion is made that the final and unambiguous proof of the existence of double β-decay process can be obtained only directly in the experiments with immediate recording of the decay acts. Possibilities of the existing and developed facilities to conduct recognition (direct) experiments are such, that with their help life time limits as to neutronless double β-decay at the level of 10 21 -10 22 years can be established. Counters on the basis of the condensed noble gases, semiconductor detectors made of TeCd, scintillators of big volume are the most perspective detectors. To conduct complete experiments it is necessary to develop a facility with sensitivity sufficient for the detection of two-neutrino double β-activeness when Tsub(1/2)=10sup(21) years [ru

Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

International Nuclear Information System (INIS)

Jones, R.J.

1985-11-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

Hot Hydrogen Test Facility

International Nuclear Information System (INIS)

W. David Swank

2007-01-01

The core in a nuclear thermal rocket will operate at high temperatures and in hydrogen. One of the important parameters in evaluating the performance of a nuclear thermal rocket is specific impulse, ISp. This quantity is proportional to the square root of the propellant's absolute temperature and inversely proportional to square root of its molecular weight. Therefore, high temperature hydrogen is a favored propellant of nuclear thermal rocket designers. Previous work has shown that one of the life-limiting phenomena for thermal rocket nuclear cores is mass loss of fuel to flowing hydrogen at high temperatures. The hot hydrogen test facility located at the Idaho National Lab (INL) is designed to test suitability of different core materials in 2500 C hydrogen flowing at 1500 liters per minute. The facility is intended to test non-uranium containing materials and therefore is particularly suited for testing potential cladding and coating materials. In this first installment the facility is described. Automated Data acquisition, flow and temperature control, vessel compatibility with various core geometries and overall capabilities are discussed

Preliminary scoping safety analyses of the limiting design basis protected accidents for the Fast Flux Test Facility tritium production core

International Nuclear Information System (INIS)

Heard, F.J.

1997-01-01

The SAS4A/SASSYS-l computer code is used to perform a series of analyses for the limiting protected design basis transient events given a representative tritium and medical isotope production core design proposed for the Fast Flux Test Facility. The FFTF tritium and isotope production mission will require a different core loading which features higher enrichment fuel, tritium targets, and medical isotope production assemblies. Changes in several key core parameters, such as the Doppler coefficient and delayed neutron fraction will affect the transient response of the reactor. Both reactivity insertion and reduction of heat removal events were analyzed. The analysis methods and modeling assumptions are described. Results of the analyses and comparison against fuel pin performance criteria are presented to provide quantification that the plant protection system is adequate to maintain the necessary safety margins and assure cladding integrity

Is the closest facility the one actually used? An assessment of travel time estimation based on mammography facilities.

Science.gov (United States)

Alford-Teaster, Jennifer; Lange, Jane M; Hubbard, Rebecca A; Lee, Christoph I; Haas, Jennifer S; Shi, Xun; Carlos, Heather A; Henderson, Louise; Hill, Deirdre; Tosteson, Anna N A; Onega, Tracy

2016-02-18

Characterizing geographic access depends on a broad range of methods available to researchers and the healthcare context to which the method is applied. Globally, travel time is one frequently used measure of geographic access with known limitations associated with data availability. Specifically, due to lack of available utilization data, many travel time studies assume that patients use the closest facility. To examine this assumption, an example using mammography screening data, which is considered a geographically abundant health care service in the United States, is explored. This work makes an important methodological contribution to measuring access--which is a critical component of health care planning and equity almost everywhere. We analyzed one mammogram from each of 646,553 women participating in the US based Breast Cancer Surveillance Consortium for years 2005-2012. We geocoded each record to street level address data in order to calculate travel time to the closest and to the actually used mammography facility. Travel time between the closest and the actual facility used was explored by woman-level and facility characteristics. Only 35% of women in the study population used their closest facility, but nearly three-quarters of women not using their closest facility used a facility within 5 min of the closest facility. Individuals that by-passed the closest facility tended to live in an urban core, within higher income neighborhoods, or in areas where the average travel times to work was longer. Those living in small towns or isolated rural areas had longer closer and actual median drive times. Since the majority of US women accessed a facility within a few minutes of their closest facility this suggests that distance to the closest facility may serve as an adequate proxy for utilization studies of geographically abundant services like mammography in areas where the transportation networks are well established.

Employee influenza vaccination in residential care facilities.

Science.gov (United States)

Apenteng, Bettye A; Opoku, Samuel T

2014-03-01

The organizational literature on infection control in residential care facilities is limited. Using a nationally representative dataset, we examined the organizational factors associated with implementing at least 1 influenza-related employee vaccination policy/program, as well as the effect of vaccination policies on health care worker (HCW) influenza vaccine uptake in residential care facilities. The study was a cross-sectional study using data from the 2010 National Survey of Residential Care Facilities. Multivariate logistic regression analysis was used to address the study's objectives. Facility size, director's educational attainment, and having a written influenza pandemic preparedness plan were significantly associated with the implementation of at least 1 influenza-related employee vaccination policy/program, after controlling for other facility-level factors. Recommending vaccination to employees, providing vaccination on site, providing vaccinations to employees at no cost, and requiring vaccination as a condition of employment were associated with higher employee influenza vaccination rates. Residential care facilities can improve vaccination rates among employees by adopting effective employee vaccination policies. Copyright © 2014 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Mosby, Inc. All rights reserved.

Probabilistic safety assessment for food irradiation facility

International Nuclear Information System (INIS)

Solanki, R.B.; Prasad, M.; Sonawane, A.U.; Gupta, S.K.

2012-01-01

Highlights: ► Different considerations are required in PSA for Non-Reactor Nuclear Facilities. ► We carried out PSA for food irradiation facility as a part of safety evaluation. ► The results indicate that the fatal exposure risk is below the ‘acceptable risk’. ► Adequate operator training and observing good safety culture would reduce the risk. - Abstract: Probabilistic safety assessment (PSA) is widely used for safety evaluation of Nuclear Power Plants (NPPs) worldwide. The approaches and methodologies are matured and general consensus exists on using these approaches in PSA applications. However, PSA applications for safety evaluation for non-reactor facilities are limited. Due to differences in the processes in nuclear reactor facilities and non-reactor facilities, the considerations are different in application of PSA to these facilities. The food irradiation facilities utilize gamma irradiation sources, X-ray machines and electron accelerators for the purpose of radiation processing of variety of food items. This is categorized as Non-Reactor Nuclear Facility. In this paper, the application of PSA to safety evaluation of food irradiation facility is presented considering the ‘fatality due to radiation overexposure’ as a risk measure. The results indicate that the frequency of the fatal exposure is below the numerical acceptance guidance for the risk to the individual. Further, it is found that the overall risk to the over exposure can be reduced by providing the adequate operator training and observing good safety culture.

Criticality safety and facility design considerations

International Nuclear Information System (INIS)

Waltz, W.R.

1991-06-01

Operations with fissile material introduce the risk of a criticality accident that may be lethal to nearby personnel. In addition, concerns over criticality safety can result in substantial delays and shutdown of facility operations. For these reasons, it is clear that the prevention of a nuclear criticality accident should play a major role in the design of a nuclear facility. The emphasis of this report will be placed on engineering design considerations in the prevention of criticality. The discussion will not include other important aspects, such as the physics of calculating limits nor criticality alarm systems

The forced flow high field test facility SULTAN

International Nuclear Information System (INIS)

Horvath, I.; Vecsey, G.; Weymuth, P.

1984-01-01

The construction of the 8 Tesla, 1 m bore Test Facility SULTAN - I, a common action of ENEA (I-Frascati), ECN (NL-Petten) and SIN (CH-Villigen), is completed. Results on assembly, cooldown and the first operation of the whole system are presented. The SULTAN facility provides a wide range of capability of parameter variations (field, current, cooling) for the investigation of steady state performance and stability of technical superconductors unders nominal and limiting conditions

Medication incident reporting in residential aged care facilities: Limitations and risks to residents’ safety

Directory of Open Access Journals (Sweden)

Tariq Amina

2012-11-01

Full Text Available Abstract Background Medication incident reporting (MIR is a key safety critical care process in residential aged care facilities (RACFs. Retrospective studies of medication incident reports in aged care have identified the inability of existing MIR processes to generate information that can be used to enhance residents’ safety. However, there is little existing research that investigates the limitations of the existing information exchange process that underpins MIR, despite the considerable resources that RACFs’ devote to the MIR process. The aim of this study was to undertake an in-depth exploration of the information exchange process involved in MIR and identify factors that inhibit the collection of meaningful information in RACFs. Methods The study was undertaken in three RACFs (part of a large non-profit organisation in NSW, Australia. A total of 23 semi-structured interviews and 62 hours of observation sessions were conducted between May to July 2011. The qualitative data was iteratively analysed using a grounded theory approach. Results The findings highlight significant gaps in the design of the MIR artefacts as well as information exchange issues in MIR process execution. Study results emphasized the need to: a design MIR artefacts that facilitate identification of the root causes of medication incidents, b integrate the MIR process within existing information systems to overcome key gaps in information exchange execution, and c support exchange of information that can facilitate a multi-disciplinary approach to medication incident management in RACFs. Conclusions This study highlights the advantages of viewing MIR process holistically rather than as segregated tasks, as a means to identify gaps in information exchange that need to be addressed in practice to improve safety critical processes.

Medication incident reporting in residential aged care facilities: Limitations and risks to residents’ safety

Science.gov (United States)

2012-01-01

Background Medication incident reporting (MIR) is a key safety critical care process in residential aged care facilities (RACFs). Retrospective studies of medication incident reports in aged care have identified the inability of existing MIR processes to generate information that can be used to enhance residents’ safety. However, there is little existing research that investigates the limitations of the existing information exchange process that underpins MIR, despite the considerable resources that RACFs’ devote to the MIR process. The aim of this study was to undertake an in-depth exploration of the information exchange process involved in MIR and identify factors that inhibit the collection of meaningful information in RACFs. Methods The study was undertaken in three RACFs (part of a large non-profit organisation) in NSW, Australia. A total of 23 semi-structured interviews and 62 hours of observation sessions were conducted between May to July 2011. The qualitative data was iteratively analysed using a grounded theory approach. Results The findings highlight significant gaps in the design of the MIR artefacts as well as information exchange issues in MIR process execution. Study results emphasized the need to: a) design MIR artefacts that facilitate identification of the root causes of medication incidents, b) integrate the MIR process within existing information systems to overcome key gaps in information exchange execution, and c) support exchange of information that can facilitate a multi-disciplinary approach to medication incident management in RACFs. Conclusions This study highlights the advantages of viewing MIR process holistically rather than as segregated tasks, as a means to identify gaps in information exchange that need to be addressed in practice to improve safety critical processes. PMID:23122411

Decommissioning Strategies Selection for Facilities Using Radioactive Material

International Nuclear Information System (INIS)

Husen Zamroni; Jaka Rachmadetin

2008-01-01

The facilities using radioactive material that have been stopped operation will require some form of the decommissioning for public and environment safety. The approaches are identified by three decommissioning strategies: immediate dismantling, deferred dismantling and entombment. If a facility undergoes immediate dismantling, most radio nuclides will have no such sufficient time to decay and therefore this strategy may not provide reduction in the worker exposure. A facility that undergoes deferred dismantling may advantage from the radioactive decay of residual radio nuclides during the long term storage period and entombment could be a viable option for other nuclear facilities containing only short lived or limited concentrations of long lived radionuclides. Mostly, only two types of the decommissioning used to be done in the world, immediate and deferred dismantling. (author)

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

International Nuclear Information System (INIS)

Sasser, K.

1994-06-01

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Laycak, D.T.

2010-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2008-06-16

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

Electromagnetic Fields Associated with Commercial Solar Photovoltaic Electric Power Generating Facilities.

Science.gov (United States)

Tell, R A; Hooper, H C; Sias, G G; Mezei, G; Hung, P; Kavet, R

2015-01-01

The southwest region of the United States is expected to experience an expansion of commercial solar photovoltaic generation facilities over the next 25 years. A solar facility converts direct current generated by the solar panels to three-phase 60-Hz power that is fed to the grid. This conversion involves sequential processing of the direct current through an inverter that produces low-voltage three-phase power, which is stepped up to distribution voltage (∼12 kV) through a transformer. This study characterized magnetic and electric fields between the frequencies of 0 Hz and 3 GHz at two facilities operated by the Southern California Edison Company in Porterville, CA and San Bernardino, CA. Static magnetic fields were very small compared to exposure limits established by IEEE and ICNIRP. The highest 60-Hz magnetic fields were measured adjacent to transformers and inverters, and radiofrequency fields from 5-100 kHz were associated with the inverters. The fields measured complied in every case with IEEE controlled and ICNIRP occupational exposure limits. In all cases, electric fields were negligible compared to IEEE and ICNIRP limits across the spectrum measured and when compared to the FCC limits (≥0.3 MHz).

Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

International Nuclear Information System (INIS)

Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

1999-01-01

A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours

Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

International Nuclear Information System (INIS)

Gagner, L.; Voinis, S.

2000-01-01

In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

Safeguarding uranium enrichment facilities. Review and analysis of the status of safeguards technology for uranium enrichment facilities

International Nuclear Information System (INIS)

1977-09-01

The objective of this paper is to examine critically the diversion potential at uranium enrichment facilities and to outline a basic safeguards strategy which counters all identified hazards as completely as possible yet with a minimum of non-essential redundancy. Where existing technology does not appear to be adequate for effective safeguards, the limitations are examined, and suggestions for further R and D effort are made. Parts of this report are generally applicable to all currently known enrichment processes, while other parts are specifically directed toward facilities based on the gas centrifuge process. It is hoped that additional sections discussing a safeguards strategy for gas diffusion facilities can be added later. It should be emphasized that this is a technical report, and does not reflect any legal positions. The safeguards strategy and subsequent inspection procedures are intended as guidelines, not as negotiating positions

The BLAIRR Irradiation Facility Hybrid Spallation Target Optimization

Energy Technology Data Exchange (ETDEWEB)

Simos N.; Hanson A.; Brown, D.; Elbakhshawn, M.

2016-04-11

BLAIRR STUDY STATUS OVERVIEW Beamline Complex Evaluation/Assessment and Adaptation to the Goals Facility Radiological Constraints ? Large scale analyses of conventional facility and integrated shield (concrete, soil)Target Optimization and Design: Beam-target interaction optimization Hadronic interaction and energy deposition limitations Single phase and Hybrid target concepts Irradiation Damage Thermo-mechanical considerations Spallation neutron fluence optimization for (a) fast neutron irradiation damage (b) moderator/reflector studies, (c) NTOF potential and optimization (d) mono-energetic neutron beam

42 CFR 93.105 - Time limitations.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Time limitations. 93.105 Section 93.105 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES HEALTH ASSESSMENTS AND HEALTH EFFECTS STUDIES OF HAZARDOUS SUBSTANCES RELEASES AND FACILITIES PUBLIC HEALTH SERVICE POLICIES ON RESEARCH...

Enhanced operator-training simulator for the Fast Flux Test Facility

International Nuclear Information System (INIS)

Schrader, F.D.; Swanson, C.D.

1983-01-01

The FFTF Plant Operator Training Simulator Facility has proven to be a valuable asset throughtout the testing, startup and early operational phases of the Fast Flux Test facility. However, limitations inherent in the existing simulation facility, increased emphasis on the required quality of operator training, and an expanded scope of applications (e.g., MNI development) justify an enhanced facility. Direct use of plant operators in the development of improved reactor control room displays and other man/machine interface equipment and procedures increases the credibility of proposed techniques and reported results. The FFTF Plant Operator Training Simulator provides a key element in this development program

Earthquake research for the safer siting of critical facilities

Energy Technology Data Exchange (ETDEWEB)

Cluff, J.L. (ed.)

1980-01-01

The task of providing the necessities for living, such as adequate electrical power, water, and fuel, is becoming more complicated with time. Some of the facilities that provide these necessities would present potential hazards to the population if serious damage were to occur to them during earthquakes. Other facilities must remain operable immediately after an earthquake to provide life-support services to people who have been affected. The purpose of this report is to recommend research that will improve the information available to those who must decide where to site these critical facilities, and thereby mitigate the effects of the earthquake hazard. The term critical facility is used in this report to describe facilities that could seriously affect the public well-being through loss of life, large financial loss, or degradation of the environment if they were to fail. The term critical facility also is used to refer to facilities that, although they pose a limited hazard to the public, are considered critical because they must continue to function in the event of a disaster so that they can provide vital services.

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

Idaho National Engineering Laboratory irradiation facilities and their applications

International Nuclear Information System (INIS)

Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

1986-05-01

Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

Fuel Assemblies Thermal Analysis in the New Spent Fuel Storage Facility at Inshass Site

International Nuclear Information System (INIS)

Khattab, M.; Mariy, Ahmed

1999-01-01

New Wet Storage Facility (NSF) is constructed at Inshass site to solve the problem of spent fuel storage capacity of ETRR-1 reactor . The Engineering Safety Heat Transfer Features t hat characterize the new facility are presented. Thermal analysis including different scenarios of pool heat load and safety limits are discussed . Cladding temperature limit during handling and storage process are specified for safe transfer of fuel

Investigating proton emitters at the limits of stability with radioactive beams from the Oak Ridge facility

Energy Technology Data Exchange (ETDEWEB)

Toth, K.S. [Oak Ridge National Lab., TN (United States); Batchelder, J.C.; Zganjar, E.F. [Louisiana State Univ., Baton Rouge, LA (United States); Bingham, C.R.; Wauters, J. [Tennessee Univ., Knoxville, TN (United States); Davinson, T.; MacKenzie, J.A.; Woods, P.J. [Edinburgh Univ. (United Kingdom)

1996-10-01

By using beams from the Holifield Radioactive Ion Beam Facility at ORNL, it should be possible to identify many new ground-state proton emitters in the mass region from Sn to Pb. In these investigations nuclei produced in fusion-evaporation reactions will be separated from incident ions and dispersed in mass/charge with a recoil mass separator and then implanted into a double-sided Si strip detector for study of proton (and {alpha}-particle) radioactivity. This paper summarizes data presently extant on proton emitters and then focuses on tests and initial experiments that will be carried out with stable beams and with radioactive ions as they are developed at the Oak Ridge facility.

Personnel neutron dosimetry at Department of Energy facilities

International Nuclear Information System (INIS)

Brackenbush, L.W.; Endres, G.W.R.; Selby, J.M.; Vallario, E.J.

1980-08-01

This study assesses the state of personnel neutron dosimetry at DOE facilities. A survey of the personnel dosimetry systems in use at major DOE facilities was conducted, a literature search was made to determine recent advances in neutron dosimetry, and several dosimetry experts were interviewed. It was concluded that personnel neutron dosimeters do not meet current needs and that serious problems exist now and will increase in the future if neutron quality factors are increased and/or dose limits are lowered

Hazardous Materials Verification and Limited Characterization Report on Sodium and Caustic Residuals in Materials and Fuel Complex Facilities MFC-799/799A

Energy Technology Data Exchange (ETDEWEB)

Gary Mecham

2010-08-01

This report is a companion to the Facilities Condition and Hazard Assessment for Materials and Fuel Complex Sodium Processing Facilities MFC-799/799A and Nuclear Calibration Laboratory MFC-770C (referred to as the Facilities Condition and Hazards Assessment). This report specifically responds to the requirement of Section 9.2, Item 6, of the Facilities Condition and Hazards Assessment to provide an updated assessment and verification of the residual hazardous materials remaining in the Sodium Processing Facilities processing system. The hazardous materials of concern are sodium and sodium hydroxide (caustic). The information supplied in this report supports the end-point objectives identified in the Transition Plan for Multiple Facilities at the Materials and Fuels Complex, Advanced Test Reactor, Central Facilities Area, and Power Burst Facility, as well as the deactivation and decommissioning critical decision milestone 1, as specified in U.S. Department of Energy Guide 413.3-8, “Environmental Management Cleanup Projects.” Using a tailored approach and based on information obtained through a combination of process knowledge, emergency management hazardous assessment documentation, and visual inspection, this report provides sufficient detail regarding the quantity of hazardous materials for the purposes of facility transfer; it also provides that further characterization/verification of these materials is unnecessary.

Adverse event reporting in Czech long-term care facilities.

Science.gov (United States)

Hěib, Zdenřk; Vychytil, Pavel; Marx, David

2013-04-01

To describe adverse event reporting processes in long-term care facilities in the Czech Republic. Prospective cohort study involving a written questionnaire followed by in-person structured interviews with selected respondents. Long-term care facilities located in the Czech Republic. Staff of 111 long-term care facilities (87% of long-term care facilities in the Czech Republic). None. Sixty-three percent of long-term health-care facilities in the Czech Republic have adverse event-reporting processes already established, but these were frequently very immature programs sometimes consisting only of paper recording of incidents. Compared to questionnaire responses, in-person interview responses only partially tended to confirm the results of the written survey. Twenty-one facilities (33%) had at most 1 unconfirmed response, 31 facilities (49%) had 2 or 3 unconfirmed responses and the remaining 11 facilities (17%) had 4 or more unconfirmed responses. In-person interviews suggest that use of a written questionnaire to assess the adverse event-reporting process may have limited validity. Staff of the facilities we studied expressed an understanding of the importance of adverse event reporting and prevention, but interviews also suggested a lack of knowledge necessary for establishing a good institutional reporting system in long-term care.

Special Analysis: Revised 14C Disposal Limits for the Saltstone Disposal Facility

International Nuclear Information System (INIS)

Kaplan, D.I.

2004-01-01

The Saltstone Special Analysis calculated a limit for 14C based on the atmospheric pathway of 52 pCi/mL using some very conservative assumptions. This was compared to the estimated Low Curie Salt concentration of 0.45 pCi/mL and since the limit was two orders of magnitude greater than the estimated concentration, the decision was made that no further analysis was needed. The 14C concentration in Tank 41 has been found to be much greater than the estimated concentration and to exceed the limit derived in the Special Analysis. A rigorous analysis of the release of 14C via the air pathway that considers the chemical effects of the Saltstone system has shown that the flux of 14C is significantly less than that assumed in the Special Analysis. The net result is an inventory limit for 14C that is significantly higher than that derived in the Special Analysis that will also meet the performance objectives of DOE Order 435.1

Investigating the Importance of Sports Facilities & Staff for Football Fans

Directory of Open Access Journals (Sweden)

Pinelopi Athanasopoulou

2012-01-01

Full Text Available (a Purpose: This study seeks to investigate the importance of facilities and staff for football fans in Greece. (b Design/methodology/approach: A survey was carried out during two matches of Superleague games with a convenience sample of 312 spectators. A structured questionnaire was used with scales based on previous research. (c Findings: Factor analysis revealed four reliable factor dimensions: facilities design; staff; facilities maintenance, and quick & easy access. Staff and quick & easy access are shown to be the most important dimensions for respondents followed by the other two. Results also indicated that there are significant differences in the importance assigned to these 4 factor dimensions among different levels of age; education; income, and marital status. (d Research limitations/implications: This study is limited to one sport and on a convenience sample of football fans. Future research can validate further these findings and increase their generalisability. (e Practical implications: The results of this study challenge sport managers to manage effectively the design of the stadium; the processes of entry and exit of fans; the environment of the game; and the quality of stadium facilities.

40 CFR Table 44 to Subpart Uuu of... - Applicability of NESHAP General Provisions to Subpart UUU

Science.gov (United States)

2010-07-01

... Refineries: Catalytic Cracking Units, Catalytic Reforming Units, and Sulfur Recovery Units Pt. 63, Subpt. UUU... facility that installs catalytic cracking feed hydrotreating and receives an extended compliance date under...

78 FR 65690 - Trees and Plantings Associated With Eligible Facilities, RP9524.5

Science.gov (United States)

2013-11-01

...] Trees and Plantings Associated With Eligible Facilities, RP9524.5 AGENCY: Federal Emergency Management... policy Trees and Plantings Associated with Eligible Facilities. The Federal Emergency Management Agency... trees, shrubs, and other plantings, including limited eligibility for replacement of grass and sod...

