78 FR 54280 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-03

... safety-related batteries would remain operable if all the inter-cell and terminal connections were at the... new acceptance criteria for total battery connection resistance to ensure that the safety-related batteries can perform their specified safety function. Basis for proposed no significant hazards...

Evaluation of Environmental Conditions on the Curing Of Commercial Fixative and Intumescent Coatings

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nicholson, J. C.

2016-09-26

Performance metrics for evaluating commercial fixatives are often not readily available for important parameters that must be considered per the facility safety basis and the facility Basis for Interim Operations (BIO). One such parameter is the behavior of such materials in varied, “non-ideal” conditions where ideal is defined as 75 °F, 40% RH. Coupled with the inherent flammable nature of the fixative materials that can act to propagate flame along surfaces that are otherwise fireproof (concrete, sheet metal), much is left unknown when considering the safety basis implications for introducing these materials into nuclear facilities. Through SRNL’s efforts, three (3)more » fixatives, one (1) decontamination gel, and six (6) intumescent coatings were examined for their responses to environmental conditions to determine whether these materials were impervious to non-nominal temperatures and humidities that may be found in nuclear facilities. Characteristics that were examined included set-to-touch time, dust free time, and adhesion testing of the fully cured compounds. Of these ten materials, three were two-part epoxy materials while the other seven consisted of only one constituent. The results show that the epoxies tested are unable to cure in sub-freezing temperatures, with the low temperatures inhibiting crosslinking to a very significant degree. These efforts show significant inhibiting of performance for non-nominal environmental conditions, something that must be addressed both in the decision process for a fixative material to apply and per the safety basis to ensure the accurate flammability and material at risk is calculated.« less

10 CFR Appendix A to Subpart B of... - General Statement of Safety Basis Policy

Code of Federal Regulations, 2011 CFR

2011-01-01

... for the design and construction of a new DOE nuclear facility or a major modification to an existing... acceptable nuclear safety design criteria for use in preparing a preliminary documented safety analysis. As a... mitigate hazards to workers, the public, or the environment. They include (1) physical, design, structural...

Equivalent Safety Basis for Evaluation of On-Site Packages for US DOE Facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Smith, A.C.

Packages for transport of radioactive material within the boundaries of a Department of Energy facility (on-site) must conform to the requirements for packages shipped in normal commerce, or must provide equivalent safety. Equivalence is achieved if the frequency of severe on-site accidents, which could result in a release of radioactive material, is less than or equal to the frequency of Beyond-HAC accidents for packages in commerce. This is shown to be achieved it the rate of on-site accident is 22 per 100 MVM or lower. For equivalence to Normal Conditions of Transport, for on-site packages, appropriate, defensible Design Basis Conditionsmore » can be established and the ability of the package to meet the reduced requirements shown in the On-site Safety Assessment.« less

Egg processing plant sanitation, SSOPs, and GMPs.

USDA-ARS?s Scientific Manuscript database

The basis of food safety programs in processing facilities is prerequisite programs such as sanitation and good manufacturing practices. Thoughtful, thorough, and complete sanitation programs are necessary to enhance the food safety of products and reduce the likelihood of foodborne illness. Egg p...

Evaluation of radiological dispersion/consequence codes supporting DOE nuclear facility SARs

DOE Office of Scientific and Technical Information (OSTI.GOV)

O`Kula, K.R.; Paik, I.K.; Chung, D.Y.

1996-12-31

Since the early 1990s, the authorization basis documentation of many U.S. Department of Energy (DOE) nuclear facilities has been upgraded to comply with DOE orders and standards. In this process, many safety analyses have been revised. Unfortunately, there has been nonuniform application of software, and the most appropriate computer and engineering methodologies often are not applied. A DOE Accident Phenomenology and Consequence (APAC) Methodology Evaluation Program was originated at the request of DOE Defense Programs to evaluate the safety analysis methodologies used in nuclear facility authorization basis documentation and to define future cost-effective support and development initiatives. Six areas, includingmore » source term development (fire, spills, and explosion analysis), in-facility transport, and dispersion/ consequence analysis (chemical and radiological) are contained in the APAC program. The evaluation process, codes considered, key results, and recommendations for future model and software development of the Radiological Dispersion/Consequence Working Group are summarized in this paper.« less

Gas Generation Testing of Spherical Resorcinol-Formaldehyde (sRF) Resin

DOE Office of Scientific and Technical Information (OSTI.GOV)

Colburn, Heather A.; Bryan, Samuel A.; Camaioni, Donald M.

This report describes gas generation testing of the spherical resorcinol-formaldehyde (sRF) resin that was conducted to support the technology maturation of the LAWPS facility. The current safety basis for the LAWPS facility is based primarily on two studies that had limited or inconclusive data sets. The two studies indicated a 40% increase in hydrogen generation rate of water (as predicted by the Hu model) with sRF resin over water alone. However, the previous studies did not test the range of conditions (process fluids and temperatures) that are expected in the LAWPS facility. Additionally, the previous studies did not obtain replicatemore » test results or comparable liquid-only control samples. All of the testing described in this report, conducted with water, 0.45M nitric acid, and waste simulants with and without sRF resin, returned hydrogen generation rates that are within the current safety basis for the facility of 1.4 times the Hu model output for water.« less

DARHT: INTEGRATION OF AUTHORIZATION BASIS REQUIREMENTS AND WORKER SAFETY

DOE Office of Scientific and Technical Information (OSTI.GOV)

D. A. MC CLURE; C. A. NELSON; R. L. BOUDRIE

2001-04-01

This document describes the results of consensus agreements reached by the DARHT Safety Planning Team during the development of the update of the DARHT Safety Analysis Document (SAD). The SAD is one of the Authorization Basis (AB) Documents required by the Department prior to granting approval to operate the DARHT Facility. The DARHT Safety Planning Team is lead by Mr. Joel A. Baca of the Department of Energy Albuquerque Operations Office (DOE/AL). Team membership is drawn from the Department of Energy Albuquerque Operations Office, the Department of Energy Los Alamos Area Office (DOE/LAAO), and several divisions of the Los Alamosmore » National Laboratory. Revision 1 of the DARHT SAD had been written as part of the process for gaining approval to operate the Phase 1 (First Axis) Accelerator. Early in the planning stage for the required update of the SAD for the approval to operate both Phase 1 and Phase 2 (First Axis and Second Axis) DARHT Accelerator, it was discovered that a conflict existed between the Laboratory approach to describing the management of facility and worker safety.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Putnam, T.M.

This report presents the objectives, organization, policies, and essential rules and procedures that have been adopted by MP Division and that form the basis of the Health and Safety Program of the Clinton P. Anderson Meson Physics Facility (LAMPF). The facility includes the beam-delivery systems for the Los Alamos Neutron Scattering Center and the Weapons Neutron Research Facility (LANSCE/WNR). The program is designed not only to assure the health and safety of all personnel, including users, in their work at LAMPF, and of MP-Division staff in their work on the LANSCE/WNR beam lines, but also to protect the facility (buildingsmore » and equipment) and the environment. 33 refs., 18 figs., 2 tabs.« less

10 CFR Appendix A to Subpart B of... - General Statement of Safety Basis Policy

Code of Federal Regulations, 2010 CFR

2010-01-01

... Analysis Reports for Nuclear Power Plants, or successor document. (2) A DOE nonreactor nuclear facility... with DOE Policy 450.2A, “Identifying, Implementing and Complying with Environment, Safety and Health..., the public and the environment from adverse consequences. These analyses and hazard controls...

Maximal design basis accident of fusion neutron source DEMO-TIN

NASA Astrophysics Data System (ADS)

Kolbasov, B. N.

2015-12-01

When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission-fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or the first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.

Assessing patient safety in Canadian ambulatory surgery facilities: A national survey

PubMed Central

Ahmad, Jamil; Ho, Olivia A; Carman, Wayne W; Thoma, Achilles; Lalonde, Donald H; Lista, Frank

2014-01-01

BACKGROUND: There has been increased interest regarding patient safety and standards of care in Canadian ambulatory surgery facilities where surgical procedures are performed. The Canadian Association for Accreditation of Ambulatory Surgical Facilities (CAAASF) is a national organization formed to establish and maintain standards to ensure that surgical procedures conducted outside of public hospitals are performed safely. OBJECTIVE: To determine how many procedures are performed annually at CAAASF member sites, and to examine complication rates and several key patient safety practices. METHODS: All 69 facilities accredited by the CAAASF were surveyed. The survey focused on procedural data, complication rates and patient safety interventions. RESULTS: In 2010, 40,240 estimated procedures were performed. A total of 263 (0.007%) complications were reported. Sixteen (0.0004%) patients required reoperations in hospital and 19 (0.0004%) patients required transfer to hospital on the day of surgery. There were only two mortalities within 30 days of surgery reported in the past five years. With regard to patient safety practices, 93% used antimicrobial prophylaxis, 100% used strategies to maintain normothermia and 82% used measures for venous thromboembolism prevention. CONCLUSION: The present study is the first to report on the Canadian experience in ambulatory surgery facilities and provides insight into current practices at these facilities. Appropriate accreditation of ambulatory surgery facilities, well-established patient safety-related standards of care, careful patient selection and procedures performed by qualified health care professionals with appropriate certification practicing within the scope of their practice form the basis for safe and effective ambulatory surgery. PMID:25152645

Systematic Evaluation Program (SEP) at Rocky Flats Plant: An overview of practical management issues for evaluation of natural phenomena hazards

DOE Office of Scientific and Technical Information (OSTI.GOV)

Badwan, F.M.; Herring, K.S.

1993-08-01

Many of the buildings at the Rocky Flats Plant were designed and built before modern standards were developed, including standards for protection against extreme natural phenomenon such as tornadoes, earthquakes, and floods. The purpose of the SEP is to establish an integrated approach to assessing the design adequacy of specific high and moderate hazard Rocky Flats facilities from a safety perspective and to establish a basis for defining any needed facility improvements. The SEP is to be carried out in three Phases. In Phase 1, topics to be evaluated and an evaluation plan for each topic were developed. Any differencesmore » between Current Design Requirements (CDR) or acceptance criteria and the design of existing facilities, will be identified during Phase 2 and assessed using an integrated systematic approach during Phase 3. The integrated assessment performed during Phase 3 provides a process for evaluating the differences between existing facility design and CDRs so that decisions on corrective actions can be made on the basis of relative risk reduction and cost effectiveness. These efforts will ensure that a balanced and integrated level of safety is achieved for long-term operation of these buildings. Through appropriate selection of topics and identification of the structures, systems, and components to be evaluated, the SEP will address outstanding design issues related to the prevention and mitigation of design basis accidents, including those arising from natural phenomena. The objective of the SEP is not to bring these buildings into strict compliance with current requirements, but rather to ensure that an adequate level of safety is achieved in an economical fashion.« less

Postirradiation Testing Laboratory (327 Building)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kammenzind, D.E.

A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompassmore » health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct responsibility of the specific facility manager. The specific DOE Orders, regulations, industry codes/standards, guidance documents and good industry practices that serve as the basis for each element/subelement are identified and aligned with each subelement.« less

Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Badwan, Faris M.; Demuth, Scott F

Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is amore » fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the UNFSF. The framework for integration of safeguards and security into the UNFSF will include 1) identification of applicable regulatory requirements, 2) selection of a common system that share dual safeguard and security functions, 3) development of functional design criteria and design requirements for the selected system, 4) identification and integration of the dual safeguards and security design requirements, and 5) assessment of the integration and potential benefit.« less

Maximal design basis accident of fusion neutron source DEMO-TIN

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kolbasov, B. N., E-mail: Kolbasov-BN@nrcki.ru

2015-12-15

When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission–fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or themore » first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.« less

Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1994-01-01

This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF{sub 6} and produce 870 tonnes ofmore » low-enriched UF{sub 6}, and 3,830 tonnes of depleted UF{sub 6} tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant`s descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Charles W. Solbrig; Chad Pope; Jason Andrus

The fuel cycle facility (FCF) at the Idaho National Laboratory is a nuclear facility which must be licensed in order to operate. A safety analysis is required for a license. This paper describes the analysis of the Design Basis Accident for this facility. This analysis involves a model of the transient behavior of the FCF inert atmosphere hot cell following an earthquake initiated breach of pipes passing through the cell boundary. The hot cell is used to process spent metallic nuclear fuel. Such breaches allow the introduction of air and subsequent burning of pyrophoric metals. The model predicts the pressure,more » temperature, volumetric releases, cell heat transfer, metal fuel combustion, heat generation rates, radiological releases and other quantities. The results show that releases from the cell are minimal and satisfactory for safety. This analysis method should be useful in other facilities that have potential for damage from an earthquake and could eliminate the need to back fit facilities with earthquake proof boundaries or lessen the cost of new facilities.« less

Medical Director Responsibilities to the ESRD Network

PubMed Central

DeOreo, Peter B.

2015-01-01

The 18 regional ESRD Networks are established in legislation and contract with the Centers for Medicare and Medicaid Services to improve the quality and safety of dialysis, maximize patient rehabilitation, encourage collaboration among and between providers toward common quality goals, and improve the reliability and the use of data in pursuit of quality improvement. The Networks are funded by a $0.50 per treatment fee deducted from the reimbursement to dialysis providers, and their deliverables are determined by a statement of work, which is updated in a new contract every 3 years. The Conditions for Coverage require dialysis providers to participate in Network activities, and failure to do so can be the basis for sanctions against the provider. However, the Networks attempt to foster a collegial relationship with dialysis facilities by offering tools, educational activities, and other resources to assist the facilities in meeting the evolving requirements by the Centers for Medicare and Medicaid Services on the basis of national aims and domains for quality improvement in health care that transcend the ESRD program. Because of his/her responsibility for implementing the quality assessment and performance improvement activities in the facility, the medical director has much to gain by actively participating in Network activities, especially those focused on quality, safety, patient grievance, patient engagement, and coordination of care. Membership on Network committees can also foster the professional growth of the medical director through participation in quality improvement activity development and implementation, authorship of articles in peer-reviewed journals, creation of educational tools and presentations, and application of Network-sponsored materials to improve patient outcomes, engagement, and satisfaction in the medical director’s facility. The improvement of care of patients on dialysis will be beneficial to the facility in achieving its goals of quality, safety, and financial viability. PMID:25255911

ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1998-07-01

This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in priormore » hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.« less

Scientific approach and practical experience for reconstruction of waste water treatment plants in Russia

NASA Astrophysics Data System (ADS)

Makisha, Nikolay; Gogina, Elena

2017-11-01

Protection of water bodies has a strict dependence on reliable operation of engineering systems and facilities for water supply and sewage. The majority of these plants and stations has been constructed in 1970-1980's in accordance with rules and regulations of that time. So now most of them require reconstruction due to serious physical or/and technological wear. The current condition of water supply and sewage systems and facilities frequently means a hidden source of serious danger for normal life support and ecological safety of cities and towns. The article reveals an obtained experience and modern approaches for reconstruction of waste water and sludge treatment plants that proved their efficiency even if applied in limited conditions such as area limits, investments limits. The main directions of reconstruction: overhaul repair and partial modernization of existing facilities on the basis of initial project; - restoration and modernization of existing systems on the basis on the current documents and their current condition; upgrade of waste water treatment plants (WWTPs) performance on the basis of modern technologies and methods; reconstruction of sewage systems and facilities and treatment quality improvement.

National Environmental Policy Act Hazards Assessment for the TREAT Alternative

DOE Office of Scientific and Technical Information (OSTI.GOV)

Boyd D. Christensen; Annette L. Schafer

2013-11-01

This document provides an assessment of hazards as required by the National Environmental Policy Act for the alternative of restarting the reactor at the Transient Reactor Test (TREAT) facility by the Resumption of Transient Testing Program. Potential hazards have been identified and screening level calculations have been conducted to provide estimates of unmitigated dose consequences that could be incurred through this alternative. Consequences considered include those related to use of the TREAT Reactor, experiment assembly handling, and combined events involving both the reactor and experiments. In addition, potential safety structures, systems, and components for processes associated with operating TREAT andmore » onsite handling of nuclear fuels and experiments are listed. If this alternative is selected, a safety basis will be prepared in accordance with 10 CFR 830, “Nuclear Safety Management,” Subpart B, “Safety Basis Requirements.”« less

National Environmental Policy Act Hazards Assessment for the TREAT Alternative

DOE Office of Scientific and Technical Information (OSTI.GOV)

Christensen, Boyd D.; Schafer, Annette L.

2014-02-01

This document provides an assessment of hazards as required by the National Environmental Policy Act for the alternative of restarting the reactor at the Transient Reactor Test (TREAT) facility by the Resumption of Transient Testing Program. Potential hazards have been identified and screening level calculations have been conducted to provide estimates of unmitigated dose consequences that could be incurred through this alternative. Consequences considered include those related to use of the TREAT Reactor, experiment assembly handling, and combined events involving both the reactor and experiments. In addition, potential safety structures, systems, and components for processes associated with operating TREAT andmore » onsite handling of nuclear fuels and experiments are listed. If this alternative is selected, a safety basis will be prepared in accordance with 10 CFR 830, “Nuclear Safety Management,” Subpart B, “Safety Basis Requirements.”« less

Experimental Fuels Facility Re-categorization Based on Facility Segmentation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Reiss, Troy P.; Andrus, Jason

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 excessmore » 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 DOE-ID Supplemental Guidance for DOE-STD-1027-92 based on the proposed downgrade of the initial facility categorization of Hazard Category 2.« less

CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kessler, S

2009-04-21

With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5,more » Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified in the applicable new/revised CSE is evaluated via the table. The results of this evaluation are documented in tables attached to the CCR as an appendix, for each CSE, to the base document.« less

75 FR 20627 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses Involving No...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-04-20

... designed, on an RAS. Basis for proposed no significant hazards consideration determination: As required by...], Time Response Design Criteria for Safety- Related Operator Actions, 1984 guidance. Although the change... changes to the RAS Allowable Values and RWT minimum required level on the RWT structural design...

SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

DOE Office of Scientific and Technical Information (OSTI.GOV)

SWENSON JA; CROWE RD; APTHORPE R

2010-03-09

The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin.more » KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of the drying cycle, more realistic treatment of uranium metal consumption during oxidation, larger water inventory, longer time scales, and graphing of results of hydrogen gas concentration.« less

Medical Director Responsibilities to the ESRD Network.

PubMed

DeOreo, Peter B; Wish, Jay B

2015-10-07

The 18 regional ESRD Networks are established in legislation and contract with the Centers for Medicare and Medicaid Services to improve the quality and safety of dialysis, maximize patient rehabilitation, encourage collaboration among and between providers toward common quality goals, and improve the reliability and the use of data in pursuit of quality improvement. The Networks are funded by a $0.50 per treatment fee deducted from the reimbursement to dialysis providers, and their deliverables are determined by a statement of work, which is updated in a new contract every 3 years. The Conditions for Coverage require dialysis providers to participate in Network activities, and failure to do so can be the basis for sanctions against the provider. However, the Networks attempt to foster a collegial relationship with dialysis facilities by offering tools, educational activities, and other resources to assist the facilities in meeting the evolving requirements by the Centers for Medicare and Medicaid Services on the basis of national aims and domains for quality improvement in health care that transcend the ESRD program. Because of his/her responsibility for implementing the quality assessment and performance improvement activities in the facility, the medical director has much to gain by actively participating in Network activities, especially those focused on quality, safety, patient grievance, patient engagement, and coordination of care. Membership on Network committees can also foster the professional growth of the medical director through participation in quality improvement activity development and implementation, authorship of articles in peer-reviewed journals, creation of educational tools and presentations, and application of Network-sponsored materials to improve patient outcomes, engagement, and satisfaction in the medical director's facility. The improvement of care of patients on dialysis will be beneficial to the facility in achieving its goals of quality, safety, and financial viability. Copyright © 2015 by the American Society of Nephrology.

Basis for Interim Operation for Fuel Supply Shutdown Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

BENECKE, M.W.

2003-02-03

This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the currentmore » and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment, the form of the uranium, and the required controls, a Criticality Alarm System (CAS) is not required as allowed by DOE Order 420.1 (DOE 2000).« less

Safety and Security Interface Technology Initiative

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dr. Michael A. Lehto; Kevin J. Carroll; Dr. Robert Lowrie

Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme)more » includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ‘tool box’ of information/successes. Specific Benefits. The expectation or end state resulting from the topical report and associated implementation plan includes: (1) A recommended process for handling the documentation of the security and safety disciplines, including an appropriate change control process and participation by all stakeholders. (2) A means to package security systems with sufficient information to help expedite the flow of that system through the process. In addition, a means to share successes among sites, to include information and safety basis to the extent such information is transportable. (3) Identification of key security systems and associated essential security elements being installed and an arrangement for the sites installing these systems to host an appropriate team to review a specific system and determine what information is exportable. (4) Identification of the security systems’ essential elements and appropriate controls required for testing of these essential elements in the facility. (5) The ability to help refine and improve an agreed to control set at the manufacture stage.« less

Child Care Center Regulations.

ERIC Educational Resources Information Center

Nebraska State Dept. of Health and Human Services, Lincoln.

This guide enumerates regulations for anyone caring for four or more children, from families other than their own, for compensation and on a regular basis, in the state of Nebraska. The purpose of the regulations is to protect and promote the health and safety of children in child care facilities. The first section of the guide lists specific…

77 FR 61433 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-09

... attacks up to and including the design basis cyber attack threat, thereby achieving high assurance that... provide assurance that safety-related SSCs are protected from cyber attacks. Implementation of 10 CFR 73... of ``high assurance of adequate protection against cyber attacks.'' The proposed revision would not...

Content of system design descriptions

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

A System Design Description (SDD) describes the requirements and features of a system. This standard provides guidance on the expected technical content of SDDs. The need for such a standard was recognized during efforts to develop SDDs for safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Existing guidance related to the corresponding documents in other industries is generally not suitable to meet the needs of DOE nuclear facilities. Across the DOE complex, different contractors have guidance documents, but they vary widely from site to site. While such guidance documents are valuable, no single guidance document has all themore » attributes that DOE considers important, including a reasonable degree of consistency or standardization. This standard is a consolidation of the best of the existing guidance. This standard has been developed with a technical content and level of detail intended to be most applicable to safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Notwithstanding that primary intent, this standard is recommended for other systems at such facilities, especially those that are important to achieving the programmatic mission of the facility. In addition, application of this standard should be considered for systems at other facilities, including non-nuclear facilities, on the basis that SDDs may be beneficial and cost-effective.« less

Health and environmental effects of refuse derived fuel (RDF) production and RDF/coal co-firing technologies

DOE Office of Scientific and Technical Information (OSTI.GOV)

O'Toole, J.J.; Wessels, T.E.; Lynch, J.F.

1981-10-01

Six facilities, representing the scope of different co-firing techniques with their associated RDF production systems were reviewed in detail for combustion equipment, firing modes, emission control systems, residue handling/disposal, and effluent wastewater treatment. These facilities encompass all currently operational or soon to be operational co-firing plants and associated RDF production systems. Occupational health and safety risks for these plants were evaluated on the basis of fatal and nonfatal accidents and disease arising from the respective fuel cycles, coal and RDF. Occupational risks include exposure to pathogenic organisms in the workplace. Unusual events that are life threatening in the RDF processingmore » industry (e.g., explosions) are also discussed and remedial and safety measures reviewed. 80 refs., 4 figs., 30 tabs.« less

High-level waste tank farm set point document

DOE Office of Scientific and Technical Information (OSTI.GOV)

Anthony, J.A. III

1995-01-15

Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREASmore » listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.« less

Corporate liability: security and violence--Part I.

PubMed

Fiesta, J

1996-03-01

Violence in the workplace is becoming one of the nation's top killers. It is like an Equal Opportunity Employer--it does not discriminate on the basis of race, color, religion, age, sex, national origin, disability or sexual orientation. A few regulatory agencies and legislators are requiring health care facilities to take steps to improve safety and security.

Review and Application of ASME NOG-1 and ASME NUM-1-2000

NASA Technical Reports Server (NTRS)

Lytle, Bradford P.; Delgado, H. (Technical Monitor)

2002-01-01

The intent of the workshop is to review the application of the ASME Nuclear Crane Standards ASME NOG-1 and ASME NUM-1-2000. The ASME Nuclear Crane standards provide a basis for purchasing overhead handling equipment with enhanced safety features, based upon accepted engineering principles, and including performance and environmental parameters specific to nuclear facilities.

14 CFR 382.53 - What information must carriers give individuals with a vision or hearing impairment at airports?

Code of Federal Regulations, 2014 CFR

2014-01-01

... foreign airport, to the extent that this does not interfere with employees' safety and security duties as... individuals with a vision or hearing impairment at airports? 382.53 Section 382.53 Aeronautics and Space... NONDISCRIMINATION ON THE BASIS OF DISABILITY IN AIR TRAVEL Accessibility of Airport Facilities § 382.53 What...

14 CFR 382.53 - What information must carriers give individuals with a vision or hearing impairment at airports?

Code of Federal Regulations, 2012 CFR

2012-01-01

... foreign airport, to the extent that this does not interfere with employees' safety and security duties as... individuals with a vision or hearing impairment at airports? 382.53 Section 382.53 Aeronautics and Space... NONDISCRIMINATION ON THE BASIS OF DISABILITY IN AIR TRAVEL Accessibility of Airport Facilities § 382.53 What...

14 CFR 382.53 - What information must carriers give individuals with a vision or hearing impairment at airports?

Code of Federal Regulations, 2013 CFR

2013-01-01

... foreign airport, to the extent that this does not interfere with employees' safety and security duties as... individuals with a vision or hearing impairment at airports? 382.53 Section 382.53 Aeronautics and Space... NONDISCRIMINATION ON THE BASIS OF DISABILITY IN AIR TRAVEL Accessibility of Airport Facilities § 382.53 What...

78 FR 46497 - Amendment of Class D and E Airspace, and Establishment of Class E Airspace; Oceana NAS, VA

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-01

... Soucek Field) now operating on a part time basis. This action enhances the safety and airspace management... Soucek Field), VA, as the air traffic control tower is transitioning from a full time facility to part... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 71 [Docket No. FAA-2013...

Little shop of errors: an innovative simulation patient safety workshop for community health care professionals.

PubMed

Tupper, Judith B; Pearson, Karen B; Meinersmann, Krista M; Dvorak, Jean

2013-06-01

Continuing education for health care workers is an important mechanism for maintaining patient safety and high-quality health care. Interdisciplinary continuing education that incorporates simulation can be an effective teaching strategy for improving patient safety. Health care professionals who attended a recent Patient Safety Academy had the opportunity to experience firsthand a simulated situation that included many potential patient safety errors. This high-fidelity activity combined the best practice components of a simulation and a collaborative experience that promoted interdisciplinary communication and learning. Participants were challenged to see, learn, and experience "ah-ha" moments of insight as a basis for error reduction and quality improvement. This innovative interdisciplinary educational training method can be offered in place of traditional lecture or online instruction in any facility, hospital, nursing home, or community care setting. Copyright 2013, SLACK Incorporated.

Preliminary Authorization Basis Documentation for the Proposed Bio Safety Level 3 (BSl-3) Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Altenbach, T J; Nguyen, S N

2003-09-20

Lawrence Livermore National Laboratory (LLNL) is proposing to construct a biosafety level (BSL-3) facility at Site 200 in Livermore, California. Biosafety level 3 (BSL-3) is a designation assigned by the Centers for Disease Control and Prevention (CDC) and National Institutes Health (NIH) for handling infectious organisms based on the specific microorganisms and associated operations. Biosafety levels range from BSL-1 (lowest hazard) to BSL-4 (highest hazard). Details about the BSL-3 criteria are described in the Center of Disease Control and Prevention (CDC)/National Institutes of Health (NIH)'s publication ''Biosafety Microbiological and Biomedical Laboratories'' (BMBL), 4th edition (CDC 1999): The BSL-3 facility willmore » be built in accordance with the required BMBL guidelines. This Preliminary Authorization Basis Documentation (PABD) for the proposed BSL-3 facility has been prepared in accordance with the current contractual requirements at LLNL. This includes the LLNL Environment, Safety, and Health Manual (ES&H Manual) and applicable Work Smart Standards, including the biosafety standards, such as the aforementioned BMBL and the NIH Guidelines for Research Involving Recombinant DNA Molecules: The proposed BSL-3 facility is a 1,100 ft{sup 2}, one-story permanent prefabricated facility, which will have three individual BSL-3 laboratory rooms (one of which is an animal biosafety level-3 [ABSL-3] laboratory to handle rodents), a mechanical room, clothes-change and shower rooms, and small storage space (Figure 3.1). The BSL-3 facility will be designed and operated accordance with guidelines for BSL-3 laboratories established by the CDC and the NIH. No radiological, high explosives, fissile, or propellant material will be used or stored in the proposed BSL-3 facility. The BSL-3 facility will be used to develop scientific tools to identify and understand the pathogens of medical, environmental, and forensic importance. Microorganisms that are to be handled in this facility will be limited in quantity, type and form in accordance with the BMBL requirements and approval by the Institutional Biosafety Committee (IBC). The proposed facility will have the unique capability within DOE/NNSA to perform aerosol studies to include challenges to rodents using infectious agents or biologically derived toxins (biotoxins). These types of aerosol studies will be strictly confined in a Class II Type B biosafety cabinet.« less

NASA Lewis Wind Tunnel Model Systems Criteria

NASA Technical Reports Server (NTRS)

Soeder, Ronald H.; Haller, Henry C.

1994-01-01

This report describes criteria for the design, analysis, quality assurance, and documentation of models or test articles that are to be tested in the aeropropulsion facilities at the NASA Lewis Research Center. The report presents three methods for computing model allowable stresses on the basis of the yield stress or ultimate stress, and it gives quality assurance criteria for models tested in Lewis' aeropropulsion facilities. Both customer-furnished model systems and in-house model systems are discussed. The functions of the facility manager, project engineer, operations engineer, research engineer, and facility electrical engineer are defined. The format for pretest meetings, prerun safety meetings, and the model criteria review are outlined Then, the format for the model systems report (a requirement for each model that is to be tested at NASA Lewis) is described, the engineers that are responsible for developing the model systems report are listed, and the time table for its delivery to the facility manager is given.

[Recommendations for inspections of the French nuclear safety authority].

PubMed

Rousse, C; Chauvet, B

2015-10-01

The French nuclear safety authority is responsible for the control of radiation protection in radiotherapy since 2002. Controls are based on the public health and the labour codes and on the procedures defined by the controlled health care facility for its quality and safety management system according to ASN decision No. 2008-DC-0103. Inspectors verify the adequacy of the quality and safety management procedures and their implementation, and select process steps on the basis of feedback from events notified to ASN. Topics of the inspection are communicated to the facility at the launch of a campaign, which enables them to anticipate the inspectors' expectations. In cases where they are not physicians, inspectors are not allowed to access information covered by medical confidentiality. The consulted documents must therefore be expunged of any patient-identifying information. Exchanges before the inspection are intended to facilitate the provision of documents that may be consulted. Finally, exchange slots between inspectors and the local professionals must be organized. Based on improvements achieved by the health care centres and on recommendations from a joint working group of radiotherapy professionals and the nuclear safety authority, changes will be made in the control procedure that will be implemented when developing the inspection program for 2016-2019. Copyright © 2015. Published by Elsevier SAS.

Environment, Safety, and Health: Status of DOE’s Reorganization of it’s Safety Oversight Function

DTIC Science & Technology

1990-01-01

facilities. After deliberation, the Congress in late 1988 directed that the Defense Nuclear Facilities Safety Board be established to provide...nuclear safety matters will be conducted by either the Advisory Committee on Nuclear Facility Safety or the recently mandated Defense Nuclear Facilities Safety...the facilities under the statutory purview of the Defense Nuclear Facilities Safety Board once the board determines it is ready to assume independent

Sandia National Laboratories/New Mexico Environmental Information Document - Volume 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

BAYLISS, LINDA S.; GUERRERO, JOSEPH V.; JOHNS, WILLIAM H.

This Sandia National Laboratories/New Mexico Environmental Information Document (EID) compiles information on the existing environment, or environmental baseline, for SNUNM. Much of the information is drawn from existing reports and databases supplemented by new research and data. The SNL/NM EID, together with the Sandia National Laboratories/New Mexico Facilities and Safety Information Document, provide a basis for assessing the environment, safety, and health aspects of operating selected facilities at SNL/NM. The environmental baseline provides a record of the existing physical, biological, and socioeconomic environment at SNL/NLM prior to being altered (beneficially or adversely) by proposed programs or projects. More specifically, themore » EID provides information on the following topics: Geology; Land Use; Hydrology and Water Resources; Air Quality and Meteorology; Ecology; Noise and Vibration; Cultural Resources; Visual Resources; Socioeconomic and Community Services; Transportation; Material Management; Waste Management; and Regulatory Requirements.« less

Buffet test in the National Transonic Facility

NASA Technical Reports Server (NTRS)

Young, Clarence P., Jr.; Hergert, Dennis W.; Butler, Thomas W.; Herring, Fred M.

1992-01-01

A buffet test of a commercial transport model was accomplished in the National Transonic Facility at the NASA Langley Research Center. This aeroelastic test was unprecedented for this wind tunnel and posed a high risk to the facility. This paper presents the test results from a structural dynamics and aeroelastic response point of view and describes the activities required for the safety analysis and risk assessment. The test was conducted in the same manner as a flutter test and employed onboard dynamic instrumentation, real time dynamic data monitoring, automatic, and manual tunnel interlock systems for protecting the model. The procedures and test techniques employed for this test are expected to serve as the basis for future aeroelastic testing in the National Transonic Facility. This test program was a cooperative effort between the Boeing Commercial Airplane Company and the NASA Langley Research Center.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sarrack, A.G.

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses tomore » calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).« less

Site-wide seismic risk model for Savannah River Site nuclear facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Eide, S.A.; Shay, R.S.; Durant, W.S.

1993-09-01

The 200,000 acre Savannah River Site (SRS) has nearly 30 nuclear facilities spread throughout the site. The safety of each facility has been established in facility-specific safety analysis reports (SARs). Each SAR contains an analysis of risk from seismic events to both on-site workers and the off-site population. Both radiological and chemical releases are considered, and air and water pathways are modeled. Risks to the general public are generally characterized by evaluating exposure to the maximally exposed individual located at the SRS boundary and to the off-site population located within 50 miles. Although the SARs are appropriate methods for studyingmore » individual facility risks, there is a class of accident initiators that can simultaneously affect several of all of the facilities, Examples include seismic events, strong winds or tornados, floods, and loss of off-site electrical power. Overall risk to the off-site population from such initiators is not covered by the individual SARs. In such cases multiple facility radionuclide or chemical releases could occur, and off-site exposure would be greater than that indicated in a single facility SAR. As a step towards an overall site-wide risk model that adequately addresses multiple facility releases, a site-wide seismic model for determining off-site risk has been developed for nuclear facilities at the SRS. Risk from seismic events up to the design basis earthquake (DBE) of 0.2 g (frequency of 2.0E-4/yr) is covered by the model. Present plans include expanding the scope of the model to include other types of initiators that can simultaneously affect multiple facilities.« less

NSR&D Program Fiscal Year (FY) 2015 Call for Proposals Mitigation of Seismic Risk at Nuclear Facilities using Seismic Isolation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Coleman, Justin

2015-02-01

Seismic isolation (SI) has the potential to drastically reduce seismic response of structures, systems, or components (SSCs) and therefore the risk associated with large seismic events (large seismic event could be defined as the design basis earthquake (DBE) and/or the beyond design basis earthquake (BDBE) depending on the site location). This would correspond to a potential increase in nuclear safety by minimizing the structural response and thus minimizing the risk of material release during large seismic events that have uncertainty associated with their magnitude and frequency. The national consensus standard America Society of Civil Engineers (ASCE) Standard 4, Seismic Analysismore » of Safety Related Nuclear Structures recently incorporated language and commentary for seismically isolating a large light water reactor or similar large nuclear structure. Some potential benefits of SI are: 1) substantially decoupling the SSC from the earthquake hazard thus decreasing risk of material release during large earthquakes, 2) cost savings for the facility and/or equipment, and 3) applicability to both nuclear (current and next generation) and high hazard non-nuclear facilities. Issue: To date no one has evaluated how the benefit of seismic risk reduction reduces cost to construct a nuclear facility. Objective: Use seismic probabilistic risk assessment (SPRA) to evaluate the reduction in seismic risk and estimate potential cost savings of seismic isolation of a generic nuclear facility. This project would leverage ongoing Idaho National Laboratory (INL) activities that are developing advanced (SPRA) methods using Nonlinear Soil-Structure Interaction (NLSSI) analysis. Technical Approach: The proposed study is intended to obtain an estimate on the reduction in seismic risk and construction cost that might be achieved by seismically isolating a nuclear facility. The nuclear facility is a representative pressurized water reactor building nuclear power plant (NPP) structure. Figure 1: Project activities The study will consider a representative NPP reinforced concrete reactor building and representative plant safety system. This study will leverage existing research and development (R&D) activities at INL. Figure 1 shows the proposed study steps with the steps in blue representing activities already funded at INL and the steps in purple the activities that would be funded under this proposal. The following results will be documented: 1) Comparison of seismic risk for the non-seismically isolated (non-SI) and seismically isolated (SI) NPP, and 2) an estimate of construction cost savings when implementing SI at the site of the generic NPP.« less

Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine

2014-03-01

Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazardsmore » from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.« less

Nuclear criticality safety evaluation of the passage of decontaminated salt solution from the ITP filters into tank 50H for interim storage

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hobbs, D.T.; Davis, J.R.

This report assesses the nuclear criticality safety associated with the decontaminated salt solution after passing through the In-Tank Precipitation (ITP) filters, through the stripper columns and into Tank 50H for interim storage until transfer to the Saltstone facility. The criticality safety basis for the ITP process is documented. Criticality safety in the ITP filtrate has been analyzed under normal and process upset conditions. This report evaluates the potential for criticality due to the precipitation or crystallization of fissionable material from solution and an ITP process filter failure in which insoluble material carryover from salt dissolution is present. It is concludedmore » that no single inadvertent error will cause criticality and that the process will remain subcritical under normal and credible abnormal conditions.« less

Low back pain among workers in care facilities for the elderly after introducing welfare equipment.

PubMed

Iwakiri, Kazuyuki; Takahashi, Masaya; Sotoyama, Midori; Liu, Xinxin; Koda, Shigeki

2016-07-29

The purpose of this study was to clarify the causes of low back pain among workers in care facilities for the elderly after the introduction of welfare equipment. We conducted anonymous questionnaire surveys among administrators and care workers in eight elderly care facilities. The questionnaires were designed to investigate the status of both the care workers and facility. In reference to the care facility, the questionnaires were comprised items for investigating basic information, occupational safety, and health activities. For care workers, in addition to basic information, occupational safety, and health activities, the questionnaires also comprised items for investigating resident transfer and bathing methods, low back pain, and occupational stress. Completed questionnaires were returned by eight care facility administrators (response rate: 100%) and 373 care workers (response rate: 92.3%), among which 367 were used for analyses. Many care workers participated in a variety of occupational safety and health activities that were conducted in the facilities. Various types of welfare equipment were introduced into the care facilities and subsequently used by many care workers during resident transfer and bathing. As a result, 89.9% of the care workers reported having only slight or no low back pain. The remaining 10.1% reported having serious low back pain that interfered with their work. On the basis of logistic regression analysis, low back pain was associated with the following variables: failure to provide the appropriate method of care to each resident, failure of colleagues to discuss methods for improving care, lack of instructions regarding the use of welfare equipment, and inappropriate job rotation. An association was also found between low back pain and poor posture, poor resident-lifting technique, insufficient time to complete work, and a shortage of workers to assist with resident transfer or bathing. Although care workers received instructions on the health and safety activities extracted from the surveys, an association was still found between these activities and low back pain. This was thought to result from some care workers not establishing the appropriate method of care for each resident, not discussing methods for improving care with other colleagues, not using the welfare equipment, and failing to practice appropriate job rotation. These results suggest that low back pain among care workers in the facilities for the elderly that have introduced welfare equipment is caused by a failure to sufficiently conduct appropriate care methods.

Joint Sandia/NIOSH exercise on aerosol contamination using the BROOM tool.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ramsey, James L., Jr.; .); Melton, Brad

In February of 2005, a joint exercise involving Sandia National Laboratories (SNL) and the National Institute for Occupational Safety and Health (NIOSH) was conducted in Albuquerque, NM. The SNL participants included the team developing the Building Restoration Operations and Optimization Model (BROOM), a software product developed to expedite sampling and data management activities applicable to facility restoration following a biological contamination event. Integrated data-collection, data-management, and visualization software improve the efficiency of cleanup, minimize facility downtime, and provide a transparent basis for reopening. The exercise was held at an SNL facility, the Coronado Club, a now-closed social club for Sandiamore » employees located on Kirtland Air Force Base. Both NIOSH and SNL had specific objectives for the exercise, and all objectives were met.« less

The impact of transportation infrastructure on bicycling injuries and crashes: a review of the literature

PubMed Central

2009-01-01

Background Bicycling has the potential to improve fitness, diminish obesity, and reduce noise, air pollution, and greenhouse gases associated with travel. However, bicyclists incur a higher risk of injuries requiring hospitalization than motor vehicle occupants. Therefore, understanding ways of making bicycling safer and increasing rates of bicycling are important to improving population health. There is a growing body of research examining transportation infrastructure and the risk of injury to bicyclists. Methods We reviewed studies of the impact of transportation infrastructure on bicyclist safety. The results were tabulated within two categories of infrastructure, namely that at intersections (e.g. roundabouts, traffic lights) or between intersections on "straightaways" (e.g. bike lanes or paths). To assess safety, studies examining the following outcomes were included: injuries; injury severity; and crashes (collisions and/or falls). Results The literature to date on transportation infrastructure and cyclist safety is limited by the incomplete range of facilities studied and difficulties in controlling for exposure to risk. However, evidence from the 23 papers reviewed (eight that examined intersections and 15 that examined straightaways) suggests that infrastructure influences injury and crash risk. Intersection studies focused mainly on roundabouts. They found that multi-lane roundabouts can significantly increase risk to bicyclists unless a separated cycle track is included in the design. Studies of straightaways grouped facilities into few categories, such that facilities with potentially different risks may have been classified within a single category. Results to date suggest that sidewalks and multi-use trails pose the highest risk, major roads are more hazardous than minor roads, and the presence of bicycle facilities (e.g. on-road bike routes, on-road marked bike lanes, and off-road bike paths) was associated with the lowest risk. Conclusion Evidence is beginning to accumulate that purpose-built bicycle-specific facilities reduce crashes and injuries among cyclists, providing the basis for initial transportation engineering guidelines for cyclist safety. Street lighting, paved surfaces, and low-angled grades are additional factors that appear to improve cyclist safety. Future research examining a greater variety of infrastructure would allow development of more detailed guidelines. PMID:19845962

EDITORIAL: Safety aspects of fusion power plants

NASA Astrophysics Data System (ADS)

Kolbasov, B. N.

2007-07-01

This special issue of Nuclear Fusion contains 13 informative papers that were initially presented at the 8th IAEA Technical Meeting on Fusion Power Plant Safety held in Vienna, Austria, 10-13 July 2006. Following recommendation from the International Fusion Research Council, the IAEA organizes Technical Meetings on Fusion Safety with the aim to bring together experts to discuss the ongoing work, share new ideas and outline general guidance and recommendations on different issues related to safety and environmental (S&E) aspects of fusion research and power facilities. Previous meetings in this series were held in Vienna, Austria (1980), Ispra, Italy (1983), Culham, UK (1986), Jackson Hole, USA (1989), Toronto, Canada (1993), Naka, Japan (1996) and Cannes, France (2000). The recognized progress in fusion research and technology over the last quarter of a century has boosted the awareness of the potential of fusion to be a practically inexhaustible and clean source of energy. The decision to construct the International Thermonuclear Experimental Reactor (ITER) represents a landmark in the path to fusion power engineering. Ongoing activities to license ITER in France look for an adequate balance between technological and scientific deliverables and complying with safety requirements. Actually, this is the first instance of licensing a representative fusion machine, and it will very likely shape the way in which a more common basis for establishing safety standards and policies for licensing future fusion power plants will be developed. Now that ITER licensing activities are underway, it is becoming clear that the international fusion community should strengthen its efforts in the area of designing the next generations of fusion power plants—demonstrational and commercial. Therefore, the 8th IAEA Technical Meeting on Fusion Safety focused on the safety aspects of power facilities. Some ITER-related safety issues were reported and discussed owing to their potential importance for the fusion power plant research programmes. The objective of this Technical Meeting was to examine in an integrated way all the safety aspects anticipated to be relevant to the first fusion power plant prototype expected to become operational by the middle of the century, leading to the first generation of economically viable fusion power plants with attractive S&E features. After screening by guest editors and consideration by referees, 13 (out of 28) papers were accepted for publication. They are devoted to the following safety topics: power plant safety; fusion specific operational safety approaches; test blanket modules; accident analysis; tritium safety and inventories; decommissioning and waste. The paper `Main safety issues at the transition from ITER to fusion power plants' by W. Gulden et al (EU) highlights the differences between ITER and future fusion power plants with magnetic confinement (off-site dose acceptance criteria, consequences of accidents inside and outside the design basis, occupational radiation exposure, and waste management, including recycling and/or final disposal in repositories) on the basis of the most recent European fusion power plant conceptual study. Ongoing S&E studies within the US inertial fusion energy (IFE) community are focusing on two design concepts. These are the high average power laser (HAPL) programme for development of a dry-wall, laser-driven IFE power plant, and the Z-pinch IFE programme for the production of an economically-attractive power plant using high-yield Z-pinch-driven targets. The main safety issues related to these programmes are reviewed in the paper `Status of IFE safety and environmental activities in the US' by S. Reyes et al (USA). The authors propose future directions of research in the IFE S&E area. In the paper `Recent accomplishments and future directions in the US Fusion Safety & Environmental Program' D. Petti et al (USA) state that the US fusion programme has long recognized that the S&E potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behaviour of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state-of-the-art S&E computer codes and risk tools for safety assessment, and evaluating and improving fusion facility design in terms of accident safety, worker safety, and waste disposal. There are three papers considering safety issues of the test blanket modules (TBM) producing tritium to be installed in ITER. These modules represent different concepts of demonstration fusion power facilities (DEMO). L. Boccaccini et al (Germany) analyses the possibility of jeopardizing the ITER safety under specific accidents in the European helium-cooled pebble-bed TBM, e.g. pressurization of the vacuum vessel (VV), hydrogen production from the Be-steam reaction, the possible interconnection between the port cell and VV causing air ingress. Safety analysis is also presented for Chinese TBM with a helium-cooled solid breeder to be tested in ITER by Z. Chen et al (China). Radiological inventories, afterheat, waste disposal ratings, electromagnetic characteristics, LOCA and tritium safety management are considered. An overview of a preliminary safety analysis performed for a US proposed TBM is presented by B. Merrill et al (USA). This DEMO relevant dual coolant liquid lead-lithium TBM has been explored both in the USA and EU. T. Pinna et al (Italy) summarize the six-year development of a failure rate database for fusion specific components on the basis of data coming from operating experience gained in various fusion laboratories. The activity began in 2001 with the study of the Joint European Torus vacuum and active gas handling systems. Two years later the neutral beam injectors and the power supply systems were considered. This year the ion cyclotron resonant heating system is under evaluation. I. Cristescu et al (Germany) present the paper `Tritium inventories and tritium safety design principles for the fuel cycle of ITER'. She and her colleagues developed the dynamic mathematical model (TRIMO) for tritium inventory evaluation within each system of the ITER fuel cycle in various operational scenarios. TRIMO is used as a tool for trade-off studies within the fuel cycle systems with the final goal of global tritium inventory minimization. M. Matsuyama et al (Japan) describes a new technique for in situ quantitative measurements of high-level tritium inventory and its distribution in the VV and tritium systems of ITER and future fusion reactors. This technique is based on utilization of x-rays induced by beta-rays emitting from tritium species. It was applied to three physical states of high-level tritium: to gaseous, aqueous and solid tritium retained on/in various materials. Finally, there are four papers devoted to safety issues in fusion reactor decommissioning and waste management. A paper by R. Pampin et al (UK) provides the revised radioactive waste analysis of two models in the PPCS. Another paper by M. Zucchetti (Italy), S.A. Bartenev (Russia) et al describes a radiochemical extraction technology for purification of V-Cr-Ti alloy components from activation products to the dose rate of 10 µSv/h allowing their clearance or hands-on recycling which has been developed and tested in laboratory stationary conditions. L. El-Guebaly (USA) and her colleagues submitted two papers. In the first paper she optimistically considers the possibility of replacing the disposal of fusion power reactor waste with recycling and clearance. Her second paper considers the implications of new clearance guidelines for nuclear applications, particularly for slightly irradiated fusion materials.

76 FR 42686 - DOE Response to Recommendation 2011-1 of the Defense Nuclear Facilities Safety Board, Safety...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-19

... DEPARTMENT OF ENERGY DOE Response to Recommendation 2011-1 of the Defense Nuclear Facilities... Nuclear Facilities Safety Board, Office of Health, Safety and Security, U.S. Department of Energy, 1000... Department of Energy (DOE) acknowledges receipt of Defense Nuclear Facilities Safety Board (Board...

Water Ingress Testing of the Turbula Jar and U-233 Lead Pig Containers

DOE Office of Scientific and Technical Information (OSTI.GOV)

Reeves, Kirk Patrick; Karns, Tristan; Smith, Paul Herrick

Understanding the water ingress behavior of containers used at the TA-55 Plutonium Facility has significant implications for criticality safety. The purpose of this report is to document the water ingress behavior of the Turbula Jar with Bakelite lid and Viton gaskets (Turbula Jar) used in oxide blending operations and the U-233 lead pig container used to store and transport U-233 material. The technical basis for water resistant containers at TA-55 is described in LA-UR-15-22781, “Water Resistant Container Technical Basis Document for the TA-55 Criticality Safety Program.” Testing of the water ingress behavior of various containers is described in LA-CP-13-00695, “Watermore » Penetration Tests on the Filters of Hagan and SAVY Containers,” LA-UR-15-23121, “Water Ingress into Crimped Convenience Containers under Flooding Conditions,” and in LA-UR- 16-2411, “Water Ingress Testing for TA-55 Containers.” Water ingress criteria are defined in TA55-AP-522 “TA-55 Criticality Safety Program”, and in PA-RD-01009 “TA55 Criticality Safety Requirements.” The water ingress criteria for submersion is no more than 50 ml of water ingress at a 6” water column height for a period of 2 hours.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searchedmore » and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included.« less

78 FR 69433 - Executive Order 13650 Improving Chemical Facility Safety and Security Listening Sessions

Federal Register 2010, 2011, 2012, 2013, 2014

2013-11-19

... Chemical Facility Safety and Security Listening Sessions AGENCY: National Protection and Programs... from stakeholders on issues pertaining to Improving Chemical Facility Safety and Security (Executive... regulations, guidance, and policies; and identifying best practices in chemical facility safety and security...

Engineering test facility design definition

NASA Technical Reports Server (NTRS)

Bercaw, R. W.; Seikel, G. R.

1980-01-01

The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

NASA Glenn Wind Tunnel Model Systems Criteria

NASA Technical Reports Server (NTRS)

Soeder, Ronald H.; Roeder, James W.; Stark, David E.; Linne, Alan A.

2004-01-01

This report describes criteria for the design, analysis, quality assurance, and documentation of models that are to be tested in the wind tunnel facilities at the NASA Glenn Research Center. This report presents two methods for computing model allowable stresses on the basis of the yield stress or ultimate stress, and it defines project procedures to test models in the NASA Glenn aeropropulsion facilities. Both customer-furnished and in-house model systems are discussed. The functions of the facility personnel and customers are defined. The format for the pretest meetings, safety permit process, and model reviews are outlined. The format for the model systems report (a requirement for each model that is to be tested at NASA Glenn) is described, the engineers responsible for developing the model systems report are listed, and the timetable for its delivery to the project engineer is given.

TA-55 and Sigma Overview

DOE Office of Scientific and Technical Information (OSTI.GOV)

Spearing, Dane Robert

These are slides from a facility overview presentation for visiting agencies to Los Alamos National Laboratory (LANL). The TA-55 Plutonium Facility (PF-4) is discussed in detail. PF-4 is a unique resource for US plutonium programs. The basic design is flexible and has adapted to changing national needs. It is a robust facility with strong safety and security implementation. It supports a variety of national programs. It will continue for many years into the future. Sigma is then discussed in detail, which handles everything from hydrogen to uranium. It has been in long term service to the Nation (nearly 60 years).more » It has a flexible authorization basis to handle almost the entire periodic table. It has a wide breadth of prototyping and characterization capabilities. It has integrated program and line management.« less

Evaluation of Isotopic Data Mismatches on DOE-STD-1027 Facility Categorization Inventories for the K-1065 Complex and the Above Grade Storage Facility (AGSF)

DOE Office of Scientific and Technical Information (OSTI.GOV)

McHugh, M.G.; Coleman, G.H.

2006-07-01

The contents of a safety basis (SB) are based upon the facility's purpose of operation, radiological inventory, and safety systems in place to mitigate any releases to the employees, general public and environment. Specifically, the radiological inventory is used for facility categorizations (e.g., Category 2, Category 3) and determining the material at risk used in the associated nuclear safety analysis calculations. Radiological inventory discrepancies, referred to as 'mismatches', have the potential to adversely impact the SB. This paper summarizes a process developed to: 1) identify these 'mismatches' based on a facility's radiological inventory, 2) categorize these 'mismatches' according to availablemore » data, and then 3) determine if these 'mismatches' yield either trivial or significant cumulative impacts on credited assumptions associated with a particular facility's SB. The two facilities evaluated for 'mismatches' were the K-1065 Complex and the Above Grade Storage Facility (AGSF). The randomly selected containers from each facility were obtained along with screening the radiological inventories found in the Waste Information Tracking System (WITS) database and the Request for Disposal (RFD) forms. Ideally, the radiological inventory, which is comprised of isotopic data for each container, is maintained in the WITS database. However, the RFD is the official repository record for isotopic data for each container. Historically, neither WITS nor the RFDs were required to contain isotopic data. Based on the WITS and RFD data, the containers were then categorized into five (5) separate conditions: Condition 1) Isotopic data in the RFD matches the isotopic data in WITS; Condition 2) Isotopic data in the RFD does not match the isotopic data in WITS; Condition 3) Isotopic data are in the RFD, but are not in WITS; Condition 4) No isotopic data in the RFD, but isotopic data are found in WITS; Condition 5) No isotopic data found in either the RFD or WITS. The results show trivial cumulative impacts (i.e., no inherent data biases) on credited assumptions associated with the K-1065 Complex and AGSF SBs. Recent random comparisons of WITS and RFDs continue to verify and validate that the administrative and procedural controls are adequate to ensure compliance with the SB for these facilities, thus providing a useful model for evaluating other facilities located at the Department of Energy's Oak Ridge Reservation (DOE-ORR). (authors)« less

77 FR 51943 - Procedures for Safety Investigations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-08-28

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period. SUMMARY: The Defense Nuclear Facilities Safety Board is extending the time for comments on its proposed...

78 FR 12042 - Public Availability of Defense Nuclear Facilities Safety Board FY 2011 Service Contract Inventory...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-02-21

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board FY 2011 Service Contract Inventory Analysis/FY 2012 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (DNFSB). ACTION: Notice of Public Availability of FY 2011 Service Contract...

76 FR 5354 - Public Availability of Defense Nuclear Facilities Safety Board FY 2010 Service Contract Inventory

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-31

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board FY 2010 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (Board). ACTION: Notice of public availability of FY 2010 Service Contract Inventories. SUMMARY: In accordance with...

77 FR 7139 - Public Availability of Defense Nuclear Facilities Safety Board; FY 2010 Service Contract...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-10

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board; FY 2010 Service Contract Inventory Analysis/FY 2011 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (DNFSB). ACTION: Notice of Public Availability of FY 2010 Service Contract...

Implementing an Integrated Commitment Management System at the Savannah River Site Tank Farms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Blanchard, A.

1999-06-16

Recently, the Savannah River Site Tank Farms have been transitioning from pre-1990 Authorization Basis requirements to new 5480.22/.23 requirements. Implementation of the new Authorization Basis has resulted in more detailed requirements, a completely new set of implementing procedures, and the expectation of even more disciplined operations. Key to the success of this implementation has been the development of an Integrated Commitment Management System (ICMS) by Westinghouse Safety Management Solutions. The ICMS has two elements: the Authorization Commitment Matrix (ACM), and a Procedure Consistency Review methodology. The Authorization Commitment Matrix is a linking database, which ties requirements and implementing documents together.more » The associated Procedure Consistency Review process ensures that the procedures to be credited in the ACM do in fact correctly and completely meet all intended commitments. This Integrated Commitment Management System helps Westinghouse Safety Management Solutions and the facility operations and engineering organizations take ownership in the implementation of the requirements that have been developed.« less

Guide for Maintaining Pedestrian Facilities for Enhanced Safety.

DOT National Transportation Integrated Search

2013-10-01

A Guide for Maintaining Pedestrian Facilities for Enhanced Safety provides guidance for maintaining pedestrian facilities with the primary goal of increasing safety and mobility. The Guide addresses the needs for pedestrian facility maintenance; comm...

76 FR 26716 - Sunshine Act Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2011-05-09

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting AGENCY: Defense Nuclear Facilities... Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing. FEDERAL REGISTER CITATIONS... Defense Nuclear Facilities Safety Board, Public Hearing Room, 625 Indiana Avenue, NW., Suite 300...