Radiological and the other safety aspects in the operation of electron beam facility

International Nuclear Information System (INIS)

Loterina, Roel Alamares

2003-01-01

The radiological safety aspects of the operation of an electron beam facility in general and the 3 MeV ALURTRON electron beam facility of the Malaysian Institute of Nuclear Technology Research (MINT) in particular were reviewed and evaluated. Evaluation was made based on existing records as well as actual monitoring around facility. Area monitoring results using TLDs are within permissible levels. The maximum reading of 7.29 mSv measured in year 2000 is very low as compared to the annual dose limit of 50 mSv/year. In general, the shielding for the installation is adequate and no significant radiation leakage were detected based on radiation survey results. However, measured radiation levels with a maximum of 1.9 mSv/h at the sampling ports easily exceed the limit of 25μSv/h. The facility is equipped with safety features, such as interlocked system, adequate shielding, engineered safety design of irradiation and accelerator rooms, and accessories such as conveyor system and product handling system. Warning lights and signals are adequately installed around the facility. Other identified hazards that may affect the operator, workers, and personnel were also evaluated based on previous records of monitoring. The ozone concentration levels with a maximum reading of 0.05 ppm measured in the environment of the facility are within the threshold limit value of 0.1 ppm. The measured noise levels at all locations around facility are generally below the maximum permissible level of 80dB. The ALURTRON has achieved a minimum safety requirement to warrant its full operation without relying on administrative controls and procedures to ensure safety in operation. (Auth.)

Technical Safety Requirements for the Waste Storage Facilities May 2014

Energy Technology Data Exchange (ETDEWEB)

Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-04-16

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Technical Safety Requirements for the Waste Storage Facilities May 2014

International Nuclear Information System (INIS)

Laycak, D. T.

2014-01-01

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

New facility shield design criteria

International Nuclear Information System (INIS)

Howell, W.P.

1981-07-01

The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources

Medicare Advantage Members' Expected Out-Of-Pocket Spending For Inpatient And Skilled Nursing Facility Services.

Science.gov (United States)

Keohane, Laura M; Grebla, Regina C; Mor, Vincent; Trivedi, Amal N

2015-06-01

Inpatient and skilled nursing facility (SNF) cost sharing in Medicare Advantage (MA) plans may reduce unnecessary use of these services. However, large out-of-pocket expenses potentially limit access to care and encourage beneficiaries at high risk of needing inpatient and postacute care to avoid or leave MA plans. In 2011 new federal regulations restricted inpatient and skilled nursing facility cost sharing and mandated limits on out-of-pocket spending in MA plans. After these regulations, MA members in plans with low premiums averaged $1,758 in expected out-of-pocket spending for an episode of seven hospital days and twenty skilled nursing facility days. Among members with the same low-premium plan in 2010 and 2011, 36 percent of members belonged to plans that added an out-of-pocket spending limit in 2011. However, these members also had a $293 increase in average cost sharing for an inpatient and skilled nursing facility episode, possibly to offset plans' expenses in financing out-of-pocket limits. Some MA beneficiaries may still have difficulty affording acute and postacute care despite greater regulation of cost sharing. Project HOPE—The People-to-People Health Foundation, Inc.

Medicare Advantage Members’ Expected Out-Of-Pocket Spending For Inpatient And Skilled Nursing Facility Services

Science.gov (United States)

Keohane, Laura M.; Grebla, Regina C.; Mor, Vincent; Trivedi, Amal N.

2015-01-01

Inpatient and skilled nursing facility (SNF) cost sharing in Medicare Advantage (MA) plans may reduce unnecessary use of these services. However, large out-of-pocket expenses potentially limit access to care and encourage beneficiaries at high risk of needing inpatient and postacute care to avoid or leave MA plans. In 2011 new federal regulations restricted inpatient and skilled nursing facility cost sharing and mandated limits on out-of-pocket spending in MA plans. After these regulations, MA members in plans with low premiums averaged $1,758 in expected out-of-pocket spending for an episode of seven hospital days and twenty skilled nursing facility days. Among members with the same low-premium plan in 2010 and 2011, 36 percent of members belonged to plans that added an out-of-pocket spending limit in 2011. However, these members also had a $293 increase in average cost sharing for an inpatient and skilled nursing facility episode, possibly to offset plans’ expenses in financing out-of-pocket limits. Some MA beneficiaries may still have difficulty affording acute and postacute care despite greater regulation of cost sharing. PMID:26056208

300 Area Treated Effluent Disposal Facility permit reopener run plan

International Nuclear Information System (INIS)

Olander, A.R.

1995-01-01

The 300 Area Treated Effluent Disposal Facility (TEDF) is authorized to discharge treated effluent to the Columbia River by National Pollutant Discharge Elimination System permit WA-002591-7. The letter accompanying the final permit noted the following: EPA recognizes that the TEDF is a new waste treatment facility for which full scale operation and effluent data has not been generated. The permit being issued by EPA contains discharge limits that are intended to force DOE's treatment technology to the limit of its capability.'' Because of the excessively tight limits the permit contains a reopener clause which may allow limits to be renegotiated after at least one year of operation. The restrictions for reopening the permit are as follows: (1) The permittee has properly operated and maintained the TEDF for a sufficient period to stabilize treatment plant operations, but has nevertheless been unable to achieve the limitation specified in the permit. (2) Effluent data submitted by the permittee supports the effluent limitation modifications(s). (3) The permittee has submitted a formal request for the effluent limitation modification(s) to the Director. The purpose of this document is to guide plant operations for approximately one year to ensure appropriate data is collected for reopener negotiations

Evaluation of multiple emission point facilities

International Nuclear Information System (INIS)

Miltenberger, R.P.; Hull, A.P.; Strachan, S.; Tichler, J.

1988-01-01

In 1970, the New York State Department of Environmental Conservation (NYSDEC) assumed responsibility for the environmental aspect of the state's regulatory program for by-product, source, and special nuclear material. The major objective of this study was to provide consultation to NYSDEC and the US NRC to assist NYSDEC in determining if broad-based licensed facilities with multiple emission points were in compliance with NYCRR Part 380. Under this contract, BNL would evaluate a multiple emission point facility, identified by NYSDEC, as a case study. The review would be a nonbinding evaluation of the facility to determine likely dispersion characteristics, compliance with specified release limits, and implementation of the ALARA philosophy regarding effluent release practices. From the data collected, guidance as to areas of future investigation and the impact of new federal regulations were to be developed. Reported here is the case study for the University of Rochester, Strong Memorial Medical Center and Riverside Campus

TU-G-BRCD-01: Will the High Cost of Proton Therapy Facilities Limit the Availability of Proton Therapy Treatment?

Science.gov (United States)

Maughan, R

2012-06-01

The potential dose distribution advantages associated with proton therapy, and particularly with pencil beam scanning (PBS) techniques, have lead to considerable interest in this modality in recent years. However, the large capital expenditure necessary for such a project requires careful financial consideration and business planning. The complexity of the beam delivery systems impacts the capital expenditure and the PBS only systems presently being advocated can reduce these costs. Also several manufacturers are considering "one-room" facilities as less expensive alternatives to multi-room facilities. This presentation includes a brief introduction to beam delivery options (passive scattering, uniform and modulated scanning) and some of the new technologies proposed for providing less expensive proton therapy systems. Based on current experience, data on proton therapy center start-up costs, running costs and the financial challenges associated with making this highly conformal therapy more widely available will be discussed. Issues associated with proton therapy implementation that are key to project success include strong project management, vendor cooperation and collaboration, staff recruitment and training. Time management during facility start up is a major concern, particularly in multi-room systems, where time must be shared between continuing vendor system validation, verification and acceptance testing, and user commissioning and patient treatments. The challenges associated with facility operation during this period and beyond are discussed, focusing on how standardization of process, downtime and smart scheduling can influence operational efficiency. 1. To understand the available choices for proton therapy facilities, the different beam delivery systems and the financial implications associated with these choices. 2. To understand the key elements necessary for successfully implementing a proton therapy program. 3. To understand the challenges

Construction of testing facilities and verifying tests of a 22.9 kV/630 A class superconducting fault current limiter

Science.gov (United States)

Yim, S.-W.; Yu, S.-D.; Kim, H.-R.; Kim, M.-J.; Park, C.-R.; Yang, S.-E.; Kim, W.-S.; Hyun, O.-B.; Sim, J.; Park, K.-B.; Oh, I.-S.

2010-11-01

We have constructed and completed the preparation for a long-term operation test of a superconducting fault current limiter (SFCL) in a Korea Electric Power Corporation (KEPCO) test grid. The SFCL with rating of 22.9 kV/630 A, 3-phases, has been connected to the 22.9 kV test grid equipped with reclosers and other protection devices in Gochang Power Testing Center of KEPCO. The main goals of the test are the verification of SFCL performance and protection coordination studies. A line-commutation type SFCL was fabricated and installed for this project, and the superconducting components were cooled by a cryo-cooler to 77 K in the sub-cooled liquid nitrogen pressurized by 3 bar of helium gas. The verification test includes un-manned - long-term operation with and without loads and fault tests. Since the test site is 170 km away from the laboratory, we will adopt the un-manned operation with real-time remote monitoring and controlling using high speed internet. For the fault tests, we will apply fault currents up to around 8 kArms to the SFCL using an artificial fault generator. The fault tests may allow us not only to confirm the current limiting capability of the SFCL, but also to adjust the SFCL - recloser coordination such as resetting over-current relay parameters. This paper describes the construction of the testing facilities and discusses the plans for the verification tests.

Construction of testing facilities and verifying tests of a 22.9 kV/630 A class superconducting fault current limiter

International Nuclear Information System (INIS)

Yim, S.-W.; Yu, S.-D.; Kim, H.-R.; Kim, M.-J.; Park, C.-R.; Yang, S.-E.; Kim, W.-S.; Hyun, O.-B.; Sim, J.; Park, K.-B.; Oh, I.-S.

2010-01-01

We have constructed and completed the preparation for a long-term operation test of a superconducting fault current limiter (SFCL) in a Korea Electric Power Corporation (KEPCO) test grid. The SFCL with rating of 22.9 kV/630 A, 3-phases, has been connected to the 22.9 kV test grid equipped with reclosers and other protection devices in Gochang Power Testing Center of KEPCO. The main goals of the test are the verification of SFCL performance and protection coordination studies. A line-commutation type SFCL was fabricated and installed for this project, and the superconducting components were cooled by a cryo-cooler to 77 K in the sub-cooled liquid nitrogen pressurized by 3 bar of helium gas. The verification test includes un-manned - long-term operation with and without loads and fault tests. Since the test site is 170 km away from the laboratory, we will adopt the un-manned operation with real-time remote monitoring and controlling using high speed internet. For the fault tests, we will apply fault currents up to around 8 kA rms to the SFCL using an artificial fault generator. The fault tests may allow us not only to confirm the current limiting capability of the SFCL, but also to adjust the SFCL - recloser coordination such as resetting over-current relay parameters. This paper describes the construction of the testing facilities and discusses the plans for the verification tests.

Effectiveness of interim remedial actions at a radioactive waste facility

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

1989-01-01

Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

The environment and urban adolescents' use of recreational facilities for physical activity: a qualitative study.

Science.gov (United States)

Ries, Amy V; Gittelsohn, Joel; Voorhees, Carolyn C; Roche, Kathleen M; Clifton, Kelly J; Astone, Nan M

2008-01-01

Investigate environmental factors influencing the use of recreational facilities for physical activity by urban African-American adolescents. Qualitative in-depth interviews and direct observation. Two public high schools and 24 public recreational facilities in Baltimore, Maryland. Forty-eight African-American adolescents aged 14 to 18 years. Data from 48 in-depth interviews and 26 observations were coded using NVivo software and analyzed using the constant comparative method. Facility use is influenced by characteristics of the physical, social, organizational, and economic environments. Adolescents are attracted to low-cost, well-maintained facilities that offer preferred activities and that are within close proximity to home. Adolescents with limited access to facilities use alternative play spaces, like the streets or vacant lots, where they risk injury from falling or being hit by a car. They are drawn to facilities where they find active adolescents, and they avoid those where young people are engaged in drug or gang activity. Concerns about facility safety largely determine use, particularly for adolescent girls. Previous research points to the importance of increasing facility availability as a means of promoting physical activity, particularly in minority communities in which availability is disproportionately limited. This study shows that, while availability is important, additional facility characteristics should be considered when using environmental change to promote facility use for physical activity.

78 FR 75679 - Position Limits for Derivatives

Science.gov (United States)

2013-12-12

... practices for compliance with Designated Contract Market (``DCM'') core principle 5 and Swap Execution Facility (``SEF'') core principle 6 in respect of exchange- set speculative position limits and position... To Become Guidance on and Acceptable Practices for Compliance with DCM Core Principle 5 3. The CFTC...

Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Sung, Suk Hyun; Jeong, Yi Yeong; Kim, Ki Hong

2008-01-01

The purpose of Radioactive Waste Acceptance Criteria (WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

International safeguards for a modern MOX [mixed-oxide] fuel fabrication facility

International Nuclear Information System (INIS)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating σ/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials

International safeguards for a modern MOX (mixed-oxide) fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating sigma/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials.

Approach to DOE threshold guidance limits

International Nuclear Information System (INIS)

Shuman, R.D.; Wickham, L.E.

1984-01-01

The need for less restrictive criteria governing disposal of extremely low-level radioactive waste has long been recognized. The Low-Level Waste Management Program has been directed by the Department of Energy (DOE) to aid in the development of a threshold guidance limit for DOE low-level waste facilities. Project objectives are concernd with the definition of a threshold limit dose and pathway analysis of radionuclide transport within selected exposure scenarios at DOE sites. Results of the pathway analysis will be used to determine waste radionuclide concentration guidelines that meet the defined threshold limit dose. Methods of measurement and verification of concentration limits round out the project's goals. Work on defining a threshold limit dose is nearing completion. Pathway analysis of sanitary landfill operations at the Savannah River Plant and the Idaho National Engineering Laboratory is in progress using the DOSTOMAN computer code. Concentration limit calculations and determination of implementation procedures shall follow completion of the pathways work. 4 references

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

International Nuclear Information System (INIS)

1996-06-01

Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

A flexible testing facility for high-power targets T-MIF

International Nuclear Information System (INIS)

Fusco, Y.; Samec, K.; Behzad, M.; Kadi, Y.

2015-01-01

A dedicated material test irradiation facility is being proposed. The testing station will allow critical issues concerning materials under irradiation to be addressed, such as the impact of proton beam irradiation, neutron irradiation, liquid metal corrosion and temperature. The material samples to be investigated in such a facility will be subjected to tensile stress, either constant or cyclical. The facility may also be used for sensor development under irradiation and isotope production. The goal of the current work is to propose a facility that is sufficiently versatile and compact so that it may be transported and used in different laboratories. The power is limited to 100 kW. The general aspect of the proposed irradiation facility is a cube, 2 metres deep and comprising within it all the necessary systems. The interface to the laboratory is limited to the coolant connections, the secondary circuit, the electric energy supply and the signals from the instrumentation. The liquid metal target placed in the centre of the facility contains the samples which are subjected to a proton beam, creating irradiation damage directly through protons or indirectly through neutrons created by spallation of the surrounding liquid metal by the incoming protons. The design of the target is based upon the EURISOL target. The same beam window design is used, albeit stretched horizontally to adopt an elliptical section which is compatible with the shape of the beam used to irradiate the samples. The liquid metal in the target is re-circulated by an electromagnetic pump that drives the liquid metal through a heat exchanger located at the top of the facility, the position of which was chosen to encourage natural circulation. The heat exchanger is made up of two separate parts which allow the primary and secondary circuit to separate cleanly

Investigation of analytical and experimental behavior of nuclear facility ventilation systems

International Nuclear Information System (INIS)

Smith, P.R.; Ricketts, C.I.; Andrae, R.W.; Bolstad, J.W.; Horak, H.L.; Martin, R.A.; Tang, P.K.; Gregory, W.S.

1979-01-01

The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting accident-induced gas dynamics and test facilities to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. A unique test facility and recently obtained structural limits for high efficiency particulate air filters are reported

10 CFR 51.76 - Draft environmental impact statement-limited work authorization.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Draft environmental impact statement-limited work...-Regulations Implementing Section 102(2) Draft Environmental Impact Statements-Production and Utilization Facilities § 51.76 Draft environmental impact statement—limited work authorization. The NRC will prepare a...

Ultraviolet Free Electron Laser Facility preliminary design report

Energy Technology Data Exchange (ETDEWEB)

Ben-Zvi, I. (ed.)

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA).

Ultraviolet Free Electron Laser Facility preliminary design report

International Nuclear Information System (INIS)

Ben-Zvi, I.

1993-02-01

This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA)

Timeliness of abnormal screening and diagnostic mammography follow-up at facilities serving vulnerable women.

Science.gov (United States)

Goldman, L Elizabeth; Walker, Rod; Hubbard, Rebecca; Kerlikowske, Karla

2013-04-01

Whether timeliness of follow-up after abnormal mammography differs at facilities serving vulnerable populations, such as women with limited education or income, in rural areas, and racial/ethnic minorities is unknown. We examined receipt of diagnostic evaluation after abnormal mammography using 1998-2006 Breast Cancer Surveillance Consortium-linked Medicare claims. We compared whether time to recommended breast imaging or biopsy depended on whether women attended facilities serving vulnerable populations. We characterized a facility by the proportion of mammograms performed on women with limited education or income, in rural areas, or racial/ethnic minorities. We analyzed 30,874 abnormal screening examinations recommended for follow-up imaging across 142 facilities and 10,049 abnormal diagnostic examinations recommended for biopsy across 114 facilities. Women at facilities serving populations with less education or more racial/ethnic minorities had lower rates of follow-up imaging (4%-5% difference, Pfacilities serving more rural and low-income populations had lower rates of biopsy (4%-5% difference, Pfacilities serving vulnerable populations had longer times until biopsy than those at facilities serving nonvulnerable populations (21.6 vs. 15.6 d; 95% confidence interval for mean difference 4.1-7.7). The proportion of women receiving recommended imaging within 11 months and biopsy within 3 months varied across facilities (interquartile range, 85.5%-96.5% for imaging and 79.4%-87.3% for biopsy). Among Medicare recipients, follow-up rates were slightly lower at facilities serving vulnerable populations, and among those women who returned for diagnostic evaluation, time to follow-up was slightly longer at facilities that served vulnerable population. Interventions should target variability in follow-up rates across facilities, and evaluate effectiveness particularly at facilities serving vulnerable populations.

findings from audits of specialist treatment facilities

African Journals Online (AJOL)

Adele

population groups in terms of the allocation of resources to, and the quality of ... facilities has decreased in real terms, limiting their treatment capacity and their capacity ... fordable, and accessible substance abuse treatment services1, ... The terms “white, black, asian/indian, and coloured” refer to demographic markers and ...

ADA Compliance and Accessibility of Fitness Facilities in Western Wisconsin.

Science.gov (United States)

Johnson, Marquell J; Stoelzle, Hannah Y; Finco, Kristi L; Foss, Sadie E; Carstens, Katie

2012-01-01

The study expands the research on fitness facility accessibility by determining how compliant fitness facilities in rural western Wisconsin were with Title III of the Americans with Disabilities Act (ADA). Comparisons were made with 4 other studies that were conducted in different geographical regions. The study also examined fitness professionals' disability knowledge and awareness. An ADA fitness facility compliance instrument and a fitness professional disability awareness survey were used. Direct observation and physical measurements were taken during on-site visits to 16 of 36 eligible fitness facilities in rural western Wisconsin. Ten fitness professionals from participating facilities completed an online survey. Frequencies were used to analyze the results. None of the participating facilities were in 100% compliance with ADA. Customer service desk (84%) and path of travel throughout the facility (72%) were the highest compliance areas. Telephone (6%) and locker rooms (32%) were the lowest compliance areas. No fitness professional was trained in wheelchair transfers and very few had received training in providing services to individuals with disabilities. Fitness facility accessibility remains a concern nationally. Continued efforts need to be made to raise the awareness of ADA compliance among fitness professionals across the United States, especially in rural areas where fitness facility availability is limited.

Preliminary site requirements and considerations for a monitored retrievable storage facility

International Nuclear Information System (INIS)

1991-08-01

This report presents preliminary requirements and considerations for siting monitored retrievable storage (MRS) facility. It purpose is to provide guidance for assessing the technical suitability of potential sites for the facility. It has been reviewed by the NRC staff, which stated that this document is suitable for ''guidance in making preliminary determinations concerning MRS site suitability.'' The MRS facility will be licensed by the US Nuclear Regulatory Commission. It will receive spent fuel from commercial nuclear power plants and provide a limited amount of storage for this spent fuel. When a geologic repository starts operations, the MRS facility will also stage spent-fuel shipments to the repository. By law, storage at the MRS facility is to be temporary, with permanent disposal provided in a geologic repository to be developed by the DOE

Design and operation of radiation facilities

International Nuclear Information System (INIS)

Gay, H.G.

1983-01-01

The design, manufacture, and operation of Cobalt-60 Radiation Processing Facilities is a well established technology. However, the products requiring radiation processing are constantly increasing. Product and dose variations create different requirements in the irradiator design. Several basic design concepts which have been developed and installed by Atomic Energy of Canada Limited are discussed. Irradiators are most efficient when designed to handle a limited product density range at an established dose. Requirements for irradiators to process a multitude of different products at different doses leads to a reduction of irradiator efficiency with resultant increase in processing costs

Innovative Procurement and Partnerships in Facilities Management

DEFF Research Database (Denmark)

Jensen, Per Anker

2010-01-01

strong requirements on the management style and company culture. Limitations of the research: The research is only based on two case studies, which obviously limits the possibility to generalize the results. Practical applications: The research presents two specific examples of innovative procurement......Aim: The aim of the paper is to present, analyse and identify learning from two case studies of innovative procurement in Facilities Management (FM) concerning the establishments of partnerships between clients and providers. Approach and methodology: A major study of FM best practice covering 36...

40 CFR 273.53 - Storage time limits.

Science.gov (United States)

2010-07-01

...) STANDARDS FOR UNIVERSAL WASTE MANAGEMENT Standards for Universal Waste Transporters § 273.53 Storage time limits. (a) A universal waste transporter may only store the universal waste at a universal waste transfer facility for ten days or less. (b) If a universal waste transporter stores universal waste for...

DOT for patients with limited access to health care facilities in a hill district of eastern Nepal.

Science.gov (United States)

Wares, D F; Akhtar, M; Singh, S

2001-08-01

The hill district in Nepal, where access to health care facilities is difficult. To compare results before and after a decentralised directly observed treatment (DOT) intervention. Prospective study of patients registered in Dhankuta district, Nepal, 1996-1999. Patients received their intensive phase treatment under health worker supervision via one of three DOT options: 1) ambulatory from the peripheral government health facilities; 2) ambulatory from an international non-governmental organisation (INGO) TB clinic in district centre; or 3) resident in INGO TB hostel in district centre. Historical data from 1995-1996, with unsupervised short-course chemotherapy, were used for comparison. Of 307 new cases, respectively 126 (41%), 86 (28%) and 95 (31%) took their intensive phase treatment via options 1, 2 and 3. Smear conversion (at 2 months) and cure rates in new smear-positive pulmonary tuberculosis cases were respectively 81.6% (vs. 58.8% historical, P = 0.001) and 84.9% (vs. 76.7% historical, P = 0.03). Overall costs to the INGO provider fell by 7%, mainly as a result of staffing reductions in the INGO services made possible by rationalisation with government services during the intervention. By offering varied DOT delivery routes, including an in-patient option, satisfactory results are possible with DOT even in areas where access to health care facilities is difficult. Provision of in-patient care via an INGO TB hostel allowed a significant proportion of new cases (31%) to receive their intensive phase treatment who otherwise may have had difficulty accessing treatment, due either to the distance to the nearest health facility or to disease severity. Substitution of government hospital beds or local hotel beds for the INGO hostel beds may allow the model to be reproduced elsewhere in similar geographical conditions in Nepal, but further studies should be performed in a non-INGO supported district beforehand.

Hazard Classification for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

Final hazard classification for the 300 Area N Reactor fuel storage facility resulted in the assignment of Nuclear Facility Hazard Category 3 for the uranium metal fuel and feed material storage buildings (303-A, 303-B, 303-G, 3712, and 3716). Radiological for the residual uranium and thorium oxide storage building and an empty former fuel storage building that may be used for limited radioactive material storage in the future (303-K/3707-G, and 303-E), and Industrial for the remainder of the Fuel Supply Shutdown buildings (303-F/311 Tank Farm, 303-M, 313-S, 333, 334 and Tank Farm, 334-A, and MO-052)

Facility effluent monitoring plan determinations for the 400 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-09-01

This Facility Effluent Monitoring Plan determination resulted from an evaluation conducted for the Westinghouse Hanford Company 400 Area facilities on the Hanford Site. The Facility Effluent Monitoring Plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans. Two major Westinghouse Hanford Company facilities in the 400 Area were evaluated: the Fast Flux Test Facility and the Fuels Manufacturing and examination Facility. The determinations were prepared by Westinghouse Hanford Company. Of these two facilities, only the Fast Flux Test Facility will require a Facility Effluent Monitoring Plan. 7 refs., 5 figs., 4 tabs

Cold Vacuum Drying facility fire protection system design description

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) fire protection system (FPS). The FPS provides fire detection, suppression, and loss limitation for the CVDF structure, personnel, and in-process spent nuclear fuel. The system provides, along with supporting interfacing systems, detection, alarm, and activation instrumentation and controls, distributive piping system, isolation valves, and materials and controls to limit combustibles and the associated fire loadings

Basic design study on plutonium electro-refining facility of oxide fuel pyroelectrochemical reprocessing

International Nuclear Information System (INIS)

Ogura, Kenji; Kondo, Naruhito; Kamoshida, Hiroshi; Omori, Takashi

2001-02-01

The test facility basic design, utility necessity and estimation cost of the Oxide Fuel Pyro-process for the use of Chemical Processing Facility (CPF) of JNC have been studied with the information of the previous year concept study and the additional conditions. Drastic down sizing design change or the building reconstruction is necessary to place the Oxide Fuel Pyro-process Facility in the laboratory ''C'', because it is not possible to reserve enough maintenance space and the weight of the facility is over the acceptable limit of the building. A further study such as facility down sizing, apparatus detail design and experiment detail process treatment has to be planned. (author)

On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

International Nuclear Information System (INIS)

1994-01-01

The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

Radiological and environmental surveillance in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Khan, A.H.; Sahoo, S.K.; Tripathi, R.M.

2004-01-01

This paper describes the occupational and environmental radiological safety measures associated with the operations of front end nuclear fuel cycle. Radiological monitoring in the facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised

Optimization of radiation protection in gamma radiography facilities

International Nuclear Information System (INIS)

Antonio Filho, Joao

1999-01-01

To determine optimized dose limits for workers, a study of optimization of radiation protection was undertaken in gamma radiography facilities closed, using the Technique Multiple Attributes Utility Analysis. A total of 217 protection options, distributed in 34 irradiation scenarios for tree facility types ( fixed open, moveable and closed (bunker) were analyzed. In the determination of the optimized limit dose, the following attributes were considered; costs of the protection barriers, costs attributed to the biological detriment for different alpha (the reference value of unit collective dose), size of the isolation area, constrained limits dose of annual individual equivalent doses and collective dose. The variables studied in the evaluation included: effective work load, type and activity of the sources of radiation ( 192 Ir and 60 Co), source-operator distance related to the characteristic of the length of the command cable and the guide tube, type and thickness of the materials used in the protection barriers (concrete, barite, ceramic, lead, steel alloy and tungsten). The optimal analytic solutions obtained in the optimization process that resulted in the indication of the optimized dose limit were determined by means of a sensitivity analysis and by direct and logic evaluations, thus, independent of the values of the monetary coefficient attributed to the biological detriment, of the annual interest rate applied to the protection cost and of the type of installation studied, it was concluded that the primary limit of annual equivalent dose for workers (now 50 mSv) can be easily reduced to an optimized annual dose limit of 5 mSv. (author)

Waste management facility acceptance - some findings

International Nuclear Information System (INIS)

Sigmon, B.

1987-01-01

Acceptance of waste management facilities remains a significant problem, despite years of efforts to reassure potential host communities. The tangible economic benefits from jobs, taxes, and expenditures are generally small, while the intangible risks of environmental or other impacts are difficult to evaluate and understand. No magic formula for winning local acceptance has yet been found. Limited case study and survey work does suggest some pitfalls to be avoided and some directions to be pursued. Among the most significant is the importance that communities place on controlling their own destiny. Finding a meaningful role for communities in the planning and operation of waste management facilities is a challenge that would-be developers should approach with the same creativity that characterizes their technical efforts

Recommissioning the K-1600 seismic test facility

International Nuclear Information System (INIS)

Wynn, C.C.; Brewer, D.W.

1991-01-01

The Center for Natural Phenomena Engineering (CNPE) was established under the technical direction of Dr. James E. Beavers with a mandate to assess, by analyses and testing, the seismic capacity of building structures that house sensitive processes at the Oak Ridge Y-12 Plant. This mandate resulted in a need to recommission the K-1600 Seismic Test Facility (STF) at the Oak Ridge K-25 Site, which had been shutdown for 6 years. This paper documents the history of the facility and gives some salient construction, operation, and performance details of its 8-ton, 20-foot center of gravity payload biaxial seismic simulator. A log of activities involved in the restart of this valuable resource is included as Table 1. Some of the problems and solutions associated with recommissioning the facility under a relatively limited budget are included. The unique attributes of the shake table are discussed. The original mission and performance requirements are compared to current expanded mission and performance capabilities. Potential upgrades to further improve the capabilities of the test facility as an adjunct to the CNPE are considered. Additional uses for the facility are proposed, including seismic qualification testing of devices unique to enrichment technologies and associated hazardous waste treatment and disposal processes. In summary, the STF restart in conjunction with CNPE has added a vital, and unique facility to the list of current national resources utilized for earthquake engineering research and development

Potable Water Treatment Facility General Permit (PWTF GP) ...

Science.gov (United States)

2017-08-28

The Final PWTF GP establishes permit eligibility conditions, Notice of Intent (NOI) requirements, effluent limitations, standards, prohibitions, and best management practices for facilities that discharge to waters in the Commonwealth of Massachusetts (including both Commonwealth and Indian country lands) and the State of New Hampshire.

Facility-level association of preoperative stress testing and postoperative adverse cardiac events.

Science.gov (United States)

Valle, Javier A; Graham, Laura; Thiruvoipati, Thejasvi; Grunwald, Gary; Armstrong, Ehrin J; Maddox, Thomas M; Hawn, Mary T; Bradley, Steven M

2018-06-22

Despite limited indications, preoperative stress testing is often used prior to non-cardiac surgery. Patient-level analyses of stress testing and outcomes are limited by case mix and selection bias. Therefore, we sought to describe facility-level rates of preoperative stress testing for non-cardiac surgery, and to determine the association between facility-level preoperative stress testing and postoperative major adverse cardiac events (MACE). We identified patients undergoing non-cardiac surgery within 2 years of percutaneous coronary intervention in the Veterans Affairs (VA) Health Care System, from 2004 to 2011, facility-level rates of preoperative stress testing and postoperative MACE (death, myocardial infarction (MI) or revascularisation within 30 days). We determined risk-standardised facility-level rates of stress testing and postoperative MACE, and the relationship between facility-level preoperative stress testing and postoperative MACE. Among 29 937 patients undergoing non-cardiac surgery at 131 VA facilities, the median facility rate of preoperative stress testing was 13.2% (IQR 9.7%-15.9%; range 6.0%-21.5%), and 30-day postoperative MACE was 4.0% (IQR 2.4%-5.4%). After risk standardisation, the median facility-level rate of stress testing was 12.7% (IQR 8.4%-17.4%) and postoperative MACE was 3.8% (IQR 2.3%-5.6%). There was no correlation between risk-standardised stress testing and composite MACE at the facility level (r=0.022, p=0.81), or with individual outcomes of death, MI or revascularisation. In a national cohort of veterans undergoing non-cardiac surgery, we observed substantial variation in facility-level rates of preoperative stress testing. Facilities with higher rates of preoperative stress testing were not associated with better postoperative outcomes. These findings suggest an opportunity to reduce variation in preoperative stress testing without sacrificing patient outcomes. © Article author(s) (or their employer(s) unless otherwise

Operational Circular nr 5 - October 2000 USE OF CERN COMPUTING FACILITIES

CERN Multimedia

Division HR

2000-01-01

New rules covering the use of CERN Computing facilities have been drawn up. All users of CERN’s computing facilites are subject to these rules, as well as to the subsidiary rules of use. The Computing Rules explicitly address your responsibility for taking reasonable precautions to protect computing equipment and accounts. In particular, passwords must not be easily guessed or obtained by others. Given the difficulty to completely separate work and personal use of computing facilities, the rules define under which conditions limited personal use is tolerated. For example, limited personal use of e-mail, news groups or web browsing is tolerated in your private time, provided CERN resources and your official duties are not adversely affected. The full conditions governing use of CERN’s computing facilities are contained in Operational Circular N° 5, which you are requested to read. Full details are available at : http://www.cern.ch/ComputingRules Copies of the circular are also available in the Divis...

Optimization (ALARA) of radiation protection at Department of Energy facilities

International Nuclear Information System (INIS)

Weadock, A.A.; Jones, C.R.

1992-01-01

Maintaining worker and public exposures As Low As Reasonably Achievable (ALARA) is a key objective of the Department of Energy (DOE). Responsibility for occupational ALARA program policy and guidance resides within the DOE Office of Health. Current Office of Health initiatives related to ALARA include the development of additional regulatory guidance related to ALARA program implementation at DOE contractor facilities, the review of ALARA program status at various facilities and the production of technical reports summarizing this status, and the support of various mechanisms to improve communication among the DOE ALARA community. The Office of Health also monitors revisions to radiogenic risk estimates and radiation protection recommendations to evaluate adequacy of current DOE limits and impacts of potentially revised limits. (author)

Radiation protection problems by the operation of the cyclotron facility

International Nuclear Information System (INIS)

Durcik, M.; Nikodemova, D.

1998-01-01

The Cyclotron Center in Bratislava will consist of two cyclotrons. First - cyclotron DC-72 with maximal energy of 72 MV for protons for making experiments, for teaching process, for radioisotope production as 123 I and for neutron and proton therapy. Second - compact cyclotron with maximal proton energy of 18 MeV will be used for radioisotopes production for medical diagnosis as 1 *F (fluorodeoxyglucose), 81 Rb/ 81 Kr generator. This paper deals with the radiation protection problems by the operation of tis cyclotron facility as radiation protection of workers, monitoring plan, ventilation, safety lock and limitation and radiation monitoring. For proposed and continuing practices at the accelerator facility, the following general principles have to be fulfilled: (1) practices should produce sufficient benefit to offset the radiation detriment they case (justification); (2) the magnitude of the individual doses should be kept as low as achievable (optimization of protection); (3) individual exposures are subject to dose limits and some control of risk from potential exposures (dose and risk limits)

Technical specifications for the Oak Ridge Critical Experiments Facility

International Nuclear Information System (INIS)

Stinnett, R.M.

1986-01-01

These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

The problem of bias when nursing facility staff administer customer satisfaction surveys.

Science.gov (United States)

Hodlewsky, R Tamara; Decker, Frederic H

2002-10-01

Customer satisfaction instruments are being used with increasing frequency to assess and monitor residents' assessments of quality of care in nursing facilities. There is no standard protocol, however, for how or by whom the instruments should be administered when anonymous, written responses are not feasible. Researchers often use outside interviewers to assess satisfaction, but cost considerations may limit the extent to which facilities are able to hire outside interviewers on a regular basis. This study was designed to investigate the existence and extent of any bias caused by staff administering customer satisfaction surveys. Customer satisfaction data were collected in 1998 from 265 residents in 21 nursing facilities in North Dakota. Half the residents in each facility were interviewed by staff members and the other half by outside consultants; scores were compared by interviewer type. In addition to a tabulation of raw scores, ordinary least-squares analysis with facility fixed effects was used to control for resident characteristics and unmeasured facility-level factors that could influence scores. Significant positive bias was found when staff members interviewed residents. The bias was not limited to questions directly affecting staff responsibilities but applied across all types of issues. The bias was robust under varying constructions of satisfaction and dissatisfaction. A uniform method of survey administration appears to be important if satisfaction data are to be used to compare facilities. Bias is an important factor that should be considered and weighed against the costs of obtaining outside interviewers when assessing customer satisfaction among long term care residents.

Using business intelligence for efficient inter-facility patient transfer.

Science.gov (United States)

Haque, Waqar; Derksen, Beth Ann; Calado, Devin; Foster, Lee

2015-01-01

In the context of inter-facility patient transfer, a transfer operator must be able to objectively identify a destination which meets the needs of a patient, while keeping in mind each facility's limitations. We propose a solution which uses Business Intelligence (BI) techniques to analyze data related to healthcare infrastructure and services, and provides a web based system to identify optimal destination(s). The proposed inter-facility transfer system uses a single data warehouse with an Online Analytical Processing (OLAP) cube built on top that supplies analytical data to multiple reports embedded in web pages. The data visualization tool includes map based navigation of the health authority as well as an interactive filtering mechanism which finds facilities meeting the selected criteria. The data visualization is backed by an intuitive data entry web form which safely constrains the data, ensuring consistency and a single version of truth. The overall time required to identify the destination for inter-facility transfers is reduced from hours to a few minutes with this interactive solution.

Design for the second phase Rokkasho LLW burial facility

International Nuclear Information System (INIS)

Kumata, Tadamasa

1997-01-01

Rokkasho Low Level radioactive Waste management center of Japan Nuclear Fuel Limited (hereafter called JNFL) has been operating for five years and about 90,000 (200 liter) drums have already been buried. Currently, JNFL is planning the 2nd phase of the burial program. The basic design of the new facility has been completed and applied for license additionally. Wastes buried in the 2nd phase facility are mainly dry active wastes from nuclear power plants. Inflammable wastes except for plastics are incinerated before they are disposed, because organic materials can generate gas and their degraded materials affect the distribution coefficients of the radionuclides. Most of the aluminum wastes which can generate hydrogen gas by corrosion are also removed from the waste. The 2nd phase facility accepts metal, plastics and non-flammable wastes. These are solidified with mortar in the 200 liter drums at the power plants. The radioactive inventory of the 2nd phase facility is considered to be as much as that of the 1st phase facility. (author)

Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

International Nuclear Information System (INIS)

Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

1979-01-01

The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

BCP selector valves and limit switches

International Nuclear Information System (INIS)

Rippy, G.L.

1995-01-01

This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the Electrical/Instrumentation systems for the BCP stream function as required by project criteria. Specifically, the test will verify the operation of the solenoid valves and associated limit switches installed for the BCP portion of W-OO7H. This equipment is part of the B-Plant Process Condensate Treatment Facility

Impacts of ramping inflexibility of conventional generators on strategic operation of energy storage facilities

DEFF Research Database (Denmark)

Nasrolahpour, Ehsan; Kazempour, Jalal; Zareipour, Hamidreza

2016-01-01

This paper proposes an approach to assist a pricemaker merchant energy storage facility in making its optimal operation decisions. The facility operates in a pool-based electricity market, where the ramping capability of other resources is limited. Also, wind power resources exist in the system...

Facilities for small-molecule crystallography at synchrotron sources.

Science.gov (United States)

Barnett, Sarah A; Nowell, Harriott; Warren, Mark R; Wilcox, Andrian; Allan, David R

2016-01-01

Although macromolecular crystallography is a widely supported technique at synchrotron radiation facilities throughout the world, there are, in comparison, only very few beamlines dedicated to small-molecule crystallography. This limited provision is despite the increasing demand for beamtime from the chemical crystallography community and the ever greater overlap between systems that can be classed as either small macromolecules or large small molecules. In this article, a very brief overview of beamlines that support small-molecule single-crystal diffraction techniques will be given along with a more detailed description of beamline I19, a dedicated facility for small-molecule crystallography at Diamond Light Source.

Diamond Light Source - A Next Generation SR Facility

International Nuclear Information System (INIS)

Materlik, G.

2004-01-01

After the very successful start and the by now almost 10 years operation of the 3rd generation x-ray sources ESRF, APS and Spring-8 smaller storage rings are being planned and constructed with properties emphasising applications with photon energies around the 10 keV spectral region. In the UK the Government and the medical foundation Wellcome Trust have decided to build the Diamond Light Source Facility in the South of Oxfordshire right next to the Rutherford Appleton Laboratory. The joint venture company Diamond Light Source Limited has been created to plan, construct, and operate this facility. (author)

CIF---Design basis for an integrated incineration facility

International Nuclear Information System (INIS)

Bennett, G.F.

1991-01-01

This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

Closed nuclear facilities in Estonia: developments and problems

International Nuclear Information System (INIS)

Realo, E.; Realo, K.

2000-01-01

At present Estonia has no operating nuclear or a radioactive material production facility. As a legacy of the past the country has become responsible for the decommissioning of two large nuclear cycle facilities of the former USSR. Besides limited funding, major problems arise from deficiencies in legislation, expertise, training and research. International co-operation has been of immense importance to overcome the problems, to establish the national radiation protection and radioactive waste management infrastructure and to launch decommissioning and remediation activities. An overview is given on the status and problems. Copyright (2000) Australasian Radiation Protection Society Inc

On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

International Nuclear Information System (INIS)

1989-01-01

The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

Factors That May Tend to Limit the Religious Education of Recruits

Science.gov (United States)

1992-05-01

chaplains also mentioned the following as tending to limit recruit religious education : (1) a lack of adequate chapel facilities , (2) not enough chaplains...inadequate chapel facilities at Recruit Training Command for recruit worship and religious education . This is a particular concern for the Catholic and... education . Procedures Data was gathered by distributing questionnaires to members of Division Six on October 22-23, 1991. Participation was voluntary

Engineering report for interim solids removal modifications of the Steam Plant Wastewater Treatment Facility

International Nuclear Information System (INIS)

1995-04-01

The Steam Plant Wastewater Treatment Facility (SPWTF) treats wastewater from the Y-12 Plant coal yard, steam plant, and water demineralizer facility. The facility is required to comply with National Pollutant Discharge Elimination System (NPDES) standards prior to discharge to East Fork Poplar Creek (EFPC). The existing facility was designed to meet Best Available Technology (BAT) standards and has been in operation since 1988. The SPWTF has had intermittent violations of the NPDES permit primarily due to difficulties in complying with the limit for total iron of 1.0 ppM. A FY-1997 Line Item project, SPWTF Upgrades, is planned to improve the capabilities of the SPWTF to eliminate non-compliances with the permit limits. The intent of the Interim Solids Removal Modification project is to improve the SPWTF effluent quality and to provide pilot treatment data to assist in the design and implementation of the SPWTF Upgrades Line Item Project

Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

1977-01-01

The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

Dance Facilities.

Science.gov (United States)

Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

Facilities inventory protection for nuclear facilities

International Nuclear Information System (INIS)

Schmitt, F.J.

1989-01-01

The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

Evaluation of electronic speed limit signs on US 30.

Science.gov (United States)

2011-09-01

This study documents the speed : reduction impacts of two dynamic, : electronic school zone speed limit signs : at United Community Schools between : Ames and Boone, Iowa. The school : facility is situated along US Highway 30, : a rural four-lane div...

Limits for the release of uranium compounds to the environment

International Nuclear Information System (INIS)

Lopez, F.; Ferruz, P.; Aguayo, A.

1987-01-01

A conservative criteria to be be followed by a Regulatory Body, in order to provide the limits of radioactive material release in the environment, When all the parameters are not available for the optimization of radiation protection is presented. This criteria can be applied to stablishment of radioactive release limits for uranium compounds from the nuclear fuel cycle facilities. (author)

Reed Reactor Facility final report, September 1, 1994--August 31, 1995

International Nuclear Information System (INIS)

1997-01-01

This report covers the period from September 1, 1994 to August 31, 1995. Information contained in this report is intended to fulfill several purposes including the reporting requirements of the US Nuclear Regulatory Commission (USNRC), the US Department of Energy (USDOE), and the Oregon Department of Energy (ODOE). Highlights of the last year include: student participation in the program is very high; the facility has been extraordinarily successful in obtaining donated equipment from Portland General Electric, US Department of Energy, Precision Castparts, Tektronix, and other sources; the facility is developing more paid work. There were 1,115 visits of the Reactor Facility by individuals during the year. Most of these visitors were students in classes at Reed College or area universities, colleges, and high schools. During the year, the reactor was operated 225 separate times on 116 days. The total energy production was 24.6 MW-hours. The reactor staff consists of a Director, an Associate Director, a contract Health Physicist, and approximately fifteen Reed College undergraduate students as hourly employees. All radiation exposures to individuals during this year were well below 1% of the federal limits. There were no releases of liquid radioactive material from the facility and airborne releases (primarily 41 Ar) were well within regulatory limits

Reed Reactor Facility final report, September 1, 1994--August 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

This report covers the period from September 1, 1994 to August 31, 1995. Information contained in this report is intended to fulfill several purposes including the reporting requirements of the US Nuclear Regulatory Commission (USNRC), the US Department of Energy (USDOE), and the Oregon Department of Energy (ODOE). Highlights of the last year include: student participation in the program is very high; the facility has been extraordinarily successful in obtaining donated equipment from Portland General Electric, US Department of Energy, Precision Castparts, Tektronix, and other sources; the facility is developing more paid work. There were 1,115 visits of the Reactor Facility by individuals during the year. Most of these visitors were students in classes at Reed College or area universities, colleges, and high schools. During the year, the reactor was operated 225 separate times on 116 days. The total energy production was 24.6 MW-hours. The reactor staff consists of a Director, an Associate Director, a contract Health Physicist, and approximately fifteen Reed College undergraduate students as hourly employees. All radiation exposures to individuals during this year were well below 1% of the federal limits. There were no releases of liquid radioactive material from the facility and airborne releases (primarily {sup 41}Ar) were well within regulatory limits.

Reasons for decision in the matter of TransCanada PipeLines Limited and TransCanada Keystone Pipeline GP Ltd. : application dated 5 June 2006 for leave to transfer pipeline facilities and for a determination of the transfer price

International Nuclear Information System (INIS)

2007-01-01

TransCanada Pipelines Limited and its fully owned subsidiary TransCanada Keystone Pipeline GP Ltd. applied to the National Energy Board in June 2006 for leave to transfer certain pipeline facilities comprising part of TransCanada's mainline natural gas transmission system from TransCanada to Keystone for use in Keystone's proposed new oil pipeline. The transfer would involve the conversion of the facilities from gas service to oil service for use in the Keystone Project. The new oil pipeline would extend from Hardisty Alberta to Wood River and Patoka, Illinois. It would initially provide access for western Canada crude oil producers to the southern Petroleum Administration Defence District (PADD) 2 region of the United states. This is a major refining area which presently has minimal access for western Canada crude oil because of the limited pipeline capacity into the region. The Board held a hearing process to seek the views of interested parties regarding the list of issues that should be considered in dealing with the application. The list of issues included arguments of the Communications, Energy and Paperworkers Union of Canada (CEP) regarding the Board's jurisdiction; regulatory standards; energy supply markets and pipelines; potential impacts of the transfer such as potential costs to gas shippers and the impact of the transfer on mainline operations; and, the transfer at net book value (NBV). This document presented the Board's views on the transfer and the public interest. After considering all factors, the Board approved the sale and purchase of the Facilities from TransCanada to Keystone. The Board further ordered that TransCanada may reduce the mainline rate base by the NBV of the facilities upon their transfer to Keystone, and that Keystone may include the NBV in its pipeline oil plant upon the transfer of the facilities. 5 tabs., 14 figs., 6 appendices

Perceived risk impacts from siting hazardous waste facilities

International Nuclear Information System (INIS)

Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

1992-01-01

This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioecconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts, resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

Perceived risk impacts from siting hazardous waste facilities

International Nuclear Information System (INIS)

Hemphill, R.C.; Edwards, B.K.; Bassett, G.W. Jr.