Mapping the Risks. Assessing the Homeland Security Implications of Publicly Available Geospatial Information

DTIC Science & Technology

2004-01-01

Defense Nuclear Facilities Safety Board 1 0.2 Export-Import Bank 1 0.2 National Archives and Records Administration 1 0.2 Supreme Court of the United...Agency Commodity Futures Trading Commission Consumer Product Safety Commission Defense Nuclear Facilities Safety Board Environmental Protection Agency...Intelligence www.cia.gov Defense Nuclear Facilities Safety Board Defense Nuclear Facilities Safety Board www.dnfsb.gov Department of

ASME Nuclear Crane Standards for Enhanced Crane Safety and Increased Profit

NASA Astrophysics Data System (ADS)

Parkhurst, Stephen N.

2000-01-01

The ASME NOG-1 standard, 'Rules for Construction of Overhead and Gantry Cranes', covers top running cranes for nuclear facilities; with the ASME NUM-1 standard, 'Rules for Construction of Cranes, Monorails, and Hoists', covering the single girder, underhung, wall and jib cranes, as well as the monorails and hoists. These two ASME nuclear crane standards provide criteria for designing, inspecting and testing overhead handling equipment with enhanced safety to meet the 'defense-in-depth' approach of the United States Nuclear Regulatory Commission (USNRC) documents NUREG 0554 and NUREG 0612. In addition to providing designs for enhanced safety, the ASME nuclear crane standards provide a basis for purchasing overhead handling equipment with standard safety features, based upon accepted engineering principles, and including performance and environmental parameters specific to nuclear facilities. The ASME NOG-1 and ASME NUM-1 standards not only provide enhanced safety for handling a critical load, but also increase profit by minimizing the possibility of load drops, by reducing cumbersome operating restrictions, and by providing the foundation for a sound licensing position. The ASME nuclear crane standards can also increase profit by providing the designs and information to help ensure that the right standard equipment is purchased. Additionally, the ASME nuclear crane standards can increase profit by providing designs and information to help address current issues, such as the qualification of nuclear plant cranes for making 'planned engineered lifts' for steam generator replacement and decommissioning.

75 FR 74022 - Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-30

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD [Recommendation 2010-1] Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers AGENCY: Defense Nuclear Facilities Safety Board... Nuclear Facilities Safety Board has made a recommendation to the Secretary of Energy requesting an...

75 FR 56080 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-15

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... Facilities Safety Board's public hearing and meeting. FEDERAL REGISTER CITATION OF PREVIOUS ANNOUNCEMENT: 75... INFORMATION: Brian Grosner, General Manager, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

78 FR 4393 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-22

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... Session II, the Board will receive testimony concerning safety at Pantex defense nuclear facilities. The...

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brink, J.

Crude oil (c. 10,700 BOPD) was produced through temporary topside facilities in the Rolf Field offshore Denmark from January 7th to September 17th, 1986. These simple, unmanned and remote controlled facilities were a low cost solution to a problem caused by delays of the permanent topside facilities. Project execution time was two months from start of conceptual design until start-up of oil production. Installation works were performed from a jack-up drilling rig - in part simultaneously with drilling operations. Materials and equipment installed were obtained with very short delivery times. The facilties which were certified by a Certification Society andmore » approved by the Danish Authoritites included all necessary safety features. Total costs for the facilities amounted to c. 1 million US$ (excl. rig time for installation). Due to simplicity high reliability of the production system was obtained. Availability of the facilities for the entire period from start-up was 99.6 percent. The facilities were manned 3.2 percent of the total operating time mainly due to wireline work for reservoir monitoring. It is considered that the experience with the concept applied for the early production from the Rolf Field could form the basis for more simple and cost effective topside facilities for minor offshore fields.« less

Facility safety study

NASA Technical Reports Server (NTRS)

1979-01-01

The safety of NASA's in house microelectronics facility is addressed. Industrial health standards, facility emission control requirements, operation and safety checklists, and the disposal of epitaxial vent gas are considered.

77 FR 479 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2012-01-05

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... of the Defense Nuclear Facilities Safety Board's (Board) public hearing and meeting described below... Nuclear Facilities Safety Board, 625 Indiana Avenue NW., Suite 700, Washington, DC 20004-2901, (800) 788...

77 FR 48970 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2012-08-15

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... (NNSA) efforts to mitigate risks to public and worker safety posed by aging defense nuclear facilities...

NASA/DOE/DOD nuclear propulsion technology planning: Summary of FY 1991 interagency panel results

NASA Technical Reports Server (NTRS)

Clark, John S.; Wickenheiser, Timothy J.; Doherty, Michael P.; Marshall, Albert; Bhattacharryya, Samit K.; Warren, John

1992-01-01

Interagency (NASA/DOE/DOD) technical panels worked in 1991 to evaluate critical nuclear propulsion issues, compare nuclear propulsion concepts for a manned Mars mission on a consistent basis, and to continue planning a technology development project for the Space Exploration Initiative (SEI). Panels were formed to address mission analysis, nuclear facilities, safety policy, nuclear fuels and materials, nuclear electric propulsion technology, and nuclear thermal propulsion technology. A summary of the results and recommendations of the panels is presented.

Antifoam degradation testing

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lambert, D. P.; Zamecnik, J. R.; Newell, D. D.

2015-08-20

This report describes the results of testing to quantify the degradation products resulting from the dilution and storage of Antifoam 747. Antifoam degradation is of concern to the Defense Waste Processing Facility (DWPF) due to flammable decomposition products in the vapor phase of the Chemical Process Cell vessels, as well as the collection of flammable and organic species in the offgas condensate. The discovery that hexamethyldisiloxane is formed from the antifoam decomposition was the basis for a Potential Inadequacy in the Safety Analysis declaration by the DWPF.

78 FR 9902 - DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-02-12

... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy; Correction AGENCY: Department of Energy... Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy. This document corrects an error in...

75 FR 69648 - Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-15

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD [Recommendation 2010-1] Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers AGENCY: Defense Nuclear Facilities Safety Board... Facilities Safety Board has made a recommendation to the Secretary of Energy requesting an amendment to the...

78 FR 48029 - Improving Chemical Facility Safety and Security

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-07

... responding to risks in chemical facilities (including during pre-inspection, inspection execution, post.... Sec. 2. Establishment of the Chemical Facility Safety and Security Working Group. (a) There is established a Chemical Facility Safety and Security Working Group (Working Group) co-chaired by the Secretary...

75 FR 13433 - Safety Zone; Invista Inc Facility Docks, Victoria Barge Canal, Victoria, TX

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-22

...-AA00 Safety Zone; Invista Inc Facility Docks, Victoria Barge Canal, Victoria, TX AGENCY: Coast Guard... safety zone for a partial blockage of the Victoria Barge Canal when the Invista Inc facility is... channel will be substantially reduced. The safety zone is necessary to help ensure the safety of the...

Health and Safety Management for Small-scale Methane Fermentation Facilities

NASA Astrophysics Data System (ADS)

Yamaoka, Masaru; Yuyama, Yoshito; Nakamura, Masato; Oritate, Fumiko

In this study, we considered health and safety management for small-scale methane fermentation facilities that treat 2-5 ton of biomass daily based on several years operation experience with an approximate capacity of 5 t·d-1. We also took account of existing knowledge, related laws and regulations. There are no qualifications or licenses required for management and operation of small-scale methane fermentation facilities, even though rural sewerage facilities with a relative similar function are required to obtain a legitimate license. Therefore, there are wide variations in health and safety consciousness of the operators of small-scale methane fermentation facilities. The industrial safety and health laws are not applied to the operation of small-scale methane fermentation facilities. However, in order to safely operate a small-scale methane fermentation facility, the occupational safety and health management system that the law recommends should be applied. The aims of this paper are to clarify the risk factors in small-scale methane fermentation facilities and encourage planning, design and operation of facilities based on health and safety management.

Mobile aviation services in the 1545-1559/1646.5-1660.5 MHz band

NASA Astrophysics Data System (ADS)

Kiesling, J. D.

1986-09-01

Plans in the U.S. for a national mobile satellite service (MSS) including satellite services to aviation for air traffic control and airline operational control are outlined. The MSS provides affordable mobile services in nonurban areas where terrestrially based systems are uneconomic. The MSS system also is available on a priority basis for aviation services, specifically AMSS(R) services involving safety and regularity of flight and other aviation services. The U.S. plan is expected to change the U.S. Tables of Allocations and proposes to change the International Table of Allocations so that MSS facilities can and will provide AMSS(R) services on a priority basis. Such arrangements can be implemented worldwide by administrations and organizations having similar interests.

78 FR 70858 - Safety Zones; Pacific Northwest Grain Handlers Association Facilities; Columbia and Willamette...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-11-27

... 1625-AA00 Safety Zones; Pacific Northwest Grain Handlers Association Facilities; Columbia and... establishing temporary safety zones around the following Pacific Northwest Grain Handlers Association... Commodities facility on the Willamette River in Portland, OR. These safety zones extend approximately between...

Flood hazard assessment for french NPPs

NASA Astrophysics Data System (ADS)

Rebour, Vincent; Duluc, Claire-Marie; Guimier, Laurent

2015-04-01

This paper presents the approach for flood hazard assessment for NPP which is on-going in France in the framework of post-Fukushima activities. These activities were initially defined considering both European "stress tests" of NPPs pursuant to the request of the European Council, and the French safety audit of civilian nuclear facilities in the light of the Fukushima Daiichi accident. The main actors in that process are the utility (EDF is, up to date, the unique NPP's operator in France), the regulatory authority (ASN) and its technical support organization (IRSN). This paper was prepared by IRSN, considering official positions of the other main actors in the current review process, it was not officially endorsed by them. In France, flood hazard to be considered for design basis definition (for new NPPs and for existing NPPs in periodic safety reviews conducted every 10 years) was revised before Fukushima-Daichi accident, due to le Blayais NPP December 1999 experience (partial site flooding and loss of some safety classified systems). The paper presents in the first part an overview of the revised guidance for design basis flood. In order to address design extension conditions (conditions that could result from natural events exceeding the design basis events), a set of flooding scenarios have been defined by adding margins on the scenarios that are considered for the design. Due to the diversity of phenomena to be considered for flooding hazard, the margin assessment is specific to each flooding scenario in terms of parameter to be penalized and of degree of variation of this parameter. The general approach to address design extension conditions is presented in the second part of the paper. The next parts present the approach for five flooding scenarios including design basis scenario and additional margin to define design extension scenarios.

Make safety awareness a priority: Use a login software in your research facility

DOE PAGES

Camino, Fernando E.

2017-01-21

We report on a facility login software, whose objective is to improve safety in multi-user research facilities. Its most important safety features are: 1) blocks users from entering the lab after being absent for more than a predetermined number of days; 2) gives users a random safety quiz question, which they need to answer satisfactorily in order to use the facility; 3) blocks unauthorized users from using the facility afterhours; and 4) displays the current users in the facility. Besides restricting access to unauthorized users, the software keeps users mindful of key safety concepts. In addition, integration of the softwaremore » with a door controller system can convert it into an effective physical safety mechanism. Depending on DOE approval, the code may be available as open source.« less

Make safety awareness a priority: Use a login software in your research facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Camino, Fernando E.

We report on a facility login software, whose objective is to improve safety in multi-user research facilities. Its most important safety features are: 1) blocks users from entering the lab after being absent for more than a predetermined number of days; 2) gives users a random safety quiz question, which they need to answer satisfactorily in order to use the facility; 3) blocks unauthorized users from using the facility afterhours; and 4) displays the current users in the facility. Besides restricting access to unauthorized users, the software keeps users mindful of key safety concepts. In addition, integration of the softwaremore » with a door controller system can convert it into an effective physical safety mechanism. Depending on DOE approval, the code may be available as open source.« less

Criticality Safety Evaluation for Small Sample Preparation and Non-Destructive Assay (NDA) Operations in Wing 7 Basement of the CMR Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kunkle, Paige Elizabeth; Zhang, Ning

Nuclear Criticality Safety (NCS) has reviewed the fissionable material small sample preparation and NDA operations in Wing 7 Basement of the CMR Facility. This is a Level-1 evaluation conducted in accordance with NCS-AP-004 [Reference 1], formerly NCS-GUIDE-01, and the guidance set forth on use of the Standard Criticality Safety Requirements (SCSRs) [Reference 2]. As stated in Reference 2, the criticality safety evaluation consists of both the SCSR CSED and the SCSR Application CSED. The SCSR CSED is a Level-3 CSED [Reference 3]. This Level-1 CSED is the SCSR Application CSED. This SCSR Application (Level-1) evaluation does not derive controls, itmore » simply applies controls derived from the SCSR CSED (Level-3) for the application of operations conducted here. The controls derived in the SCSR CSED (Level-3) were evaluated via the process described in Section 6.6.5 of SD-130 (also reproduced in Section 4.3.5 of NCS-AP-004 [Reference 1]) and were determined to not meet the requirements for consideration of elevation into the safety basis documentation for CMR. According to the guidance set forth on use of the SCSRs [Reference 2], the SCSR CSED (Level-3) is also applicable to the CMR Facility because the process and the normal and credible abnormal conditions in question are bounded by those that are described in the SCSR CSED. The controls derived in the SCSR CSED include allowances for solid materials and solution operations. Based on the operations conducted at this location, there are less-than-accountable (LTA) amounts of 233U. Based on the evaluation documented herein, the normal and credible abnormal conditions that might arise during the execution of this process will remain subcritical with the following recommended controls.« less

78 FR 4404 - DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-22

... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy AGENCY: Department of Energy. ACTION: Notice. SUMMARY: On September 28, 2012 the Defense Nuclear Facilities Safety Board submitted...

The Organization and Management of the Nuclear Weapons Program.

DTIC Science & Technology

1997-03-01

over operations include the Defense Nuclear Facilities Safety Board, the Environmental Protection Agency, the Occupational Safety and Health...Safety, and Health. Still more guidance is received from the Defense Nuclear Facilities Safety Board and other external bodies such as the...state regulatory agencies, and the Defense Nuclear Facilities Safety Board. This chapter briefly reviews the most recent decade of this history, describes

Safety aspects of nuclear waste disposal in space

NASA Technical Reports Server (NTRS)

Rice, E. E.; Edgecombe, D. S.; Compton, P. R.

1981-01-01

Safety issues involved in the disposal of nuclear wastes in space as a complement to mined geologic repositories are examined as part of an assessment of the feasibility of nuclear waste disposal in space. General safety guidelines for space disposal developed in the areas of radiation exposure and shielding, containment, accident environments, criticality, post-accident recovery, monitoring systems and isolation are presented for a nuclear waste disposal in space mission employing conventional space technology such as the Space Shuttle. The current reference concept under consideration by NASA and DOE is then examined in detail, with attention given to the waste source and mix, the waste form, waste processing and payload fabrication, shipping casks and ground transport vehicles, launch site operations and facilities, Shuttle-derived launch vehicle, orbit transfer vehicle, orbital operations and space destination, and the system safety aspects of the concept are discussed for each component. It is pointed out that future work remains in the development of an improved basis for the safety guidelines and the determination of the possible benefits and costs of the space disposal option for nuclear wastes.

Criticality Safety Evaluations on the Use of 200-gram Pu Mass Limit for RHWM Waste Storage Operations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chou, P

This work establishes the criticality safety technical basis to increase the fissile mass limit from 120 grams to 200 grams for Type A 55-gallon drums and their equivalents. Current RHWM fissile mass limit is 120 grams Pu for Type A 55-gallon containers and their equivalent. In order to increase the Type A 55-gallon drum limit to 200 grams, a few additional criticality safety control requirements are needed on moderators, reflectors, and array controls to ensure that the 200-gram Pu drums remain criticality safe with inadvertent criticality remains incredible. The purpose of this work is to analyze the use of 200-grammore » Pu drum mass limit for waste storage operations in Radioactive and Hazardous Waste Management (RHWM) Facilities. In this evaluation, the criticality safety controls associated with the 200-gram Pu drums are established for the RHWM waste storage operations. With the implementation of these criticality safety controls, the 200-gram Pu waste drum storage operations are demonstrated to be criticality safe and meet the double-contingency-principle requirement per DOE O 420.1.« less

Technical Report for Calculations of Atmospheric Dispersion at Onsite Locations for Department of Energy Nuclear Facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Levin, Alan; Chaves, Chris

2015-04-04

The Department of Energy (DOE) has performed an evaluation of the technical bases for the default value for the atmospheric dispersion parameter χ/Q. This parameter appears in the calculation of radiological dose at the onsite receptor location (co-located worker at 100 meters) in safety analysis of DOE nuclear facilities. The results of the calculation are then used to determine whether safety significant engineered controls should be established to prevent and/or mitigate the event causing the release of hazardous material. An evaluation of methods for calculation of the dispersion of potential chemical releases for the purpose of estimating the chemical exposuremore » at the co-located worker location was also performed. DOE’s evaluation consisted of: (a) a review of the regulatory basis for the default χ/Q dispersion parameter; (b) an analysis of this parameter’s sensitivity to various factors that affect the dispersion of radioactive material; and (c) performance of additional independent calculations to assess the appropriate use of the default χ/Q value.« less

Launch Services Safety Overview

NASA Technical Reports Server (NTRS)

Loftin, Charles E.

2008-01-01

NASA/KSC Launch Services Division Safety (SA-D) services include: (1) Assessing the safety of the launch vehicle (2) Assessing the safety of NASA ELV spacecraft (S/C) / launch vehicle (LV) interfaces (3) Assessing the safety of spacecraft processing to ensure resource protection of: - KSC facilities - KSC VAFB facilities - KSC controlled property - Other NASA assets (4) NASA personnel safety (5) Interfacing with payload organizations to review spacecraft for adequate safety implementation and compliance for integrated activities (6) Assisting in the integration of safety activities between the payload, launch vehicle, and processing facilities

NREL Provides First-of-its-Kind Guidance Promoting Safety Standards for

Science.gov Websites

Promoting Safety Standards for Natural Gas Vehicle Maintenance Facilities NREL Provides First-of-its-Kind Guidance Promoting Safety Standards for Natural Gas Vehicle Maintenance Facilities December 1, 2017 The U.S vehicle maintenance facilities with a new handbook and webinar that outline safety factors and standards

77 FR 43583 - DOE Response to Recommendation 2012-1 of the Defense Nuclear Facilities Safety Board, Savannah...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-07-25

... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-1 of the Defense Nuclear Facilities Safety Board, Savannah River Site Building 235-F Safety AGENCY: Department of Energy. ACTION: Notice. SUMMARY: On May 8, 2012, the Defense Nuclear Facilities Safety Board submitted Recommendation 2012-1...

Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program

DTIC Science & Technology

2007-07-16

The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent oversight organization within the Executive Branch charged... nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov/about/index.html]. beginning, addressed safety...approach, if successful, would “reduce or eliminate the need for ESD controls.”55 Kent Fortenberry, Technical Director of the Defense Nuclear Facilities Safety

Animal-assisted interventions: A national survey of health and safety policies in hospitals, eldercare facilities, and therapy animal organizations.

PubMed

Linder, Deborah E; Siebens, Hannah C; Mueller, Megan K; Gibbs, Debra M; Freeman, Lisa M

2017-08-01

Animal-assisted intervention (AAI) programs are increasing in popularity, but it is unknown to what extent therapy animal organizations that provide AAI and the hospitals and eldercare facilities they work with implement effective animal health and safety policies to ensure safety of both animals and humans. Our study objective was to survey hospitals, eldercare facilities, and therapy animal organizations on their AAI policies and procedures. A survey of United States hospitals, eldercare facilities, and therapy animal organizations was administered to assess existing health and safety policies related to AAI programs. Forty-five eldercare facilities, 45 hospitals, and 27 therapy animal organizations were surveyed. Health and safety policies varied widely and potentially compromised human and animal safety. For example, 70% of therapy animal organizations potentially put patients at risk by allowing therapy animals eating raw meat diets to visit facilities. In general, hospitals had stricter requirements than eldercare facilities. This information suggests that there are gaps between the policies of facilities and therapy animal organizations compared with recent guidelines for animal visitation in hospitals. Facilities with AAI programs need to review their policies to address recent AAI guidelines to ensure the safety of animals and humans involved. Copyright © 2017 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

PubMed

Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

2016-07-01

There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.

Safe design of healthcare facilities

PubMed Central

Reiling, J

2006-01-01

The physical environment has a significant impact on health and safety; however, hospitals have not been designed with the explicit goal of enhancing patient safety through facility design. In April 2002, St Joseph's Community Hospital of West Bend, a member of SynergyHealth, brought together leaders in healthcare and systems engineering to develop a set of safety‐driven facility design recommendations and principles that would guide the design of a new hospital facility focused on patient safety. By introducing safety‐driven innovations into the facility design process, environmental designers and healthcare leaders will be able to make significant contributions to patient safety. PMID:17142606

76 FR 17627 - Sunshine Act Meeting Postponed

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-30

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting Postponed AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of public meeting postponement. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register of March 3, 2011 (76 FR 11764...

77 FR 14007 - Sunshine Act Meeting Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-08

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting Notice Federal Register CITATION OF... THE MEETING: The Defense Nuclear Facilities Safety Board (Board) is expanding the matters to be.../ resolution of safety and technical issues across the defense nuclear facilities complex. Since this panel...

Confinement of Radioactive Materials at Defense Nuclear Facilities

DTIC Science & Technology

2004-10-01

The design of defense nuclear facilities includes systems whose reliable operation is vital to the protection of the public, workers, and the...final safety-class barrier to the release of hazardous materials with potentially serious public consequences. The Defense Nuclear Facilities Safety...the public at certain defense nuclear facilities . This change has resulted in downgrading of the functional safety classification of confinement

Fire safety of ground-based space facilities on the spaceport ;Vostochny;

NASA Astrophysics Data System (ADS)

Artamonov, Vladimir S.; Gordienko, Denis M.; Melikhov, Anatoly S.

2017-06-01

The facilities of the spaceport ;Vostochny; and the innovative technologies for fire safety to be implemented are considered. The planned approaches and prospects for fire safety ensuring at the facilities of the spaceport ;Vostochny; are presented herein, based on the study of emergency situations having resulted in fire accidents and explosion cases at the facilities supporting space vehicles operation.

75 FR 27228 - Proposed FOIA Fee Schedule Update

Federal Register 2010, 2011, 2012, 2013, 2014

2010-05-14

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of proposed rulemaking. SUMMARY: Pursuant to 10 CFR 1703.107(b)(6) of the Board's regulations, the Defense Nuclear Facilities Safety Board is...

77 FR 41258 - FOIA Fee Schedule Update

Federal Register 2010, 2011, 2012, 2013, 2014

2012-07-13

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

76 FR 28194 - Proposed FOIA Fee Schedule Update

Federal Register 2010, 2011, 2012, 2013, 2014

2011-05-16

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of proposed rulemaking. SUMMARY: Pursuant to 10 CFR 1703.107(b)(6) of the Board's regulations, the Defense Nuclear Facilities Safety Board is...

76 FR 43819 - FOIA Fee Schedule Update

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-22

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

78 FR 20625 - Extension of Hearing Record Closure Date

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-05

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on January 22, 2013...

77 FR 65871 - Extension of Hearing Record Closure Date

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-31

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on August 15, 2012...

78 FR 1206 - Second Extension of Hearing Record Closure Date

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-08

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Second Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Second extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on...

28 CFR 54.410 - Comparable facilities.

Code of Federal Regulations, 2013 CFR

2013-07-01

....410 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex... provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities...

Technical basis, supporting information, and strategy for development and implementation of DOE policy for natural phenomena hazards

DOE Office of Scientific and Technical Information (OSTI.GOV)

Murray, R.C.

1991-09-01

Policy for addressing natural phenomenon comprises a hierarchy of interrelated documents. The top level of policy is contained in the code of Federal Regulations which establishes the framework and intent to ensure overall safety of DOE facilities when subjected to the effects of natural phenomena. The natural phenomena to be considered include earthquakes and tsunami, winds, hurricanes and tornadoes, floods, volcano effects and seiches. Natural phenomena criteria have been established for design of new facilities; evaluation of existing facilities; additions, modifications, and upgrades to existing facilities; and evaluation criteria for new or existing sites. Steps needed to implement these fourmore » general criteria are described. The intent of these criteria is to identify WHAT needs to be done to ensure adequate protection from natural phenomena. The commentary provides discussion of WHY this is needed for DOE facilities within the complex. Implementing procedures identifying HOW to carry out these criteria are next identified. Finally, short and long term tasks needed to identify the implementing procedure are tabulated. There is an overall need for consistency throughout the DOE complex related to natural phenomena including consistent terminology, policy, and implementation. 1 fig, 6 tabs.« less

78 FR 65978 - Draft Revised Strategic Plan for FY 2014-2018

Federal Register 2010, 2011, 2012, 2013, 2014

2013-11-04

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Draft Revised Strategic Plan for FY 2014-2018 AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice. SUMMARY: In accordance with Office of Management and Budget Circular No. A-11, the Defense Nuclear Facilities Safety Board (DNFSB) is soliciting...

75 FR 4794 - Draft Revised Strategic Plan for FY 2010-2015

Federal Register 2010, 2011, 2012, 2013, 2014

2010-01-29

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Draft Revised Strategic Plan for FY 2010-2015 AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice. SUMMARY: In accordance with OMB Circular No. A-11, the Defense Nuclear Facilities Safety Board is soliciting comments from all interested and potentially...

Proposed Activities to Address Regulatory Gaps and Challenges for Licensing Advanced Reactors Using Seismic Isolation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Coleman, Justin Leigh; Kammerer, Annie M.; Whittaker, Andrew S.

Over the last decade, particularly since implementation of the certified design regulatory approaches outlined in 10 CFR 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” interest has been increasing in the use of seismic isolation (SI) technology to support seismic safety in nuclear facilities. In 2009, the United States (U.S.) Nuclear Regulatory Commission (NRC) initiated research activities to develop new guidance targeted at isolated facilities because SI is being considered for nuclear power plants in the U.S. One product of that research, which was developed around a risk-informed regulatory approach, is a draft NRC NUREG series (NUREG/CR) report thatmore » investigates and discusses considerations for use of SI in otherwise traditionally founded large light water reactors (LWRs). A coordinated effort led to new provisions for SI of LWRs in the American Society of Civil Engineers standard ASCE/SEI 4-16, “Seismic Analysis of Safety Related Nuclear Structures.” The risk-informed design philosophy that underpinned development of the technical basis for these documents led to a set of proposed performance objectives and acceptance criteria intended to serve as the foundation for future NRC guidance on the use of SI and related technology. Although the guidance provided in the draft SI NUREG/CR report and ASCE/SEI 4 16 provides a sound basis for further development of nuclear power plant designs incorporating SI, these initial documents were focused on surface-founded or near-surface-founded LWRs and were, necessarily, limited in scope. For example, there is limited information in both the draft NUREG/CR report and ASCE/SEI 4-16 related to nonlinear analysis of soil-structure systems for deeply-embedded reactors, the isolation of components, and the use of vertical isolation systems. Also not included in the draft SI NUREG/CR report are special considerations for licensing of isolated facilities using the certified design approach in 10 CFR 52 and a detailed discussion of seismic probabilistic risk assessments for isolated facilities.« less

Annual Report To Congress. Department of Energy Activities Relating to the Defense Nuclear Facilities Safety Board, Calendar Year 2003

DOE Office of Scientific and Technical Information (OSTI.GOV)

None, None

2004-02-28

The Department of Energy (Department) submits an Annual Report to Congress each year detailing the Department’s activities relating to the Defense Nuclear Facilities Safety Board (Board), which provides advice and recommendations to the Secretary of Energy (Secretary) regarding public health and safety issues at the Department’s defense nuclear facilities. In 2003, the Department continued ongoing activities to resolve issues identified by the Board in formal recommendations and correspondence, staff issue reports pertaining to Department facilities, and public meetings and briefings. Additionally, the Department is implementing several key safety initiatives to address and prevent safety issues: safety culture and review ofmore » the Columbia accident investigation; risk reduction through stabilization of excess nuclear materials; the Facility Representative Program; independent oversight and performance assurance; the Federal Technical Capability Program (FTCP); executive safety initiatives; and quality assurance activities. The following summarizes the key activities addressed in this Annual Report.« less

75 FR 66683 - Defense Federal Acquisition Regulation Supplement; Safety of Facilities, Infrastructure, and...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-10-29

... operation of facilities, infrastructure, and equipment for use by DoD military or civilian should be...-7004, Safety of Facilities, Infrastructure, and Equipment for Military Operations. DFARS 246.270-1... operation of facilities. This includes contracts for facilities, infrastructure, and equipment configured...

49 CFR 25.410 - Comparable facilities.

Code of Federal Regulations, 2013 CFR

2013-10-01

... Transportation Office of the Secretary of Transportation NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in... toilet, locker room, and shower facilities on the basis of sex, but such facilities provided for students...

48 CFR 252.246-7004 - Safety of Facilities, Infrastructure, and Equipment for Military Operations.

Code of Federal Regulations, 2011 CFR

2011-10-01

...: SAFETY OF FACILITIES, INFRASTRUCTURE, AND EQUIPMENT FOR MILITARY OPERATIONS (OCT 2010) (a) Definition... 48 Federal Acquisition Regulations System 3 2011-10-01 2011-10-01 false Safety of Facilities, Infrastructure, and Equipment for Military Operations. 252.246-7004 Section 252.246-7004 Federal Acquisition...