1992-01-01

This paper describes methods for evaluating perception-based economic impacts resulting from siting hazardous waste facilities. Socioeconomic impact analysis has devoted increasing attention to the potential implications of changed public perceptions of risk due to an activity or situation. This contrasts with traditional socioeconomic impact analysis, which has been limited to measuring direct and indirect consequences of activities, e.g., the employment effects of placing a military base in a specified location. Approaches to estimating economic impacts due to changes in public perceptions are ex ante or ex post. The former predict impacts prior to the construction and operation of a facility, while the later is based on impacts that become evident only when the facility is up and running. The theoretical foundations and practical requirements for demonstrating impacts resulting from the siting of a hazardous facility are described. The theoretical rationale supporting the study of perceived risk research is presented along with discussion of problems that arise in demonstrating the existence and measuring the quantitative importance of economic impacts due to changes in perceived risk. The high-level nuclear waste facility being considered in Nevada is presented as an example in which there is potential for impacts, but where the link between perceived risk and economic conditions has not yet been developed

BRENDA, the GSI RIB-facility

International Nuclear Information System (INIS)

Armbruster, P.

1994-04-01

In 1985 the decision was taken to build the Heavy-Ion Synchrotron (SIS) together with an Experimental Storage Ring (ESR) and a number of experimental facilities. The energy range covered by SIS is the same as the former BEVALAC. Higher beam intensities, better beam quality of SIS, the ESR, and the dedicated experiments allowed to plan an experimental programme going beyond what was done at LBL. The SIS filled to its space charge limit, and fast ramping times (1 s) promised high beam intensities. The field of exotic nuclei and secondary beams has been from the beginning an integral part of the planned new facility. A new high current injector modifying the UNILAC serving now as SIS-injector, a high dose target station at the end of SIS, and a fragment separator (FRS) for relativistic projectile fragments supplying all facilities with secondary beams were endorsed by the Machine- and Programme-Advisory Committees of the SIS-Project. Since 1991 Beams of Relativistic Exotic Nuclei from Darmstadt (BRENDA) are available with moderate intensities. Higher intensities wait for the projected, but not yet built high current injector. I show that interesting experiments were done nevertheless and why we were quite successful even with low intensity secondary beams. (orig.)

Emission of Tc-99 from nuclear facilities

International Nuclear Information System (INIS)

Luxenburger, H.J.; Schuettelkopf, H.; Bohn, B.

1984-11-01

No noticeable Tc-activities are emitted from nuclear power stations. The emissions with the gaseous effluents exceed but rarely the detection limit of 25 nCi/h. Likewise, the emission with the liquid effluents remains below the detection limit of about 0.5 nCi/m 3 . Neither can a remarkable emission be recorded from the facilities of the Central Decontamination Services Department (HDB) of KfK. The emissions from the evaporation system for low level solutions and from the evaporation system for low level solutions and from the incineration facility for solid wastes do not exceed or rarely exceed to a minor extent the detection limit of 0.3 pCi/m 3 waste air. Also with the liquid effluents only minor Tc-amounts are discharged of 0.3 nCi/m 3 at the maximum. In the distillate of the medium level solutions discharged from the Karlsruhe Reprocessing Plant (WAK) to HDB as so-called tritiated water 2 nCi/m 3 Tc-99 at the maximum are contained. Only in the gaseous effluents from the evaporation system for medium level solutions emissions of up to 14 pCi/m 3 can be detected. The detection limits are almost permanently exceeded by the gaseous effluents from WAK. Small amounts of Tc-99 of 7 pCi/m 3 exhaust air at the maximum are released to the environment. However, the amount of Tc accumulated over the sampling period is insignificant from the radioecological point of view. (orig./HP) [de

10 CFR 51.49 - Environmental report-limited work authorization.

Science.gov (United States)

2010-01-01

... reduce environmental impacts. (b) Phased application for limited work authorization and construction... where an environmental impact statement was prepared, but the facility construction was not completed... Commission has previously prepared an environmental impact statement for the construction and operation of a...

Performance of grid-tied PV facilities: A case study based on real data

International Nuclear Information System (INIS)

Díez-Mediavilla, M.; Dieste-Velasco, M.I.; Rodríguez-Amigo, M.C.; García-Calderón, T.; Alonso-Tristán, C.

2013-01-01

Highlights: • A new procedure to analyse the performance of PV facilities is presented. • It only requires limited amounts of data that are easily sourced. • Data sets on production were collected over two complete years. • The transformerless inverter outperforms the isolated inverter. - Abstract: A new procedure is presented to analyse the performance of grid-tied PV facilities. It needs limited amounts of data that are easily sourced and is based on knowledge of the analysed system and its mode of operation. The procedure is applied, in a case study, to compare real PV production at two 100 kW p grid-connected PV installations. Located in the same geographical region, the installation of these two facilities followed the same construction criteria – PV panels, panel support system and wiring – and the facilities were exposed to the same atmospheric temperature and solar radiation. They differ with regard to their inverter technology: one facility uses an inverter with an integrated transformer system and the other uses a transformerless inverter. The results show that the transformerless inverter system performed better than the isolated system by a factor of 1.2%, which, in economic terms, represents more than 2000 €/year

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Preliminary design of a Tandem-Mirror-Next-Step facility

International Nuclear Information System (INIS)

Damm, C.C.; Doggett, J.N.; Bulmer, R.H.

1980-01-01

The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m 3 , with a resultant neutron wall loading of 0.5 MW/m 2 . Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-yang magnets to provide magnetohydrodynamic (MHD) stability and thermal-barrier cells to help achieve a plasma Q of 4.7 (where Q = fusion power/injected power). Neutral beams at energies up to 200 keV are used for plasma heating, fueling, and barrier pumping. Electron cyclotron resonant heating at 50 and 100 GHz is used to control the electron temperature in the barriers. Based on the resulting engineering design, the overall cost of the facility is estimated to be just under $1 billion. Unresolved physics issues include central-cell β-limits against MHD ballooning modes (the assumed reference value of β exceeds the current theory-derived limit), and the removal of thermalized α-particles from the plasma

Managing public acceptance for a new enrichment facility

International Nuclear Information System (INIS)

Boyd, M.

1992-01-01

The Claiborne Enrichment Center has many first associated with it, and a solid nuclear-based community relations experience has been combined with fly-by-the-seat-of-your-pants techniques to successfully introduce a first-of-a-kind facility not only to Louisiana, but also to the US. The project is being developed by Louisiana Energy Services (LES), a limited partnership consisting of Urenco, the European enrichment consortium that operates centrifuge enrichment facilities in the United Kingdom, the Netherlands, and Germany; Fluor Daniel, an internationally known engineering and construction firm; and three utilities - Duke Power, Northern States Power, and Louisiana Power and Light (LP and L). Louisiana Energy will build the nation's first privately owned uranium enrichment facility. It will be the first commercial use of centrifuge technology for enrichment in the US. Some of the community relations challenges the project has had and their solutions are described

Conceptual design of an RTG Shipping and Receiving Facility Transportation System

International Nuclear Information System (INIS)

Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

1994-01-01

The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines

Conceptual design of an RTG shipping and receiving facility transportation system

International Nuclear Information System (INIS)

Black, S.J.; Gentzlinger, R.C.; Lujan, R.E.

1995-01-01

The conceptual design of an RTG Facility Transportation System which is part of the overall RTG Transportation System has been completed and is described in detail. The Facility Transportation System serves to provide locomotion, cooling, shock protection and data acquisition for the RTG package during onloading and offloading sequences. The RTG Shipping ampersand Receiving Facility Transportation System consists of a Transporter Subsystem, a Package Cooling Subsystem, and a Shock Limiting Transit Device Subsystem. The Transporter Subsystem is a custom designed welded steel cart combined with a pneumatically-driven hand tug for locomotion. The Package Cooling Subsystem provides five kilowatts of active liquid cooling via an on-board refrigeration system. The Shock Limiting Transit Device Subsystem consists of a consumable honeycomb anti-shock frame which provides shock protection for the 3855 kg (8500 LB) RTG package. These subsystems have been combined into an integrated system which will facilitate the offloading and onloading of the RTG Package into and out of the semitrailer as well as meet ALARA (as low as reasonably achievable) radiation exposure guidelines. copyright 1995 American Institute of Physics

Hearing in the matter of an application by Erie Shores Wind Farm Limited Partnership for an Order granting leave to construct transmission facilities to connect a wind farm to the transmission facilities of Hydro One Network Inc.[In the matter of the Ontario Energy Board Act, 1998, S.O. 1998, c. 15, Schedule B

Energy Technology Data Exchange (ETDEWEB)

Kaiser, G.; Vlahos, P.; Betts, B.

2005-06-20

This document presents the transcripts of an Ontario Energy Board hearing regarding an application filed by Erie Shores Wind Farm Limited to construct transmission facilities that will connect Erie Shores' wind farm on the north shore of Lake Erie to the transmission facilities of Hydro One Network. This document presents the examinations by representatives of the Board Counsel, Erie Shores Wind Farm Limited Partnership, Hydro One Networks Inc., Ontario's Independent Electricity System Operator and intervenors. Erie Shores is a limited partnership between AIM PowerGen Corporation and Clean Power Income Fund. The proposed wind farm is to be located along the north shore of Lake Erie, covering about 14,000 acres of farmland in the townships of Bayham, Malahide and Norfolk County. It consists of 66 wind turbines with a net output of 99 MW. The construction of transmission facilities would involve the construction of a new transformer station with a 34.5/115 kV transformer, a capacitor bank, switch gear, and space for a future transformer. It would also include a transmission line from the Port Burwell transmission station to Hydro One's circuits at Cranberry Junction near Tillsonburg. Erie Shores also proposes to construct 27 km of the transmission line within the existing Otter Valley utility corridor, 3 km along the active Canadian Pacific Rail corridor, and over certain private lands located south of Tillsonburg Junction. Erie Shores was one of the successful bidders that has entered into a 20-year renewable energy supply contract with the Ontario Electricity Financial Corporation. The Board considers that the project is in the public interest and granted approval for the project, subject to certain conditions regarding communications, monitoring and reporting requirements. 2 refs., 1 appendix.

Facilities & Leadership

Data.gov (United States)

Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

Radiological Dose Calculations And Supplemental Dose Assessment Data For Neshap Compliance For SNL Nevada Facilities 1996.

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-05-01

Operations of Sandia National Laboratories, Nevada (SNL/NV) at the Tonopah Test Range (TTR) resulted in no planned point radiological releases during 1996. Other releases from SNL/NV included diffuse transuranic sources consisting of the three Clean Slate sites. Air emissions from these sources result from wind resuspension of near-surface transuranic contaminated soil particulates. The total area of contamination has been estimated to exceed 20 million square meters. Soil contamination was documented in an aerial survey program in 1977 (EG&G 1979). Surface contamination levels were generally found to be below 400 pCi/g of combined plutonium-238, plutonium-239, plutonium-240, and americium-241 (i.e., transuranic) activity. Hot spot areas contain up to 43,000 pCi/g of transuranic activity. Recent measurements confirm the presence of significant levels of transuranic activity in the surface soil. An annual diffuse source term of 0.39 Ci of transuranic material was calculated for the cumulative release from all three Clean Slate sites. A maximally exposed individual dose of 1.1 mrem/yr at the TTR airport area was estimated based on the 1996 diffuse source release amounts and site-specific meteorological data. A population dose of 0.86 person-rem/yr was calculated for the local residents. Both dose values were attributable to inhalation of transuranic contaminated dust.

High-energy x-ray microscopy of laser-fusion plasmas at the National Ignition Facility

International Nuclear Information System (INIS)

Koch, J.A.; Landen, O.L.; Hammel, B.A.

1997-01-01

Multi-keV x-ray microscopy will be an important laser-produced plasma diagnostic at future megajoule facilities such as the National Ignition Facility (NIF).In preparation for the construction of this facility, we have investigated several instrumentation options in detail, and we conclude that near normal incidence single spherical or toroidal crystals may offer the best general solution for high-energy x-raymicroscopy at NIF and at similar large facilities. Kirkpatrick-Baez microscopes using multi-layer mirrors may also be good secondary options, particularly if apertures are used to increase the band-width limited field of view

Evaluation of {sup 18}F radioactive concentration in exhaust at cyclotron facility at Chosun University

Energy Technology Data Exchange (ETDEWEB)

Jeong, Cheol Ki; Jang, Han; Lee, Goung Jin [Dept. of Nuclear Engineering, Chsoun University, Gwangju (Korea, Republic of)

2016-11-15

the recent prevalence of PET examinations in Korea has led to an increase in the number of cyclotrons. the medical isotope 18F produced in most cyclotron facilities currently operating in Korea is emitted into the environment during the production of [{sup 18}F]FdG, a cancerdiagnosis reagent. the amount of [{sup 18}F]FdG synthesized determines the radioactive concentration of {sup 18}F in the exhaust. at some facilities, this amount temporarily exceeds the emission limit. In this study, we evaluated the {sup 18}F radioactivity concentration in the exhaust from the cyclotron facility at chosun university. the {sup 18}F radioactivity concentration was measured using an air sampler and a hPGe semiconductor detector. the measurements showed that the radioactive concentration of {sup 18}F in the exhaust at the cyclotron facility at Chosun university was the highest during [{sup 18}F]FdG synthesis but remained under the legal limit of 2,000 Bq m{sup -3}.

Contamination limits for real and personal property. Progress report, January--June 1976

International Nuclear Information System (INIS)

Healy, J.W.; Wenzel, W.J.

1976-09-01

Progress is reported on the plutonium in soils limit and on the surface contamination study. The report on the soils limit is being typed in draft form for review at other ERDA facilities. A model for surface contamination was derived and programmed but parametric studies have not yet been done

Gas Test Loop Facilities Alternatives Assessment Report Rev 1

International Nuclear Information System (INIS)

William J. Skerjanc; William F. Skerjanc

2005-01-01

An important task in the Gas Test Loop (GTL) conceptual design was to determine the best facility to serve as host for this apparatus, which will allow fast-flux neutron testing in an existing nuclear facility. A survey was undertaken of domestic and foreign nuclear reactors and accelerator facilities to arrive at that determination. Two major research reactors in the U.S. were considered in detail, the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), each with sufficient power to attain the required neutron fluxes. HFIR routinely operates near its design power limit of 100 MW. ATR has traditionally operated at less than half its design power limit of 250 MW. Both of these reactors should be available for at least the next 30 years. The other major U.S. research reactor, the Missouri University Research Reactor, does not have sufficient power to reach the required neutron flux nor do the smaller research reactors. Of the foreign reactors investigated, BOR-60 is perhaps the most attractive. Monju and BN 600 are power reactors for their respective electrical grids. Although the Joyo reactor is vigorously campaigning for customers, local laws regarding transport of radioactive material mean it would be very difficult to retrieve test articles from either Japanese reactor for post irradiation examination. PHENIX is scheduled to close in 2008 and is fully booked until then. FBTR is limited to domestic (Indian) users only. Data quality is often suspect in Russia. The only accelerator seriously considered was the Fuel and Material Test Station (FMTS) currently proposed for operation at Los Alamos National Laboratory. The neutron spectrum in FMTS is similar to that found in a fast reactor, but it has a pronounced high-energy tail that is atypical of fast fission reactor spectra. First irradiation in the FMTS is being contemplated for 2008. Detailed review of these facilities resulted in the recommendation that the ATR would be the best host for the GTL

Water, sanitation and hygiene in Jordan's healthcare facilities.

Science.gov (United States)

Khader, Yousef Saleh

2017-08-14

Purpose The purpose of this paper is to determine water availability, sanitation and hygiene (WSH) services, and healthcare waste management in Jordan healthcare facilities. Design/methodology/approach In total, 19 hospitals (15 public and four private) were selected. The WSH services were assessed in hospitals using the WSH in health facilities assessment tool developed for this purpose. Findings All hospitals (100 percent) had a safe water source and most (84.2 percent) had functional water sources to provide enough water for users' needs. All hospitals had appropriate and sufficient gender separated toilets in the wards and 84.2 percent had the same in outpatient settings. Overall, 84.2 percent had sufficient and functioning handwashing basins with soap and water, and 79.0 percent had sufficient showers. Healthcare waste management was appropriately practiced in all hospitals. Practical implications Jordan hospital managers achieved major achievements providing access to drinking water and improved sanitation. However, there are still areas that need improvements, such as providing toilets for patients with special needs, establishing handwashing basins with water and soap near toilets, toilet maintenance and providing sufficient trolleys for collecting hazardous waste. Efforts are needed to integrate WSH service policies with existing national policies on environmental health in health facilities, establish national standards and targets for the various healthcare facilities to increase access and improve services. Originality/value There are limited WSH data on healthcare facilities and targets for basic coverage in healthcare facilities are also lacking. A new assessment tool was developed to generate core WSH indicators and to assess WSH services in Jordan's healthcare facilities. This tool can be used by a non-WSH specialist to quickly assess healthcare facility-related WSH services and sanitary hazards in other countries. This tool identified some areas

Managing Waste Inventory and License Limits at the Perma-Fix Northwest Facility to Meet CH2M Hill Plateau Remediation Company (CHPRC) American Recovery and Reinvestment Act (ARRA) Deliverables - 12335

Energy Technology Data Exchange (ETDEWEB)

Moak, Don J.; Grondin, Richard L. [Perma-Fix Environmental Services, Inc. - PESI, Richland, WA 99354 (United States); Triner, Glen C.; West, Lori D. [East Tennessee Materials and Energy Corporation - M and EC, Richland, WA 99354 (United States)

2012-07-01

CH2M Hill Plateau Remediation Company (CHRPC) is a prime contractor to the U.S. Department of Energy (DOE) focused on the largest ongoing environmental remediation project in the world at the DOE Hanford Site Central Plateau, i.e. the DOE Hanford Plateau Remediation Contract. The East Tennessee Materials and Energy Corporation (M and EC); a wholly owned subsidiary of Perma-Fix Environmental Services, Inc. (PESI), is a small business team member to CHPRC. Our scope includes project management; operation and maintenance of on-site storage, repackaging, treatment, and disposal facilities; and on-site waste management including waste receipt from generators and delivery to on-site and off-site treatment, storage, and disposal facilities. As part of this scope, M and EC staffs the centralized Waste Support Services organization responsible for all waste characterization and acceptance required to support CHPRC and waste generators across the Hanford Site. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 cubic meters (m{sup 3}) of legacy waste was defined as 'no-path-forward waste'. A significant portion of this waste (7,650 m{sup 3}) comprised wastes with up to 50 grams of special nuclear materials (SNM) in oversized packages recovered during retrieval operations and large glove boxes removed from the Plutonium Finishing Plant (PFP). Through a collaborative effort between the DOE, CHPRC, and Perma-Fix Environmental Services, Inc. (PESI), pathways for these problematic wastes were developed that took advantage of commercial treatment capabilities at a nearby vendor facility, Perma-Fix Northwest (PFNW). In the spring of 2009, CHPRC initiated a pilot program under which they began shipping large package, low gram suspect TRU (<15 g SNM per container), and large package contact and remote handled MLLW to the off-site PFNW facility for treatment. PFNW is restricted by the SNM limits set for the total quantity of SNM allowed at the

Healthy firms: constraints to growth among private health sector facilities in Ghana and Kenya.

Directory of Open Access Journals (Sweden)

Nicholas E Burger

Full Text Available BACKGROUND: Health outcomes in developing countries continue to lag the developed world, and many countries are not on target to meet the Millennium Development Goals. The private health sector provides much of the care in many developing countries (e.g., approximately 50 percent in Sub-Saharan Africa, but private providers are often poorly integrated into the health system. Efforts to improve health systems performance will need to include the private sector and increase its contributions to national health goals. However, the literature on constraints private health care providers face is limited. METHODOLOGY/PRINCIPAL FINDINGS: We analyze data from a survey of private health facilities in Kenya and Ghana to evaluate growth constraints facing private providers. A significant portion of facilities (Ghana: 62 percent; Kenya: 40 percent report limited access to finance as the most significant barrier they face; only a small minority of facilities report using formal credit institutions to finance day to day operations (Ghana: 6 percent; Kenya: 11 percent. Other important barriers include corruption, crime, limited demand for goods and services, and poor public infrastructure. Most facilities have paper-based rather than electronic systems for patient records (Ghana: 30 percent; Kenya: 22 percent, accounting (Ghana: 45 percent; Kenya: 27 percent, and inventory control (Ghana: 41 percent; Kenya: 24 percent. A majority of clinics in both countries report undertaking activities to improve provider skills and to monitor the level and quality of care they provide. However, only a minority of pharmacies report undertaking such activities. CONCLUSIONS/SIGNIFICANCE: The results suggest that improved access to finance and improving business processes especially among pharmacies would support improved contributions by private health facilities. These strategies might be complementary if providers are more able to take advantage of increased access to

Healthy firms: constraints to growth among private health sector facilities in Ghana and Kenya.

Science.gov (United States)

Burger, Nicholas E; Kopf, Daniel; Spreng, Connor P; Yoong, Joanne; Sood, Neeraj

2012-01-01

Health outcomes in developing countries continue to lag the developed world, and many countries are not on target to meet the Millennium Development Goals. The private health sector provides much of the care in many developing countries (e.g., approximately 50 percent in Sub-Saharan Africa), but private providers are often poorly integrated into the health system. Efforts to improve health systems performance will need to include the private sector and increase its contributions to national health goals. However, the literature on constraints private health care providers face is limited. We analyze data from a survey of private health facilities in Kenya and Ghana to evaluate growth constraints facing private providers. A significant portion of facilities (Ghana: 62 percent; Kenya: 40 percent) report limited access to finance as the most significant barrier they face; only a small minority of facilities report using formal credit institutions to finance day to day operations (Ghana: 6 percent; Kenya: 11 percent). Other important barriers include corruption, crime, limited demand for goods and services, and poor public infrastructure. Most facilities have paper-based rather than electronic systems for patient records (Ghana: 30 percent; Kenya: 22 percent), accounting (Ghana: 45 percent; Kenya: 27 percent), and inventory control (Ghana: 41 percent; Kenya: 24 percent). A majority of clinics in both countries report undertaking activities to improve provider skills and to monitor the level and quality of care they provide. However, only a minority of pharmacies report undertaking such activities. The results suggest that improved access to finance and improving business processes especially among pharmacies would support improved contributions by private health facilities. These strategies might be complementary if providers are more able to take advantage of increased access to finance when they have the business processes in place for operating a successful business

Advanced Electron Beam Ion Sources (EBIS) for 2-nd generation carbon radiotherapy facilities

CERN Document Server

Shornikov, A.

2016-01-01

In this work we analyze how advanced Electron Beam Ion Sources (EBIS) can facilitate the progress of carbon therapy facilities. We will demonstrate that advanced ion sources enable operation of 2-nd generation ion beam therapy (IBT) accelerators. These new accelerator concepts with designs dedicated to IBT provide beams better suited for therapy and, are more cost efficient than contemporary IBT facilities. We will give a sort overview of the existing new IBT concepts and focus on those where ion source technology is the limiting factor. We will analyse whether this limitation can be overcome in the near future thanks to ongoing EBIS development.

76 FR 51961 - Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility Trust No. 1, Topsham Hydro...

Science.gov (United States)

2011-08-19

... On August 3, 2011, Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility (Trust No. 1... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 4784-082] Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility Trust No. 1, Topsham Hydro Partners Limited Partnership...

Animal facilities

International Nuclear Information System (INIS)

Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

1981-01-01

The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

Facilities Performance Indicators Report 2013-14: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2015

2015-01-01

This paper features an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA: Association of Higher Education Facilities Officers (APPA's) Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. "The Facilities Performance…

Communication grounding facility

International Nuclear Information System (INIS)

Lee, Gye Seong

1998-06-01

It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

The dynamic analysis facility at the Chalk River Nuclear Laboratories

International Nuclear Information System (INIS)

Argue, D.S.; Howatt, W.T.

1979-10-01

The Dynamic Analysis Facility at the Chalk River Nuclear Laboratories (CRNL) of Atomic Energy of Canada Limited (AECL) comprises a Hybrid Computer, consisting of two Applied Dynamic International AD/FIVE analog computers and a Digital Equipment Corporation (DEC) PDP-11/55 digital computer, and a Program Development System based on a DEC PDP-11/45 digital computer. This report describes the functions of the various hardware components of the Dynamic Analysis Facility and the interactions between them. A brief description of the software available to the user is also given. (auth)

A Strategy for Quantifying Radioactive Material in a Low-Level Waste Incineration Facility

International Nuclear Information System (INIS)

Hochel, R.C.

1997-03-01

One of the methods proposed by the U.S. Department of Energy (DOE) for the volume reduction and stabilization of a variety of low-level radioactive wastes (LLW) is incineration. Many commercial incinerators are in operation treating both non-hazardous and hazardous wastes. These can obtain volume reductions factors of 50 or more for certain wastes, and produce a waste (ash) that can be easily stabilized if necessary by vitrification or cementation. However, there are few incinerators designed to accommodate radioactive wastes. One has been recently built at the Savannah River Site (SRS) near Aiken, SC and is burning non-radioactive hazardous waste and radioactive wastes in successive campaigns. The SRS Consolidated Incineration Facility (CIF) is RCRA permitted as a Low Chemical Hazard, Radiological facility as defined by DOE criteria (Ref. 1). Accordingly, the CIF must operate within specified chemical, radionuclide, and fissile material inventory limits (Ref. 2). The radionuclide and fissile material limits are unique to radiological or nuclear facilities, and require special measurement and removal strategies to assure compliance, and the CIF may be required to shut down periodically in order to clean out the radionuclide inventory which builds up in various parts of the facility

An assessment of testing requirement impacts on nuclear thermal propulsion ground test facility design

International Nuclear Information System (INIS)

Shipers, L.R.; Ottinger, C.A.; Sanchez, L.C.

1993-01-01

Programs to develop solid core nuclear thermal propulsion (NTP) systems have been under way at the Department of Defense (DoD), the National Aeronautics and Space Administration (NASA), and the Department of Energy (DOE). These programs have recognized the need for a new ground test facility to support development of NTP systems. However, the different military and civilian applications have led to different ground test facility requirements. The Department of Energy (DOE) in its role as landlord and operator of the proposed research reactor test facilities has initiated an effort to explore opportunities for a common ground test facility to meet both DoD and NASA needs. The baseline design and operating limits of the proposed DoD NTP ground test facility are described. The NASA ground test facility requirements are reviewed and their potential impact on the DoD facility baseline is discussed

Taking into account of dismantling constraints in the design of nuclear facilities

International Nuclear Information System (INIS)

Gouhier, E.; Moitrier, C.; Girones, P.; Pitrou, Y.; Poncet, P.; O'Sullivan, P.

2014-01-01

The taking into account of dismantling constraints in the design of nuclear facilities allows the reduction of the dosimetry during the dismantling operations, the reduction of the amount of wastes to manage and the saving of time and money by foreseeing an adequate and simple solution for each component. It is to notice that the strategy of life-extension strengthens that of dismantling because life-extension implies the possibility for any component of the reactor except the pressure vessel to be replaced. The feedback experience capitalized on various types of nuclear facilities have enabled IAEA and OECD to publish recommendations to facilitate dismantling. For instance, pipes and ventilation ducts must be designed to minimize the deposit of dust and residues, the natural porosity of concrete must be limited through the use of polishing products or a metal liner, the type and concentrations of impurities present in the structure materials must be controlled to limit radioactivation, the documentation describing the facility must be kept up to date, or the history of contamination events must be recorded all along the life of the facility. The integration of the dismantling constraints in the design stage is illustrated with 3 examples: the Georges Besse 2 enrichment fuel plant, new reactors (EPR, ASTRID and RJH), and ITER. (A.C.)

Final Rule: NESHAP for the Portland Cement Manufacturing Industry: Alternative Monitoring Method

Science.gov (United States)

EPA is extending its approval for the use of an alternative method to show compliance with hydrogen chloride (HCl) emissions limits in the National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing Industry

Design criteria tank farm storage and staging facility. Revision 1

International Nuclear Information System (INIS)

Lott, D.T.

1994-01-01

Tank Farms Operations must store/stage material and equipment until work packages are ready to work. Consumable materials are also required to be stored for routine and emergency work. Connex boxes and open storage is currently used for much of the storage because of the limited space at 272AW and 272WA. Safety issues based on poor housekeeping and material deteriorating due to weather damage has resulted from this inadequate storage space. It has been determined that a storage building in close proximity to the Tank Farm work force would be cost effective. Project W-402 and W-413 will provide a storage/staging area in 200 East and West Areas by the construction of two new storage facilities. The new facilities will be used by Operations, Maintenance and Materials groups to adequately store material and equipment. These projects will also furnish electrical services to the facilities for lighting and HVAC. Fire Protection shall be extended to the 200 East facility from 272AW if necessary

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

1994-11-01

The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Beta limits for ETF

International Nuclear Information System (INIS)

Helton, F.J.; Miller, R.L.

1982-01-01

ETF (Engineering Test Facility) one-dimensional transport simulations indicate that a volume-average beta of 4% is required for ignition. It is therefore important that theoretical beta limits, determined by requiring equilibria to be stable to all ideal modes, exceed 4%. This paper documents an ideal MHD analysis wherein it is shown that, with appropriate plasma cross-sectional shape and current profile optimization, operation near 5% is possible. The critical beta value, however, depends on the functional form used for ff', which suggests that higher critical betas could be achieved by directly optimizing the safety factor profile. (author)

Global patient safety and antiretroviral drug-drug interactions in the resource-limited setting.

Science.gov (United States)

Seden, Kay; Khoo, Saye H; Back, David; Byakika-Kibwika, Pauline; Lamorde, Mohammed; Ryan, Mairin; Merry, Concepta

2013-01-01

Scale-up of HIV treatment services may have contributed to an increase in functional health facilities available in resource-limited settings and an increase in patient use of facilities and retention in care. As more patients are reached with medicines, monitoring patient safety is increasingly important. Limited data from resource-limited settings suggest that medication error and antiretroviral drug-drug interactions may pose a significant risk to patient safety. Commonly cited causes of medication error in the developed world include the speed and complexity of the medication use cycle combined with inadequate systems and processes. In resource-limited settings, specific factors may contribute, such as inadequate human resources and high disease burden. Management of drug-drug interactions may be complicated by limited access to alternative medicines or laboratory monitoring. Improving patient safety by addressing the issue of antiretroviral drug-drug interactions has the potential not just to improve healthcare for individuals, but also to strengthen health systems and improve vital communication among healthcare providers and with regulatory agencies.

Facility effluent monitoring plan for the 325 Facility

International Nuclear Information System (INIS)

1998-01-01

The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP Facility

International Nuclear Information System (INIS)

Goldberg, H.J.

1998-01-01

The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of special nuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations

Moderator Demonstration Facility Design and Optimization

Energy Technology Data Exchange (ETDEWEB)

McClanahan, Tucker C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gallmeier, Franz X. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Iverson, Erik B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-02-01

The Spallation Neutron Source (SNS) facility at Oak Ridge National Laboratory (ORNL) is implementing a Moderator Demonstration Facility (MDF) to demonstrate the performance characteristics of advanced moderators central to the Second Target Station (STS) for SNS. The MDF will use the "spare" front-end installation within the SNS accelerator support complex – an ion source, radio-frequency quadrupole (RFQ) accelerator, and medium-energy beam transport (MEBT) chopper - to provide a 2.5 MeV proton beam of peak current 50 mA and maximum pulse length of less than 10 s at a repetition rate of no more than 60 Hz to a suitable neutron-producing target to demonstrate those aspects of moderator performance necessary to meet the goals of the STS design e ort. The accelerator beam parameters are not open to variation beyond that described above - they are fixed by the nature of the spare front-end installation (the Integrated Test Stand Facility; ITSF). Accordingly, there are some neutronic challenges in developing prototypic moderator illumination from a very non-prototypic primary neutron source; the spallation source we are attempting to mimic has an extended neutron source volume approximately 40 cm long (in the direction of the proton beam), approximately 10 cm wide (horizontally transverse to the proton beam) and approximately 5 cm high (vertically transverse to the proton beam), and an isotropic evaporation energy spectrum with mean energy above 1 MeV. In contrast, the primary neutron source available from the 7Li(p,n) reaction (the most prolific at 2.5 MeV proton energy by more than an order of magnitude) is strongly anisotropic, with an energy spectrum that is both strongly dependent on emission angle and kinematically limited to less than 700 keV, and the interaction zone between the incident protons and any target material (neutron-producing or not) is intrinsically limited to a few tens of microns. The MDF will be unique and innovative amongst the world�

Air Quality Facilities

Data.gov (United States)

Iowa State University GIS Support and Research Facility — Facilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

Facilities Performance Indicators Report, 2004-05. Facilities Core Data Survey

Science.gov (United States)

Glazner, Steve, Ed.

2006-01-01

The purpose of "Facilities Performance Indicators" is to provide a representative set of statistics about facilities in educational institutions. The second iteration of the web-based Facilities Core Data Survey was posted and available to facilities professionals at more than 3,000 institutions in the Fall of 2005. The website offered a printed…

High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

International Nuclear Information System (INIS)

Kloepfer, Michael

2012-01-01

The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

Safeguardability of a commercial-scaled ACP facility

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility.

Automation of electromagnetic compatability (EMC) test facilities

Science.gov (United States)

Harrison, C. A.

1986-01-01

Efforts to automate electromagnetic compatibility (EMC) test facilities at Marshall Space Flight Center are discussed. The present facility is used to accomplish a battery of nine standard tests (with limited variations) deigned to certify EMC of Shuttle payload equipment. Prior to this project, some EMC tests were partially automated, but others were performed manually. Software was developed to integrate all testing by means of a desk-top computer-controller. Near real-time data reduction and onboard graphics capabilities permit immediate assessment of test results. Provisions for disk storage of test data permit computer production of the test engineer's certification report. Software flexibility permits variation in the tests procedure, the ability to examine more closely those frequency bands which indicate compatibility problems, and the capability to incorporate additional test procedures.

Safeguardability of a commercial-scaled ACP facility

International Nuclear Information System (INIS)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H.

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility

Nuclear facilities

International Nuclear Information System (INIS)

Anon.

2000-01-01

Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

Facility effluent monitoring plan for 242-A Evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1993-03-01

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 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

Study on applying technology of utilizing long-term materials for corrosion facilities

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Chul; Park, Young Kyu; Baek, Soo Gon; Lee, Jong Sub [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Park, Yong Soo [Yonsei University, Seoul (Korea, Republic of); Hwang, Won Suk [Inha University (Korea, Republic of); Song, Rhyo Seong [Hankuk Aviation, University (Korea, Republic of)

1996-12-31

Nowadays, as the pollution in seawater is escalating rapidly because of fast industrialization, corrosion rate and repairing frequency of seawater facilities in power plant are increasing. In addition, new construction is restricted with narrow limits due to the deterioration of social condition, asking for extension of facility life and repairing frequency. The objectives of this study are to select the appropriate new high corrosion resistance materials and apply them in the field, to make the corrosion data base in accordance with their usage conditions and to predict the remaining life and optimum repairing period by predicting the life of facilities. (author). 77 refs., 54 figs.

Gas processing at DOE nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Jacox, J.

1995-02-01

The term {open_quotes}Gas Processing{close_quotes} has many possible meanings and understandings. In this paper, and panel, we will be using it to generally mean the treatment of gas by methods other than those common to HVAC and Nuclear Air Treatment. This is only a working guideline not a rigorous definition. Whether a rigorous definition is desirable, or even possible is a question for some other forum. Here we will be discussing the practical aspects of what {open_quotes}Gas Processing{close_quotes} includes and how existing Codes, Standards and industry experience can, and should, apply to DOE and NRC Licensed facilities. A major impediment to use of the best engineering and technology in many nuclear facilities is the administrative mandate that only systems and equipment that meet specified {open_quotes}nuclear{close_quotes} documents are permissible. This paper will highlight some of the limitations created by this approach.

North Slope, Alaska ESI: FACILITY (Facility Points)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

Prompt gamma neutron activation analysis facility at the RA-6 research reactor

International Nuclear Information System (INIS)

Sanchez, F. A.; Calzetta, O

2004-01-01

A prompt gamma neutron activation activation analysis facility was developed at the 500 kw thermal power RA-6 research reactor of the Bariloche Atomic Center, Argentina.This facility consist of a radial beam port with external positioning of the sample.The gamma radiation is reduced by a bismuth filter placed inside the extraction tube and the beam diameter is limited by a set of two collimators up to 5 cm.The neutron flux at the sample position is 7 10 6 n/cm 2 s with a Cadmium ratio of 20/1.The gamma detector is a 50 % efficiency type p HPGe rounded by a NaI(Tl) for Compton suppressioning.The gamma spectra is measured through 0 to 8.5 MeV.The background have counting rate of 350 cps without sample. In this work is shown the efficiency curve, the calculed sensibilities and the lower detection limits for B, Cd, Sm, Gd, H, Cl, Hg, Eu, Ti, Ag, Au, Mo. The RA-6's PGNAA facility is fully working, although the analytic capacity is under improvement [es

340 Waste handling Facility Hazard Categorization and Safety Analysis

International Nuclear Information System (INIS)

Rodovsky, T.J.

2010-01-01

The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3. The final hazard categorization for the deactivated 340 Waste Handling Facility (340 Facility) is presented in this document. This hazard categorization was prepared in accordance with DOE-STD-1 027-92, Change Notice 1, Hazard Categorization and Accident Analysis Techniques for Compliance with Doe Order 5480.23, Nuclear Safety Analysis Reports. The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category (HC) 3. Routine nuclear waste receiving, storage, handling, and shipping operations at the 340 Facility have been deactivated, however, the facility contains a small amount of radioactive liquid and/or dry saltcake in two underground vault tanks. A seismic event and hydrogen deflagration were selected as bounding accidents. The generation of hydrogen in the vault tanks without active ventilation was determined to achieve a steady state volume of 0.33%, which is significantly less than the lower flammability limit of 4%. Therefore, a hydrogen deflagration is not possible in these tanks. The unmitigated release from a seismic event was used to categorize the facility consistent with the process defined in Nuclear Safety Technical Position (NSTP) 2002-2. The final sum-of-fractions calculation concluded that the facility is less than HC 3. The analysis did not identify any required engineered controls or design features. The Administrative Controls that were derived from the analysis are: (1) radiological inventory control, (2) facility change control, and (3) Safety Management Programs (SMPs). The facility configuration and radiological inventory shall be controlled to ensure that the assumptions in the analysis remain valid. The facility commitment to SMPs protects the integrity of the facility and environment by ensuring training, emergency response, and radiation protection. The full scale

Post 9-11 Security Issues for Non-Power Reactor Facilities

International Nuclear Information System (INIS)

Zaffuts, P. J.

2003-01-01

This paper addresses the legal and practical issues arising out of the design and implementation of a security-enhancement program for non power reactor nuclear facilities. The security enhancements discussed are derived from the commercial nuclear power industry's approach to security. The nuclear power industry's long and successful experience with protecting highly sensitive assets provides a wealth of information and lessons that should be examined by other industries contemplating security improvements, including, but not limited to facilities using or disposing of nuclear materials. This paper describes the nuclear industry's approach to security, the advantages and disadvantages of its constituent elements, and the legal issues that facilities will need to address when adopting some or all of these elements in the absence of statutory or regulatory requirements to do so

A proposed community reaction-wall facility at the JRC Ispra

Energy Technology Data Exchange (ETDEWEB)

Jones, P M; Donea, J [Commission of the European Communities, Joint Research Centre - Ispra Establishment Applied Mechanics Division, Ispra (Italy)

1988-07-01

The paper describes a large-size structural laboratory based on a reaction-wall facility proposed for the JRC Ispra establishment. It is foreseen that this will be used for large and full-scale testing of a wide variety of structures and components in the fields of civil/structural, mechanical, and geotechnical engineering. After briefly reviewing the background market research done to establish the needs for a large central facility in the Community, the main advantages and limitations of reaction-wall testing in comparison with other experimental techniques are summarized. The main characteristics of the proposed facility are then given followed by the identified fields of research in which significant tests can be performed. Finally, the proposed method of implementing an integral programme of work within the European Community member states is presented. (author)

Post 9-11 Security Issues for Non-Power Reactor Facilities

Energy Technology Data Exchange (ETDEWEB)

Zaffuts, P. J.

2003-02-25

This paper addresses the legal and practical issues arising out of the design and implementation of a security-enhancement program for non power reactor nuclear facilities. The security enhancements discussed are derived from the commercial nuclear power industry's approach to security. The nuclear power industry's long and successful experience with protecting highly sensitive assets provides a wealth of information and lessons that should be examined by other industries contemplating security improvements, including, but not limited to facilities using or disposing of nuclear materials. This paper describes the nuclear industry's approach to security, the advantages and disadvantages of its constituent elements, and the legal issues that facilities will need to address when adopting some or all of these elements in the absence of statutory or regulatory requirements to do so.

A proposed community reaction-wall facility at the JRC Ispra

International Nuclear Information System (INIS)

Jones, P.M.; Donea, J.

1988-01-01

The paper describes a large-size structural laboratory based on a reaction-wall facility proposed for the JRC Ispra establishment. It is foreseen that this will be used for large and full-scale testing of a wide variety of structures and components in the fields of civil/structural, mechanical, and geotechnical engineering. After briefly reviewing the background market research done to establish the needs for a large central facility in the Community, the main advantages and limitations of reaction-wall testing in comparison with other experimental techniques are summarized. The main characteristics of the proposed facility are then given followed by the identified fields of research in which significant tests can be performed. Finally, the proposed method of implementing an integral programme of work within the European Community member states is presented. (author)

Criticality safety analysis for mockup facility

International Nuclear Information System (INIS)

Shin, Young Joon; Shin, Hee Sung; Kim, Ik Soo; Oh, Seung Chul; Ro, Seung Gy; Bae, Kang Mok

2000-03-01

Benchmark calculations for SCALE4.4 CSAS6 module have been performed for 31 UO 2 fuel, 15MOX fuel and 10 metal material criticality experiments and then calculation biases of the SCALE 4.4 CSAS6 module have been revealed to be 0.00982, 0.00579 and 0.02347, respectively. When CSAS6 is applied to the criticality safety analysis for the mockup facility in which several kinds of nuclear material components are included, the calculation bias of CSAS6 is conservatively taken to be 0.02347. With the aid of this benchmarked code system, criticality safety analyses for the mockup facility at normal and hypothetical accidental conditions have been carried out. It appears that the maximum K eff is 0.28356 well below than the critical limit, K eff =0.95 at normal condition. In a hypothetical accidental condition, the maximum K eff is found to be 0.73527 much lower than the subcritical limit. For another hypothetical accidental condition the nuclear material leaks out of container and spread or lump in the floor, it was assumed that the nuclear material is shaped into a slab and water exists in the empty space of the nuclear material. K eff has been calculated as function of slab thickness and the volume ratio of water to nuclear material. The result shows that the K eff increases as the water volume ratio increases. It is also revealed that the K eff reaches to the maximum value when water if filled in the empty space of nuclear material. The maximum K eff value is 0.93960 lower than the subcritical limit

Iodine-129 Dose in LLW Disposal Facility Performance Assessments

International Nuclear Information System (INIS)

Wilhite, E.L.

1999-01-01

Iodine-129 has the lowest Performance Assessment derived inventory limit in SRS disposal facilities. Because iodine is concentrated in the body to one organ, the thyroid, it has been thought that dilution with stable iodine would reduce the dose effects of 129I.Examination of the dose model used to establish the Dose conversion factor for 129I shows that, at the levels considered in performance assessments of low-level waste disposal facilities, the calculated 129I dose already accounts for ingestion of stable iodine. At higher than normal iodine ingestion rates, the uptake of iodine by the thyroid itself decrease, which effectively cancels out the isotopic dilution effect

Facility and market factors affecting transitions from nursing home to community.

Science.gov (United States)

Arling, Greg; Abrahamson, Kathleen A; Cooke, Valerie; Kane, Robert L; Lewis, Teresa

2011-09-01

Research into nursing home transitions has given limited attention to the facility or community contexts. To identify facility and market factors affecting transitions of nursing home residents back to the community. Multilevel models were used to estimate effects of facility and market factors on facility-level community discharge rates after controlling for resident demographic, health, and functional conditions. Facility discharge rates were adjusted using Empirical Bayes estimation. Annual cohort of first-time admissions (N=24,648) to 378 Minnesota nursing facilities in 75 nursing home markets from July 2005 to June 2006. Community discharge within 90 days of admission; facility occupancy, payer mix, ownership, case-mix acuity, size, admissions from hospitals, nurse staffing level, and proportion of admissions preferring or having support to return to the community; and nursing market population size, average occupancy, market concentration, and availability of home and community-based services. Rates of community discharge (Empirical Bayes residual) were highest in facilities with more residents preferring community discharge, more Medicare days, higher nurse staffing levels, and higher occupancy. In addition, facilities had higher community discharge rates if they were located in markets with a greater ratio of home and community-based services recipients to nursing home residents and with larger populations. State Medicaid programs should undertake system-level interventions that encourage nursing facilities to reduce unused bed capacity, balance the mix of payers, invest in nurse staffing, and take other steps to promote community discharges. In addition, states should increase home and community-based services, particularly in markets with low community discharge rates.

Australian proton therapy facilities - status report

International Nuclear Information System (INIS)

Bleasel, S.; Jackson, M.

2000-01-01

Full text: Radiotherapy plays an important role in the treatment of cancer; both in the curative treatment of localised disease and in alleviating symptoms in more advanced disease. Radiotherapy is usually given with megavoltage X-rays which give good penetration at depth and a lower dose on the skin. The aim is to give a high dose to the tumour while keeping the dose to normal tissues as low as possible. While X-rays continue beyond the target volume, protons and other charged particles have a finite range in tissue and this allows the high dose region to closely conform to the tumour, thereby giving the best chance of tumour control with minimum side effects. This is particularly important for small tumours adjacent to critical normal structures. The unmodified Bragg peak is too narrow to be useful but can be spread out to cover the tumour. Protons of energy 70 - 250 MeV are required to achieve the optimal depth in the body. Protons have been used for cancer treatment since 1954 but most of these treatments have been given in physics-based facilities which do not provide an ideal environment for the patient and may have only limited beam time available. A dedicated, hospital based facility was built at Loma Linda in California in 1991 and has now treated over 5,000 patients. Several other centres are being built in the USA, Japan and Europe and one is now being considered for Australia. Early 1998 Hitachi Australia Ltd. was asked to research the possibility of building a facility in Australia to serve Oceania. Two major hospitals showed interest, Royal Brisbane Hospital and Royal Prince Alfred Hospital. Both hospitals are undergoing redevelopment and have space for a building 3 stories high with a foot-print of approximately 50 m x 50 m. What is proposed for Australia is a principally clinical research facility with a dedicated area for physics research. A Steering Committee will be established to develop a document for presentation to Government. The facility

26 CFR 1.142(a)(5)-1 - Exempt facility bonds: Sewage facilities.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Exempt facility bonds: Sewage facilities. 1.142... Bonds § 1.142(a)(5)-1 Exempt facility bonds: Sewage facilities. (a) In general. Under section 103(a), a... in section 142(a) is a sewage facility. This section defines the term sewage facility for purposes of...

A Game Theoretical Model for Location of Terror Response Facilities under Capacitated Resources

Directory of Open Access Journals (Sweden)

Lingpeng Meng

2013-01-01

Full Text Available This paper is concerned with the effect of capacity constraints on the locations of terror response facilities. We assume that the state has limited resources, and multiple facilities may be involved in the response until the demand is satisfied consequently. We formulate a leader-follower game model between the state and the terrorist and prove the existence and uniqueness of the Nash equilibrium. An integer linear programming is proposed to obtain the equilibrium results when the facility number is fixed. The problem is demonstrated by a case study of the 19 districts of Shanghai, China.

Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-09-19

This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

Use of probabilistic risk assessment in fuel cycle facilities

International Nuclear Information System (INIS)

Gonzalez, Felix; Gonzalez, Michelle; Wagner, Brian

2013-01-01

As expressed in its Policy Statement on the Use of Probabilistic Risk Assessment (PRA) Methods in Nuclear Regulatory Activities, the U.S Nuclear Regulatory Commission has been working for decades to increase the use of PRA technology in its regulatory activities. Since the policy statement was issued in 1995, PRA has become a core component of the nuclear power plant (NPP) licensing and oversight processes. In the last several years, interest has increased in PRA technologies and their possible application to other areas including, but not limited to, spent fuel handling, fuel cycle facilities, reprocessing facilities, and advanced reactors. This paper describes the application of PRA technology currently used in NPPs and its application in other areas such as fuel cycle facilities and advanced reactors. It describes major challenges that are being faced in the application of PRA into new technical areas and possible ways to resolve them. (authors)

Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

Energy Technology Data Exchange (ETDEWEB)

Liu, James C.; Rokni, Sayed H.; /SLAC; Vylet, Vaclav; /Jefferson Lab

2009-12-11

The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power ({approx} 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

International Nuclear Information System (INIS)

Liu, James C.; Rokni, Sayed H.; Vylet, Vaclav

2009-01-01

The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power (∼ 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

Facility transition instruction

International Nuclear Information System (INIS)

Morton, M.R.

1997-01-01

The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

Neutron activation analysis detection limits using 252Cf sources

International Nuclear Information System (INIS)

DiPrete, D.P.; Sigg, R.A.

2000-01-01

The Savannah River Technology Center (SRTC) developed a neutron activation analysis (NAA) facility several decades ago using low-flux 252 Cf neutron sources. Through this time, the facility has addressed areas of applied interest in managing the Savannah River Site (SRS). Some applications are unique because of the site's operating history and its chemical-processing facilities. Because sensitivity needs for many applications are not severe, they can be accomplished using an ∼6-mg 252 Cf NAA facility. The SRTC 252 Cf facility continues to support applied research programs at SRTC as well as other SRS programs for environmental and waste management customers. Samples analyzed by NAA include organic compounds, metal alloys, sediments, site process solutions, and many other materials. Numerous radiochemical analyses also rely on the facility for production of short-lived tracers, yielding by activation of carriers and small-scale isotope production for separation methods testing. These applications are more fully reviewed in Ref. 1. Although the flux [approximately2 x 10 7 n/cm 2 ·s] is low relative to reactor facilities, more than 40 elements can be detected at low and sub-part-per-million levels. Detection limits provided by the facility are adequate for many analytical projects. Other multielement analysis methods, particularly inductively coupled plasma atomic emission and inductively coupled plasma mass spectrometry, can now provide sensitivities on dissolved samples that are often better than those available by NAA using low-flux isotopic sources. Because NAA allows analysis of bulk samples, (a) it is a more cost-effective choice when its sensitivity is adequate than methods that require digestion and (b) it eliminates uncertainties that can be introduced by digestion processes

Upgraded Features of Newly Constructed Fuel Assembly Mechanical Characterization Test Facility in KAERI

Energy Technology Data Exchange (ETDEWEB)

Lee, Kang Hee; Kang, Heung Seok; Yoon, Kyung Ho; Kim, Hyung Kyu; Lee, Young Ho; Kim, Soo Ho; Yang, Jae Ho [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Fuel assembly mechanical characterization test facility (FAMeCT) in KAERI is newly constructed with upgraded functional features such as increased loading capacity, under-water vibration testing and severe earthquake simulation for extended fuel design guideline. The facility building is compactly designed in the scale of 3rd floor building and has regions for assembly-wise mechanical test equipment, dynamic load (seismic) simulating test system, small scale hydraulic loop and component wise test equipment. Figure 1 shows schematic regional layout of the facility building. Mechanical test platform and system is designed to increase loading capacity for axial compression test. Structural stability of the support system of new upper core plate simulator is validated through a limit case functional test. Fuel assembly mechanical characterization test facility in KAERI is newly constructed and upgraded with advanced functional features such as uprated loading capacity, under-water vibration testing and severe earthquake simulation for extended fuel design guideline. This paper briefly introduce the test facility construction and scope of the facility and is focused on the upgraded design features of the facility. Authors hope to facilitate the facility more in the future and collaborate with the industry.

Facilities Performance Indicators Report 2012-13: Tracking Your Facilities Vital Signs

Science.gov (United States)

APPA: Association of Higher Education Facilities Officers, 2014

2014-01-01

This paper features an expanded Web-based "Facilities Performance Indicators (FPI) Report." The purpose of APPA's Facilities Performance Indicators is to provide a representative set of statistics about facilities in educational institutions. "The Facilities Performance Indicators Report" is designed for survey…

Guide to research facilities

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Radiation protection program at an accelerator facility complex

International Nuclear Information System (INIS)

Ramanuja, Jaya

2007-01-01

Broad aspects of Radiation Protection Program at the Tyco Healthcare/Mallinckrodt Inc. will be presented with emphasis on Occupational dose, Public dose and ALARA program. Regulatory requirements, compliance and radio nuclides of concern for external exposure and internal contamination will be discussed. The facility is subject to in depth annual inspections by the Nuclear Regulatory Commission (NRC) to ensure compliance with regulations and operating license requirements. The facility is required to have an emergency contingency plan in place. A simulated emergency drill scenario is witnessed and graded by the NRC and state inspectors, with full participation by the fire department and the local hospital. Radiation Safety Officer (RSO) is in charge of all radiological aspects of the facility, and reports to the plant manager directly. The RSO or any of his staff has the authority to stop a job if there is a radiological concern. The Radiation protection organization interfaces with Production, QA and Engineering and ensures there is no conflict with Industrial Safety, OSHA and FDA requirements. Any employee has the right to call the regulatory officials if he/she has a concern. Operational aspects of Radiation protection program such as radiological survey, contamination control and limits, air sample survey, radio active waste processing and record retention requirements are per plant procedures and regulatory requirements. Shielding and administrative requirements for designing a modification to an existing design or a new lab/hot cell is subject to in-depth review and approval by Radiation Safety Committee. Each department has a Dose Reduction Subcommittee which meets periodically to discuss if any changes in procedures or facility can be made to decrease the dose. The subcommittee also trends the dose to ensure it is trending downward. Even though 99 Mo/ 99m TC generators are manufactured at the facility, majority of the dose is from cyclotron maintenance

The CMS CERN Analysis Facility (CAF)

Energy Technology Data Exchange (ETDEWEB)

Buchmueller, O [Imperial College (United Kingdom); Bonacorsi, D [Universita and INFN, Bologna (Italy); Fanzago, F [Universita and INFN, Padova (Italy); Gowdy, S; Malgeri, L; Panzer-Steindel, B; Schwickerath, U; Spiga, D; Toebbicke, Rainer [Conseil Europeen Recherche Nucl. (CERN) Switzerland (Switzerland); Kreuzer, P [Rheinisch-Westfaelische Tech. Hoch. (RWTH) (Germany); Mankel, R [Deutsches Elektronen-Synchrotron (DESY) (Germany); Metson, S [University of Bristol (United Kingdom); Sanches, J Afonso; Teodoro, D, E-mail: Peter.Kreuzer@cern.c [Universidade do Estado do Rio De Janeiro (UERJ) (Brazil)

2010-04-01

The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workflows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast-turnaround. In addition to the low latency requirement on the batch farm, another mandatory condition is the efficient access to the RAW detector data stored at the CERN Tier-0 facility. The CMS CAF also foresees resources for interactive login by a large number of CMS collaborators located at CERN, as an entry point for their day-by-day analysis. These resources will run on a separate partition in order to protect the high-priority use-cases described above. While the CMS CAF represents only a modest fraction of the overall CMS resources on the WLCG GRID, an appropriately sized user-support service needs to be provided. We will describe the building, commissioning and operation of the CMS CAF during the year 2008. The facility was heavily and routinely used by almost 250 users during multiple commissioning and data challenge periods. It reached a CPU capacity of 1.4MSI2K and a disk capacity at the Peta byte scale. In particular, we will focus on the performances in terms of networking, disk access and job efficiency and extrapolate prospects for the upcoming LHC first year data taking. We will also present the experience gained and the limitations observed in operating such a large facility, in which well controlled workflows are combined with more chaotic type analysis by a large number of physicists.

The CMS CERN Analysis Facility (CAF)

International Nuclear Information System (INIS)

Buchmueller, O; Bonacorsi, D; Fanzago, F; Gowdy, S; Malgeri, L; Panzer-Steindel, B; Schwickerath, U; Spiga, D; Toebbicke, Rainer; Kreuzer, P; Mankel, R; Metson, S; Sanches, J Afonso; Teodoro, D

2010-01-01

The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workflows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast-turnaround. In addition to the low latency requirement on the batch farm, another mandatory condition is the efficient access to the RAW detector data stored at the CERN Tier-0 facility. The CMS CAF also foresees resources for interactive login by a large number of CMS collaborators located at CERN, as an entry point for their day-by-day analysis. These resources will run on a separate partition in order to protect the high-priority use-cases described above. While the CMS CAF represents only a modest fraction of the overall CMS resources on the WLCG GRID, an appropriately sized user-support service needs to be provided. We will describe the building, commissioning and operation of the CMS CAF during the year 2008. The facility was heavily and routinely used by almost 250 users during multiple commissioning and data challenge periods. It reached a CPU capacity of 1.4MSI2K and a disk capacity at the Peta byte scale. In particular, we will focus on the performances in terms of networking, disk access and job efficiency and extrapolate prospects for the upcoming LHC first year data taking. We will also present the experience gained and the limitations observed in operating such a large facility, in which well controlled workflows are combined with more chaotic type analysis by a large number of physicists.

Progress towards a new Canadian irradiation-research facility

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.

1993-01-01

As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

Opportunities for artificial intelligence application in computer- aided management of mixed waste incinerator facilities

International Nuclear Information System (INIS)

Rivera, A.L.; Ferrada, J.J.; Singh, S.P.N.

1992-01-01

The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site. It is designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conservation and Recovery Act (RCRA). This facility, known as the TSCA Incinerator, services seven DOE/OR installations. This incinerator was recently authorized for production operation in the United States for the processing of mixed (radioactively contaminated-chemically hazardous) wastes as regulated under TSCA and RCRA. Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. These requirements impact the characteristics and disposition of incinerator residues, limits the quality of liquid and gaseous effluents, limit the characteristics and rates of waste feeds and operating conditions, and restrict the handling of the waste feed inventories. This incinerator facility presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. Demonstrated computer-aided management systems could be transferred to future mixed waste incinerator facilities

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

International Nuclear Information System (INIS)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-01-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period

Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

Energy Technology Data Exchange (ETDEWEB)

Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

1978-01-01

This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period.

Recommended practice for the design of a computer driven Alarm Display Facility for central control rooms of nuclear power generating stations

International Nuclear Information System (INIS)

Ben-Yaacov, G.

1984-01-01

This paper's objective is to explain the process by which design can prevent human errors in nuclear plant operation. Human factor engineering principles, data, and methods used in the design of computer driven alarm display facilities are discussed. A ''generic'', advanced Alarm Display Facility is described. It considers operator capabilities and limitations in decision-making processes, response dynamics, and human memory limitations. Highlighted are considerations of human factor criteria in the designing and layout of alarm displays. Alarm data sources are described, and their use within the Alarm Display Facility are illustrated

Facility effluent monitoring plan for 242-A evaporator facility

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.

1995-02-01

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

EPA Facility Registry Service (FRS): Facility Interests Dataset

Data.gov (United States)

U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

Results of RCRA groundwater quality assessment at the 216-B-3 Pond Facility

International Nuclear Information System (INIS)

Barnett, D.B.; Teel, S.S.

1997-06-01

This document describes a groundwater quality assessment of the 216-B-3 pond system, a Resources Conservation and Recovery act of 1976 (RCRA) waste facility. In 1990, sampling and chemical analysis of groundwater underlying the facility indicated that the contamination indicator parameters, total organic halogens (TOX), and total organic carbon (TOC) had exceeded established limits in two wells. This discovery placed the facility into RCRA groundwater assessment status and subsequently led to a more detailed hydrochemical analysis of groundwater underlying the facility. Comprehensive chemical analyses of groundwater samples from 1994 through 1996 revealed one compound, tris (2-chloroethyl) phosphate (TRIS2CH), that may have contributed to elevated TOX concentrations. No compound was identified as a contributor to TOC. Detailed evaluations of TOX, TOC, and TRIS2CH and comparison of occurrences of these parameters led to conclusions that (1) with few exceptions, these constituents occur at low concentrations below or near limits of quantitation; (2) it is problematic whether the low concentrations of TRIS2CH represent a contaminant originating from the facility or if it is a product of well construction; and (3) given the low and diminishing concentration of TOX, TOC, and TRIS2CH, no further investigation into the occurrent of these constituents is justified. Continued groundwater monitoring should include an immediate recalculation of background critical means of upgradient/downgradient comparisons and a return to seminannual groundwater monitoring under a RCRA indicator parameter evaluation program

Integration of optical fibers in mega-joule class laser environments: advantages and limitations

International Nuclear Information System (INIS)

Girard, S.; Marcandella, C.; Bisutti, J.; Ouerdane, Y.; Boukenter, A.; Meunier, J.P.; Baggio, J.

2012-01-01

We review the advantages and limitations for the integration of optical fibers in the radiative environment associated with Megajoule class lasers as Laser Megajoule (LMJ) in France or National Ignition Facility (NIF) in the USA. Optical fibers present numerous advantages, like their electromagnetic immunity, for integration in these facilities devoted to the fusion by inertial confinement studies. Despite these advantages, it is also well-known that optical fibers suffer from a degradation of their macroscopic properties under irradiation, limiting their transmission capability. We studied the major mechanisms governing the amplitude of this degradation, focusing our discussion on the transient radiation-induced attenuation (RIA) phenomena that is often the limiting factor for LMJ applications. The amplitude and growth and decay kinetics of RIA are affected by different parameters related to the fibers themselves but also depend on the application and irradiation characteristics. We particularly investigated the fiber transient radiation responses when the optical links have to operate during the pulsed and mixed environment associated with ignition shots. Our study shows that, if the same parameters affect the fiber sensitivity for steady state and transient irradiations, the radiation tolerances of the different classes of waveguides strongly differ, implying dedicated experiments for LMJ facility needs. (authors)

Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

International Nuclear Information System (INIS)

Lee, Seunghee; Kim, Juyoul

2017-01-01

Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • 14 C, 226 Ra, 241 Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing 14 C, 226 Ra and 241 Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10 −7 mSv/yr, for both disposal options and satisfied the regulatory limit of 0.1 mSv/yr. However, in the

National Ignition Facility environmental protection systems

International Nuclear Information System (INIS)

Mintz, J.M.; Reitz, T.C.; Tobin, M.T.

1994-06-01

The conceptual design of Environmental Protection Systems (EPS) for the National Ignition Facility (NIF) is described. These systems encompass tritium and activated debris handling, chamber, debris shield and general decontamination, neutron and gamma monitoring, and radioactive, hazardous and mixed waste handling. Key performance specifications met by EPS designs include limiting the tritium inventory to 300 Ci and total tritium release from NIF facilities to less than 10 Ci/yr. Total radiation doses attributable to NIF shall remain below 10 mrem/yr for any member of the general public and 500 mrem/yr for NIF staff. ALARA-based design features and operational procedures will, in most cases, result in much lower measured exposures. Waste minimization, improved cycle time and reduced exposures all result from the proposed CO2 robotic arm cleaning and decontamination system, while effective tritium control is achieved through a modern system design based on double containment and the proven detritiation technology

Longitudinal variation in pressure injury incidence among long-term aged care facilities.

Science.gov (United States)

Jorgensen, Mikaela; Siette, Joyce; Georgiou, Andrew; Westbrook, Johanna I

2018-05-04

To examine variation in pressure injury (PI) incidence among long-term aged care facilities and identify resident- and facility-level factors that explain this variation. Longitudinal incidence study using routinely-collected electronic care management data. A large aged care service provider in New South Wales and the Australian Capital Territory, Australia. About 6556 people aged 65 years and older who were permanent residents in 60 long-term care facilities between December 2014 and November 2016. Risk-adjusted PI incidence rates over eight study quarters. Incidence density over the study period was 1.33 pressure injuries per 1000 resident days (95% confidence interval (CI) = 1.29-1.37). Funnel plots were used to identify variation among facilities. On average, 14% of facilities had risk-adjusted PI rates that were higher than expected in each quarter (above 95% funnel plot control limits). Ten percent of facilities had persistently high rates in any three or more consecutive quarters (n = 6). The variation between facilities was only partly explained by resident characteristics in multilevel regression models. Residents were more likely to have higher-pressure injury rates in facilities in regional areas compared with major city areas (adjusted incidence rate ratio = 1.25, 95% CI = 1.04-1.51), and facilities with persistently high rates were more likely to be located in areas with low socioeconomic status (P = 0.038). There is considerable variation among facilities in PI incidence. This study demonstrates the potential of routinely-collected care management data to monitor PI incidence and to identify facilities that may benefit from targeted intervention.

Pilot-scale reactor activation facility at SRL

International Nuclear Information System (INIS)

Bowman, W.W.

1976-01-01

The Hydrogeocemical and Stream Sediment Reconnaissance portion of the National Uranium Resource Evaluation program requires an analytical technique for uranium and other elements. Based on an automated absolute activation analysis technique using 252 Cf, a pilt-scale facility installed in a production reactor has provided analyses for 2800 samples. Key features include: an automated sample transport system, a delayed neutron detector, two GeLi detectors, a loader, and an unloader, with all components controlled by a microprocessor; a dedicated PDP-9 computer and pulse height analyzer; and correlation and reduction of acquired data by a series of programs using an IBM 360/195 computer. The facility was calibrated with elemental and isotopic standards. Results of analyses of standard reference materials and operational detection limits for typical sediment samples are presented. Plans to increase sample throughput are discussed briefly

First hohlraum drive studies on the National Ignition Facility

International Nuclear Information System (INIS)

Dewald, E.L.; Landen, O.L.; Suter, L.J.; Schein, J.; Holder, J.; Campbell, K.; Glenzer, S.H.; McDonald, J.W.; Niemann, C.; Mackinnon, A.J.; Schneider, M.S.; Haynam, C.; Hinkel, D.; Hammel, B.A.

2006-01-01

The first hohlraum experiments on the National Ignition Facility (NIF) [G. H. Miller, E. I. Moses, and C. R. Wuest, Nucl. Fusion 44, 228 (2004)] using the first four laser beams have activated the indirect-drive experimental capabilities and tested radiation temperature limits imposed by hohlraum plasma filling. Vacuum hohlraums have been irradiated with laser powers up to 9 TW, 1 to 9 ns long square pulses and energies of up to 17 kJ to study the hohlraum radiation temperature scaling with the laser power and hohlraum size, and to make contact with hohlraum experiments performed previously at other laser facilities. Furthermore, for a variety of hohlraum sizes and pulse lengths, the measured x-ray flux shows signatures of plasma filling that coincide with hard x-ray emission from plasma streaming out of the hohlraum. These observations agree with hydrodynamic simulations and with analytical modeling that includes hydrodynamic and coronal radiative losses. The modeling predicts radiation temperature limits on full NIF (1.8 MJ) that are significantly greater than required for ignition hohlraums

Preliminary safety assessment of the WIPP facility

International Nuclear Information System (INIS)

Balestri, R.J.; Torres, B.W.; Pahwa, S.B.; Brannen, J.P.

1979-01-01

This paper summarizes the efforts to perform a safety assessment of the Waste Isolation Pilot Plant (WIPP) facility being proposed for southeastern New Mexico. This preliminary safety assessment is limited to a consequence assessment in terms of the dose to a maximally exposed individual as a result of introducing the radionuclides into the biosphere. The extremely low doses to the organs as a result of the liquid breach scenarios are contrasted with the background radiation

Study on system integration of robots operated in nuclear fusion facility and nuclear power plant facilities

International Nuclear Information System (INIS)

Oka, Kiyoshi

2004-07-01

A present robot is required to apply to many fields such as amusement, welfare and protection against disasters. The are however only limited numbers of the robots, which can work under the actual conditions as a robot system. It is caused by the following reasons: (1) the robot system cannot be realized by the only collection of the elemental technologies, (2) the performance of the robot is determined by that of the integrated system composed of the complicated elements with many functions, and (3) the respective elements have to be optimized in the integrated robot system with a well balance among them, through their examination, adjustment and improvement. Therefore, the system integration of the robot composed of a large number of elements is the most critical issue to realize the robot system for actual use. In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environment and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. (author)

The regulation of uranium refineries and conversion facilities in Canada

International Nuclear Information System (INIS)

Didyk, J.P.

1986-04-01

The nuclear regulatory process as it applies to uranium refineries and conversion facilities in Canada is reviewed. In the early 1980s, Eldorado Resources Limited proposed to construct and operate new facilities for refining yellowcake and for the production of uranium hexafluoride (UF 6 ). These projects were subject to regulation by the Atomic Energy Control Board (AECB). A description of the AECB's comprehensive licensing process covering all stages of siting, construction, operation and eventual decommissioning of nuclear facilities is traced as it was applied to the Eldorado projects. The AECB's concern with occupational health and safety, with public health and safety and with the protection of the environment in so far as it affects public health and safety is emphasized. Some regulatory difficulties encountered during the project's development which led to opening up the licensing process to public input and closer coordination of regulatory activities with other provincial and federal regulatory agencies are described. The Board's regulatory operational compliance program for uranium refineries and conversion facilities is summarized

Interim nuclear spent fuel storage facility - From complete refusal to public acceptance

International Nuclear Information System (INIS)

Kacena, Michal

1998-01-01

Full text: As usual in P.R., there was a complicated, politically sensitive situation we had to face at the beginning and it wasn't easy to create the right P.R. programme with the right targets: CEZ needed a new storage facility for the nuclear spent fuel from its two NPPs - Dukovany and Temelin. Firstly, CEZ preferred to build an on-site facility for the Dukovany NPP to last until the year 2004; secondly, a facility for the Temelin NPP several years later. But the Czech Government decided to limit Dukovany's storage capacity during a public discussion in 1992. Therefore, at the end of 1993, CEZ started the site selection process for a central storage facility targeted at ten regions in the country. In P.R. we decided on two main goals: 1. To gain public acceptance of a central storage facility at least at one site, and hopefully at more. 2. To change public opinion (especially around the Dukovany NPP) in order to create the proper atmosphere for changing the government's decision to limit storage capacity. We wanted to prove that we could choose the fight technical and economical solution without political limits. This obviously presented a challenge as it would be problematic for CEZ to be very visible in the campaign: We wanted people to know that the government had made a bad decision, but we also had to make it clear that our objections were based not on questions of momentary corporate advantage but instead on solid technical grounds. Most would only see self interest. We wanted to show them the facts. Of course, some times it wasn't easy to hit both targets at the same time. There was a lot of hard work in the middle. We gained new experience and we learned a lot trying to get public confidence in nuclear safety, in our company's reliability and in some local profits for a storage site: Firstly none of those regions was excited by the idea o a storage facility in its backyard. Most of them were very strongly and actively against it and did not want to

State of exposure control for workers engaging in radiation works and state of radioactive waste management in nuclear reactor facilities for test and research and nuclear reactor facilities at research and development stage, fiscal year 1995

International Nuclear Information System (INIS)

1996-01-01

This is the summary of the reports submitted in fiscal year 1995 by the installers of the nuclear reactor facilities for test and research or at research and development stage, conforming to the related law. The individual dose equivalent of the workers engaging in radiation works in fiscal year 1995 was sufficiently lower than the prescribed limit in all reactor facilities. As for the released quantities of gaseous and liquid wastes, the radioactive substances in the air and water outside the monitor zones never exceeded the prescribed concentration limit in all reactor facilities. In the reactor facilities, for which the target values of release control have been determined, the values were less than the targets in all cases. The increase of stored radioactive solid waste decreased as the dismantling works of the reactor auxiliary system of the nuclear powered ship 'Mutsu' were finished in fiscal year 1994. As the amount of stored radioactive solid waste approaches the installed capacity, the preservation capacity of the existing waste preservation building was increased. (K.I.)

Phytochrome-mediated responses: Implications for controlled environment research facilities

Science.gov (United States)

Smith, Harry

1994-01-01

Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic response that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at about 700 nm, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

Phytochrome-mediated responses implications for controlled environment research facilities

Energy Technology Data Exchange (ETDEWEB)

Smith, H. [Univ. of Leicester (United Kingdom)

1994-12-31

Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic responses that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at ca. 700 mn, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

Challenges with implementing malaria rapid diagnostic tests at primary care facilities in a Ghanaian district: a qualitative study.