48 CFR 246.270 - Safety of facilities, infrastructure, and equipment for military operations.

Code of Federal Regulations, 2011 CFR

2011-10-01

... ASSURANCE Contract Quality Requirements 246.270 Safety of facilities, infrastructure, and equipment for... 48 Federal Acquisition Regulations System 3 2011-10-01 2011-10-01 false Safety of facilities, infrastructure, and equipment for military operations. 246.270 Section 246.270 Federal Acquisition Regulations...

Safety Information, Transportation & Public Facilities, State of Alaska

Science.gov Websites

Department of Transportation & Public Facilities/ Safety Information Search DOT&PF State of Alaska DOT&PF> Safety Information DOT&PF Safety Information link to 511 511.alaska.gov - Traveler Information link to AHSO Alaska Highway Safety Office link to HSIP Highway Safety Improvement Program link to

16 CFR 1203.30 - Purpose, basis, and scope.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 1203.30 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR BICYCLE HELMETS Certification § 1203.30 Purpose, basis, and scope. (a) Purpose. The... of compliance in the form specified. (b) Basis. Section 14(a)(1) of the Consumer Product Safety Act...

Challenges Ahead for Nuclear Facility Site-Specific Seismic Hazard Assessment in France: The Alternative Energies and the Atomic Energy Commission (CEA) Vision

NASA Astrophysics Data System (ADS)

Berge-Thierry, C.; Hollender, F.; Guyonnet-Benaize, C.; Baumont, D.; Ameri, G.; Bollinger, L.

2017-09-01

Seismic analysis in the context of nuclear safety in France is currently guided by a pure deterministic approach based on Basic Safety Rule ( Règle Fondamentale de Sûreté) RFS 2001-01 for seismic hazard assessment, and on the ASN/2/01 Guide that provides design rules for nuclear civil engineering structures. After the 2011 Tohohu earthquake, nuclear operators worldwide were asked to estimate the ability of their facilities to sustain extreme seismic loads. The French licensees then defined the `hard core seismic levels', which are higher than those considered for design or re-assessment of the safety of a facility. These were initially established on a deterministic basis, and they have been finally justified through state-of-the-art probabilistic seismic hazard assessments. The appreciation and propagation of uncertainties when assessing seismic hazard in France have changed considerably over the past 15 years. This evolution provided the motivation for the present article, the objectives of which are threefold: (1) to provide a description of the current practices in France to assess seismic hazard in terms of nuclear safety; (2) to discuss and highlight the sources of uncertainties and their treatment; and (3) to use a specific case study to illustrate how extended source modeling can help to constrain the key assumptions or parameters that impact upon seismic hazard assessment. This article discusses in particular seismic source characterization, strong ground motion prediction, and maximal magnitude constraints, according to the practice of the French Atomic Energy Commission. Due to increases in strong motion databases in terms of the number and quality of the records in their metadata and the uncertainty characterization, several recently published empirical ground motion prediction models are eligible for seismic hazard assessment in France. We show that propagation of epistemic and aleatory uncertainties is feasible in a deterministic approach, as in a probabilistic way. Assessment of seismic hazard in France in the framework of the safety of nuclear facilities should consider these recent advances. In this sense, the opening of discussions with all of the stakeholders in France to update the reference documents (i.e., RFS 2001-01; ASN/2/01 Guide) appears appropriate in the short term.

Safety analysis, 200 Area, Savannah River Plant: Separations area operations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Perkins, W.C.; Lee, R.; Allen, P.M.

1991-07-01

The nev HB-Line, located on the fifth and sixth levels of Building 221-H, is designed to replace the aging existing HB-Line production facility. The nev HB-Line consists of three separate facilities: the Scrap Recovery Facility, the Neptunium Oxide Facility, and the Plutonium Oxide Facility. There are three separate safety analyses for the nev HB-Line, one for each of the three facilities. These are issued as supplements to the 200-Area Safety Analysis (DPSTSA-200-10). These supplements are numbered as Sup 2A, Scrap Recovery Facility, Sup 2B, Neptunium Oxide Facility, Sup 2C, Plutonium Oxide Facility. The subject of this safety analysis, the, Plutoniummore » Oxide Facility, will convert nitrate solutions of {sup 238}Pu to plutonium oxide (PuO{sub 2}) powder. All these new facilities incorporate improvements in: (1) engineered barriers to contain contamination, (2) barriers to minimize personnel exposure to airborne contamination, (3) shielding and remote operations to decrease radiation exposure, and (4) equipment and ventilation design to provide flexibility and improved process performance.« less

10 CFR 1042.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-01-01

... DEPARTMENT OF ENERGY (GENERAL PROVISIONS) NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or..., and shower facilities on the basis of sex, but such facilities provided for students of one sex shall...

29 CFR 36.410 - Comparable facilities.

Code of Federal Regulations, 2012 CFR

2012-07-01

... of the Secretary of Labor NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or..., and shower facilities on the basis of sex, but such facilities provided for students of one sex shall...

45 CFR 618.410 - Comparable facilities.

Code of Federal Regulations, 2014 CFR

2014-10-01

... NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

29 CFR 36.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-07-01

... of the Secretary of Labor NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or..., and shower facilities on the basis of sex, but such facilities provided for students of one sex shall...

Hypergol Systems: Design, Buildup, and Operation

NASA Technical Reports Server (NTRS)

Baker, David; Rathgeber, Kurt

2006-01-01

This course was developed by personnel at the NASA JSC White Sands Test Facility in conjunction with the NASA Safety Training Center (NSTC). The NSTC was established in May 1991 by the NASA Headquarters Safety Directorate to provide up-to-date, high-quality, NASA specific safety training on location at NASA centers, or simultaneously to multiple centers over the Video Teleconferencing System (ViTS). Our desire is to establish and maintain a strong, long-lasting relationship with all NASA centers in order to fulfill your safety training needs on a cost-effective basis. Our ultimate goal is to provide a positive contribution to safe operations at NASA. NSTC Course 055 is a 2-day course discussing the safe usage of hypergols (hydrazine fuels and nitrogen tetroxide). During the course we will identify the hazards associated with hypergols including toxicity, reactivity, fire, and explosion. Management of risk is discussed in terms of the primary engineering controls design, buildup, and operation; and secondary controls personal protective equipment and detectors/monitors. The emphasis is on the design and buildup of compatible systems and the safe operation of these systems by technicians and engineers.

Modelling of Field-Reversed Configuration Experiment with Large Safety Factor

DOE Office of Scientific and Technical Information (OSTI.GOV)

Steinhauer, L; Guo, H; Hoffman, A

2005-11-28

The Translation-Confinement-Sustainment facility has been operated in the 'translation-formation' mode in which a plasma is ejected at high-speed from a {theta}-pinch-like source into a confinement chamber where it settles into a field-reversed-configuration state. Measurements of the poloidal and toroidal field have been the basis of modeling to infer the safety factor. It is found that the edge safety factor exceeds two, and that there is strong forward magnetic shear. The high-q arises because the large elongation compensates for the modest ratio of toroidal-to-poloidal field in the plasma. This is the first known instance of a very high-{beta} plasma with amore » safety factor greater than unity. Two-fluid modeling of the measurements also indicate several other significant features: a broad 'transition layer' at the plasma boundary with probable line-tying effects, complex high-speed flows, and the appearance of a two-fluid minimum-energy state in the plasma core. All these features may contribute to both the stability and good confinement of the plasma.« less

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467

DOE Office of Scientific and Technical Information (OSTI.GOV)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger

2013-07-01

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA formore » re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)« less

A safety management system for an offshore Azerbaijan Caspian Sea Project

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brasic, M.F.; Barber, S.W.; Hill, A.S.

1996-11-01

This presentation will describe the Safety Management System that Azerbaijan International Operating Company (AIOC) has structured to assure that Company activities are performed in a manner that protects the public, the environment, contractors and AIOC employees. The Azerbaijan International Oil Company is a consortium of oil companies that includes Socar, the state oil company of Azerbaijan, a number of major westem oil companies, and companies from Russia, Turkey and Saudi Arabia. The Consortium was formed to develop and produce a group of large oil fields in the Caspian Sea. The Management of AIOC, in starting a new operation in Azerbaijan,more » recognized the need for a formal HSE management system to ensure that their HSE objectives for AIOC activities were met. As a consortium of different partners working together in a unique operation, no individual partner company HSE Management system was appropriate. Accordingly AIOC has utilized the E & P Forum {open_quotes}Guidelines for the Development and Application of Health Safety and Environmental Management Systems{close_quotes} as the framework document for the development of the new AIOC system. Consistent with this guideline, AIOC has developed 19 specific HSE Management System Expectations for implementing its HSE policy and objectives. The objective is to establish and continue to maintain operational integrity in all AIOC activities and site operations. An important feature is the use of structured Safety Cases for the design engineering activity. The basis for the Safety Cases is API RP 75 and 14 J for offshore facilities and API RP 750 for onshore facilities both complimented by {open_quotes}Best International Oilfield Practice{close_quotes}. When viewed overall, this approach provides a fully integrated system of HSE management from design into operation.« less

Medicare and Medicaid Programs; Fire Safety Requirements for Certain Health Care Facilities. Final rule.

PubMed

2016-05-04

This final rule will amend the fire safety standards for Medicare and Medicaid participating hospitals, critical access hospitals (CAHs), long-term care facilities, intermediate care facilities for individuals with intellectual disabilities (ICF-IID), ambulatory surgery centers (ASCs), hospices which provide inpatient services, religious non-medical health care institutions (RNHCIs), and programs of all-inclusive care for the elderly (PACE) facilities. Further, this final rule will adopt the 2012 edition of the Life Safety Code (LSC) and eliminate references in our regulations to all earlier editions of the Life Safety Code. It will also adopt the 2012 edition of the Health Care Facilities Code, with some exceptions.

Stochastic Modeling of Radioactive Material Releases

DOE Office of Scientific and Technical Information (OSTI.GOV)

Andrus, Jason; Pope, Chad

2015-09-01

Nonreactor nuclear facilities operated under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculatesmore » the radiation dose associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA was developed using the MATLAB coding framework. The software application has a graphical user input. SODA can be installed on both Windows and Mac computers and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC, rather it is viewed as an easy to use supplemental tool to help improve risk understanding and support better informed decisions. The work was funded through a grant from the DOE Nuclear Safety Research and Development Program.« less

33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...

33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...

33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...

33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...

76 FR 20588 - FDA Food Safety Modernization Act: Focus on Preventive Controls for Facilities; Public Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-13

.... FDA-2011-N-0251] FDA Food Safety Modernization Act: Focus on Preventive Controls for Facilities... comment. SUMMARY: The Food and Drug Administration (FDA) is announcing a public meeting entitled ``FDA... controls for facilities provisions of the recently enacted FDA Food Safety Modernization Act (FSMA). FDA is...

PWR-related integral safety experiments in the PKL 111 test facility SBLOCA under beyond-design-basis accident conditions

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weber, P.; Umminger, K.J.; Schoen, B.

1995-09-01

The thermal hydraulic behavior of a PWR during beyond-design-basis accident scenarios is of vital interest for the verification and optimization of accident management procedures. Within the scope of the German reactor safety research program experiments were performed in the volumetrically scaled PKL 111 test facility by Siemens/KWU. This highly instrumented test rig simulates a KWU-design PWR (1300 MWe). In particular, the latest tests performed related to a SBLOCA with additional system failures, e.g. nitrogen entering the primary system. In the case of a SBLOCA, it is the goal of the operator to put the plant in a condition where themore » decay heat can be removed first using the low pressure emergency core cooling system and then the residual heat removal system. The experimental investigation presented assumed the following beyond-design-basis accident conditions: 0.5% break in a cold leg, 2 of 4 steam generators (SGs) isolated on the secondary side (feedwater- and steam line-valves closed), filled with steam on the primary side, cooldown of the primary system using the remaining two steam generators, high pressure injection system only in the two loops with intact steam generators, if possible no operator actions to reach the conditions for residual heat removal system activation. Furthermore, it was postulated that 2 of the 4 hot leg accumulators had a reduced initial water inventory (increased nitrogen inventory), allowing nitrogen to enter the primary system at a pressure of 15 bar and nearly preventing the heat transfer in the SGs ({open_quotes}passivating{close_quotes} U-tubes). Due to this the heat transfer regime in the intact steam generators changed remarkably. The primary system showed self-regulating system effects and heat transfer improved again (reflux-condenser mode in the U-tube inlet region).« less

75 FR 43495 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-26

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities..., structures, and components, and (5) safety-related design aspects of new facilities or modifications of existing facilities needed to deliver high-level waste feed. The Board will be prepared to accept any other...

Study on the evaluation method for fault displacement based on characterized source model

NASA Astrophysics Data System (ADS)

Tonagi, M.; Takahama, T.; Matsumoto, Y.; Inoue, N.; Irikura, K.; Dalguer, L. A.

2016-12-01

In IAEA Specific Safety Guide (SSG) 9 describes that probabilistic methods for evaluating fault displacement should be used if no sufficient basis is provided to decide conclusively that the fault is not capable by using the deterministic methodology. In addition, International Seismic Safety Centre compiles as ANNEX to realize seismic hazard for nuclear facilities described in SSG-9 and shows the utility of the deterministic and probabilistic evaluation methods for fault displacement. In Japan, it is required that important nuclear facilities should be established on ground where fault displacement will not arise when earthquakes occur in the future. Under these situations, based on requirements, we need develop evaluation methods for fault displacement to enhance safety in nuclear facilities. We are studying deterministic and probabilistic methods with tentative analyses using observed records such as surface fault displacement and near-fault strong ground motions of inland crustal earthquake which fault displacements arose. In this study, we introduce the concept of evaluation methods for fault displacement. After that, we show parts of tentative analysis results for deterministic method as follows: (1) For the 1999 Chi-Chi earthquake, referring slip distribution estimated by waveform inversion, we construct a characterized source model (Miyake et al., 2003, BSSA) which can explain observed near-fault broad band strong ground motions. (2) Referring a characterized source model constructed in (1), we study an evaluation method for surface fault displacement using hybrid method, which combines particle method and distinct element method. At last, we suggest one of the deterministic method to evaluate fault displacement based on characterized source model. This research was part of the 2015 research project `Development of evaluating method for fault displacement` by the Secretariat of Nuclear Regulation Authority (S/NRA), Japan.

Sharp Decrease of Reported Occupational Blood and Body Fluid Exposures in French Hospitals, 2003-2012: Results of the French National Network Survey, AES-RAISIN.

PubMed

Floret, N; Ali-Brandmeyer, O; L'Hériteau, F; Bervas, C; Barquins-Guichard, S; Pelissier, G; Abiteboul, D; Parneix, P; Bouvet, E; Rabaud, C

2015-08-01

To assess the temporal trend of reported occupational blood and body fluid exposures (BBFE) in French healthcare facilities. Retrospective follow-up of reported BBFE in French healthcare facilities on a voluntary basis from 2003 to 2012 with a focus on those enrolled every year from 2008 to 2012 (stable cohort 2008-12). Reported BBFE incidence rate per 100 beds decreased from 7.5% in 2003 to 6.3% in 2012 (minus 16%). Percutaneous injuries were the most frequent reported BBFE (84.0% in 2003 and 79.1% in 2012). Compliance with glove use (59.1% in 2003 to 67.0% in 2012) and sharps-disposal container accessibility (68.1% in 2003 to 73.4% in 2012) have both increased. A significant drop in preventable BBFE was observed (48.3% in 2003 to 30.9% in 2012). Finally, the use of safety-engineered devices increased from 2008 to 2012. Of the 415,209 hospital beds in France, 26,158 BBFE could have occurred in France in 2012, compared with 35,364 BBFE in 2003. Healthcare personnel safety has been sharply improved during the past 10 years in France.

An Overview of INEL Fusion Safety R&D Facilities

NASA Astrophysics Data System (ADS)

McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.

1997-06-01

The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.

Criticality safety strategy and analysis summary for the fuel cycle facility electrorefiner at Argonne National Laboratory West

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mariani, R.D.; Benedict, R.W.; Lell, R.M.

1996-05-01

As part of the termination activities of Experimental Breeder Reactor II (EBR-II) at Argonne National Laboratory (ANL) West, the spent metallic fuel from EBR-II will be treated in the fuel cycle facility (FCF). A key component of the spent-fuel treatment process in the FCF is the electrorefiner (ER) in which the actinide metals are separated from the active metal fission products and the reactive bond sodium. In the electrorefining process, the metal fuel is anodically dissolved into a high-temperature molten salt, and refined uranium or uranium/plutonium products are deposited at cathodes. The criticality safety strategy and analysis for the ANLmore » West FCF ER is summarized. The FCF ER operations and processes formed the basis for evaluating criticality safety and control during actinide metal fuel refining. To show criticality safety for the FCF ER, the reference operating conditions for the ER had to be defined. Normal operating envelopes (NOEs) were then defined to bracket the important operating conditions. To keep the operating conditions within their NOEs, process controls were identified that can be used to regulate the actinide forms and content within the ER. A series of operational checks were developed for each operation that will verify the extent or success of an operation. The criticality analysis considered the ER operating conditions at their NOE values as the point of departure for credible and incredible failure modes. As a result of the analysis, FCF ER operations were found to be safe with respect to criticality.« less

33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...

33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...

33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...

33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...

33 CFR 165.1406 - Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...

33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false ExxonMobil Hoover Floating OCS... Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos... (1640.4 feet) from each point on the structure's outer edge is a safety zone. (b) Regulation. No vessel...

Nuclear Warheads: The Reliable Replacement Warhead program and the Life Extension Program

DTIC Science & Technology

2007-12-03

eliminate the need for ESD controls.”67 CRS-22 68 The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent oversight...public health and safety’ at DOE’s defense nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov...about/index.html]. 69 Personal communication, Kent Fortenberry, Technical Director, Defense Nuclear Facilities Safety Board, September 14, 2006. 70

Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program

DTIC Science & Technology

2007-04-04

Information provided by Pantex Plant, Sept. 19, 2006. 50 The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent...protection of public health and safety’ at DOE’s defense nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http...www.dnfsb.gov/about/index.html]. 51 Personal communication, Kent Fortenberry, Technical Director, Defense Nuclear Facilities Safety Board, Sept. 14, 2006

Medicare and Medicaid programs; fire safety requirements for certain health care facilities. Final rule.

PubMed

2003-01-10

This final rule amends the fire safety standards for hospitals, long-term care facilities, intermediate care facilities for the mentally retarded, ambulatory surgery centers, hospices that provide inpatient services, religious nonmedical health care institutions, critical access hospitals, and Programs of All-Inclusive Care for the Elderly facilities. Further, this final rule adopts the 2000 edition of the Life Safety Code and eliminates references in our regulations to all earlier editions.

Recent Upgrades at the Safety and Tritium Applied Research Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cadwallader, Lee Charles; Merrill, Brad Johnson; Stewart, Dean Andrew

This paper gives a brief overview of the Safety and Tritium Applied Research (STAR) facility operated by the Fusion Safety Program (FSP) at the Idaho National Laboratory (INL). FSP researchers use the STAR facility to carry out experiments in tritium permeation and retention in various fusion materials, including wall armor tile materials. FSP researchers also perform other experimentation as well to support safety assessment in fusion development. This lab, in its present two-building configuration, has been in operation for over ten years. The main experiments at STAR are briefly described. This paper discusses recent work to enhance personnel safety atmore » the facility. The STAR facility is a Department of Energy less than hazard category 3 facility; the personnel safety approach calls for ventilation and tritium monitoring for radiation protection. The tritium areas of STAR have about 4 to 12 air changes per hour, with air flow being once through and then routed to the facility vent stack. Additional radiation monitoring has been installed to read the laboratory room air where experiments with tritium are conducted. These ion chambers and bubblers are used to verify that no significant tritium concentrations are present in the experiment rooms. Standby electrical power has been added to the facility exhaust blower so that proper ventilation will now operate during commercial power outages as well as the real-time tritium air monitors.« less

Health and safety programs for art and theater schools.

PubMed

McCann, M

2001-01-01

A wide variety of health and safety hazards exist in schools and colleges of art and theater due to a lack of formal health and safety programs and a failure to include health and safety concerns during planning of new facilities and renovation of existing facilities. This chapter discusses the elements of a health and safety program as well as safety-related structural and equipment needs that should be in the plans for any school of art or theater. These elements include curriculum content, ventilation, storage, housekeeping, waste management, fire and explosion prevention, machine and tool safety, electrical safety, noise, heat stress, and life safety and emergency procedures and equipment. Ideally, these elements should be incorporated into the plans for any new facilities, but ongoing programs can also benefit from a review of existing health and safety programs.

78 FR 49262 - Sunshine Act Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-13

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... associated with continued operation of aging defense nuclear [[Page 49263

76 FR 11339 - Update to NFPA 101, Life Safety Code, for State Home Facilities

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-02

... DEPARTMENT OF VETERANS AFFAIRS 38 CFR Part 51 RIN 2900-AN59 Update to NFPA 101, Life Safety Code..., Life Safety Code. The change is designed to assure that State Home facilities meet current industry- wide standards regarding life safety and fire safety. DATES: Effective Date: This final rule is...

30 CFR 75.1712-2 - Location of surface facilities.

Code of Federal Regulations, 2014 CFR

2014-07-01

... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Location of surface facilities. 75.1712-2...

30 CFR 75.1712-2 - Location of surface facilities.

Code of Federal Regulations, 2012 CFR

2012-07-01

... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Location of surface facilities. 75.1712-2...

30 CFR 75.1712-2 - Location of surface facilities.

Code of Federal Regulations, 2011 CFR

2011-07-01

... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Location of surface facilities. 75.1712-2...

30 CFR 75.1712-2 - Location of surface facilities.

Code of Federal Regulations, 2013 CFR

2013-07-01

... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Location of surface facilities. 75.1712-2...

30 CFR 75.1712-2 - Location of surface facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Location of surface facilities. 75.1712-2... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location...

42 CFR 413.330 - Basis and scope.

Code of Federal Regulations, 2010 CFR

2010-10-01

... PROSPECTIVELY DETERMINED PAYMENT RATES FOR SKILLED NURSING FACILITIES Prospective Payment for Skilled Nursing Facilities § 413.330 Basis and scope. (a) Basis. This subpart implements section 1888(e) of the Act, which...

42 CFR 413.330 - Basis and scope.

Code of Federal Regulations, 2014 CFR

2014-10-01

... PROSPECTIVELY DETERMINED PAYMENT RATES FOR SKILLED NURSING FACILITIES Prospective Payment for Skilled Nursing Facilities § 413.330 Basis and scope. (a) Basis. This subpart implements section 1888(e) of the Act, which...

42 CFR 413.330 - Basis and scope.

Code of Federal Regulations, 2012 CFR

2012-10-01

... PROSPECTIVELY DETERMINED PAYMENT RATES FOR SKILLED NURSING FACILITIES Prospective Payment for Skilled Nursing Facilities § 413.330 Basis and scope. (a) Basis. This subpart implements section 1888(e) of the Act, which...

42 CFR 413.330 - Basis and scope.

Code of Federal Regulations, 2011 CFR

2011-10-01

... PROSPECTIVELY DETERMINED PAYMENT RATES FOR SKILLED NURSING FACILITIES Prospective Payment for Skilled Nursing Facilities § 413.330 Basis and scope. (a) Basis. This subpart implements section 1888(e) of the Act, which...

42 CFR 413.330 - Basis and scope.

Code of Federal Regulations, 2013 CFR

2013-10-01

... PROSPECTIVELY DETERMINED PAYMENT RATES FOR SKILLED NURSING FACILITIES Prospective Payment for Skilled Nursing Facilities § 413.330 Basis and scope. (a) Basis. This subpart implements section 1888(e) of the Act, which...

Highway Safety Manual applied in Missouri - freeway/software.

DOT National Transportation Integrated Search

2016-06-01

AASHTOs Highway Safety Manual (HSM) facilitates the quantitative safety analysis of highway facilities. In a 2014 : supplement, freeway facilities were added to the original HSM manual which allows the modeling of highway : interchanges. This repo...

75 FR 44817 - Notice of Availability of Uranium Enrichment Fuel Cycle Facility Inspection Reports Regarding...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-29

... Uranium Enrichment Fuel Cycle Facility Inspection Reports Regarding Louisiana Energy Services, National... Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and... Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and...

43 CFR 41.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 43 Public Lands: Interior 1 2011-10-01 2011-10-01 false Comparable facilities. 41.410 Section 41... Basis of Sex in Education Programs or Activities Prohibited § 41.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

6 CFR 17.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 6 Domestic Security 1 2010-01-01 2010-01-01 false Comparable facilities. 17.410 Section 17.410... the Basis of Sex in Education Programs or Activities Prohibited § 17.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

13 CFR 113.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Comparable facilities. 113.410... Discrimination on the Basis of Sex in Education Programs Or Activities Prohibited § 113.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

34 CFR 106.33 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 34 Education 1 2010-07-01 2010-07-01 false Comparable facilities. 106.33 Section 106.33 Education... Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 106.33 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

31 CFR 28.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Comparable facilities. 28.410 Section... on the Basis of Sex in Education Programs or Activities Prohibited § 28.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

Analyses in Support of Risk-Informed Natural Gas Vehicle Maintenance Facility Codes and Standards: Phase II.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Blaylock, Myra L.; LaFleur, Chris Bensdotter; Muna, Alice Baca

Safety standards development for maintenance facilities of liquid and compressed natural gas fueled vehicles is required to ensure proper facility design and operating procedures. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase II work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest using risk ranking. Detailed simulations and modeling were performed to estimate the location and behaviormore » of natural gas releases based on these scenarios. Specific code conflicts were identified, and ineffective code requirements were highlighted and resolutions proposed. These include ventilation rate basis on area or volume, as well as a ceiling offset which seems ineffective at protecting against flammable gas concentrations. ACKNOWLEDGEMENTS The authors gratefully acknowledge Bill Houf (SNL -- Retired) for his assistance with the set-up and post-processing of the numerical simulations. The authors also acknowledge Doug Horne (retired) for his helpful discussions. We would also like to acknowledge the support from the Clean Cities program of DOE's Vehicle Technology Office.« less

Preliminary hazards analysis -- vitrification process

DOE Office of Scientific and Technical Information (OSTI.GOV)

Coordes, D.; Ruggieri, M.; Russell, J.

1994-06-01

This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s constructionmore » and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.« less

42 CFR 413.335 - Basis of payment.

Code of Federal Regulations, 2010 CFR

2010-10-01

... Facilities § 413.335 Basis of payment. (a) Method of payment. Under the prospective payment system, SNFs... and, during a transition period, on the basis of a blend of the Federal rate and the facility-specific...

30 CFR 71.400 - Bathing facilities; change rooms; sanitary flush toilet facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... flush toilet facilities. 71.400 Section 71.400 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE... installations and at the surface worksites of such mine. (Note: Sanitary facilities at surface work areas of...

49 CFR 193.2001 - Scope of part.

Code of Federal Regulations, 2010 CFR

2010-10-01

... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES... LNG facilities used in the transportation of gas by pipeline that is subject to the pipeline safety...

UMTRA project list of reportable occurrences

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1994-04-01

This UMTRA Project List of Reportable occurrences is provided to facilitate efficient categorization of reportable occurrences. These guidelines have been established in compliance with DOE minimum reporting requirements under DOE Order 5000.3B. Occurrences are arranged into nine groups relating to US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project operations for active sites. These nine groupings are provided for reference to determined whether an occurrence meets reporting requirement criteria in accordance with the minimum reporting requirements. Event groups and significance categories that cannot or will not occur, and that do not apply to UMTRA Project operations, aremore » omitted. Occurrence categorization shall be as follows: Group 1. Facility Condition; Group 2. Environmental; Group 3. Personnel Safety; Group 4. Personnel Radiation Protection; Group 5. Safeguards and Security; Group 6. Transportation; Group 7. Value Basis Reporting; Group 8. Facility Status; and Group 9. Cross-Category Items.« less

25 CFR 559.7 - May the Chairman request Indian lands or environmental and public health and safety documentation...

Code of Federal Regulations, 2012 CFR

2012-04-01

... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...

25 CFR 559.7 - May the Chairman request Indian lands or environmental and public health and safety documentation...

Code of Federal Regulations, 2010 CFR

2010-04-01

... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...

25 CFR 559.7 - May the Chairman request Indian lands or environmental and public health and safety documentation...

Code of Federal Regulations, 2011 CFR

2011-04-01

... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...

3S (Safeguards, Security, Safety) based pyroprocessing facility safety evaluation plan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ku, J.H.; Choung, W.M.; You, G.S.

The big advantage of pyroprocessing for the management of spent fuels against the conventional reprocessing technologies lies in its proliferation resistance since the pure plutonium cannot be separated from the spent fuel. The extracted materials can be directly used as metal fuel in a fast reactor, and pyroprocessing reduces drastically the volume and heat load of the spent fuel. KAERI has implemented the SBD (Safeguards-By-Design) concept in nuclear fuel cycle facilities. The goal of SBD is to integrate international safeguards into the entire facility design process since the very beginning of the design phase. This paper presents a safety evaluationmore » plan using a conceptual design of a reference pyroprocessing facility, in which 3S (Safeguards, Security, Safety)-By-Design (3SBD) concept is integrated from early conceptual design phase. The purpose of this paper is to establish an advanced pyroprocessing hot cell facility design concept based on 3SBD for the successful realization of pyroprocessing technology with enhanced safety and proliferation resistance.« less

75 FR 33899 - Advisory Committee on Structural Safety of Department of Veterans Affairs Facilities; Notice of...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-06-15

... Construction & Facilities Management (00CFM1A), Department of Veterans Affairs, 810 Vermont Avenue, NW... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under Public... Safety of Department of Veterans Affairs Facilities will be held on June 24-25, 2010, in Room 442, Export...

76 FR 21108 - Advisory Committee on Structural Safety of Department of Veterans Affairs Facilities; Notice of...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-14

... Quality Service, Office of Construction and Facilities Management (00CFM1A), Department of Veterans... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under Public... Safety of Department of Veterans Affairs Facilities will be held on May 12-13, 2011, in Room 442, at the...

Report to Congress on innovative safety and security technology solutions for alternative transportation facilities

DOT National Transportation Integrated Search

2017-05-01

This research collected information on the frequency and impact of safety and security incidents (threats) at selected facilities and identified priority incidents at each facility. A customized all hazards approach was used to determine the ha...

Safety Management for Water Play Facilities.

ERIC Educational Resources Information Center

Thompson, Claude

1986-01-01

Modern aquatic facilities, which include wave pools, water slides, and shallow water activity play pools, have a greater potential for injuries and lawsuits than conventional swimming pools. This article outlines comprehensive safety management for such facilities, including potential accident identification and injury control planning. (MT)

76 FR 11764 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-03

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... Defense Nuclear Facilities Safety Board's public hearing and meeting described below. Interested persons... the matters to be considered. TIME AND DATE OF MEETING: 9 a.m., March 31, 2011. PLACE: Defense Nuclear...

10 CFR 1703.105 - Requests for board records not available through the public reading room (FOIA requests).

Code of Federal Regulations, 2014 CFR

2014-01-01

... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...

10 CFR 1703.105 - Requests for board records not available through the public reading room (FOIA requests).

Code of Federal Regulations, 2013 CFR

2013-01-01

... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...

10 CFR 1703.105 - Requests for board records not available through the public reading room (FOIA requests).

Code of Federal Regulations, 2012 CFR

2012-01-01

... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...

10 CFR 1703.105 - Requests for board records not available through the public reading room (FOIA requests).

Code of Federal Regulations, 2010 CFR

2010-01-01

... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...

10 CFR 1703.105 - Requests for board records not available through the public reading room (FOIA requests).

Code of Federal Regulations, 2011 CFR

2011-01-01

... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...

Designing Effective Safety Signs, Based on a Study of Recall for Safety Signs.

ERIC Educational Resources Information Center

Berry, Dennis W.

Aside from direct supervision at a recreational facility, safety signs, if designed properly, are the most effective approach to facility safety. This study was conducted to investigate the effectiveness of various sign designs: (l) multiple concepts with text; (2) single concept with text; and (3) single concept with graphics. A discussion of…

30 CFR 57.6160 - Main facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Explosives Storage... facilities will not prevent escape from the mine, or cause detonation of the contents of another storage...

Limited-scope probabilistic safety analysis for the Los Alamos Meson Physics Facility (LAMPF)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sharirli, M.; Rand, J.L.; Sasser, M.K.

1992-01-01

The reliability of instrumentation and safety systems is a major issue in the operation of accelerator facilities. A probabilistic safety analysis was performed or the key safety and instrumentation systems at the Los Alamos Meson Physics Facility (LAMPF). in Phase I of this unique study, the Personnel Safety System (PSS) and the Current Limiters (XLs) were analyzed through the use of the fault tree analyses, failure modes and effects analysis, and criticality analysis. Phase II of the program was done to update and reevaluate the safety systems after the Phase I recommendations were implemented. This paper provides a brief reviewmore » of the studies involved in Phases I and II of the program.« less

Limited-scope probabilistic safety analysis for the Los Alamos Meson Physics Facility (LAMPF)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sharirli, M.; Rand, J.L.; Sasser, M.K.

1992-12-01

The reliability of instrumentation and safety systems is a major issue in the operation of accelerator facilities. A probabilistic safety analysis was performed or the key safety and instrumentation systems at the Los Alamos Meson Physics Facility (LAMPF). in Phase I of this unique study, the Personnel Safety System (PSS) and the Current Limiters (XLs) were analyzed through the use of the fault tree analyses, failure modes and effects analysis, and criticality analysis. Phase II of the program was done to update and reevaluate the safety systems after the Phase I recommendations were implemented. This paper provides a brief reviewmore » of the studies involved in Phases I and II of the program.« less

Criticality safety strategy for the Fuel Cycle Facility electrorefiner at Argonne National Laboratory, West

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mariani, R.D.; Benedict, R.W.; Lell, R.M.

1993-09-01

The Integral Fast Reactor being developed by Argonne National Laboratory (ANL) combines the advantages of metal-fueled, liquid-metal-cooled reactors and a closed fuel cycle. Presently, the Fuel Cycle Facility (FCF) at ANL-West in Idaho Falls, Idaho is being modified to recycle spent metallic fuel from Experimental Breeder Reactor II as part of a demonstration project sponsored by the Department of Energy. A key component of the FCF is the electrorefiner (ER) in which the actinides are separated from the fission products. In the electrorefining process, the metal fuel is anodically dissolved into a high-temperature molten salt and refined uranium or uranium/plutoniummore » products are deposited at cathodes. In this report, the criticality safety strategy for the FCF ER is summarized. FCF ER operations and processes formed the basis for evaluating criticality safety and control during actinide metal fuel refining. In order to show criticality safety for the FCF ER, the reference operating conditions for the ER had to be defined. Normal operating envelopes (NOES) were then defined to bracket the important operating conditions. To keep the operating conditions within their NOES, process controls were identified that can be used to regulate the actinide forms and content within the ER. A series of operational checks were developed for each operation that wig verify the extent or success of an operation. The criticality analysis considered the ER operating conditions at their NOE values as the point of departure for credible and incredible failure modes. As a result of the analysis, FCF ER operations were found to be safe with respect to criticality.« less

Effect of a Manager Training and Certification Program on Food Safety and Hygiene in Food Service Operations

PubMed Central

Kassa, Hailu; Silverman, Gary S.; Baroudi, Karim

2010-01-01

Food safety is an important public health issue in the U.S. Eating at restaurants and other food service facilities increasingly has been associated with food borne disease outbreaks. Food safety training and certification of food mangers has been used as a method for reducing food safety violations at food service facilities. However, the literature is inconclusive about the effectiveness of such training programs for improving food safety and protecting consumer health. The purpose of this study was to examine the effect of food manger training on reducing food safety violations. We examined food inspection reports from the Toledo/Lucas County Health Department (Ohio) from March 2005 through February 2006 and compared food hygiene violations between food service facilities with certified and without certified food managers. We also examined the impact on food safety of a food service facility being part of a larger group of facilities. Restaurants with trained and certified food managers had significantly fewer critical food safety violations but more non-critical violations than restaurants without certified personnel. Institutional food service facilities had significantly fewer violations than restaurants, and the number of violations did not differ as a function of certification. Similarly, restaurants with many outlets had significantly fewer violations than restaurants with fewer outlets, and training was not associated with lower numbers of violations from restaurants with many outlets. The value of having certified personnel was only observed in independent restaurants and those with few branches. This information may be useful in indicating where food safety problems are most likely to occur. Furthermore, we recommend that those characteristics of institutional and chain restaurants that result in fewer violations should be identified in future research, and efforts made to apply this knowledge at the level of individual restaurants. PMID:20523880

Effect of a manager training and certification program on food safety and hygiene in food service operations.

PubMed

Kassa, Hailu; Silverman, Gary S; Baroudi, Karim

2010-05-06

Food safety is an important public health issue in the U.S. Eating at restaurants and other food service facilities increasingly has been associated with food borne disease outbreaks. Food safety training and certification of food mangers has been used as a method for reducing food safety violations at food service facilities. However, the literature is inconclusive about the effectiveness of such training programs for improving food safety and protecting consumer health. The purpose of this study was to examine the effect of food manger training on reducing food safety violations. We examined food inspection reports from the Toledo/Lucas County Health Department (Ohio) from March 2005 through February 2006 and compared food hygiene violations between food service facilities with certified and without certified food managers. We also examined the impact on food safety of a food service facility being part of a larger group of facilities.Restaurants with trained and certified food managers had significantly fewer critical food safety violations but more non-critical violations than restaurants without certified personnel. Institutional food service facilities had significantly fewer violations than restaurants, and the number of violations did not differ as a function of certification. Similarly, restaurants with many outlets had significantly fewer violations than restaurants with fewer outlets, and training was not associated with lower numbers of violations from restaurants with many outlets. The value of having certified personnel was only observed in independent restaurants and those with few branches. This information may be useful in indicating where food safety problems are most likely to occur. Furthermore, we recommend that those characteristics of institutional and chain restaurants that result in fewer violations should be identified in future research, and efforts made to apply this knowledge at the level of individual restaurants.

30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...

30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...

30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...

30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...

30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...

75 FR 21605 - Sunshine Act Notice

Federal Register 2010, 2011, 2012, 2013, 2014

2010-04-26

... depth federal safety management and oversight policies being developed by DOE and NNSA for defense... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... in the Sunshine Act'' (5 U.S.C. 552b), notice is hereby given of the Defense Nuclear Facilities...

The Future of U.S. Nuclear Forces: Boom or Bust

DTIC Science & Technology

2007-03-30

materials, and nuclear waste.45 The Defense Nuclear Facilities Safety Board (DNFSB) was established by Congress in 1988 as an independent federal...adequate protection of public health and safety" at DOE’s defense nuclear facilities .46 This 100- person agency looks at four areas of the nuclear weapons...47 A.J. Eggenberger, Sixteenth Annual Report to Congress (Washington DC: Defense Nuclear Facilities Safety Board, February 2006), 13; available

45 CFR 86.33 - Comparable facilities.

Code of Federal Regulations, 2012 CFR

2012-10-01

... SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 86.33 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

43 CFR 41.410 - Comparable facilities.

Code of Federal Regulations, 2014 CFR

2014-10-01

... SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 41.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

45 CFR 86.33 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-10-01

... SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 86.33 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

77 FR 40891 - Towing Safety Advisory Committee

Federal Register 2010, 2011, 2012, 2013, 2014

2012-07-11

... ``Recommendations for Safety Standards of Portable Facility Vapor Control Systems.'' (4) Period for public comment... teleconference to review and discuss a new Task Statement titled ``Recommendations for Safety Standards of Portable Facility Vapor Control Systems'' and to discuss the progress of open Task Statements. This meeting...

78 FR 41991 - Pipeline Safety: Potential for Damage to Pipeline Facilities Caused by Flooding

Federal Register 2010, 2011, 2012, 2013, 2014

2013-07-12

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice; Issuance of Advisory... Gas and Hazardous Liquid Pipeline Systems. Subject: Potential for Damage to Pipeline Facilities Caused...

77 FR 63437 - Advisory Committee on Structural Safety of Department of Veterans Affairs Facilities, Notice of...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-16

..., Office of Construction & Facilities Management (003C2B), Department of Veterans Affairs, 425 I Street NW... Affairs Facilities, Notice of Meeting The Department of Veterans Affairs (VA) gives notice under the... Safety of Department of Veterans Affairs Facilities will be held on October 29-30, 2012, in Room 6W405...

78 FR 21198 - Advisory Committee on Structural Safety of Department of Veterans Affairs Facilities; Notice of...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-09

... Construction and Facilities Management (003C2B), Department of Veterans Affairs, 810 Vermont Avenue NW... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under the... Safety of Department of Veterans Affairs Facilities will be held on April 25-26, 2013, in Room 6W405, 425...

PRELIMINARY NUCLEAR CRITICALITY NUCLEAR SAFETY EVLAUATION FOR THE CONTAINER SURVEILLANCE AND STORAGE CAPABILITY PROJECT

DOE Office of Scientific and Technical Information (OSTI.GOV)

Low, M; Matthew02 Miller, M; Thomas Reilly, T

2007-04-30

Washington Safety Management Solutions (WSMS) provides criticality safety services to Washington Savannah River Company (WSRC) at the Savannah River Site. One activity at SRS is the Container Surveillance and Storage Capability (CSSC) Project, which will perform surveillances on 3013 containers (hereafter referred to as 3013s) to verify that they meet the Department of Energy (DOE) Standard (STD) 3013 for plutonium storage. The project will handle quantities of material that are greater than ANS/ANSI-8.1 single parameter mass limits, and thus required a Nuclear Criticality Safety Evaluation (NCSE). The WSMS methodology for conducting an NCSE is outlined in the WSMS methods manual.more » The WSMS methods manual currently follows the requirements of DOE-O-420.1B, DOE-STD-3007-2007, and the Washington Savannah River Company (WSRC) SCD-3 manual. DOE-STD-3007-2007 describes how a NCSE should be performed, while DOE-O-420.1B outlines the requirements for a Criticality Safety Program (CSP). The WSRC SCD-3 manual implements DOE requirements and ANS standards. NCSEs do not address the Nuclear Criticality Safety (NCS) of non-reactor nuclear facilities that may be affected by overt or covert activities of sabotage, espionage, terrorism or other security malevolence. Events which are beyond the Design Basis Accidents (DBAs) are outside the scope of a double contingency analysis.« less

30 CFR 57.20008 - Toilet facilities.

Code of Federal Regulations, 2011 CFR

2011-07-01

... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...

30 CFR 57.20008 - Toilet facilities.

Code of Federal Regulations, 2013 CFR

2013-07-01

... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...

30 CFR 57.20008 - Toilet facilities.

Code of Federal Regulations, 2014 CFR

2014-07-01

... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...

30 CFR 57.20008 - Toilet facilities.

Code of Federal Regulations, 2012 CFR

2012-07-01

... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...

30 CFR 77.1608 - Dumping facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Dumping facilities. 77.1608 Section 77.1608 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH... Haulage § 77.1608 Dumping facilities. (a) Dumping locations and haulage roads shall be kept reasonably...

Leveraging Safety Programs to Improve and Support Security Programs

DOE Office of Scientific and Technical Information (OSTI.GOV)

Leach, Janice; Snell, Mark K.; Pratt, R.

2015-10-01

There has been a long history of considering Safety, Security, and Safeguards (3S) as three functions of nuclear security design and operations that need to be properly and collectively integrated with operations. This paper specifically considers how safety programmes can be extended directly to benefit security as part of an integrated facility management programme. The discussion will draw on experiences implementing such a programme at Sandia National Laboratories’ Annular Research Reactor Facility. While the paper focuses on nuclear facilities, similar ideas could be used to support security programmes at other types of high-consequence facilities and transportation activities.

Safety Analysis and Protection Measures of the Control System of the Pulsed High Magnetic Field Facility in WHMFC

NASA Astrophysics Data System (ADS)

Shi, J. T.; Han, X. T.; Xie, J. F.; Yao, L.; Huang, L. T.; Li, L.

2013-03-01

A Pulsed High Magnetic Field Facility (PHMFF) has been established in Wuhan National High Magnetic Field Center (WHMFC) and various protection measures are applied in its control system. In order to improve the reliability and robustness of the control system, the safety analysis of the PHMFF is carried out based on Fault Tree Analysis (FTA) technique. The function and realization of 5 protection systems, which include sequence experiment operation system, safety assistant system, emergency stop system, fault detecting and processing system and accident isolating protection system, are given. The tests and operation indicate that these measures improve the safety of the facility and ensure the safety of people.

Safety in Elevators and Grain Handling Facilities. Module SH-27. Safety and Health.

ERIC Educational Resources Information Center

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on safety in elevators and grain handling facilities is one of 50 modules concerned with job safety and health. Following the introduction, 15 objectives (each keyed to a page in the text) the student is expected to accomplish are listed (e.g., Explain how explosion suppression works). Then each objective is taught in detail,…

Guidance on health effects of toxic chemicals. Safety Analysis Report Update Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

Foust, C.B.; Griffin, G.D.; Munro, N.B.

1994-02-01

Martin Marietta Energy Systems, Inc. (MMES), and Martin Marietta Utility Services, Inc. (MMUS), are engaged in phased programs to update the safety documentation for the existing US Department of Energy (DOE)-owned facilities. The safety analysis of potential toxic hazards requires a methodology for evaluating human health effects of predicted toxic exposures. This report provides a consistent set of health effects and documents toxicity estimates corresponding to these health effects for some of the more important chemicals found within MMES and MMUS. The estimates are based on published toxicity information and apply to acute exposures for an ``average`` individual. The healthmore » effects (toxicological endpoints) used in this report are (1) the detection threshold; (2) the no-observed adverse effect level; (3) the onset of irritation/reversible effects; (4) the onset of irreversible effects; and (5) a lethal exposure, defined to be the 50% lethal level. An irreversible effect is defined as a significant effect on a person`s quality of life, e.g., serious injury. Predicted consequences are evaluated on the basis of concentration and exposure time.« less

A psychometric evaluation of the Chinese version of the nursing home survey on patient safety culture.

PubMed

Lin, Shu-Yuan; Tseng, Wei Ting; Hsu, Miao-Ju; Chiang, Hui-Ying; Tseng, Hui-Chen

2017-12-01

To test the psychometric properties of the Chinese version of the Nursing Home Survey on Patient Safety Culture scale among staff in long-term care facilities. The Nursing Home Survey on Patient Safety Culture scale is a standard tool for safety culture assessment in nursing homes. Extending its application to different types of long-term care facilities and varied ethnic populations is worth pursuing. A national random survey. A total of 306 managers and staff completed the Chinese version of the Nursing Home Survey on Patient Safety Culture scale among 30 long-term care facilities in Taiwan. Content validity and construct validity were tested by content validity index (CVI) and principal axis factor analysis (PAF) with Promax rotation. Concurrent validity was tested through correlations between the scale and two overall rating items. Reliability was computed by intraclass correlation coefficient and Cronbach's α coefficients. Statistical analyses such as descriptive, Pearson's and Spearman's rho correlations and PAF were completed. Scale-level and item-level CVIs (0.91-0.98) of the Chinese version of the Nursing Home Survey on Patient Safety Culture scale were satisfactory. Four-factor construct and merged item composition differed from the Nursing Home Survey on Patient Safety Culture scale, and it accounted for 53% of variance. Concurrent validity was evident by existing positive correlations between the scale and two overall ratings of resident safety. Cronbach's α coefficients of the subscales and the Chinese version of the Nursing Home Survey on Patient Safety Culture scale ranged from .76-.94. The Chinese version of the Nursing Home Survey on Patient Safety Culture scale identified essential dimensions to reflect the important features of a patient safety culture in long-term care facilities. The researchers introduced the Chinese version of the Nursing Home Survey on Patient Safety Culture for safety culture assessment in long-term care facilities, but further testing of the reliability of the scale in a large Chinese sample and in different long-term care facilities was recommended. The Chinese version of the Nursing Home Survey on Patient Safety Culture scale was developed to increase the users' intention towards safety culture assessment. It can identify areas for improvement, understand safety culture changes over time and evaluate the effectiveness of interventions. © 2017 John Wiley & Sons Ltd.

A case study of potential human health impacts from petroleum coke transfer facilities.

PubMed

Dourson, Michael L; Chinkin, Lyle R; MacIntosh, David L; Finn, Jennifer A; Brown, Kathleen W; Reid, Stephen B; Martinez, Jeanelle M

2016-11-01

Petroleum coke or "petcoke" is a solid material created during petroleum refinement and is distributed via transfer facilities that may be located in densely populated areas. The health impacts from petcoke exposure to residents living in proximity to such facilities were evaluated for a petcoke transfer facilities located in Chicago, Illinois. Site-specific, margin of safety (MOS) and margin of exposure (MOE) analyses were conducted using estimated airborne and dermal exposures. The exposure assessment was based on a combined measurement and modeling program that included multiyear on-site air monitoring, air dispersion modeling, and analyses of soil and surfaces in residential areas adjacent to two petcoke transfer facilities located in industrial areas. Airborne particulate matter less than 10 microns (PM 10 ) were used as a marker for petcoke. Based on daily fence line monitoring, the average daily PM 10 concentration at the KCBX Terminals measured on-site was 32 μg/m 3 , with 89% of 24-hr average PM 10 concentrations below 50 μg/m 3 and 99% below 100 μg/m 3 . A dispersion model estimated that the emission sources at the KCBX Terminals produced peak PM 10 levels attributed to the petcoke facility at the most highly impacted residence of 11 μg/m 3 on an annual average basis and 54 μg/m 3 on 24-hr average basis. Chemical indicators of petcoke in soil and surface samples collected from residential neighborhoods adjacent to the facilities were equivalent to levels in corresponding samples collected at reference locations elsewhere in Chicago, a finding that is consistent with limited potential for off-site exposure indicated by the fence line monitoring and air dispersion modeling. The MOE based upon dispersion model estimates ranged from 800 to 900 for potential inhalation, the primary route of concern for particulate matter. This indicates a low likelihood of adverse health effects in the surrounding community. Implications: Handling of petroleum coke at bulk material transfer facilities has been identified as a concern for the public health of surrounding populations. The current assessment, based on measurements and modeling of two facilities located in a densely populated urban area, indicates that petcoke transport and accumulation in off-site locations is minimal. In addition, estimated human exposures, if any, are well below levels that could be anticipated to produce adverse health effects in the general population.

40 CFR 5.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 5.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

40 CFR 5.410 - Comparable facilities.

Code of Federal Regulations, 2013 CFR

2013-07-01

... OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 5.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

42 CFR 412.400 - Basis and scope of subpart.

Code of Federal Regulations, 2010 CFR

2010-10-01

... Inpatient Hospital Services of Inpatient Psychiatric Facilities § 412.400 Basis and scope of subpart. (a... psychiatric facilities. (b) Scope. This subpart sets forth the framework for the prospective payment system for the inpatient hospital services of inpatient psychiatric facilities, including the methodology...

49 CFR 192.171 - Compressor stations: Additional safety equipment.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 49 Transportation 3 2011-10-01 2011-10-01 false Compressor stations: Additional safety equipment... Pipeline Components § 192.171 Compressor stations: Additional safety equipment. (a) Each compressor station must have adequate fire protection facilities. If fire pumps are a part of these facilities, their...

Neutron transmutation doping of silicon in the SAFARI-1 research reactor

DOE Office of Scientific and Technical Information (OSTI.GOV)

Louw, P.A.; Robertson, D.G.; Strydom, W.J.

1994-12-31

The SAFARI-1 research reactor has operated with an exemplary safety record since commissioning in 1965. As part of a commercialisation effort a silicon irradiation facility (SILIRAD) has been installed in the poolside region of SAFARI-1 for Neutron Transmutation Doping (NTD) of silicon. Commissioning of the facility took place in the last quarter of 1992 with a series of trial irradiations which were performed in close collaboration with Wacker Chemitronic of Germany. A methodology for the determination of irradiation times necessary to achieve the target resistivities was verified on the basis of the results from the trial irradiations. All production activitiesmore » are controlled by quality assurance procedures. To date some hundred and twelve silicon ingots (103 mm diameter) have been successfully irradiated on a commercial contract basis. The observed axial and radial variations in the resistivity profile of the ingots are very small compared to the profiles associated with conventionally doped silicon and small tolerances on target resistivities are attained. In this paper an overview of the design and characterisation of SILIRAD is given and the methods applied that ensure a quality product are described. Results obtained from trial and production irradiations are presented and the envisaged future modifications to SILIRAD discussed.« less

Hanford immobilized low-activity tank waste performance assessment

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mann, F.M.

1998-03-26

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plansmore » to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis to set requirements on the waste form and the facility design that will protect the long-term public health and safety and protect the environment.« less

Financial Management: Extending the Financial Statements Audit Requirement of the CFO Act to Additional Federal Agencies

DTIC Science & Technology

2002-05-14

Defense Nuclear Facilities Safety Board has balance-sheet-only audits every 3 to 5 years, most recently for fiscal year 1997. It did not prepare fiscal...associated with the agency’s operations were the most important factors to Have had financial statements audits Defense Nuclear Facilities Safety...audits, the International Trade Commission and the Defense Nuclear Facilities Safety Board, did not have financial statements audits for fiscal year

75 FR 45678 - Notice of Availability of Interim Staff Guidance Document for Fuel Cycle Facilities

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-03

... Document for Fuel Cycle Facilities AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability..., Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S... Commission (NRC) prepares and issues Interim Staff Guidance (ISG) documents for fuel cycle facilities. These...

30 CFR 71.404 - Application for waiver of surface facilities requirements.

Code of Federal Regulations, 2010 CFR

2010-07-01

... requirements. 71.404 Section 71.404 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS... Facilities at Surface Coal Mines § 71.404 Application for waiver of surface facilities requirements. (a...

HSE's safety assessment principles for criticality safety.

PubMed

Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R

2008-06-01

The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf).

Occupational Violence and Aggression Experienced by Nursing and Caring Professionals.

PubMed

Shea, Tracey; Sheehan, Cathy; Donohue, Ross; Cooper, Brian; De Cieri, Helen

2017-03-01

To examine the extent and source of occupational violence and aggression (OVA) experienced by nursing and caring professionals. This study also examines the relative contributions of demographic characteristics and workplace and individual safety factors in predicting OVA. A cross-sectional study design with data collected using an online survey of employees in the nursing and caring professions in Victoria, Australia. Survey data collected from 4,891 members of the Australian Nursing and Midwifery Federation (Victorian branch) were analyzed using logistic regression. Sixty-seven percent of respondents reported experiencing OVA in the preceding 12 months, with nearly 20% experiencing OVA on a weekly or daily basis. The dominant sources of OVA were patients (79%) or relatives of patients (48%). Logistic regression analysis revealed that respondents working in public hospitals and aged care facilities were more likely to experience OVA, compared to those working in other workplaces. While higher levels of safety compliance reduced the likelihood of experiencing OVA, role overload and workplace safety factors such as prioritization of employee safety and leading indicators of occupational health and safety were stronger predictors. The likelihood of healthcare workers experiencing OVA varies across demographic and workplace characteristics. While some demographic characteristics and individual safety factors were significant predictors, our results suggest that a greater reduction in OVA could be achieved by improving workplace safety. The study's outcomes identify workforce segments that are most vulnerable to OVA. The study also highlights workplace safety factors such as the prioritization of employee safety that might assist in the reduction of OVA. © 2016 Sigma Theta Tau International.

Assessment of radiological protection systems among diagnostic radiology facilities in North East India.

PubMed

Singh, Thokchom Dewan; Jayaraman, T; Arunkumar Sharma, B

2017-03-01

This study aims to assess the adequacy level of radiological protection systems available in the diagnostic radiology facilities located in three capital cities of North East (NE) India. It further attempts to understand, using a multi-disciplinary approach, how the safety codes/standards in diagnostic radiology framed by the Atomic Energy Regulatory Board (AERB) and the International Atomic Energy Agency (IAEA) to achieve adequate radiological protection in facilities, have been perceived, conceptualized, and applied accordingly in these facilities. About 30 diagnostic radiology facilities were randomly selected from three capitals of states in NE India; namely Imphal (Manipur), Shillong (Meghalaya) and Guwahati (Assam). A semi-structured questionnaire developed based on a multi-disciplinary approach was used for this study. It was observed that radiological practices undertaken in these facilities were not exactly in line with safety codes/standards in diagnostic radiology of the AERB and the IAEA. About 50% of the facilities had registered/licensed x-ray equipment with the AERB. More than 80% of the workers did not use radiation protective devices, although these devices were available in the facilities. About 85% of facilities had no institutional risk management system. About 70% of the facilities did not carry out periodic quality assurance testing of their x-ray equipment or surveys of radiation leakage around the x-ray room, and did not display radiation safety indicators in the x-ray rooms. Workers in these facilities exhibited low risk perception about the risks associated with these practices. The majority of diagnostic radiology facilities in NE India did not comply with the radiological safety codes/standards framed by the AERB and IAEA. The study found inadequate levels of radiological protection systems in the majority of facilities. This study suggests a need to establish firm measures that comply with the radiological safety codes/standards of the AERB and IAEA to protect patients, workers and the public of this region.

14 CFR 1253.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 14 Aeronautics and Space 5 2011-01-01 2010-01-01 true Comparable facilities. 1253.410 Section 1253.410 Aeronautics and Space NATIONAL AERONAUTICS AND SPACE ADMINISTRATION NONDISCRIMINATION ON THE BASIS... recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

49 CFR 192.171 - Compressor stations: Additional safety equipment.

Code of Federal Regulations, 2010 CFR

2010-10-01

... SAFETY TRANSPORTATION OF NATURAL AND OTHER GAS BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Design of... must have adequate fire protection facilities. If fire pumps are a part of these facilities, their... event of inadequate cooling or lubrication of the unit. (d) Each compressor station gas engine that...