Science.gov (United States)

Boadu, Nana Yaa; Amuasi, John; Ansong, Daniel; Einsiedel, Edna; Menon, Devidas; Yanow, Stephanie K

2016-02-27

Rapid diagnostic Tests (RDTs) for malaria enable diagnostic testing at primary care facilities in resource-limited settings, where weak infrastructure limits the use of microscopy. In 2010, Ghana adopted a test-before-treat guideline for malaria, with RDT use promoted to facilitate diagnosis. Yet healthcare practitioners still treat febrile patients without testing, or despite negative malaria test results. Few studies have explored RDT implementation beyond the notions of provider or patient acceptability. The aim of this study was to identify the factors directly influencing malaria RDT implementation at primary care facilities in a Ghanaian district. Qualitative interviews, focus groups and direct observations were conducted with 50 providers at six purposively selected primary care facilities in the Atwima-Nwabiagya district. Data were analysed thematically. RDT implementation was hampered by: (1) healthcare delivery constraints (weak supply chain, limited quality assurance and control, inadequate guideline emphasis, staffing limitations); (2) provider perceptions (entrenched case-management paradigms, limited preparedness for change); (3) social dynamics of care delivery (expected norms of provider-patient interaction, test affordability); and (4) limited provider engagement in policy processes leading to fragmented implementation of health sector reform. Limited health system capacity, socio-economic, political, and historical factors hampered malaria RDT implementation at primary care facilities in the study district. For effective RDT implementation providers must be: (1) adequately enabled through efficient allocation and management of essential healthcare commodities; (2) appropriately empowered with the requisite knowledge and skill through ongoing, effective professional development; and (3) actively engaged in policy dialogue to demystify socio-political misconceptions that hinder health sector reform policies from improving care delivery. Clear

Atmospheric Pathway Screening Analysis for Saltstone Disposal Facility Vault 4

International Nuclear Information System (INIS)

COOK, JAMES

2004-01-01

A sequential screening process using a methodology developed by the National Council on Radiation Protection and Measurements, professional judgment and process knowledge has been used to produce a list of radionuclides requiring detailed analysis to derive disposal limits for the Saltstone Disposal Facility based on the atmospheric pathway

9 CFR 203.12 - Statement with respect to providing services and facilities at stockyards on a reasonable and...

Science.gov (United States)

2010-01-01

..., marketing, buying, or selling on a commission basis or otherwise, feeding, watering, holding, delivery..., buying, or selling on a commission basis or otherwise, marketing, feeding, watering, holding, delivery... facilities. Such services and facilities include, but are not limited to, the restaurant, restrooms, drinking...

Safety assessment on the human intrusion scenarios of near surface disposal facility for low and very low level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Hong, Sung Wook; Park, Jin Baek [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Park, Sang Ho [Chungnam National University, Daejeon (Korea, Republic of)

2016-03-15

The second-stage near surface disposal facility for low and very low level radioactive waste's permanent disposal is to be built. During the institutional control period, the inadvertent intrusion of the general public is limited. But after the institutional control period, the access to the general public is not restricted. Therefore human who has purpose of residence and resource exploration can intrude the disposal facility. In this case, radioactive effects to the intruder should be limited within regulatory dose limits. This study conducted the safety assessment of human intrusion on the second-stage surface disposal facility through drilling and post drilling scenario. Results of drilling and post drilling scenario were satisfied with regulatory dose limits. The result showed that post-drilling scenario was more significant than drilling scenario. According to the human intrusion time and behavior after the closure of the facility, dominant radionuclide contributing to the intruder was different. Sensitivity analyses on the parameters about the human behavior were also satisfied with regulatory dose limits. Especially, manual redistribution factor was the most sensitive parameter on exposure dose. A loading plan of spent filter waste and dry active waste was more effective than a loading plan of spent filter waste and other wastes for the radiological point of view. These results can be expected to provide both robustness and defense in depth for the development of safety case further.

Scoping-level Probabilistic Safety Assessment of a complex experimental facility: Challenges and first results from the application to a neutron source facility (MEGAPIE)

International Nuclear Information System (INIS)

Podofillini, L.; Dang, V.N.; Thomsen, K.

2008-01-01

This paper presents a scoping-level application of Probabilistic Safety Assessment (PSA) to selected systems of a complex experimental facility. In performing a PSA for this type of facility, a number of challenges arise, mainly due to the extensive use of electronic and programmable components and of one-of-a-kind components. The experimental facility is the Megawatt Pilot Target Experiment (MEGAPIE), which was hosted at the Paul Scherrer Institut (PSI). MEGAPIE demonstrated the feasibility of a liquid lead-bismuth target for spallation facilities at a proton beam power level of 1 MW. Given the challenges to estimate initiating event frequencies and failure event probabilities, emphasis is placed on the qualitative results obtainable from the PSA. Even though this does not allow a complete and appropriate characterization of the risk profile, some level of importance/significance evaluation was feasible, and practical and detailed recommendations on potential system improvements were derived. The second part of the work reports on a preliminary quantification of the facility risk. This provides more information on risk significance, which allows prioritizing the insights and recommendations obtained from the PSA. At the present stage, the limited knowledge on initiating and failure events is reflected in the uncertainties in their probabilities as well as in inputs quantified with bounding values. Detailed analyses to improve the quantification of these inputs, many of which turn out to be important contributors, were out of the scope of this study. Consequently, the reported results should be primarily considered as a demonstration of how quantification of the facility risk by a PSA can support risk-informed decisions, rather than precise figures of the facility risk

Facility Design and Health Management Program at the Sinnhuber Aquatic Research Laboratory.

Science.gov (United States)

Barton, Carrie L; Johnson, Eric W; Tanguay, Robert L

2016-07-01

The number of researchers and institutions moving to the utilization of zebrafish for biomedical research continues to increase because of the recognized advantages of this model. Numerous factors should be considered before building a new or retooling an existing facility. Design decisions will directly impact the management and maintenance costs. We and others have advocated for more rigorous approaches to zebrafish health management to support and protect an increasingly diverse portfolio of important research. The Sinnhuber Aquatic Research Laboratory (SARL) is located ∼3 miles from the main Oregon State University campus in Corvallis, Oregon. This facility supports several research programs that depend heavily on the use of adult, larval, and embryonic zebrafish. The new zebrafish facility of the SARL began operation in 2007 with a commitment to build and manage an efficient facility that diligently protects human and fish health. An important goal was to ensure that the facility was free of Pseudoloma neurophilia (Microsporidia), which is very common in zebrafish research facilities. We recognize that there are certain limitations in space, resources, and financial support that are institution dependent, but in this article, we describe the steps taken to build and manage an efficient specific pathogen-free facility.

Hong kong chemical waste treatment facilities: a technology overview

Energy Technology Data Exchange (ETDEWEB)

Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

1994-12-31

The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

Extraction and beam transfer for the SHiP facility

CERN Document Server

Goddard, Brennan; Borburgh, Jan; Balhan, Bruno; Le Godec, Gilles; Zerlauth, Markus; Tommasini, Davide; Kain, Verena; Cornelis, Karel; Wenninger, Jorg; Jensen, Lars; Todd, Benjamin; Bauche, Jeremie; Puccio, Bruno

2015-01-01

This document summarises the key feasibility issues associated with the SPS extraction and beam transfer systems required for the SHiP facility. It describes the expected performance limits of the electrostatic septa, the expected beam losses during extraction and consequences, the design of the new beamline geometry and equipment systems and the expected extracted spill structure.

Hong kong chemical waste treatment facilities: a technology overview

Energy Technology Data Exchange (ETDEWEB)

Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

1993-12-31

The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

Biochemistry Facility

Data.gov (United States)

Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

Facility effluent monitoring plan for the plutonium-uranium extraction facility

International Nuclear Information System (INIS)

Nickels, J.M.; Geiger, J.L.

1992-11-01

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. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation requires 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. 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

Jupiter Laser Facility

Data.gov (United States)

Federal Laboratory Consortium — The Jupiter Laser Facility is an institutional user facility in the Physical and Life Sciences Directorate at LLNL. The facility is designed to provide a high degree...

Capability of the electromagnetic isotope-enrichment facility at ORNL

International Nuclear Information System (INIS)

Newman, E.

1982-01-01

The isotope separation program at Oak Ridge National Laboratory (ORNL) prepares and distributes electromagnetically enriched stable isotopes to the worldwide scientific community. Among the topics discussed in the present paper are the methods of enriching isotopes, the limitations that apply to the quantity and final assay of the separation products, and a generalized production flowsheet indicating the capability of the facility. A brief description of each of the production steps, from the selection and preparation of initial feedstock to the recovery and distribution of the isotopically enriched material, is presented. The future of the facility, the continued supply of enriched isotopes, and the response of the program to new and changing requirements are emphasized

Potential reuse of petroleum-contaminated soil: A directory of permitted recycling facilities

International Nuclear Information System (INIS)

Rosenthal, S.; Wolf, G.; Avery, M.; Nash, J.H.

1992-06-01

Soil contaminated by virgin petroleum products leaking from underground storage tanks is a pervasive problem in the United States. Economically feasible disposal of such soil concerns the responsible party (RP), whether the RP is one individual small business owner, a group of owners, or a large multinational corporation. They may need a starting point in their search for an appropriate solution, such as recycling. The report provides initial assistance in two important areas. First it discusses four potential recycling technologies that manufacture marketable products from recycled petroleum-contaminated soil: the hot mix asphalt process, the cold mix asphalt system, cement production, and brick manufacturing. The report also presents the results of a project survey designed to identify recycling facilities. It lists recycling facilities alphabetically by location within each state, organized by U.S. Environmental Protection Agency (EPA) Region. The report also includes detailed addresses, recycling locations, telephone numbers, and contacts for these facilities. The scope of the project limits listings to fixed facilities or small mobile facility owners that recycle soil contaminated by virgin petroleum products into marketable commodities. It does not address site-specific or commercial hazardous waste remediation facilities

Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

International Nuclear Information System (INIS)

Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

1993-08-01

Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

Liquid Effluent Retention Facility/Effluent Treatment Facility Hazards Assessment

International Nuclear Information System (INIS)

Simiele, G.A.

1994-01-01

This document establishes the technical basis in support of Emergency Planning activities for the Liquid Effluent Retention Facility and Effluent Treatment Facility the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

Antimicrobial stewardship in long term care facilities: what is effective?

Science.gov (United States)

Nicolle, Lindsay E

2014-02-12

Intense antimicrobial use in long term care facilities promotes the emergence and persistence of antimicrobial resistant organisms and leads to adverse effects such as C. difficile colitis. Guidelines recommend development of antimicrobial stewardship programs for these facilities to promote optimal antimicrobial use. However, the effectiveness of these programs or the contribution of any specific program component is not known. For this review, publications describing evaluation of antimicrobial stewardship programs for long term care facilities were identified through a systematic literature search. Interventions included education, guidelines development, feedback to practitioners, and infectious disease consultation. The studies reviewed varied in types of facilities, interventions used, implementation, and evaluation. Comprehensive programs addressing all infections were reported to have improved antimicrobial use for at least some outcomes. Targeted programs for treatment of pneumonia were minimally effective, and only for indicators of uncertain relevance for stewardship. Programs focusing on specific aspects of treatment of urinary infection - limiting treatment of asymptomatic bacteriuria or prophylaxis of urinary infection - were reported to be effective. There were no reports of cost-effectiveness, and the sustainability of most of the programs is unclear. There is a need for further evaluation to characterize effective antimicrobial stewardship for long term care facilities.

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

Principles and guidelines for radioactive waste disposal facilities

International Nuclear Information System (INIS)

1988-06-01

Four basic principles relevant to radioactive waste disposal identified. These principles cover the justification of the activity giving rise to the waste, the consideration of risk to present and future generations, the minimization of the need for intervention in the future, and the financial obligations of the licensee. The use of risk limits as opposed to dose limits associated with disposal is discussed, as are the concepts of critical group, de minimis, and ALARA, in the context of a waste disposal facility. Guidance is given on the selection of the preferred waste disposal concept from among several alternatives, and for judging proposed design improvements to the chosen concept

40 CFR 63.5780 - What is the purpose of this subpart?

Science.gov (United States)

2010-07-01

... Standards for Hazardous Air Pollutants: Reinforced Plastic Composites Production What This Subpart Covers... for hazardous air pollutants (NESHAP) for reinforced plastic composites production. This subpart also...

Critical Protection Item classification for a waste processing facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.; Garrett, R.J.

1993-01-01

This paper describes the methodology for Critical Protection Item (CPI) classification and its application to the Structures, Systems and Components (SSC) of a waste processing facility at the Savannah River Site (SRS). The WSRC methodology for CPI classification includes the evaluation of the radiological and non-radiological consequences resulting from postulated accidents at the waste processing facility and comparison of these consequences with allowable limits. The types of accidents considered include explosions and fire in the facility and postulated accidents due to natural phenomena, including earthquakes, tornadoes, and high velocity straight winds. The radiological analysis results indicate that CPIs are not required at the waste processing facility to mitigate the consequences of radiological release. The non-radiological analysis, however, shows that the Waste Storage Tank (WST) and the dike spill containment structures around the formic acid tanks in the cold chemical feed area and waste treatment area of the facility should be identified as CPIs. Accident mitigation options are provided and discussed

Strategic analysis of International Forest Products Limited

OpenAIRE

Modesto, Robin M.

2005-01-01

International Forest Products Limited is a sawmilling company that produces softwood lumber for sale in domestic and international markets including the United States and Japan. Production facilities located in British Columbia, Washington and Oregon produce nearly 1.5 billion board feet of lumber annually. Timber is secured through Crown forest tenure holdings and external open market purchases. This paper includes: a strategic analysis of the firm; an industry analysis; a strategic fit anal...

Research Facilities | Wind | NREL

Science.gov (United States)

Research Facilities Research Facilities NREL's state-of-the-art wind research facilities at the Research Facilities Photo of five men in hard hards observing the end of a turbine blade while it's being tested. Structural Research Facilities A photo of two people silhouetted against a computer simulation of

Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.

1993-01-01

This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

Waste Facilities

Data.gov (United States)

Vermont Center for Geographic Information — This dataset was developed from the Vermont DEC's list of certified solid waste facilities. It includes facility name, contact information, and the materials...

Fabrication Facilities

Data.gov (United States)

Federal Laboratory Consortium — The Fabrication Facilities are a direct result of years of testing support. Through years of experience, the three fabrication facilities (Fort Hood, Fort Lewis, and...

Operational Readiness Review: Savannah River Replacement Tritium Facility

International Nuclear Information System (INIS)

1993-02-01

The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members

Potential applications of fusion neutral beam facilities for advanced material processing

International Nuclear Information System (INIS)

Williams, J.M.; Tsai, C.C.; Stirling, W.L.; Whealton, J.H.

1994-01-01

Surface processing techniques involving high energy ion implantation have achieved commercial success for semiconductors and biomaterials. However, wider use has been limited in good part by economic factors, some of which are related to the line-of-sight nature of the beam implantation process. Plasma source ion implantation is intended to remove some of the limitations imposed by directionality of beam systems and also to help provide economies of scale. The present paper will outline relevant technologies and areas of expertise that exist at Oak Ridge National Laboratory in relation to possible future needs in materials processing. Experience in generation of plasmas, control of ionization states, pulsed extraction, and sheath physics exists. Contributions to future technology can be made either for the immersion mode or for the extracted beam mode. Existing facilities include the High Power Test Facility, which could conservatively operate at 1 A of continuous current at 100 kV delivered to areas of about 1 m 2 . Higher instantaneous voltages and currents are available with a reduced duty cycle. Another facility, the High Heat Flux Facility can supply a maximum of 60 kV and currents of up to 60 A for 2 s on a 10% duty cycle. Plasmas may be generated by use of microwaves, radio-frequency induction or other methods and plasma properties may be tailored to suit specific needs. In addition to ion implantation of large steel components, foreseeable applications include ion implantation of polymers, ion implantation of Ti alloys, Al alloys, or other reactive surfaces

Reed Reactor Facility annual report, September 1, 1994--August 31, 1995

International Nuclear Information System (INIS)

1995-01-01

This report covers the period from September 1, 1994 to August 31, 1995. Information contained in this report is intended to fulfill several purposes including the reporting requirements of the US Nuclear Regulatory Commission (USNRC), the US Department of Energy (USDOE), and the Oregon Department of Energy (ODOE). Highlights of the last year include: (1) The number of new licensed student operators more than replaced the number of graduating seniors. Seven Reed College seniors used the reactor as part of their thesis projects. (2) The facility has been extraordinarily successful in obtaining donated equipment from Portland General Electric, US Department of Energy, Precision Castparts, Tektronix, and other sources. Battelle (Pacific Northwest Laboratory) has been generous in lending valuable equipment to the college. (3) The facility is developing more paid work. Income in the past academic year was much greater than the previous year, and next year should increase by even more. Additionally, the US Department of Energy's Reactor-Use Sharing grant increased significantly this year. During the year, the reactor was operated 225 separate times on 116 days. The total energy production was 24.6 MW-hours. The reactor staff consists of a Director, an Assistant Director, a contract Health Physicist, and approximately fifteen Reed College undergraduate students as hourly employees. All radiation exposures to individuals during this year were well below one percent of the federal limits. There were no releases of liquid radioactive material from the facility and airborne releases (primarily 41 Ar) were well within regulatory limits. No radioactive waste was shipped from the facility during this period

Reed Reactor Facility annual report, September 1, 1994--August 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

This report covers the period from September 1, 1994 to August 31, 1995. Information contained in this report is intended to fulfill several purposes including the reporting requirements of the US Nuclear Regulatory Commission (USNRC), the US Department of Energy (USDOE), and the Oregon Department of Energy (ODOE). Highlights of the last year include: (1) The number of new licensed student operators more than replaced the number of graduating seniors. Seven Reed College seniors used the reactor as part of their thesis projects. (2) The facility has been extraordinarily successful in obtaining donated equipment from Portland General Electric, US Department of Energy, Precision Castparts, Tektronix, and other sources. Battelle (Pacific Northwest Laboratory) has been generous in lending valuable equipment to the college. (3) The facility is developing more paid work. Income in the past academic year was much greater than the previous year, and next year should increase by even more. Additionally, the US Department of Energy`s Reactor-Use Sharing grant increased significantly this year. During the year, the reactor was operated 225 separate times on 116 days. The total energy production was 24.6 MW-hours. The reactor staff consists of a Director, an Assistant Director, a contract Health Physicist, and approximately fifteen Reed College undergraduate students as hourly employees. All radiation exposures to individuals during this year were well below one percent of the federal limits. There were no releases of liquid radioactive material from the facility and airborne releases (primarily {sup 41}Ar) were well within regulatory limits. No radioactive waste was shipped from the facility during this period.

Target Visualization at the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Potter, Daniel Abraham [Univ. of California, Davis, CA (United States)

2011-01-01

As the National Ignition Facility continues its campaign to achieve ignition, new methods and tools will be required to measure the quality of the targets used to achieve this goal. Techniques have been developed to measure target surface features using a phase-shifting diffraction interferometer and Leica Microsystems confocal microscope. Using these techniques we are able to produce a detailed view of the shell surface, which in turn allows us to refine target manufacturing and cleaning processes. However, the volume of data produced limits the methods by which this data can be effectively viewed by a user. This paper introduces an image-based visualization system for data exploration of target shells at the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory. It aims to combine multiple image sets into a single visualization to provide a method of navigating the data in ways that are not possible with existing tools.

The rare isotope accelerator (RIA) facility project

International Nuclear Information System (INIS)

Christoph Leemann

2000-01-01

The envisioned Rare-Isotope Accelerator (RIA) facility would add substantially to research opportunities for nuclear physics and astrophysics by combining increased intensities with a greatly expanded variety of high-quality rare-isotope beams. A flexible superconducting driver linac would provide 100 kW, 400 MeV/nucleon beams of any stable isotope from hydrogen to uranium onto production targets. Combinations of projectile fragmentation, target fragmentation, fission, and spallation would produce the needed broad assortment of short-lived secondary beams. This paper describes the project's background, purpose, and status, the envisioned facility, and the key subsystem, the driver linac. RIA's scientific purposes are to advance current theoretical models, reveal new manifestations of nuclear behavior, and probe the limits of nuclear existence [3]. Figures 1 and 2 show, respectively, examples of RIA research opportunities and the yields projected for pursuing them. Figure 3 outlines a conceptual approach for delivering the needed beams

Phase 1 sampling and analysis plan for the 304 Concretion Facility closure activities

International Nuclear Information System (INIS)

Adler, J.G.

1994-01-01

This document provides guidance for the initial (Phase 1) sampling and analysis activities associated with the proposed Resource Conservation and Recovery Act of 1976 (RCRA) clean closure of the 304 Concretion Facility. Over its service life, the 304 Concretion Facility housed the pilot plants associated with cladding uranium cores, was used to store engineering equipment and product chemicals, was used to treat low-level radioactive mixed waste, recyclable scrap uranium generated during nuclear fuel fabrication, and uranium-titanium alloy chips, and was used for the repackaging of spent halogenated solvents from the nuclear fuels manufacturing process. The strategy for clean closure of the 304 Concretion Facility is to decontaminate, sample (Phase 1 sampling), and evaluate results. If the evaluation indicates that a limited area requires additional decontamination for clean closure, the limited area will be decontaminated, resampled (Phase 2 sampling), and the result evaluated. If the evaluation indicates that the constituents of concern are below action levels, the facility will be clean closed. Or, if the evaluation indicates that the constituents of concern are present above action levels, the condition of the facility will be evaluated and appropriate action taken. There are a total of 37 sampling locations comprising 12 concrete core, 1 concrete chip, 9 soil, 11 wipe, and 4 asphalt core sampling locations. Analysis for inorganics and volatile organics will be performed on the concrete core and soil samples. Separate concrete core samples will be required for the inorganic and volatile organic analysis (VOA). Analysis for inorganics only will be performed on the concrete chip, wipe, and asphalt samples

Overview of a conceptualized waste water treatment facility for the Consolidated Incinerator Facility

International Nuclear Information System (INIS)

McCabe, D.J.

1992-01-01

The offgas system in the Consolidated Incinerator Facility (CIF) will generate an aqueous waste stream which is expected to contain hazardous, nonhazardous, and radioactive components. The actual composition of this waste stream will not be identified until startup of the facility, and is expected to vary considerably. Wastewater treatment is being considered as a pretreatment to solidification in order to make a more stable final waste form and to reduce disposal costs. A potential treatment scenario has been defined which may allow disposition of this waste in compliance with all applicable regulations. The conceptualized wastewater treatment plant is based on literature evaluations for treating hazardous metals. Laboratory tests hwill be run to verify the design for its ability to remove the hazardous and radioactive components from this waste stream. The predominant mechanism employed for removal of the hazardous and radioactive metal ions is coprecipitation. The literature indicates that reasonably low quantities of hazardous metals can be achieved with this technique. The effect on the radioactive metal ions is not predictable and has not been tested. The quantity of radioactive metal ions predicted to be present in the waste is significantly less than the solubility limit of those ions, but is higher than the discharge guidelines established by DOE Order 5400.5

Leading by walking around in long-term care and transitional care facilities.

Science.gov (United States)

Kemerer, Douglas; Cwiekala-Lewis, Klaudia

2017-05-30

Nursing staff in long-term care/transitional care (LTC/TC) facilities in the US work in unique environments that can be stressful and demanding. There is much in the literature that describes different leadership styles in nursing, but a limited amount on leadership in LTC/TC environments. This article explores the concept of leading by walking around (LBWA), also known as leadership by walking, to cultivate therapeutic work environments in LTC/TC facilities in the US. It defines therapeutic work environments and describes the specific environment of LTC/TC facilities. It also briefly describes the nursing hierarchy and nurse education in the US. Finally, it describes the cultivation of therapeutic work environments by using LBWA and includes two examples of the concept in action.

EPA Facility Registry Service (FRS): Facility Interests Dataset Download

Data.gov (United States)

U.S. Environmental Protection Agency — This downloadable data package consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are...