30 CFR 75.1712 - Bath houses and toilet facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Bath houses and toilet facilities. 75.1712 Section 75.1712 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712 Bath houses...

76 FR 67765 - Notice of Availability of Uranium Enrichment Fuel Cycle Facility's Inspection Reports Regarding...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-11-02

... Uranium Enrichment Fuel Cycle Facility's Inspection Reports Regarding Louisiana Energy Services, National..., Uranium Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety... Commission. Brian W. Smith, Chief, Uranium Enrichment Branch, Division of Fuel Cycle Safety and Safeguards...

30 CFR 75.1712 - Bath houses and toilet facilities.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Bath houses and toilet facilities. 75.1712 Section 75.1712 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712 Bath houses...

Canadian regulatory requirements for recombinant fish vaccines.

PubMed

Sethi, M S; Gifford, G A; Samagh, B S

1997-01-01

In Canada, veterinary biological products derived by using conventional and new techniques of biotechnology are licensed and regulated under the Health of Animals Act and Regulations. Biological products include vaccines, bacterins, bacterin-toxoids and diagnostic kits which are used for the prevention, treatment or diagnosis of infectious diseases in all species of animals, including fish. Veterinary biologicals are licensed on the basis of fulfillment of four criteria: purity, potency, safety and efficacy. A risk-based approach is used to evaluate the safety of the product in target species, as well as non-target species, humans and the environment. On the basis of biological characteristics, biotechnology derived veterinary biologicals have been divided into two broad categories, high and low risk products. The paper describes the regulatory framework for the licensing of veterinary biologicals in Canada, with emphasis on the regulatory considerations for recombinant fish vaccines. Stages of movement of the product from research in a contained laboratory facility to a fully licensed product for free sale are discussed. The requirements for field testing and environmental assessment involved in these stages are highlighted. Manufacturers and researchers who intend to commercialize experimental vaccines are encouraged to consult with the Veterinary Biologics and Biotechnology Section early in the product development process so that the research data and quality assurance documentation are consistent with regulatory requirements.

33 CFR 6.14-1 - Safety measures.

Code of Federal Regulations, 2011 CFR

2011-07-01

..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...

33 CFR 6.14-1 - Safety measures.

Code of Federal Regulations, 2014 CFR

2014-07-01

..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...

33 CFR 6.14-1 - Safety measures.

Code of Federal Regulations, 2013 CFR

2013-07-01

..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...

33 CFR 6.14-1 - Safety measures.

Code of Federal Regulations, 2012 CFR

2012-07-01

..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...

NSR&D Program Fiscal Year 2015 Funded Research Stochastic Modeling of Radioactive Material Releases Final Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Andrus, Jason P.; Pope, Chad; Toston, Mary

2016-12-01

Nonreactor nuclear facilities operating under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculatesmore » the radiation dose distribution associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. Users can also specify custom distributions through a user defined distribution option. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA, developed using the MATLAB coding framework, has a graphical user interface and can be installed on both Windows and Mac computers. SODA is a standalone software application and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC; rather it is viewed as an easy to use supplemental tool to help improve risk understanding and support better informed decisions. The SODA development project was funded through a grant from the DOE Nuclear Safety Research and Development Program.« less

NSR&D Program Fiscal Year 2015 Funded Research Stochastic Modeling of Radioactive Material Releases Final Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Andrus, Jason P.; Pope, Chad; Toston, Mary

Nonreactor nuclear facilities operating under the approval authority of the U.S. Department of Energy use unmitigated hazard evaluations to determine if potential radiological doses associated with design basis events challenge or exceed dose evaluation guidelines. Unmitigated design basis events that sufficiently challenge dose evaluation guidelines or exceed the guidelines for members of the public or workers, merit selection of safety structures, systems, or components or other controls to prevent or mitigate the hazard. Idaho State University, in collaboration with Idaho National Laboratory, has developed a portable and simple to use software application called SODA (Stochastic Objective Decision-Aide) that stochastically calculatesmore » the radiation dose distribution associated with hypothetical radiological material release scenarios. Rather than producing a point estimate of the dose, SODA produces a dose distribution result to allow a deeper understanding of the dose potential. SODA allows users to select the distribution type and parameter values for all of the input variables used to perform the dose calculation. Users can also specify custom distributions through a user defined distribution option. SODA then randomly samples each distribution input variable and calculates the overall resulting dose distribution. In cases where an input variable distribution is unknown, a traditional single point value can be used. SODA, developed using the MATLAB coding framework, has a graphical user interface and can be installed on both Windows and Mac computers. SODA is a standalone software application and does not require MATLAB to function. SODA provides improved risk understanding leading to better informed decision making associated with establishing nuclear facility material-at-risk limits and safety structure, system, or component selection. It is important to note that SODA does not replace or compete with codes such as MACCS or RSAC; rather it is viewed as an easy to use supplemental tool to help improve risk understanding and support better informed decisions. The SODA development project was funded through a grant from the DOE Nuclear Safety Research and Development Program.« less

Fire Safety in Nursing Facilities: Participant's Coursebook.

ERIC Educational Resources Information Center

Walker (Bonnie) and Associates, Inc., Crofton, MD.

Fewer people die in nursing facility fires than in fires occurring in other places where older people live. Fire remains, however, a significant threat in nursing facilities. This book is centered around six "modules" that present a fire safety training program for managers and staff in nursing homes. These modules present the following…

9 CFR 390.4 - Facilities for inspection and copying.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 9 Animals and Animal Products 2 2012-01-01 2012-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...

9 CFR 390.4 - Facilities for inspection and copying.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 9 Animals and Animal Products 2 2013-01-01 2013-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...

9 CFR 390.4 - Facilities for inspection and copying.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 9 Animals and Animal Products 2 2011-01-01 2011-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...

9 CFR 390.4 - Facilities for inspection and copying.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 9 Animals and Animal Products 2 2014-01-01 2014-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...

High-Explosives Applications Facility (HEAF)

NASA Astrophysics Data System (ADS)

Morse, J. L.; Weingart, R. C.

1989-03-01

This Safety Analysis Report (SAR) reviews the safety and environmental aspects of the High Explosives Applications Facility (HEAF). Topics covered include the site selected for the HEAF, safety design criteria, operations planned within the facility, and the safety and environmental analyses performed on this project to date. Provided in the Summary section is a review of hazards and the analyses, conclusions, and operating limits developed in this SAR. Appendices provide supporting documents relating to this SAR. This SAR is required by the LLNL Health and Safety Manual and DOE Order 5481.1B(2) to document the safety analysis efforts. The SAR was assembled by the Hazards Control Department, B-Division, and HEAF project personnel. This document was reviewed by B Division, the Chemistry Department, the Hazards Control Department, the Laboratory Associate Director for Administration and Operations, and the Associate Directors ultimately responsible for HEAF operations.

DOE standard 3009 - a reasoned, practical approach to integrating criticality safety into SARs

DOE Office of Scientific and Technical Information (OSTI.GOV)

Vessard, S.G.

1995-12-31

In the past there have been efforts by the U.S. Department of Energy (DOE) to provide guidance on those elements that should be included in a facility`s safety analysis report (SAR). In particular, there are two DOE Orders (5480.23, {open_quotes}Nuclear Safety Analysis Reports,{close_quotes} and 5480.24, {open_quotes}Nuclear Criticality Safety{close_quotes}), an interpretive guidance document (NE-70, Interpretive Guidance for DOE Order 5480.24, {open_quotes}Nuclear Criticality Safety{close_quotes}), and DOE Standard DOE-STD-3009-94 {open_quotes}Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports.{close_quotes} Of these, the most practical and useful (pertaining to the application of criticality safety) is DOE-STD-3009-94. This paper is a reviewmore » of Chapters 3, 4, and 6 of this standard and how they provide very clear, helpful, and reasoned criticality safety guidance.« less

30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...

30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...

30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...

30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...

Nuclear Weapons: NNSA Needs to Establish a Cost and Schedule Baseline for Manufacturing a Critical Nuclear Weapon Component

DTIC Science & Technology

2008-05-01

building up to and beyond the 2013 time frame. However, in October 2007, the Defense Nuclear Facilities Safety Board, which monitors safety...manufacturing. They said that NNSA is still working through this process with the Defense Nuclear Facilities Safety Board. Processing of waste

GAO’s Views on DOE’s 1991 Budget for Addressing Problems at the Nuclear Weapons Complex

DTIC Science & Technology

1990-03-02

management, and efforts by DOE to make its contractors more accountable. Also, the Defense Nuclear Facilities Safety Board mandated by the Congress became...and safety matters. 6 Finally, the Defense Nuclear Facilities Safety Board was established. Although not a DOE action, its establishment, nevertheless

76 FR 37798 - DOE Response to Recommendation 2010-2 of the Defense Nuclear Facilities Safety Board, Pulse Jet...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-06-28

... Safety Board, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant AGENCY: Department of... their Recommendation 2010-2, concerning Pulse Jet Mixing at the Waste Treatment and Immobilization Plant... Nuclear Facilities Safety Board (Board) Recommendation 2010-2, Pulse Jet Mixing (PJM) at the Waste...

78 FR 6209 - Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-30

... 1625-AA00 Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers AGENCY: Coast Guard, DHS... temporary safety zone around all inbound and outbound grain-shipment vessels involved in commerce with the Columbia Grain facility on the Willamette River in Portland, OR, the United Grain Corporation facility on...

Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA

DOE Office of Scientific and Technical Information (OSTI.GOV)

Marvy, A.; Lioure, A; Heriard-Dubreuil, G.

2003-02-24

As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periodsmore » of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. The case study looks into several past and actual human enterprises conducted over significant periods o f time, one of them dating back to the end of the 18th century, and all identified out of the nuclear field. Then-prevailing societal behavior and organizational structures are screened out to show how they were or are still able to cope with similar oversight and control goals. As a result, the study group formulated a set of performance criteria relating to issues like responsibility, securing funds, legal and legislative implications, economic sustainable development, all being areas which are not traditionally considered as far as technical studies are concerned. These criteria can be most useful from the design stage onward, first in an attempt to define the facility construction and operating guiding principles, and thereafter to substantiate the safety case for long term storage and get geared to the public dialogue on that undertaking should it become a reality.« less

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neupauer, R.M.; Thurmond, S.M.

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neupauer, R.M.; Thurmond, S.M.

This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

Effects of health and safety problem recognition on small business facility investment

PubMed Central

2013-01-01

Objectives This study involved a survey of the facility investment experiences, which was designed to recognize the importance of health and safety problems, and industrial accident prevention. Ultimately, we hope that small scale industries will create effective industrial accident prevention programs and facility investments. Methods An individual survey of businesses’ present physical conditions, recognition of the importance of the health and safety problems, and facility investment experiences for preventing industrial accidents was conducted. The survey involved 1,145 business operators or management workers in small business places with fewer than 50 workers in six industrial complexes. Results Regarding the importance of occupational health and safety problems (OHS), 54.1% said it was “very important”. Received technical and financial support, and industrial accidents that occurred during the past three years were recognized as highly important for OHS. In an investigation regarding facility investment experiences for industrial accident prevention, the largest factors were business size, greater numbers of industrial accidents, greater technical and financial support received, and greater recognition of the importance of the OHS. The related variables that decided facility investment for industry accident prevention in a logistic regression analysis were the experiences of business facilities where industrial accidents occurred during the past three years, received technical and financial support, and recognition of the OHS. Those considered very important were shown to be highly significant. Conclusions Recognition of health and safety issues was higher when small businesses had experienced industrial accidents or received financial support. The investment in industrial accidents was greater when health and safety issues were recognized as important. Therefore, the goal of small business health and safety projects is to prioritize health and safety issues in terms of business management and recognition of importance. Therefore, currently various support projects are being conducted. However, there are issues regarding the limitations of the target businesses and inadequacies in maintenance and follow-up. Overall, it is necessary to provide various incentives for onsite participation that can lead to increased recognition of health and safety issues and practical investments, while perfecting maintenance and follow up measures by thoroughly revising existing operating systems. PMID:24472180

Effects of health and safety problem recognition on small business facility investment.

PubMed

Park, Jisu; Jeong, Harin; Hong, Sujin; Park, Jong-Tae; Kim, Dae-Sung; Kim, Jongseo; Kim, Hae-Joon

2013-10-23

This study involved a survey of the facility investment experiences, which was designed to recognize the importance of health and safety problems, and industrial accident prevention. Ultimately, we hope that small scale industries will create effective industrial accident prevention programs and facility investments. An individual survey of businesses' present physical conditions, recognition of the importance of the health and safety problems, and facility investment experiences for preventing industrial accidents was conducted. The survey involved 1,145 business operators or management workers in small business places with fewer than 50 workers in six industrial complexes. Regarding the importance of occupational health and safety problems (OHS), 54.1% said it was "very important". Received technical and financial support, and industrial accidents that occurred during the past three years were recognized as highly important for OHS. In an investigation regarding facility investment experiences for industrial accident prevention, the largest factors were business size, greater numbers of industrial accidents, greater technical and financial support received, and greater recognition of the importance of the OHS. The related variables that decided facility investment for industry accident prevention in a logistic regression analysis were the experiences of business facilities where industrial accidents occurred during the past three years, received technical and financial support, and recognition of the OHS. Those considered very important were shown to be highly significant. Recognition of health and safety issues was higher when small businesses had experienced industrial accidents or received financial support. The investment in industrial accidents was greater when health and safety issues were recognized as important. Therefore, the goal of small business health and safety projects is to prioritize health and safety issues in terms of business management and recognition of importance. Therefore, currently various support projects are being conducted. However, there are issues regarding the limitations of the target businesses and inadequacies in maintenance and follow-up. Overall, it is necessary to provide various incentives for onsite participation that can lead to increased recognition of health and safety issues and practical investments, while perfecting maintenance and follow up measures by thoroughly revising existing operating systems.

49 CFR 193.2005 - Applicability.

Code of Federal Regulations, 2010 CFR

2010-10-01

... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES..., design, installation, or construction of LNG facilities (including material incorporated by reference in...

Do Safety Culture Scores in Nursing Homes Depend on Job Role and Ownership? Results from a National Survey.

PubMed

Banaszak-Holl, Jane; Reichert, Heidi; Todd Greene, M; Mody, Lona; Wald, Heidi L; Crnich, Christopher; McNamara, Sara E; Meddings, Jennifer

2017-10-01

To identify facility- and individual-level predictors of nursing home safety culture. Cross-sectional survey of individuals within facilities. Nursing homes participating in the national Agency for Healthcare Research and Quality Safety Program for Long-Term Care: Healthcare-Associated Infections/Catheter-Associated Urinary Tract Infections Project. Responding nursing home staff (N = 14,177) from 170 (81%) of 210 participating facilities. Staff responses to the Nursing Home Survey on Patient Safety Culture (NHSOPS), focused on five domains (teamwork, training and skills, communication openness, supervisor expectations, organizational learning) and individual respondent characteristics (occupation, tenure, hours worked), were merged with data on facility characteristics (from the Certification and Survey Provider Enhanced Reporting): ownership, chain membership, percentage residents on Medicare, bed size. Data were analyzed using multivariate hierarchical models. Nursing assistants rated all domains worse than administrators did (P < .001), with the largest differences for communication openness (24.3 points), teamwork (17.4 points), and supervisor expectations (16.1 points). Clinical staff rated all domains worse than administrators. Nonprofit ownership was associated with worse training and skills (by 6.0 points, P =.04) and communication openness (7.3 points, P =.004), and nonprofit and chain ownership were associated with worse supervisor expectations (5.2 points, P =.001 and 3.2 points, P =.03, respectively) and organizational learning (5.6 points, P =.009 and 4.2 points, P = .03). The percentage of variation in safety culture attributable to facility characteristics was less than 22%, with ownership having the strongest effect. Perceptions of safety culture vary widely among nursing home staff, with administrators consistently perceiving better safety culture than clinical staff who spend more time with residents. Reporting safety culture scores according to occupation may be more important than facility-level scores alone to describe and assess barriers, facilitators, and changes in safety culture. © 2017, Copyright the Authors Journal compilation © 2017, The American Geriatrics Society.

Report on SARS backfit evaluation, Catalytic, Inc. Solvent Refined Coal Pilot Plant, Wilsonville, Alabama

DOE Office of Scientific and Technical Information (OSTI.GOV)

Meyer, A.F. Jr.

1980-07-02

A site visit was made in company with the DOE-OPTA-EA Safety and Health Official for the purpose of providing that official with technical assistance in evaluating the validity of an earlier DOE-OPTA recommendation exempting this facility from the Safety and Analysis and Review backfit requirements of DOE Order 5481.1. A further purpose of the visit was to assess and evaluate the occupational safety and health program at this facility, as compared with the criteria and guidelines contained in ASFE Order 5481.1. Adequate documentation regarding compliance with codes, standards, and regulations were observed at this facility. There is in existence anmore » ongoing continuous safety analysis effort for both modifications or additions to this facility. Adequate environmental safeguards and plans and procedures were observed. The SARS backfit exemption is appropriate. The occupational safety and health program is in many ways a model for the scope of work and nature of hazards involved, and is consistent with ASFE guidelines and statutory requirements.« less

Water safety in healthcare facilities. The Vieste Charter.

PubMed

Bonadonna, L; Cannarozzi de Grazia, M; Capolongo, S; Casini, B; Cristina, M L; Daniele, G; D'Alessandro, D; De Giglio, O; Di Benedetto, A; Di Vittorio, G; Ferretti, E; Frascolla, B; La Rosa, G; La Sala, L; Lopuzzo, M G; Lucentini, L; Montagna, M T; Moscato, U; Pasquarella, C; Prencipe, R; Ricci, M L; Romano Spica, V; Signorelli, C; Veschetti, E

2017-01-01

The Study Group on Hospital Hygiene of the Italian Society of Hygiene, Preventive Medicine and Public Health (GISIO-SItI) and the Local Health Authority of Foggia, Apulia, Italy, after the National Convention "Safe water in healthcare facilities" held in Vieste-Pugnochiuso on 27-28 May 2016, present the "Vieste Charter", drawn up in collaboration with experts from the National Institute of Health and the Ministry of Health. This paper considers the risk factors that may affect the water safety in healthcare facilities and reports the current regulatory frameworks governing the management of installations and the quality of the water. The Authors promote a careful analysis of the risks that characterize the health facilities, for the control of which specific actions are recommended in various areas, including water safety plans; approval of treatments; healthcare facilities responsibility, installation and maintenance of facilities; multidisciplinary approach; education and research; regional and national coordination; communication.

Light Water Reactor Sustainability Program Reactor Safety Technologies Pathway Technical Program Plan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Corradini, M. L.; Peko, D.; Farmer, M.

In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safetymore » initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary “end user” of the results from this DOE-sponsored work. The response to the Fukushima accident has been global, and there is a continuing multinational interest in collaborations to better quantify accident consequences and to incorporate lessons learned from the accident. DOE will continue to seek opportunities to facilitate collaborations that are of value to the U.S. industry, particularly where the collaboration provides access to vital data from the accident or otherwise supports or leverages other important R&D work. The purpose of the Reactor Safety Technology R&D is to improve understanding of beyond design basis events and reduce uncertainty in severe accident progression, phenomenology, and outcomes using existing analytical codes and information gleaned from severe accidents, in particular the Fukushima Daiichi events. This information will be used to aid in developing mitigating strategies and improving severe accident management guidelines for the current light water reactor fleet.« less

Light Water Reactor Sustainability Program: Reactor Safety Technologies Pathway Technical Program Plan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Corradini, M. L.

In the aftermath of the March 2011 multi-unit accident at the Fukushima Daiichi nuclear power plant (Fukushima), the nuclear community has been reassessing certain safety assumptions about nuclear reactor plant design, operations and emergency actions, particularly with respect to extreme events that might occur and that are beyond each plant’s current design basis. Because of our significant domestic investment in nuclear reactor technology (99 operating reactors in the fleet of commercial LWRs with five under construction), the United States has been a major leader internationally in these activities. The U.S. nuclear industry is voluntarily pursuing a number of additional safetymore » initiatives. The NRC continues to evaluate and, where deemed appropriate, establish new requirements for ensuring adequate protection of public health and safety in the occurrence of low probability events at nuclear plants; (e.g., mitigation strategies for beyond design basis events initiated by external events like seismic or flooding initiators). The DOE has also played a major role in the U.S. response to the Fukushima accident. Initially, DOE worked with the Japanese and the international community to help develop a more complete understanding of the Fukushima accident progression and its consequences, and to respond to various safety concerns emerging from uncertainties about the nature of and the effects from the accident. DOE R&D activities are focused on providing scientific and technical insights, data, analyses methods that ultimately support industry efforts to enhance safety. These activities are expected to further enhance the safety performance of currently operating U.S. nuclear power plants as well as better characterize the safety performance of future U.S. plants. In pursuing this area of R&D, DOE recognizes that the commercial nuclear industry is ultimately responsible for the safe operation of licensed nuclear facilities. As such, industry is considered the primary “end user” of the results from this DOE-sponsored work. The response to the Fukushima accident has been global, and there is a continuing multinational interest in collaborations to better quantify accident consequences and to incorporate lessons learned from the accident. DOE will continue to seek opportunities to facilitate collaborations that are of value to the U.S. industry, particularly where the collaboration provides access to vital data from the accident or otherwise supports or leverages other important R&D work. The purpose of the Reactor Safety Technology R&D is to improve understanding of beyond design basis events and reduce uncertainty in severe accident progression, phenomenology, and outcomes using existing analytical codes and information gleaned from severe accidents, in particular the Fukushima Daiichi events. This information will be used to aid in developing mitigating strategies and improving severe accident management guidelines for the current light water reactor fleet.« less

75 FR 36773 - Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil Spill

Federal Register 2010, 2011, 2012, 2013, 2014

2010-06-28

.... PHMSA-2010-0175] Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil... 194. In light of the Deepwater Horizon oil spill in the Gulf of Mexico, which has resulted in the... Systems. Subject: Updating Facility Response Plans in Light of the Deepwater Horizon Oil Spill. Advisory...

Industrial Sanitation and Personal Facilities. Module SH-13. Safety and Health.

ERIC Educational Resources Information Center

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on industrial sanitation and personal facilities is one of 50 modules concerned with job safety and health. This module deals wth many facets of industrial sanitation and the facilities industries should provide so that proper health procedures may be followed. Following the introduction, 14 objectives (each keyed to a page in…

76 FR 37799 - DOE Final Decision in Response to Recommendation 2010-1 of the Defense Nuclear Facilities Safety...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-06-28

... the public, workers, and the environment. For example, the Board clarified that use of the term.... Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as a safe harbor methodology..., our workers, and the environment at all of our facilities. We share your conviction that a clear set...

41 CFR 102-74.140 - On what basis does the Administrator select construction and alteration projects?

Code of Federal Regulations, 2010 CFR

2010-07-01

... Property Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 74-FACILITY MANAGEMENT Facility Management Asset Services § 102-74.140 On what basis... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false On what basis does the...

An approach to radiation safety department benchmarking in academic and medical facilities.

PubMed

Harvey, Richard P

2015-02-01

Based on anecdotal evidence and networking with colleagues at other facilities, it has become evident that some radiation safety departments are not adequately staffed and radiation safety professionals need to increase their staffing levels. Discussions with management regarding radiation safety department staffing often lead to similar conclusions. Management acknowledges the Radiation Safety Officer (RSO) or Director of Radiation Safety's concern but asks the RSO to provide benchmarking and justification for additional full-time equivalents (FTEs). The RSO must determine a method to benchmark and justify additional staffing needs while struggling to maintain a safe and compliant radiation safety program. Benchmarking and justification are extremely important tools that are commonly used to demonstrate the need for increased staffing in other disciplines and are tools that can be used by radiation safety professionals. Parameters that most RSOs would expect to be positive predictors of radiation safety staff size generally are and can be emphasized in benchmarking and justification report summaries. Facilities with large radiation safety departments tend to have large numbers of authorized users, be broad-scope programs, be subject to increased controls regulations, have large clinical operations, have significant numbers of academic radiation-producing machines, and have laser safety responsibilities.

[Considering the current state of fire safety in Taiwan's care environment from the perspective of the nation's worst recent hospital fire].

PubMed

Tseng, Wei-Wen; Shih, Chung-Liang; Chien, Shen-Wen

2013-04-01

Taiwan's worst hospital fire in history on October 23rd, 2012 at Sinying Hospital's Bei-Men Branch resulted in 13 elderly patient deaths and over 70 injuries. The heavy casualties were due in part to the serious condition of patients. Some patients on life-support machines were unable to move or be moved. This disaster highlights the issue of fire safety in small-scale hospitals that have transformed existing hospital space into special care environments for elderly patients. Compared with medical centers and general hospitals, these small-scale health facilities are ill equipped to deal properly with fire safety management and emergency response issues due to inadequate fire protection facilities, fire safety equipment, and human resources. Small-scale facilities that offer health care and medical services to mostly immobile patients face fire risks that differ significantly from general health care facilities. This paper focuses on fire risks in small-scale facilities and suggests a strategy for fire prevention and emergency response procedures, including countermeasures for fire risk assessment, management, and emergency response, in order to improve fire safety at these institutions in Taiwan.

76 FR 13397 - DOE Response to Recommendation 2010-2 of the Defense Nuclear Facilities Safety Board, Pulse Jet...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-11

... Safety Board, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant AGENCY: Department of..., concerning Pulse Jet Mixing at the Waste Treatment and Immobilization Plant was published in the Federal... Defense Nuclear Facilities Safety Board (Board) Recommendation 2010-2, Pulse Jet Mixing at the Waste...

DOE Office of Scientific and Technical Information (OSTI.GOV)

MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood ofmore » these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Stickney, R.G.

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

340 Facility secondary containment and leak detection

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bendixsen, R.B.

1995-01-31

This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4.

Evaluation of Canisterized Foams and Evaluation of Radiation Hardened Foams for D&D Activities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nicholson, J. C.

The introduction of polyurethane foams has previously been examined elsewhere within the DOE complex with regards to decontamination and decommissioning (D&D) activities, though its use has been prohibited as a result of excessive heat generation and flammability concerns per the safety basis. Should these foams be found compatible with respect to the facility safety basis requirements, D&D work involving large void containing structures such as gloveboxes could be eased through the fixation of residual contamination after decontamination efforts have concluded. To this end, SRNL embarked on a characterization of commercial epoxy foams to identify the characteristics that would be mostmore » important to safety basis requirements. Through SRNL’s efforts, the performance of commercial two-part epoxy foams was evaluated for their foaming characteristics, temperature profiles, loading capability with high-Z (high density) additives, and applicability for shielding gamma emission from isotopes including; Am-241, Cs-137, and Co-60. It was found that these foams are capable of encapsulation of a desired volume, though the ideal and experimental expansion coefficients were found to differ. While heat is generated during the reaction, no samples generated heat above 70 °C. Of the down–selected materials, heating was on the order of 40 °C for the flexible foam and 60 °C for the rigid foam. Both were found to return to room temperature after 20 minutes regardless of the volume of foam cast. It was also found that the direct introduction of high-Z additives were capable of attenuating 98% of Am-241 gamma signal, 16% of Cs-137 signal, and 9.5% of Co-60 signal at 1:1 loading capacities of total liquid constituent weight to additive weight. These efforts are currently being reviewed for the ASTM January 2017 subcommittee discussions to address the lack of test methods and standards regarding these materials with respect to D&D environments.« less

Health Care Worker Fatigue.

PubMed

Gardner, Lea Anne; Dubeck, Deborah

2016-08-01

The Pennsylvania Patient Safety Reporting System is a confidential, statewide Internet reporting system to which all Pennsylvania hospitals, outpatient-surgery facilities, birthing centers, and abortion facilities must file information on incidents and serious events.Safety Monitor is a column from Pennsylvania's Patient Safety Authority, the authority that informs nurses on issues that can affect patient safety and presents strategies they can easily integrate into practice. For more information on the authority, visit www.patientsafetyauthority.org. For the original article discussed in this column or for other articles on patient safety, click on "Patient Safety Advisories" and then "Advisory Library" in the left-hand navigation menu.

Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program

DTIC Science & Technology

2006-12-13

Defense Nuclear Facilities Safety Board was created by Congress 1988 "as an independent oversight organization within the Executive Branch charged... nuclear facilities ." U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov/about/index.html]. involving CHE and plutonium...approach, if successful, would “reduce or eliminate the need for ESD controls.”42 Kent Fortenberry, Technical Director of the Defense Nuclear Facilities

Options Assessment Report: Treatment of Nitrate Salt Waste at Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robinson, Bruce Alan; Stevens, Patrice Ann

2015-12-17

This report documents the methodology used to select a method of treatment for the remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The method selected should treat the containerized waste in a manner that renders the waste safe and suitable for transport and final disposal in the Waste Isolation Pilot Plant (WIPP) repository, under specifications listed in the WIPP Waste Acceptance Criteria (DOE/CBFO, 2013). LANL recognizes that the results must be thoroughly vetted with the New Mexico Environment Department (NMED) and that a modification to the LANL Hazardous Waste Facility Permitmore » is a necessary step before implementation of this or any treatment option. Likewise, facility readiness and safety basis approvals must be received from the Department of Energy (DOE). This report presents LANL’s preferred option, and the documentation of the process for reaching the recommended treatment option for RNS and UNS waste, and is presented for consideration by NMED and DOE.« less

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1999-02-01

This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the majormore » Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.« less

77 FR 70193 - Shaw Areva MOX Services (Mixed Oxide Fuel Fabrication Facility); Notice of Atomic Safety and...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-11-23

... MOX Services (Mixed Oxide Fuel Fabrication Facility); Notice of Atomic Safety and Licensing Board Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and Licensing Board (Board) in the... Rockville, Maryland this 16th day of November 2012. E. Roy Hawkens, Chief Administrative Judge, Atomic...

29 CFR 1975.2 - Basis of authority.

Code of Federal Regulations, 2010 CFR

2010-07-01

... Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) COVERAGE OF EMPLOYERS UNDER THE WILLIAMS-STEIGER OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 § 1975.2 Basis... Occupational Safety and Health Act of 1970, is derived mainly from the Commerce Clause of the Constitution...

Overview of NORM and activities by a NORM licensed permanent decontamination and waste processing facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mirro, G.A.

1997-02-01

This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.

A security/safety survey of long term care facilities.

PubMed

Acorn, Jonathan R

2010-01-01

What are the major security/safety problems of long term care facilities? What steps are being taken by some facilities to mitigate such problems? Answers to these questions can be found in a survey of IAHSS members involved in long term care security conducted for the IAHSS Long Term Care Security Task Force. The survey, the author points out, focuses primarily on long term care facilities operated by hospitals and health systems. However, he believes, it does accurately reflect the security problems most long term facilities face, and presents valuable information on security systems and practices which should be also considered by independent and chain operated facilities.

DWPF Melter Off-Gas Flammability Assessment for Sludge Batch 9

DOE Office of Scientific and Technical Information (OSTI.GOV)

Choi, A. S.

2016-07-11

The slurry feed to the Defense Waste Processing Facility (DWPF) melter contains several organic carbon species that decompose in the cold cap and produce flammable gases that could accumulate in the off-gas system and create potential flammability hazard. To mitigate such a hazard, DWPF has implemented a strategy to impose the Technical Safety Requirement (TSR) limits on all key operating variables affecting off-gas flammability and operate the melter within those limits using both hardwired/software interlocks and administrative controls. The operating variables that are currently being controlled include; (1) total organic carbon (TOC), (2) air purges for combustion and dilution, (3)more » melter vapor space temperature, and (4) feed rate. The safety basis limits for these operating variables are determined using two computer models, 4-stage cold cap and Melter Off-Gas (MOG) dynamics models, under the baseline upset scenario - a surge in off-gas flow due to the inherent cold cap instabilities in the slurry-fed melter.« less

A High Capacity Polymeric Micelle of Paclitaxel: Implication of High Dose Drug Therapy to Safety and In Vivo Anti-Cancer Activity

PubMed Central

He, Zhijian; Wan, Xiaomeng; Schulz, Anita; Bludau, Herdis; Dobrovolskaia, Marina A.; Stern, Stephan T.; Montgomery, Stephanie A.; Yuan, Hong; Li, Zibo; Alakhova, Daria; Sokolsky, Marina; Darr, David B.; Perou, Charles M.; Jordan, Rainer; Luxenhofer, Robert; Kabanov, Alexander V.

2016-01-01

The poor solubility of paclitaxel (PTX), the commercially most successful anticancer drug, has long been hampering the development of suitable formulations. Here, we present translational evaluation of a nanoformulation of PTX, which is characterized by a facile preparation, extraordinary high drug loading of 50 % wt. and PTX solubility of up to 45 g/L, excellent shelf stability and controllable, sub-100 nm size. We observe favorable in vitro and in vivo safety profiles and a higher maximum tolerated dose compared to clinically approved formulations. Pharmacokinetic analysis reveals that the higher dose administered leads to a higher exposure of the tumor to PTX. As a result, we observed improved therapeutic outcome in orthotopic tumor models including particularly faithful and aggressive “T11” mouse claudin-low breast cancer orthotopic, syngeneic transplants. The promising preclinical data on the presented PTX nanoformulation showcase the need to investigate new excipients and is a robust basis to translate into clinical trials. PMID:27315213

Anticipating and addressing workplace static magnetic field effects at levels <0.5 mT.

PubMed

Emery, R J; Hopkins, J R; Charlton, M A

2000-11-01

Magnetic resonance, once a research tool limited to the basic sciences, has experienced an increase in popularity due to its unique ability to analyze certain living systems in vivo. Expanding applications in the biomedical sciences have resulted in magnetic sources being located in research institutions nationally. Space and resource limitations sometimes necessitate siting magnetic resonance units in proximity to other institutional operations. For magnetic field shielding and personnel protection considerations, the generally accepted 0.5 mT (milliTesla) limit for implanted cardiac devices is commonly used as the conservative basis for decisions. But the effects of magnetic fields on equipment can be easily observed at levels far below 0.5 mT, often resulting in concern and apprehension on the part of personnel in the surrounding areas. Responding to recurrent worker concerns spawned by noticeable effects on equipment at exposure levels <0.5 mT can strain finite radiation safety program resources. To enhance the ability to anticipate possible facility incompatibility issues associated with the installation of magnetic sources, a literature review was conducted to summarize documented equipment effects. Various types of equipment were found to be impacted at levels ranging down to perhaps 0.001 mT. Armed with this information, practicing radiation safety professionals can better anticipate facility incompatibility issues and improve their responses to worker concerns initiated by observed effects on equipment.

Safety Assessment for a Surface Repository in the Chernobyl Exclusion Zone - Methodology for Assessing Disposal under Intervention Conditions - 13476

DOE Office of Scientific and Technical Information (OSTI.GOV)

Haverkamp, B.; Krone, J.; Shybetskyi, I.

The Radioactive Waste Disposal Facility (RWDF) Buryakovka was constructed in 1986 as part of the intervention measures after the accident at Chernobyl NPP (ChNPP). Today, RWDF Buryakovka is still being operated but its maximum capacity is nearly reached. Plans for enlargement of the facility exist since more than 10 years but have not been implemented yet. In the framework of an European Commission Project DBE Technology GmbH prepared a safety analysis report of the facility in its current state (SAR) and a preliminary safety analysis report (PSAR) based on the planned enlargement. Due to its history RWDF Buryakovka does notmore » fully comply with today's best international practices and the latest Ukrainian regulations in this area. The most critical aspects are its inventory of long-lived radionuclides, and the non-existent multi-barrier waste confinement system. A significant part of the project was dedicated, therefore, to the development of a methodology for the safety assessment taking into consideration the facility's special situation and to reach an agreement with all stakeholders involved in the later review and approval procedure of the safety analysis reports. Main aspect of the agreed methodology was to analyze the safety, not strictly based on regulatory requirements but on the assessment of the actual situation of the facility including its location within the Exclusion Zone. For both safety analysis reports, SAR and PSAR, the assessment of the long-term safety led to results that were either within regulatory limits or within the limits allowing for a specific situational evaluation by the regulator. (authors)« less

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 9. Methodologies for review of the health and safety aspects of proposed nuclear, geothermal, and fossil-fuel sites and facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nero, A.V.; Quinby-Hunt, M.S.

1977-01-01

This report sets forth methodologies for review of the health and safety aspects of proposed nuclear, geothermal, and fossil-fuel sites and facilities for electric power generation. The review is divided into a Notice of Intention process and an Application for Certification process, in accordance with the structure to be used by the California Energy Resources Conservation and Development Commission, the first emphasizing site-specific considerations, the second examining the detailed facility design as well. The Notice of Intention review is divided into three possible stages: an examination of emissions and site characteristics, a basic impact analysis, and an assessment of publicmore » impacts. The Application for Certification review is divided into five possible stages: a review of the Notice of Intention treatment, review of the emission control equipment, review of the safety design, review of the general facility design, and an overall assessment of site and facility acceptability.« less

Integration of functional safety systems on the Daniel K. Inouye Solar Telescope

NASA Astrophysics Data System (ADS)

Williams, Timothy R.; Hubbard, Robert P.; Shimko, Steve

2016-07-01

The Daniel K. Inouye Solar Telescope (DKIST) was envisioned from an early stage to incorporate a functional safety system to ensure the safety of personnel and equipment within the facility. Early hazard analysis showed the need for a functional safety system. The design used a distributed approach in which each major subsystem contains a PLC-based safety controller. This PLC-based system complies with the latest international standards for functional safety. The use of a programmable controller also allows for flexibility to incorporate changes in the design of subsystems without adversely impacting safety. Various subsystems were built by different contractors and project partners but had to function as a piece of the overall control system. Using distributed controllers allows project contractors and partners to build components as standalone subsystems that then need to be integrated into the overall functional safety system. Recently factory testing was concluded on the major subsystems of the facility. Final integration of these subsystems is currently underway on the site. Building on lessons learned in early factory tests, changes to the interface between subsystems were made to improve the speed and ease of integration of the entire system. Because of the distributed design each subsystem can be brought online as it is delivered and assembled rather than waiting until the entire facility is finished. This enhances safety during the risky period of integration and testing. The DKIST has implemented a functional safety system that has allowed construction of subsystems in geographically diverse locations but that function cohesively once they are integrated into the facility currently under construction.

The safety attitudes of people who use multi-purpose recreation facilities as a physical activity setting.

PubMed

Finch, Caroline F; Otago, Leonie; White, Peta; Donaldson, Alex; Mahoney, Mary

2011-06-01

Multi-purpose recreation facilities (MPRFs) are a popular setting for physical activity and it is therefore important that they are safe for all patrons. However, the attitudes of MPRF users towards safety are a potential barrier to the success of injury prevention programmes implemented within MPRFs. This article reports a survey of the safety attitudes of over 700 users of four indoor MPRFs. Factor analysis of 12 five-point Likert scale statements showed that the attitudes clustered around three major dimensions - the importance of safety, the benefits of safety and the perceptions of injury risk. Together, these three dimensions accounted for 49% of the variability in the attitudes. More than 85% of respondents agreed/strongly agreed that: safety was an important aspect of physical activity participation; being injured affected enjoyment of physical activity; people should adopt appropriate safety measures for all physical activity; and individuals were responsible for their own safety. The MPRF users, particularly women and older people, were generally safety conscious, believed in adopting safety measures, and were willing to take responsibility for their own safety. Facility managers can be confident that if they provide evidence-based injury prevention interventions in these settings, then users will respond appropriately and adopt the promoted behaviours.

Recent Accomplishments and Future Directions in US Fusion Safety & Environmental Program

DOE Office of Scientific and Technical Information (OSTI.GOV)

David A. Petti; Brad J. Merrill; Phillip Sharpe

2006-07-01

The US fusion program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behavior of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state of the art S&E computer codes and risk tools for safety assessment, and evaluating S&E issues associated with current fusion designs. In thismore » paper, recent accomplishments are reviewed and future directions outlined.« less

Safety equipment list for the 241-SY-101 RAPID mitigation project

DOE Office of Scientific and Technical Information (OSTI.GOV)

MORRIS, K.L.

1999-06-29

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein.

Facilities Condition and Hazards Assessment for Materials and Fuel Complex Facilities MFC-799, 799A, and 770C

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gary Mecham; Don Konoyer

2009-11-01

The Materials & Fuel Complex (MFC) facilities 799 Sodium Processing Facility (a single building consisting of two areas: the Sodium Process Area (SPA) and the Carbonate Process Area (CPA), 799A Caustic Storage Area, and 770C Nuclear Calibration Laboratory have been declared excess to future Department of Energy mission requirements. Transfer of these facilities from Nuclear Energy to Environmental Management, and an associated schedule for doing so, have been agreed upon by the two offices. The prerequisites for this transfer to occur are the removal of nonexcess materials and chemical inventory, deinventory of the calibration source in MFC-770C, and the reroutingmore » and/or isolation of utility and service systems. This report provides a description of the current physical condition and any hazards (material, chemical, nuclear or occupational) that may be associated with past operations of these facilities. This information will document conditions at time of transfer of the facilities from Nuclear Energy to Environmental Management and serve as the basis for disposition planning. The process used in obtaining this information included document searches, interviews and facility walk-downs. A copy of the facility walk-down checklist is included in this report as Appendix A. MFC-799/799A/770C are all structurally sound and associated hazardous or potentially hazardous conditions are well defined and well understood. All installed equipment items (tanks, filters, etc.) used to process hazardous materials remain in place and appear to have maintained their integrity. There is no evidence of leakage and all openings are properly sealed or closed off and connections are sound. The pits appear clean with no evidence of cracking or deterioration that could lead to migration of contamination. Based upon the available information/documentation reviewed and the overall conditions observed during the facilities walk-down, it is concluded that these facilities may be disposed of at minimal risk to human health, safety or the environment.« less

Relationship between the Quality of Educational Facilities, School Climate, and School Safety of High School Tenth Graders in the United States

ERIC Educational Resources Information Center

Bell, Darnell Brushawn

2011-01-01

The purpose of the study was to understand the relationships among facility conditions, school climate, and school safety of high school tenth graders in the United States. Previous research on the quality of educational facilities influence on student achievement has varied. Recent research has suggested that the quality of educational facilities…

76 FR 57980 - Senior Executive Service Performance Review Board

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-19

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review... summary rating of the senior executive's performance, the executive's response, and the higher level...

78 FR 55244 - Senior Executive Service Performance Review Board; Membership

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-10

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board... the membership of the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES... rating of a senior executive's performance, the executive's response, and the higher level official's...

77 FR 54570 - Senior Executive Service Performance Review Board

Federal Register 2010, 2011, 2012, 2013, 2014

2012-09-05

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review.... The PRB shall review and evaluate the initial summary rating of the senior executive's performance...

24 CFR 232.515 - Refund of fees.

Code of Federal Regulations, 2011 CFR

2011-04-01

... INSURANCE FOR NURSING HOMES, INTERMEDIATE CARE FACILITIES, BOARD AND CARE HOMES, AND ASSISTED LIVING FACILITIES Eligibility Requirements-Supplemental Loans To Finance Purchase and Installation of Fire Safety... that the installation of fire safety equipment for the project has been prevented because of...

34 CFR 75.683 - Health or safety standards for facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or safety... to the facilities that the grantee uses for the project. (Authority: 20 U.S.C. 1221e-3 and 3474) ...

77 FR 34457 - Pipeline Safety: Mechanical Fitting Failure Reports

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-11

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... notice provides clarification to owners and operators of gas distribution pipeline facilities when... of a gas distribution pipeline facility to file a written report for any mechanical fitting failure...

77 FR 61826 - Pipeline Safety: Communication During Emergency Situations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-10-11

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... liquefied natural gas pipeline facilities that operators should immediately and directly notify the Public.... Background Federal regulations for gas, liquefied natural gas (LNG), and hazardous liquid pipeline facilities...

Updating fire safety standards. Final rule; affirmation.

PubMed

2011-11-16

This document affirms as final, without changes, a provision included in a final rule with request for comments that amended the Department of Veterans Affairs (VA) regulations concerning community residential care facilities, contract facilities for certain outpatient and residential services, and State home facilities. That provision established a five-year period within which all covered buildings with nursing home facilities existing as of June 25, 2001, must conform to the automatic sprinkler requirement of the 2009 edition of the National Fire Protection Association (NFPA) 101. This rule helps ensure the safety of veterans in the affected facilities.

Caring for class III obese patients.

PubMed

Gardner, Lea Anne

2013-11-01

The Pennsylvania Patient Safety Reporting System is a confidential, statewide Internet reporting system to which all Pennsylvania hospitals, outpatient-surgery facilities, and birthing centers, as well as some abortion facilities, must file information on medical errors.Safety Monitor is a column from Pennsylvania's Patient Safety Authority, the authority that informs nurses on issues that can affect patient safety and presents strategies they can easily integrate into practice. For more information on the authority, visit www.patientsafetyauthority.org. For the original article discussed in this column or for other articles on patient safety, click on "Patient Safety Advisories" and then "Advisory Library" in the left-hand navigation menu.

16 CFR Figures 3 and 4 to Part 1204 - High Voltage Test Facility and Antenna System Test Setup

Code of Federal Regulations, 2012 CFR

2012-01-01

... 16 Commercial Practices 2 2012-01-01 2012-01-01 false High Voltage Test Facility and Antenna System Test Setup 3 Figures 3 and 4 to Part 1204 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR OMNIDIRECTIONAL CITIZENS BAND BASE STATION ANTENNAS Pt. 1204, Figs. 3, 4 Figures 3 and 4...

Safety and the Human Factor.

ERIC Educational Resources Information Center

Smith, Ann

1982-01-01

Discusses four elements of safety programs: (1) safety training; (2) safety inspections; (3) accident investigations; and (4) protective safety equipment. Also discusses safety considerations in water/wastewater treatment facilities focusing on falls, drowning hazards, trickling filters, confined space entry, collection/distribution system safety,…

Recent global trends in structural materials research

NASA Astrophysics Data System (ADS)

Murakami, Hideyuki; Ohmura, Takahito; Nishimura, Toshiyuki

2013-02-01

Structural materials support the basis of global society, such as infrastructure and transportation facilities, and are therefore essential for everyday life. The optimization of such materials allows people to overcome environmental, energy and resource depletion issues on a global scale. The creation and manufacture of structural materials make a large contribution to economies around the world every year. The use of strong, resistant materials can also have profound social effects, providing a better quality of life at both local and national levels. The Great East Japan Earthquake of 11 March 2011 caused significant structural damage in the Tohoku and Kanto regions of Japan. On a global scale, accidents caused by the ageing and failure of structural materials occur on a daily basis. Therefore, the provision and inspection of structural reliability, safety of nuclear power facilities and construction of a secure and safe society hold primary importance for researchers and engineers across the world. Clearly, structural materials need to evolve further to address both existing problems and prepare for new challenges that may be faced in the future. With this in mind, the National Institute for Materials Science (NIMS) organized the 'NIMS Conference 2012' to host an extensive discussion on a variety of global issues related to the future development of structural materials. Ranging from reconstruction following natural disasters, verification of structural reliability, energy-saving materials to fundamental problems accompanying the development of materials for high safety standards, the conference covered many key issues in the materials industry today. All the above topics are reflected in this focus issue of STAM, which introduces recent global trends in structural materials research with contributions from world-leading researchers in this field. This issue covers the development of novel alloys, current methodologies in the characterization of structural materials and fundamental research on structure-property relationships. We are grateful to the authors who contributed to cover these issues, and sincerely hope that our readers will expand their knowledge of emerging international research within the field of structural materials.

The Sepsis Early Recognition and Response Initiative (SERRI)

PubMed Central

Jones, Stephen L.; Ashton, Carol M.; Kiehne, Lisa; Gigliotti, Elizabeth; Bell-Gordon, Charyl; Pinn, Teresa T.; Tran, Shirley K.; Nicolas, Juan C.; Rose, Alexis L.; Shirkey, Beverly A.; Disbot, Maureen; Masud, Faisal; Wray, Nelda P.

2016-01-01

Duration of Initiative 48 months and currently ongoing. Setting The Houston Methodist Hospital System and affiliated hospitals (3 facilities with 2 hospital-run skilled nursing facilities in and around Houston), St. Joseph’s Regional Health Center (1 acute care hospital and 2 skilled nursing facilities in Bryan, Texas), Hospital Corporation of America (2 acute care facilities in Houston, 1 acute care facility in McAllen, Texas [Rio Grande Valley]), Kindred Healthcare (2 long term acute care facilities in Houston), Select Medical Specialty Hospitals (2 long term acute care facilities in Houston). Whom This Should Concern Hospital administrators, quality and safety officers, performance improvement and patient safety professionals, clinic managers, infection control and prevention staff, and other physicians, nurses, and clinical staff. PMID:26892701

A Pilot Assessment of Occupational Health Hazards in the US Electronic Scrap Recycling Industry

PubMed Central

Ceballos, Diana M.; Gong, Wei; Page, Elena

2015-01-01

The National Institute for Occupational Safety and Health (NIOSH) surveyed a randomly selected sample of electronic scrap (e-scrap) recycling facilities nationwide to characterize work processes, exposures, and controls. Despite multiple attempts to contact 278 facilities, only 47 responded (17% response rate). Surveyed facilities reported recycling a wide variety of electronics. The most common recycling processes were manual dismantling and sorting. Other processes included shredding, crushing, and automated separation. Many facilities reported that they had health and safety programs in place. However, some facilities reported the use of compressed air for cleaning, a practice that can lead to increased employee dust exposures, and some facilities allowed food and drinks in the production areas, a practice that can lead to ingestion of contaminants. Although our results may not be generalizable to all US e-scrap recycling facilities, they are informative regarding health and safety programs in the industry. We concluded that e-scrap recycling has the potential for a wide variety of occupational exposures particularly because of the frequent use of manual processes. On-site evaluations of e-scrap recyclers are needed to determine if reported work processes, practices, and controls are effective and meet current standards and guidelines. Educating the e-scrap recycling industry about health and safety best practices, specifically related to safe handling of metal dust, would help protect employees. PMID:25738822

A Pilot Assessment of Occupational Health Hazards in the US Electronic Scrap Recycling Industry.

PubMed

Ceballos, Diana M; Gong, Wei; Page, Elena

2015-01-01

The National Institute for Occupational Safety and Health (NIOSH) surveyed a randomly selected sample of electronic scrap (e-scrap) recycling facilities nationwide to characterize work processes, exposures, and controls. Despite multiple attempts to contact 278 facilities, only 47 responded (17% response rate). Surveyed facilities reported recycling a wide variety of electronics. The most common recycling processes were manual dismantling and sorting. Other processes included shredding, crushing, and automated separation. Many facilities reported that they had health and safety programs in place. However, some facilities reported the use of compressed air for cleaning, a practice that can lead to increased employee dust exposures, and some facilities allowed food and drinks in the production areas, a practice that can lead to ingestion of contaminants. Although our results may not be generalizable to all US e-scrap recycling facilities, they are informative regarding health and safety programs in the industry. We concluded that e-scrap recycling has the potential for a wide variety of occupational exposures particularly because of the frequent use of manual processes. On-site evaluations of e-scrap recyclers are needed to determine if reported work processes, practices, and controls are effective and meet current standards and guidelines. Educating the e-scrap recycling industry about health and safety best practices, specifically related to safe handling of metal dust, would help protect employees.

Surrogate Safety Assessment Model and Validation : Final Report

DOT National Transportation Integrated Search

2008-06-01

Safety of traffic facilities is most often measured by counting the number (and severity) of crashes that occur. It is not possible to apply such a measurement technique to traffic facility designs that have not yet been built or deployed in the real...

75 FR 56999 - Senior Executive Service Performance Review Board

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-17

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review... performance review boards. The PRB shall review and evaluate the initial summary rating of the senior...

The effect of motorcycle travel on the safety and operations of HOV facilities in Virginia.

DOT National Transportation Integrated Search

1995-01-01

The Intermodal Surface Transportation Efficiency Act of 1991 mandated that motorcycles be permitted to travel on federally funded high-occupancy vehicle (HOV) facilities unless they created a safety hazard or adversely affected HOV operations. Althou...

Preschool Comes to School: Design Concerns of Preschool Facilities.

ERIC Educational Resources Information Center

Passantino, Richard J.

1994-01-01

Addresses design and safety issues of which school business administrators should be aware when they become involved in integrating a preschool facility with an elementary school. Discusses building environmental factors, safety, health codes, play surfaces, energy conservation, and architectural considerations. (KDP)

A bicycle safety index for evaluating urban street facilities.

PubMed

Asadi-Shekari, Zohreh; Moeinaddini, Mehdi; Zaly Shah, Muhammad

2015-01-01

The objectives of this research are to conceptualize the Bicycle Safety Index (BSI) that considers all parts of the street and to propose a universal guideline with microscale details. A point system method comparing existing safety facilities to a defined standard is proposed to estimate the BSI. Two streets in Singapore and Malaysia are chosen to examine this model. The majority of previous measurements to evaluate street conditions for cyclists usually cannot cover all parts of streets, including segments and intersections. Previous models also did not consider all safety indicators and cycling facilities at a microlevel in particular. This study introduces a new concept of a practical BSI to complete previous studies using its practical, easy-to-follow, point system-based outputs. This practical model can be used in different urban settings to estimate the level of safety for cycling and suggest some improvements based on the standards.

Quarterly report on Defense Nuclear Facilities Safety Board Recommendation 90-7 for the period ending December 31, 1992

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cash, R.J.; Dukelow, G.T.; Forbes, C.J.

1993-03-01

This is the seventh quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285{degrees}C (545{degrees}F)]. In the mid 1950s approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities thatmore » were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to US Department of Energy by Westinghouse Hanford Company in December 1992. Milestones completed this quarter are described in this report. Contents of this report include: Introduction; Defense Nuclear Facilities Safety Board Implementation Plan Task Activities (Defense Nuclear Facilities Safety Board Recommendation for enhanced temperature measurement, Recommendation for continuous temperature monitoring, Recommendation for cover gas monitoring, Recommendation for ferrocyanide waste characterization, Recommendation for chemical reaction studies, and Recommendation for emergency response planning); Schedules; and References. All actions recommended by the Defense Nuclear Facilities Safety Board for emergency planning by Hanford Site emergency preparedness organizations have been completed.« less

Safety assessment of discharge chute isolation barrier preparation and installation. Revision 1

DOE Office of Scientific and Technical Information (OSTI.GOV)

Meichle, R.H.

1994-10-10

This revision responds to RL comments and increases the discussion of the ``effective hazard categorization`` and the readiness review basis. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparison of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions were made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classification.

45 CFR 618.410 - Comparable facilities.

Code of Federal Regulations, 2012 CFR

2012-10-01

... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities...

45 CFR 618.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-10-01

... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities...

45 CFR 618.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-10-01

... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities...

45 CFR 618.410 - Comparable facilities.

Code of Federal Regulations, 2013 CFR

2013-10-01

... Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION NONDISCRIMINATION ON THE BASIS OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities...

10 CFR 830.201 - Performance of work.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Performance of work. 830.201 Section 830.201 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Safety Basis Requirements § 830.201 Performance of work. A contractor must perform work in accordance with the safety basis for a hazard category 1, 2, or 3 DOE nuclear...

Preliminary safety evaluation of an aircraft impact on a near-surface radioactive waste repository

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lo Frano, R.; Forasassi, G.; Pugliese, G.

2013-07-01

The aircraft impact accident has become very significant in the design of a nuclear facilities, particularly, after the tragic September 2001 event, that raised the public concern about the potential damaging effects that the impact of a large civilian airplane could bring in safety relevant structures. The aim of this study is therefore to preliminarily evaluate the global response and the structural effects induced by the impact of a military or commercial airplane (actually considered as a 'beyond design basis' event) into a near surface radioactive waste (RWs) disposal facility. The safety evaluation was carried out according to the Internationalmore » safety and design guidelines and in agreement with the stress tests requirements for the security track. To achieve the purpose, a lay out and a scheme of a possible near surface repository, like for example those of the El Cabril one, were taken into account. In order to preliminarily perform a reliable analysis of such a large-scale structure and to determine the structural effects induced by such a types of impulsive loads, a realistic, but still operable, numerical model with suitable materials characteristics was implemented by means of FEM codes. In the carried out structural analyses, the RWs repository was considered a 'robust' target, due to its thicker walls and main constitutive materials (steel and reinforced concrete). In addition to adequately represent the dynamic response of repository under crashing, relevant physical phenomena (i.e. penetration, spalling, etc.) were simulated and analysed. The preliminary assessment of the effects induced by the dynamic/impulsive loads allowed generally to verify the residual strength capability of the repository considered. The obtained preliminary results highlighted a remarkable potential to withstand the impact of military/large commercial aircraft, even in presence of ongoing concrete progressive failure (some penetration and spalling of the concrete wall) of the impacted area. (authors)« less

Understanding the impact of supervision on reducing medication risks: an interview study in long-term elderly care.

PubMed

Vermeulen, J A; Kleefstra, S M; Zijp, E M; Kool, R B

2017-07-06

In 2009, the Dutch Health Care Inspectorate (IGZ) observed several serious risks to safety involving medication within elderly care facilities. However, by 2011, high risks had been reduced in almost all the organisations we visited. And yet the IGZ analysed too the alarming increase in the number of incidents arising in the self-reported national indicator of medication safety between 2009 and 2010. The aim of this study was to understand the factors that can explain this contradiction between the increase in self-reported medication incidents and the observation of the IGZ in reducing the risks to medication safety through supervision. We interviewed health care professionals of ten care facilities, visited by the IGZ, who were involved in, or responsible for, the improvement of medication safety in their institutions. As outcome measures we used the rate of medication safety risk per facility; the perceptions of the participant with regard to the reports of medication incidents; the level of medication safety of the facility; the measures used to improve medication safety; and the supervision of medication safety. This was a mixed methods study, qualitative in that we used semi-structured interviews, and quantitative, by calculating risks for the different organisations we visited. The findings from both study methods resulted in a comprehensive view and an in-depth understanding of this contradiction. The contradiction between the increase in self-reported medication incidents and the observation of reduced risks was explained by three themes: activities designed to improve medication safety, the reporting of medication incidents, and, lastly, the impact of supervision. The focus of the IGZ on issues of medication safety stimulated most elderly care facilities to reduce medication risks. Also, a change in the culture of reporting incidents caused an increase in the number of reported incidents. Supervision contributed to an improvement in actions geared towards reducing the risks associated with the safety of medication. It also increased a willingness to report such incidents. The more incidents reported are therefore not necessarily a sign of an increase in the risks, but can also be considered as a sign of a safer culture.