Retrofit of waste-to-energy facilities equipped with electrostatic precipitators. Volume I: Report

Energy Technology Data Exchange (ETDEWEB)

Rigo, H.G. [Rigo & Rigo Associates, Inc., Berea, OH (US); Chandler, A.J. [A.J. Chandler & Associates, Ltd., Toronto, Ontario (Canada)

1996-04-01

To help lower the cost of compliance for waste-to-energy facilities, a retrofit technology using water spray temperature reduction combined with dry acid gas control reagent and powdered activated carbon [PAC] injection was tested in November, 1995 as part of an American Society of Mechanical Engineers' [ASME] Center for Research and Technology Development [CRTD] effort supported in part by the Department of Energy's National Renewable Energy Laboratory [NREL] and directed by the ASME Research Committee on Industrial and Municipal Waste. 2,000 mg/dsm{sup 3} @ 7% O{sub 2} (150 lb/hr) of trona (a natural sodium sesquicarbonate ore) injected through a rapid dispersion lance successfully controlled more than 50 percent of the acid gases. This should let facilities under 250 TPD meet the small plant guidelines for acid gas control. Various levels of PAC were injected along with the trona. 300 mg/dsm{sup 3} 7% O{sub 2} of PAC provides a comfortable margin between the emissions limitations achieved and both large and small plant regulatory guidelines for tetra- through octachlorinated dibenzo-p-dioxins and dibenzofurans [PCDD/F] and mercury when the ESP is operated below 350 F. Bi-fluid nozzles were used to spray finely atomized water between the economizer outlet and ESP inlet to maintain temperatures in the desired 300-350 F range. Particulate and metals emissions limitations were met by this 400 ft{sup 2}/1,000 acft{sup 2} specific collector area [SCA], 3-field ESP. Both the water sprays and PAC improved ESP performance. The demonstration was successful. With dry PAC, acid gas reagent injection, and temperature reduction, MWC emissions guidelines for facilities smaller than 250 TPD can be reliably met. Everything except the large facilities SO{sub 2} and HCl guideline emissions limitations was achieved. Better acid gas control should be achievable with more reagent addition if the ESP is efficient enough to avoid violating particulate limits.

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

Directory of Open Access Journals (Sweden)

M. V. Vedernikova

2017-01-01

Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

A spatial decision support system for special health facility location ...

African Journals Online (AJOL)

Access to healthcare is a determinant of the wellbeing of the people. Planning the location and distribution of health facilities to ensure efficiency and equity in the face of limited resources can be challenging, especially where the type of care requires expensive equipments and specialists. This study attempts to provide a ...

S.E.T., CSNI Separate Effects Test Facility Validation Matrix

International Nuclear Information System (INIS)

1997-01-01

1 - Description of test facility: The SET matrix of experiments is suitable for the developmental assessment of thermal-hydraulics transient system computer codes by selecting individual tests from selected facilities, relevant to each phenomena. Test facilities differ from one another in geometrical dimensions, geometrical configuration and operating capabilities or conditions. Correlation between SET facility and phenomena were calculated on the basis of suitability for model validation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant and is sufficiently instrumented); limited suitability for model variation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant but has problems associated with imperfect scaling, different test fluids or insufficient instrumentation); and unsuitability for model validation. 2 - Description of test: Whereas integral experiments are usually designed to follow the behaviour of a reactor system in various off-normal or accident transients, separate effects tests focus on the behaviour of a single component, or on the characteristics of one thermal-hydraulic phenomenon. The construction of a separate effects test matrix is an attempt to collect together the best sets of openly available test data for code validation, assessment and improvement, from the wide range of experiments that have been carried out world-wide in the field of thermal hydraulics. In all, 2094 tests are included in the SET matrix

Irradiation Facilities at CERN

CERN Document Server

Gkotse, Blerina; Carbonez, Pierre; Danzeca, Salvatore; Fabich, Adrian; Garcia, Alia, Ruben; Glaser, Maurice; Gorine, Georgi; Jaekel, Martin, Richard; Mateu,Suau, Isidre; Pezzullo, Giuseppe; Pozzi, Fabio; Ravotti, Federico; Silari, Marco; Tali, Maris

2017-01-01

CERN provides unique irradiation facilities for applications in many scientific fields. This paper summarizes the facilities currently operating for proton, gamma, mixed-field and electron irradiations, including their main usage, characteristics and information about their operation. The new CERN irradiation facilities database is also presented. This includes not only CERN facilities but also irradiation facilities available worldwide.

NESHAP for the Portland Cement Manufacturing Industry: Fact Sheets for Actions Since 2015

Science.gov (United States)

EPA is extending its approval for the use of an alternative method to show compliance with hydrogen chloride (HCl) emissions limits in the National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing Industry

The facilities management market in Denmark

DEFF Research Database (Denmark)

Jensen, Per Anker

2010-01-01

for researching the market but particular the definition of space including acquisition as well as development, administration, operation, maintenance and utilities in the same main product is problematic. Research limitations/implications: The market research is limited to the Danish market, but the results......Purpose: To present the results of market surveys in Denmark, which have been based on and used to test a proposal for a new European standard for a taxonomy of Facilities Management (FM). Design/methodology: The market research included surveys of both the client side and the provider side...... and was carried out by a management consultant company by telephone interviews based on definitions developed from drafts for the European FM taxonomy standard by a university researcher, who is a member of the standardisation work group. Findings: The proposed taxonomy for FM is in general a good basis...

Post-closure safety assessment of near surface disposal facilities for disused sealed radioactive sources

Energy Technology Data Exchange (ETDEWEB)

Lee, Seunghee; Kim, Juyoul, E-mail: gracemi@fnctech.com

2017-03-15

Highlights: • Post-closure safety assessment of near surface disposal facility for DSRS was performed. • Engineered vault and rock-cavern type were considered for normal and well scenario. • {sup 14}C, {sup 226}Ra, {sup 241}Am were primary nuclides contributing large portion of exposure dose. • Near surface disposal of DSRSs containing {sup 14}C, {sup 226}Ra and {sup 241}Am should be restricted. - Abstract: Great attention has been recently paid to the post-closure safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility for disused sealed radioactive sources (DSRSs) around the world. Although the amount of volume of DSRSs generated from industry, medicine and research and education organization was relatively small compared with radioactive wastes from commercial nuclear power plants, some DSRSs can pose a significant hazard to human health due to their high activities and long half-lives, if not appropriately managed and disposed. In this study, post-closure safety assessment was carried out for DSRSs generated from 1991 to 2014 in Korea in order to ensure long-term safety of near surface disposal facilities. Two kinds of disposal options were considered, i.e., engineered vault type disposal facility and rock-cavern type disposal facility. Rock-cavern type disposal facility has been under operation in Gyeongju city, republic of Korea since August 2015 and engineered vault type disposal facility will be constructed until December 2020 in the vicinity of rock-cavern disposal facility. Assessment endpoint was individual dose to the member of critical group, which was modeled by GoldSim, which has been widely used as probabilistic risk analysis software based on Monte Carlo simulation in the area of safety assessment of radioactive waste facilities. In normal groundwater scenario, the maximum exposure dose was extremely low, approximately 1 × 10{sup −7} mSv/yr, for both disposal options and satisfied the regulatory limit

EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet

Data.gov (United States)

U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

International Nuclear Information System (INIS)

1993-08-01

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993

Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

76 FR 28121 - Notice of Passenger Facility Charge (PFC) Approvals and Disapprovals

Science.gov (United States)

2011-05-13

... fencing. Acquire radio equipment for emergency operations center. Interactive employee training system... survey and wildlife assessment. Decision Date: March 17, 2011. FOR FURTHER INFORMATION CONTACT: Lori...: Aircraft rescue and firefighting facility. Determination: The approval of this project is limited to the...

Detailed description of an SSAC at the facility level for research reactors

International Nuclear Information System (INIS)

Jones, R.J.

1984-09-01

The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

EPA Facility Registry Service (FRS): AIRS_AFS Sub Facilities

Data.gov (United States)

U.S. Environmental Protection Agency — The Air Facility System (AFS) contains compliance and permit data for stationary sources regulated by EPA, state and local air pollution agencies. The sub facility...

Food irradiation: Gamma processing facilities

Energy Technology Data Exchange (ETDEWEB)

Kunstadt, P. [MDS Nordion International, 447 March Road. Kanata, Ontario, K2K148 (Canada)

1997-12-31

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Food irradiation: Gamma processing facilities

Energy Technology Data Exchange (ETDEWEB)

Kunstadt, P [MDS Nordion International, 447 March Road. Kanata, Ontario, K2K148 (Canada)

1998-12-31

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Food irradiation: Gamma processing facilities

International Nuclear Information System (INIS)

Kunstadt, P.

1997-01-01

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Facility effluent monitoring plan for the fast flux test facility

International Nuclear Information System (INIS)

Nickels, J.M.; Dahl, N.R.

1992-11-01

A facility effluent monitoring plan is required by the US Department of Energy in US Department of Energy 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 requires the need for a facility effluent monitoring plan. 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

Integrated safeguards and facility design and operations

International Nuclear Information System (INIS)

Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

1987-01-01

The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

Project W-420 Stack Monitoring system upgrades conceptual design report

International Nuclear Information System (INIS)

TUCK, J.A.

1998-01-01

This document describes the scope, justification, conceptual design, and performance of Project W-420 stack monitoring system upgrades on six NESHAP-designated, Hanford Tank Farms ventilation exhaust stacks

Project W-420 Stack Monitoring system upgrades conceptual design report

Energy Technology Data Exchange (ETDEWEB)

TUCK, J.A.

1998-11-06

This document describes the scope, justification, conceptual design, and performance of Project W-420 stack monitoring system upgrades on six NESHAP-designated, Hanford Tank Farms ventilation exhaust stacks.

DUPIC facility engineering

Energy Technology Data Exchange (ETDEWEB)

Lee, J S; Choi, J W; Go, W I; Kim, H D; Song, K C; Jeong, I H; Park, H S; Im, C S; Lee, H M; Moon, K H; Hong, K P; Lee, K S; Suh, K S; Kim, E K; Min, D K; Lee, J C; Chun, Y B; Paik, S Y; Lee, E P; Yoo, G S; Kim, Y S; Park, J C

1997-09-01

In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs.

DUPIC facility engineering

International Nuclear Information System (INIS)

Lee, J. S.; Choi, J. W.; Go, W. I.; Kim, H. D.; Song, K. C.; Jeong, I. H.; Park, H. S.; Im, C. S.; Lee, H. M.; Moon, K. H.; Hong, K. P.; Lee, K. S.; Suh, K. S.; Kim, E. K.; Min, D. K.; Lee, J. C.; Chun, Y. B.; Paik, S. Y.; Lee, E. P.; Yoo, G. S.; Kim, Y. S.; Park, J. C.

1997-09-01

In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs

Innovations to increase throughput of the multipurpose irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, Estelita G; Lanuza, Luvimina G; Maningas, Aurelio L; Solomon, Haydee M [Irradiation Services Unit, Nuclear Services and Training Division, Philippine Nuclear Research Institute, Quezon City (Philippines)

1998-07-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Innovations to increase throughput of the multipurpose irradiation facility

International Nuclear Information System (INIS)

Cabalfin, Estelita G.; Lanuza, Luvimina G.; Maningas, Aurelio L.; Solomon, Haydee M.

1998-01-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Assessment of concentration limit for the safe disposal of very low level wastes

International Nuclear Information System (INIS)

Nam, Yun Seog

2008-02-01

The large amounts of radionuclides are generated from the decommissioning of nuclear facilities (included the nuclear power plant). Because of this, countries or agencies using the nuclear power are one of considering issues for the effective disposal. Among decommissioning wastes, wastes have no or very limited radioactivity are disposed of in conventional landfill or recycled thought approval from regulatory control. And wastes like LILW (Low and Intermediate Level Wastes) or HLW (High Level Wastes) are sent the repository or the interim storage facilities. In order to solve the space problem of the LILW repository and reduce disposal costs, some LLW which are relatively lower than other LLW are classified as VLLW (Very Low Level Wastes). IAEA is added to the VLLW category of the radioactive waste classification and some countries are operating a VLLW disposal facility or will be operating. In this study, the VLLW acceptance criteria of each radionuclide are derived by considering the inadvertent human intrusion scenario applying to a study on the near-surface disposal (LILW). The effect of important parameter, especially, waste isolation period, dilution factor and food consumption rate, is considered. It is concluded that the concentration limits of radionuclides considering in this study are evaluated approximately between 1 and 100 Bq/g. These values are similar to the case of France and Spain and the IAEA's predicted values. Based on this study, acceptance criteria of VLLW disposal facilities are suggested. And this study is contributed to the public relations for the safety of the VLLW disposal facility

National Emission Standards for Hazardous Air Pollutants (NESHAP) for Lime Manufacturing Background Information Document (BID): Public Comments and Responses

Science.gov (United States)

On December 20, 2002, the EPA proposed national emission standards for HAP emissions from lime manufacturing plants located at major source facilities (67 FR 78046). Summaries of the comments, and the EPA's responses, are presented in this BID.

Health Facilities

Science.gov (United States)

Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, ... psychiatric care centers. When you choose a health facility, you might want to consider How close it ...

Effects of an oxidizing atmosphere in a spent fuel packaging facility

International Nuclear Information System (INIS)

Einziger, R.E.

1991-09-01

Sufficient oxidation of spent fuel can cause a cladding breach to propagate, resulting in dispersion of fuel particulates and gaseous radionuclides. The literature for spent fuel oxidation in storage and disposal programs was reviewed to evaluate the effect of an oxidizing atmosphere in a preclosure packaging facility on (1) physical condition of the fuel and (2) operations in the facility. Effects such as cladding breach propagation, cladding oxidation, rod dilation, fuel dispersal, 14 C and 85 Kr release, and crud release were evaluated. The impact of these effects, due to oxidation, upon a spent fuel handling facility is generally predicted to be less than the impact of similar effects due to fuel rod breached during handling in an inert-atmosphere facility. Preliminary temperature limits of 240 degree C and 227 degree C for a 2-week or 4-week handling period and 175 degree C for 2-year lag storage would prevent breach propagation and fuel dispersal. Additional data that are needed to support the assumptions in this analysis or complete the database were identified

Radiological and environmental safety in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Puranik, V.D.

2011-01-01

The front end nuclear fuel cycle comprises of mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad. The Health Physics Units (HPUs)/Environmental Survey Laboratories (ESLs) set up at each site from inception of operation to carry out regular in-plant, personnel monitoring and environmental surveillance to ensure safe working conditions, evaluate radiation exposure of workers, ensure compliance with statutory norms, help in keeping the environmental releases well within the limits and advise appropriate control measures. This paper describes the occupational and environmental radiological safety measures associated with the operations of front end of nuclear fuel cycle. Radiological monitoring in these facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised in this paper

Report: EPA Lacks Internal Controls to Prevent Misuse of Emergency Drinking Water Facilities

Science.gov (United States)

Report #11-P-0001, October 12, 2010. EPA cannot accurately assess the risk of public water systems delivering contaminated drinking water from emergency facilities because of limitations in Safe Drinking Water Information System (SDWIS) data management.

ORNL facilities for testing first-wall components

International Nuclear Information System (INIS)

Tsai, C.C.; Becraft, W.R.; Gardner, W.L.; Haselton, H.H.; Hoffman, D.J.; Menon, M.M.; Stirling, W.L.

1985-01-01

Future long-impulse magnetic fusion devices will have operating characteristics similar to those described in the design studies of the Tokamak Fusion Core Experiment (TFCX), the Fusion Engineering Device (FED), and the International Tokamak Reactor (INTOR). Their first-wall components (pumped limiters, divertor plates, and rf waveguide launchers with Faraday shields) will be subjected to intense bombardment by energetic particles exhausted from the plasma, including fusion products. These particles are expected to have particle energies of approx.100 eV, particle fluxes of approx.10 18 cm -2 .s -1 , and heat fluxes of approx.1 kW/cm 2 CW to approx.100 kW/cm 2 transient. No components are available to simultaneously handle these particle and heat fluxes, survive the resulting sputtering erosion, and remove exhaust gas without degrading plasma quality. Critical issues for research and development of first-wall components have been identified in the INTOR Activity. Test facilities are needed to qualify candidate materials and develop components. At Oak Ridge National Laboratory (ORNL), existing neutral beam and wave heating test facilities can be modified to simulate first-wall environments with heat fluxes up to 30 kW/cm 2 , particle fluxes of approx.10 18 cm -2 .s -1 , and pulse lengths up to 30 s, within test volumes up to approx.100 L. The characteristics of these test facilities are described, with particular attention to the areas of particle flux, heat flux, particle energy, pulse length, and duty cycle, and the potential applications of these facilities for first-wall component development are discussed

Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

International Nuclear Information System (INIS)

Chatt, A.; Holzbecher, J.

1990-01-01

SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

The BNCT facility at the HFR Petten: Quality assurance for reactor facilities in clinical trials

International Nuclear Information System (INIS)

Moss, R.; Watkins, P.; Vroegindeweij, C.; Stecher-Rasmussen, F.; Huiskamp, R.; Ravensberg, K.; Appelman, K.; Sauerwein, W.; Hideghety, K.; Gabel, D.

2001-01-01

The first clinical trial in Europe of Boron Neutron Capture Therapy (BNCT) for the treatment of glioblastoma was opened in July 1997. The trial is a Phase I study with the principal aim to establish the maximum tolerated radiation dose and the dose limiting toxicity under defined conditions. It is the first time that a clinical application could be realised on a completely multi-national scale. The treatment takes place at the High Flux Reactor (HFR) in Petten, the Netherlands, is operated by an international team of experts under the leadership of a German radiotherapist, and treats patients coming from different European countries. It has therefore been necessary to create a very specialised organisation and contractual structure with the support of administrations from different countries, who had to find and adapt solutions within existing laws that had never foreseen such a situation. Furthermore, the treatment does not take place in an hospital environment and even more so, the facility is at a nuclear research reactor. Hence, special efforts were made on quality assurance, in order that the set-up at the facility and the personnel involved complied, as closely as possible, with similar practices in conventional radiotherapy departments. (author)

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, Michele; Kus, Jean-Pierre; Mogavero, Robert; Genelot, Gabriel

2009-01-01

Although the operational life of nuclear plants is long (around 60 years for French reactors) it is nonetheless limited in time, the stopping of it being essentially due to the obsolescence of materials and processes or to economic or safety considerations. The nuclear power plants are then subjected to cleanup and dismantling operations which have different objectives and require specific techniques. The cleanup and/or dismantling of a nuclear power produces significant quantities of waste which is generally of a different nature to that produced during the operation of the concerned plant. The radioactive waste produced by these operations is destined to be sent to the waste disposal facilities of the French National Agency for the Management of Nuclear Waste. (authors)

DUPIC facility engineering

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Lee, H. H.; Kim, K. H. and others

2000-03-01

The objectives of this study are (1) the refurbishment for PIEF(Post Irradiation Examination Facility) and M6 hot-cell in IMEF(Irradiated Material Examination Facility), (2) the establishment of the compatible facility for DUPIC fuel fabrication experiments which is licensed by government organization, and (3) the establishment of the transportation system and transportation cask for nuclear material between facilities. The report for this project describes following contents, such as objectives, necessities, scope, contents, results of current step, R and D plan in future and etc.

Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment

Energy Technology Data Exchange (ETDEWEB)

Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

2004-09-30

CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and

A study on building performance analysis for energy retrofit of existing industrial facilities

International Nuclear Information System (INIS)

Gourlis, Georgios; Kovacic, Iva

2016-01-01

Highlights: • Thermal simulation of a historical industrial hall with limited data availability. • Considering waste heat from machinery after measuring production fluctuations. • Test of retrofit alternatives for roof and skylights. • Results indicate a significant reduction in heating energy demand up to 52%. • After retrofit naturally ventilated hall can achieve thermal comfort in summer. - Abstract: Due to the strengthening of regulations and codes on building energy performance, as well as with the application of national legislations regarding energy management and efficiency, existing industrial facilities are using thermal refurbishment and renovation as impetus for increasing their overall energy efficiency. This paper analyzes a building envelope refurbishment for a case study of an existing historical industrial facility. Critical parameters affecting energy performance of industrial buildings were identified by reviewing relevant literate. Two retrofit scenarios were developed and dynamic thermal simulation using EnergyPlus was implemented to evaluate the potential for improvement. Thereby the impact of interior loads was considered, determined by measurements conducted on factory machines, occupancy and lighting operation patterns. However, information regarding constructions of the existing facility and installed technical building services is limited. There is also uncertainty in the quantification of natural ventilation air change rate for such buildings. To overcome these limitations a study of various material databases was carried out, in order to assess data for building envelope composition. Input values for missing data were provided based on literature, allowing a fair comparison between refurbishment alternatives. Simulation results showed that the heating demand of the facility could be reduced up to 52%, indicating a significant potential for energy savings. Beyond that, thermal performance against summer overheating also

Subproject L-045H 300 Area Treated Effluent Disposal Facility

International Nuclear Information System (INIS)

1991-06-01

The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The ''300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations

Commissioning for the European XFEL facility

Science.gov (United States)

Nölle, D.

2017-06-01

The European XFEL is a 4th generation light source based on the Self Amplified Spontaneous Emission (SASE) FreeElectron-Laser concept. It is currently being commissioned in North- Germany. The core installation is a 17.5 GeV superconducting accelerator driving 3 SASE lines with photon energies from 1 to beyond 20 keV range with a maximum of 27.000 pulses per second. The international facility is organized as a limited liability company with shareholders from the contributing countries. DESY has taken over the leadership of the accelerator construction consortium, and will be in charge of the operation of the accelerator complex. The facility was set up with contributions from the 11 shareholder countries, either being hardware systems and/or staff or cash contributions. The construction is almost complete, and the commissioning phase has started by the end of 2015. This contribution will report the status of the accelerator complex with emphasis on the commissioning of the accelerator and an outlook to the commissioning of the SASE 1 FEL line.

Legal problems of waste treatment in German atomic energy facilities

International Nuclear Information System (INIS)

Pfaffelhuber, J.K.

1980-01-01

The execution of the strategies of waste treatment and disposal calls for the laws and regulations on the obligations of the owners of equipments and facilities and of the state for securing safety and the final elimination of radioactive wastes, which are defined mainly in Article 9 of Atomgesetz and Section 2 (Article 44 - 48) of the order on protection from radiation. The owners of equipments and facilities of atomic energy technology shall limit the emission of radiation to about 6% of internationally permissible values, avoid uncontrolled emission without fail, inspect emission and submit reports yearly to government offices. The owners have attention obligations to utilize harmlessly produced radioactive residues and the expanded or dismantled parts of radioactive equipments or to eliminate orderly such things as radioactive wastes, only when such utilization is unable technically or economically, or not adequate under the protection aims of Atomgesetz. The possessors of radioactive wastes shall deliver the wastes to the accumulation places of provinces for intermediate storage, to the facilities of the Federal Republic for securing safety or final storage, or the facilities authorized by government offices for the elimination of radioactive wastes. Provinces shall install the accumulation places for the intermediate storage of radioactive wastes produced in their territories, and the Federal Republic shall set up the facilities for securing safety and the final elimination of radioactive wastes (Article 9, Atomgesetz). (Okada, K.)

Development of an auditable safety analysis in support of a radiological facility classification

International Nuclear Information System (INIS)

Kinney, M.D.; Young, B.

1995-01-01

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

Pharmaceutical and Medicine Manufacturing Sector (NAICS 3254)

Science.gov (United States)

Find environmental regulatory and compliance information for the pharmaceutical manufacturing sector, including essential uses of CFCs, NESHAP for pharmaceutical production, effluent guidelines for wastewater and management of hazardous waste.

Cold Vacuum Drying facility design basis accident analysis documentation

International Nuclear Information System (INIS)

CROWE, R.D.

2000-01-01

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls

Cold Vacuum Drying facility design basis accident analysis documentation

Energy Technology Data Exchange (ETDEWEB)

CROWE, R.D.

2000-08-08

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

Environmental licensing of nuclear facilities: compatibility of technical competencies

International Nuclear Information System (INIS)

Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

1996-01-01

The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)