41 CFR 102-80.60 - Are Federal agencies responsible for performing facility assessments?

Code of Federal Regulations, 2010 CFR

2010-07-01

... Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 80-SAFETY AND ENVIRONMENTAL MANAGEMENT Safety and Environmental Management Facility Assessments... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Are Federal agencies...

10 CFR 1707.103 - Definitions.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...

10 CFR 1707.103 - Definitions.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...

10 CFR 1707.103 - Definitions.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...

10 CFR 1707.103 - Definitions.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...

10 CFR 1707.103 - Definitions.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...

Enhancing the traditional hospital design process: a focus on patient safety.

PubMed

Reiling, John G; Knutzen, Barbara L; Wallen, Thomas K; McCullough, Susan; Miller, Ric; Chernos, Sonja

2004-03-01

In 2002 St. Joseph's Community Hospital (West Bend, WI), a member of SynergyHealth, brought together leaders in health care and systems engineering to develop a set of safety-driven facility design principles that would guide the hospital design process. DESIGNING FOR SAFETY: Hospital leadership recognized that a cross-departmental team approach would be needed and formed the 11-member Facility Design Advisory Council, which, with departmental teams and the aid of architects, was responsible for overseeing the design process and for ensuring that the safety considerations were met. The design process was a team approach, with input from national experts, patients and families, hospital staff and physicians, architects, contractors, and the community. The new facility, designed using safety-driven design principles, reflects many innovative design elements, including truly standardized patient rooms, new technology to minimize falls, and patient care alcoves for every patient room. The new hospital has been designed with maximum adaptability and flexibility in mind, to accommodate changes and provide for future growth. The architects labeled the innovative design. The Synergy Model, to describe the process of shaping the entire building and its spaces to work efficiently as a whole for the care and safety of patients. Construction began on the new facility in August 2003 and is expected to be completed in 2005.

Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999

DOE Office of Scientific and Technical Information (OSTI.GOV)

None

2000-02-01

This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted inmore » the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.« less

42 CFR 456.610 - Basis for determinations.

Code of Federal Regulations, 2010 CFR

2010-10-01

... (CONTINUED) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL Inspections of Care in Intermediate Care Facilities and Institutions for Mental Diseases § 456.610 Basis for determinations. In making the... psychiatric facilities, and mental hospitals; and (2) At least quarterly in ICFs; (c) Tests or observations of...

10 CFR 1707.301 - Fees.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...

10 CFR 1707.301 - Fees.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...

10 CFR 1707.301 - Fees.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...

10 CFR 1707.301 - Fees.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...

10 CFR 1707.301 - Fees.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...

10 CFR 70.62 - Safety program and integrated safety analysis.

Code of Federal Regulations, 2011 CFR

2011-01-01

...) Radiological hazards related to possessing or processing licensed material at its facility; (ii) Chemical hazards of licensed material and hazardous chemicals produced from licensed material; (iii) Facility... performed by a team with expertise in engineering and process operations. The team shall include at least...

Hazardous Waste Cleanup: Safety-Kleen Corporation - Congers 2-118-01 in Congers, New York

EPA Pesticide Factsheets

Safety-Kleen Corporation, the Congers facility is located at 68 North Harrison Avenue, Congers, Rockland County, New York. The facility is about 2,000 feet northeast of the intersection of Congers Road and Kings Highway, situated atop a small hill located

30 CFR 71.501 - Sanitary toilet facilities; maintenance.

Code of Federal Regulations, 2010 CFR

2010-07-01

... Section 71.501 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Sanitary Toilet Facilities at Surface Worksites of Surface Coal Mines § 71.501 Sanitary...

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

DOE Office of Scientific and Technical Information (OSTI.GOV)

CROWE, R.D.; PIEPHO, M.G.

2000-03-23

This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building 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 Canister Storage Building Final Safety Analysis Report.

Validation of a physically based catchment model for application in post-closure radiological safety assessments of deep geological repositories for solid radioactive wastes.

PubMed

Thorne, M C; Degnan, P; Ewen, J; Parkin, G

2000-12-01

The physically based river catchment modelling system SHETRAN incorporates components representing water flow, sediment transport and radionuclide transport both in solution and bound to sediments. The system has been applied to simulate hypothetical future catchments in the context of post-closure radiological safety assessments of a potential site for a deep geological disposal facility for intermediate and certain low-level radioactive wastes at Sellafield, west Cumbria. In order to have confidence in the application of SHETRAN for this purpose, various blind validation studies have been undertaken. In earlier studies, the validation was undertaken against uncertainty bounds in model output predictions set by the modelling team on the basis of how well they expected the model to perform. However, validation can also be carried out with bounds set on the basis of how well the model is required to perform in order to constitute a useful assessment tool. Herein, such an assessment-based validation exercise is reported. This exercise related to a field plot experiment conducted at Calder Hollow, west Cumbria, in which the migration of strontium and lanthanum in subsurface Quaternary deposits was studied on a length scale of a few metres. Blind predictions of tracer migration were compared with experimental results using bounds set by a small group of assessment experts independent of the modelling team. Overall, the SHETRAN system performed well, failing only two out of seven of the imposed tests. Furthermore, of the five tests that were not failed, three were positively passed even when a pessimistic view was taken as to how measurement errors should be taken into account. It is concluded that the SHETRAN system, which is still being developed further, is a powerful tool for application in post-closure radiological safety assessments.

Prevention of fall-related injuries in long-term care: a randomized controlled trial of staff education.

PubMed

Ray, Wayne A; Taylor, Jo A; Brown, Anne K; Gideon, Patricia; Hall, Kathi; Arbogast, Patrick; Meredith, Sarah

2005-10-24

Fall-related injuries, a major public health problem in long-term care, may be reduced by interventions that improve safety practices. Previous studies have shown that safety practice interventions can reduce falls; however, in long-term care these have relied heavily on external funding and staff. The aim of this study was to test whether a training program in safety practices for staff could reduce fall-related injuries in long-term care facilities. A cluster randomization clinical trial with 112 qualifying facilities and 10,558 study residents 65 years or older and not bedridden. The intervention was an intensive 2-day safety training program with 12-month follow-up. The training program targeted living space and personal safety; wheelchairs, canes, and walkers; psychotropic medication use; and transferring and ambulation. The main outcome measure was serious fall-related injuries during the follow-up period. There was no difference in injury occurrence between the intervention and control facilities (adjusted rate ratio, 0.98; 95% confidence interval, 0.83-1.16). For residents with a prior fall in facilities with the best program compliance, there was a nonsignificant trend toward fewer injuries in the intervention group (adjusted rate ratio, 0.79; 95% confidence interval, 0.57-1.10). More intensive interventions are required to prevent fall-related injuries in long-term care facilities.

Exploring Operational Safeguards, Safety, and Security by Design to Address Real Time Threats in Nuclear Facilities

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schanfein, Mark J.; Mladineo, Stephen V.

2015-07-07

Over the last few years, significant attention has been paid to both encourage application and provide domestic and international guidance for designing in safeguards and security in new facilities.1,2,3 However, once a facility is operational, safeguards, security, and safety often operate as separate entities that support facility operations. This separation is potentially a serious weakness should insider or outsider threats become a reality.Situations may arise where safeguards detects a possible loss of material in a facility. Will they notify security so they can, for example, check perimeter doors for tampering? Not doing so might give the advantage to an insidermore » who has already, or is about to, move nuclear material outside the facility building. If outsiders break into a facility, the availability of any information to coordinate the facility’s response through segregated alarm stations or a failure to include all available radiation sensors, such as safety’s criticality monitors can give the advantage to the adversary who might know to disable camera systems, but would most likely be unaware of other highly relevant sensors in a nuclear facility.This paper will briefly explore operational safeguards, safety, and security by design (3S) at a high level for domestic and State facilities, identify possible weaknesses, and propose future administrative and technical methods, to strengthen the facility system’s response to threats.« less

Waste Receiving and Processing (WRAP) Module 1 Hazards Assessment

DOE Office of Scientific and Technical Information (OSTI.GOV)

CAMPBELL, L.R.

1999-09-29

This document establishes the technical basis in support of Emergency Planning activities for the WRAP Module 1 Facility on the Hanford Site. Through this document, the technical basis for the development of facility specific Emergency Action Levels and Emergency Planning Zone is demonstrated.

Nuclear criticality safety calculational analysis for small-diameter containers

DOE Office of Scientific and Technical Information (OSTI.GOV)

LeTellier, M.S.; Smallwood, D.J.; Henkel, J.A.

This report documents calculations performed to establish a technical basis for the nuclear criticality safety of favorable geometry containers, sometimes referred to as 5-inch containers, in use at the Portsmouth Gaseous Diffusion Plant. A list of containers currently used in the plant is shown in Table 1.0-1. These containers are currently used throughout the plant with no mass limits. The use of containers with geometries or material types other than those addressed in this evaluation must be bounded by this analysis or have an additional analysis performed. The following five basic container geometries were modeled and bound all container geometriesmore » in Table 1.0-1: (1) 4.32-inch-diameter by 50-inch-high polyethylene bottle; (2) 5.0-inch-diameter by 24-inch-high polyethylene bottle; (3) 5.25-inch-diameter by 24-inch-high steel can ({open_quotes}F-can{close_quotes}); (4) 5.25-inch-diameter by 15-inch-high steel can ({open_quotes}Z-can{close_quotes}); and (5) 5.0-inch-diameter by 9-inch-high polybottle ({open_quotes}CO-4{close_quotes}). Each container type is evaluated using five basic reflection and interaction models that include single containers and multiple containers in normal and in credible abnormal conditions. The uranium materials evaluated are UO{sub 2}F{sub 2}+H{sub 2}O and UF{sub 4}+oil materials at 100% and 10% enrichments and U{sub 3}O{sub 8}, and H{sub 2}O at 100% enrichment. The design basis safe criticality limit for the Portsmouth facility is k{sub eff} + 2{sigma} < 0.95. The KENO study results may be used as the basis for evaluating general use of these containers in the plant.« less

DOE’s Management and Oversight of the Nuclear Weapons Complex

DTIC Science & Technology

1990-03-22

and Economic Development Division Before the Department of Energy Defense Nuclear Facilities Panel Committee on Armed Services House of Representatives...and newly created DOE offices. The Defense Nuclear Facilities Safety Board, whose board members were appointed this past year, was created to provide 6...mandated Defense Nuclear Facilities Safety Board. Continuing dialogue between DOE and the Board can also serve to enhance DOE’s ability to respond more

Use of Structure as a Basis for Abstraction in Air Traffic Control

NASA Technical Reports Server (NTRS)

Davison, Hayley J.; Hansman, R. John

2004-01-01

The safety and efficiency of the air traffic control domain is highly dependent on the capabilities and limitations of its human controllers. Past research has indicated that structure provided by the airspace and procedures could aid in simplifying the controllers cognitive tasks. In this paper, observations, interviews, voice command data analyses, and radar analyses were conducted at the Boston Terminal Route Control (TRACON) facility to determine if there was evidence of controllers using structure to simplify their cognitive processes. The data suggest that controllers do use structure-based abstractions to simplify their cognitive processes, particularly the projection task. How structure simplifies the projection task and the implications of understanding the benefits structure provides to the projection task was discussed.

Training and certification program of the operating staff for a 90-day test of a regenerative life support system

NASA Technical Reports Server (NTRS)

1972-01-01

Prior to beginning a 90-day test of a regenerative life support system, a need was identified for a training and certification program to qualify an operating staff for conducting the test. The staff was responsible for operating and maintaining the test facility, monitoring and ensuring crew safety, and implementing procedures to ensure effective mission performance with good data collection and analysis. The training program was designed to ensure that each operating staff member was capable of performing his assigned function and was sufficiently cross-trained to serve at certain other positions on a contingency basis. Complicating the training program were budget and schedule limitations, and the high level of sophistication of test systems.

[Road map for health and safety management systems in healthcare facilities, according to the OHSAS 18001:2007 standard].

PubMed

Pugliese, F; Albini, E; Serio, O; Apostoli, P

2011-01-01

The 81/2008 Act has defined a model of a health and safety management system that can contribute to prevent the occupational health and safety risks. We have developed the structure of a health and safety management system model and the necessary tools for its implementation in health care facilities. The realization of a model is structured in various phases: initial review, safety policy, planning, implementation, monitoring, management review and continuous improvement. Such a model, in continuous evolution, is based on the responsibilities of the different corporate characters and on an accurate analysis of risks and involved norms.

The National Shipbuilding Research Program. Ship Breaking: Environmental Health and Safety Regulatory Overview

DTIC Science & Technology

1999-09-27

facility in Alang , India, where ship scrapping typically is performed on beach front property, allowing toxins, oils, PCBs, asbestos, and chromates...in Alang are operated in a manner that endanger the health and safety of their laborers and that government enforcement of...Id. According to the Baltimore Sun, none of the men who work at the Alang facility wear hard hats, safety harnesses, or respirators even though each

75 FR 51500 - Advisory Committee on Reactor Safeguards

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-20

..., October 14, 2009 (74 FR 52829-52830). Thursday, September 9, 2010, Conference Room T2-B1, Two White Flint... Fabrication Facility and the Associated Safety Evaluation Report (Open/ Closed)--The Committee will hold... the MOX Fuel Fabrication Facility and the associated Safety Evaluation Report. [Note: A portion of...

41 CFR 301-11.11 - How do I select lodging and make lodging reservations?

Code of Federal Regulations, 2012 CFR

2012-07-01

... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...

41 CFR 301-11.11 - How do I select lodging and make lodging reservations?

Code of Federal Regulations, 2013 CFR

2013-07-01

... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...

41 CFR 301-11.11 - How do I select lodging and make lodging reservations?

Code of Federal Regulations, 2014 CFR

2014-07-01

... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...

49 CFR 1155.27 - Board determinations under 49 U.S.C. 10909.

Code of Federal Regulations, 2010 CFR

2010-10-01

... determines that the facility at the existing or proposed location would not pose an unreasonable risk to... risk to public health, safety, or the environment, the Board shall weigh the particular facility's... comply with an environmental, public health, or public safety standard that falls under the traditional...

Implementation of the Generic Safety Analysis Report - Lessons Learned

DOE Office of Scientific and Technical Information (OSTI.GOV)

Blanchard, A.

1999-06-02

The Savannah River Site has completed the development, review and approval process for the Generic Safety Analysis Report (GSAR) and implemented this information in facility SARs and BIOs. This includes the yearly revision of the GSAR and the facility-specific SARs. The process has provided us with several lessons learned.

10 CFR 1706.1 - Scope; statement of policy.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...

10 CFR 1707.205 - Processing demands or requests.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...

10 CFR 1707.205 - Processing demands or requests.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...

10 CFR 1707.205 - Processing demands or requests.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...

10 CFR 1707.204 - Service of subpoenas or requests.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

10 CFR 1705.03 - Systems of records notification.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...

10 CFR 1707.205 - Processing demands or requests.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...

10 CFR 1707.205 - Processing demands or requests.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...

10 CFR 1707.204 - Service of subpoenas or requests.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

10 CFR 1706.1 - Scope; statement of policy.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...

10 CFR 1707.204 - Service of subpoenas or requests.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

10 CFR 1706.1 - Scope; statement of policy.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...

10 CFR 1707.204 - Service of subpoenas or requests.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

10 CFR 1706.1 - Scope; statement of policy.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...

10 CFR 1707.204 - Service of subpoenas or requests.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...

10 CFR 1706.1 - Scope; statement of policy.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...

76 FR 58049 - Atomic Safety and Licensing Board; Honeywell International, Inc.; Metropolis Works Uranium...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-19

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-3392-MLA; ASLBP No. 11-910-01-MLA-BD01] Atomic Safety and Licensing Board; Honeywell International, Inc.; Metropolis Works Uranium Conversion Facility... assurance for its Metropolis Works uranium conversion facility in Metropolis, Illinois. \\1\\ LBP-11-19, 74...

Response to in-depth safety audit of the L Lake sampling station

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gladden, J.B.

1986-10-15

An in-depth safety audit of several of the facilities and operations supporting the Biological Monitoring Program on L Lake was conducted. Subsequent to the initial audit, the audit team evaluated the handling of samples taken for analysis of Naegleria fowleri at the 704-U laboratory facility.

10 CFR 1705.08 - Appeals from correction denials.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...

10 CFR 1705.06 - Appeals from access denials.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...

10 CFR 1705.03 - Systems of records notification.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...

10 CFR 1705.08 - Appeals from correction denials.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...

10 CFR 1705.03 - Systems of records notification.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...

10 CFR 1705.07 - Requests for correction of records.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...

10 CFR 1705.08 - Appeals from correction denials.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...

10 CFR 1705.07 - Requests for correction of records.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...

10 CFR 1705.06 - Appeals from access denials.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...

10 CFR 1705.07 - Requests for correction of records.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...

10 CFR 1705.06 - Appeals from access denials.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...

10 CFR 1705.06 - Appeals from access denials.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...

10 CFR 1705.03 - Systems of records notification.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...

10 CFR 1705.08 - Appeals from correction denials.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...

10 CFR 1705.07 - Requests for correction of records.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...

10 CFR 1705.07 - Requests for correction of records.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...

10 CFR 1705.03 - Systems of records notification.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...

10 CFR 1705.06 - Appeals from access denials.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...

10 CFR 1705.08 - Appeals from correction denials.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...

Application of the Life Safety Code to a Historic Test Stand

NASA Technical Reports Server (NTRS)

Askins, Bruce; Lemke, Paul R.; Lewis, William L.; Covell, Carol C.

2011-01-01

NASA has conducted a study to assess alternatives to refurbishing existing launch vehicle modal test facilities as opposed to developing new test facilities to meet the demands of a very fiscally constrained test and evaluation environment. The results of this study showed that Marshall Space Flight Center (MSFC) Test Stand (TS) 4550 could be made compliant, within reasonable cost and schedule impacts, if safety processes and operational limitations were put in place to meet the safety codes and concerns of the Fire Marshall. Trades were performed with key selection criteria to ensure that appropriate levels of occupant safety are incorporated into test facility design modifications. In preparation for the ground vibration tests that were to be performed on the Ares I launch vehicle, the Ares Flight and Integrated Test Office (FITO) organization evaluated the available test facility options, which included the existing mothballed structural dynamic TS4550 used by Apollo and Shuttle, alternative ground vibration test facilities at other locations, and construction of a new dynamic test stand. After an exhaustive assessment of the alternatives, the results favored modifying the TS4550 because it was the lowest cost option and presented the least schedule risk to the NASA Constellation Program for Ares Integrated Vehicle Ground Vibration Test (IVGVT). As the renovation design plans and drawings were being developed for TS4550, a safety concern was discovered the original design for the construction of the test stand, originally built for the Apollo Program and renovated for the Shuttle Program, was completed before NASA s adoption of the currently imposed safety and building codes per National Fire Protection Association Life Safety Code [NFPA 101] and International Building Codes. The initial FITO assessment of the design changes, required to make TS4550 compliant with current safety and building standards, identified a significant cost increase and schedule impact. An effort was launched to thoroughly evaluate the applicable life safety requirements, examine the context in which they were derived, and determine a means by which the TS4550 modifications could be made within budget and on schedule, while still providing the occupants with appropriate levels of safety.

Passive Safety Features Evaluation of KIPT Neutron Source Facility

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zhong, Zhaopeng; Gohar, Yousry

2016-06-01

Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have cooperated on the development, design, and construction of a neutron source facility. The facility was constructed at Kharkov, Ukraine and its commissioning process is underway. It will be used to conduct basic and applied nuclear research, produce medical isotopes, and train young nuclear specialists. The facility has an electron accelerator-driven subcritical assembly. The electron beam power is 100 kW using 100 MeV electrons. Tungsten or natural uranium is the target material for generating neutrons driving the subcritical assembly. The subcritical assemblymore » is composed of WWR-M2 - Russian fuel assemblies with U-235 enrichment of 19.7 wt%, surrounded by beryllium reflector assembles and graphite blocks. The subcritical assembly is seated in a water tank, which is a part of the primary cooling loop. During normal operation, the water coolant operates at room temperature and the total facility power is ~300 KW. The passive safety features of the facility are discussed in in this study. Monte Carlo computer code MCNPX was utilized in the analyses with ENDF/B-VII.0 nuclear data libraries. Negative reactivity temperature feedback was consistently observed, which is important for the facility safety performance. Due to the design of WWR-M2 fuel assemblies, slight water temperature increase and the corresponding water density decrease produce large reactivity drop, which offset the reactivity gain by mistakenly loading an additional fuel assembly. The increase of fuel temperature also causes sufficiently large reactivity decrease. This enhances the facility safety performance because fuel temperature increase provides prompt negative reactivity feedback. The reactivity variation due to an empty fuel position filled by water during the fuel loading process is examined. Also, the loading mistakes of removing beryllium reflector assemblies and replacing them with dummy assemblies were analyzed. In all these circumstances, the reactivity change results do not cause any safety concerns.« less

Posttest examination of Sodium Loop Safety Facility experiments. [LMFBR

DOE Office of Scientific and Technical Information (OSTI.GOV)

Holland, J.W.

In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehensive posttest examinations (PTE) to characterize the postirradiation condition of the cladding, fuel, and other test-subassembly components. PTE information and on-line instrumentation data, are analyzed to identify the sequence of events and the severity of the accident for each experiment. Following in-reactor experimentation, the SLSF loop and test assembly are transported to the Hot Fuel Examination Facility (HFEF) for initial disassembly. Goals of the HFEF-phase of the PTE are to retrieve the fuel bundle by dismantling the loop and withdrawing the test assembly, to assess the macro-conditionmore » of the fuel bundle by nondestructive examination techniques, and to prepare the fuel bundle for shipment to the Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory.« less

Energy Systems Integration Facility Control Room | Energy Systems

Science.gov Websites

Integration Facility | NREL Energy Systems Integration Facility Control Room Energy Systems Integration Facility Control Room The Energy Systems Integration Facility control room allows system engineers as the monitoring point for the facility's integrated safety and control systems. Photo of employees

42 CFR 442.1 - Basis and purpose.

Code of Federal Regulations, 2014 CFR

2014-10-01

...) MEDICAL ASSISTANCE PROGRAMS STANDARDS FOR PAYMENT TO NURSING FACILITIES AND INTERMEDIATE CARE FACILITIES... of services furnished by nursing facilities and intermediate care facilities for individuals with... agreements; Section 1902(a)(28), nursing facility standards; Section 1902(a)(33)(B), State survey agency...

Development and perceived effects of an educational programme on quality and safety in medication handling in residential facilities.

PubMed

Mygind, Anna; El-Souri, Mira; Rossing, Charlotte; Thomsen, Linda Aagaard

2018-04-01

To develop and test an educational programme on quality and safety in medication handling for staff in residential facilities for the disabled. The continuing pharmacy education instructional design model was used to develop the programme with 22 learning objectives on disease and medicines, quality and safety, communication and coordination. The programme was a flexible, modular seven + two days' course addressing quality and safety in medication handling, disease and medicines, and medication supervision and reconciliation. The programme was tested in five Danish municipalities. Municipalities were selected based on their application for participation; each independently selected a facility for residents with mental and intellectual disabilities, and a facility for residents with severe mental illnesses. Perceived effects were measured based on a questionnaire completed by participants before and after the programme. Effects on motivation and confidence as well as perceived effects on knowledge, skills and competences related to medication handling, patient empowerment, communication, role clarification and safety culture were analysed conducting bivariate, stratified analyses and test for independence. Of the 114 participants completing the programme, 75 participants returned both questionnaires (response rate = 66%). Motivation and confidence regarding quality and safety in medication handling significantly improved, as did perceived knowledge, skills and competences on 20 learning objectives on role clarification, safety culture, medication handling, patient empowerment and communication. The programme improved staffs' motivation and confidence and their perceived ability to handle residents' medication safely through improved role clarification, safety culture, medication handling and patient empowerment and communication skills. © 2017 Royal Pharmaceutical Society.

Activities of the US-Japan Safety Monitor Joint Working Group

DOE Office of Scientific and Technical Information (OSTI.GOV)

Richard L. Savercool; Lee C. Cadwallader

2004-09-01

This paper documents the activities of the US-Japan exchange in the area of personnel safety at magnetic and laser fusion experiments. A near-miss event with a visiting scientist to the US in 1992 was the impetus for forming the Joint Working Group on Fusion Safety. This exchnge has been under way for over ten years and has provided many safety insights for both US and Japanese facility personnel at national institutes and at universities. The background and activities of the Joint Working Group are described, including the facilities that have been visited for safety walkthroughs, the participants from both countries,more » and the main safety issues examined during visits. Based on these visits, some operational safety ideas to enhance experiment safety are given. The near-term future plans of the Safety Monitor Joint Working group are also discussed.« less

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zull, Lawrence M.; Yeniscavich, William

2008-01-15

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive materialmore » contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.« less

Advanced reactors and associated fuel cycle facilities: safety and environmental impacts.

PubMed

Hill, R N; Nutt, W M; Laidler, J J

2011-01-01

The safety and environmental impacts of new technology and fuel cycle approaches being considered in current U.S. nuclear research programs are contrasted to conventional technology options in this paper. Two advanced reactor technologies, the sodium-cooled fast reactor (SFR) and the very high temperature gas-cooled reactor (VHTR), are being developed. In general, the new reactor technologies exploit inherent features for enhanced safety performance. A key distinction of advanced fuel cycles is spent fuel recycle facilities and new waste forms. In this paper, the performance of existing fuel cycle facilities and applicable regulatory limits are reviewed. Technology options to improve recycle efficiency, restrict emissions, and/or improve safety are identified. For a closed fuel cycle, potential benefits in waste management are significant, and key waste form technology alternatives are described. Copyright © 2010 Health Physics Society

Enhanced Time Out: An Improved Communication Process.

PubMed

Nelson, Patricia E

2017-06-01

An enhanced time out is an improved communication process initiated to prevent such surgical errors as wrong-site, wrong-procedure, or wrong-patient surgery. The enhanced time out at my facility mandates participation from all members of the surgical team and requires designated members to respond to specified time out elements on the surgical safety checklist. The enhanced time out incorporated at my facility expands upon the safety measures from the World Health Organization's surgical safety checklist and ensures that all personnel involved in a surgical intervention perform a final check of relevant information. Initiating the enhanced time out at my facility was intended to improve communication and teamwork among surgical team members and provide a highly reliable safety process to prevent wrong-site, wrong-procedure, and wrong-patient surgery. Copyright © 2017 AORN, Inc. Published by Elsevier Inc. All rights reserved.

Criticality Safety Analysis on the Mixed Be, Nat-U, and C (Graphite) Reflectors in 55-Gallon Waste Drums and Their Equivalents for HWM Applications

DOE Office of Scientific and Technical Information (OSTI.GOV)

Chou, P

The objective of this analysis is to develop and establish the technical basis on the criticality safety controls for the storage of mixed beryllium (Be), natural uranium (Nat-U), and carbon (C)/graphite reflectors in 55-gallon waste containers and/or their equivalents in Hazardous Waste Management (HWM) facilities. Based on the criticality safety limits and controls outlined in Section 3.0, the operations involving the use of mixed-reflector drums satisfy the double-contingency principle as required by DOE Order 420.1 and are therefore criticality safe. The mixed-reflector mass limit is 120 grams for each 55-gallon drum or its equivalent. a reflector waiver of 50 gramsmore » is allowed for Be, Nat-U, or C/graphite combined. The waived reflectors may be excluded from the reflector mass calculations when determining if a drum is compliant. The mixed-reflector drums are allowed to mix with the typical 55-gallon one-reflector drums with a Pu mass limit of 120 grams. The fissile mass limit for the mixed-reflector container is 65 grams of Pu equivalent each. The corresponding reflector mass limits are 300 grams of Be, and/or 100 kilograms of Nat-U, and/or 110 kilograms of C/graphite for each container. All other unaffected control parameters for the one-reflector containers remain in effect for the mixed-reflector drums. For instance, Superior moderators, such as TrimSol, Superla white mineral oil No. 9, paraffin, and polyethylene, are allowed in unlimited quantities. Hydrogenous materials with a hydrogen density greater than 0.133 gram/cc are not allowed. Also, an isolation separation of no less than 76.2 cm (30-inch) is required between a mixed array and any other array. Waste containers in the action of being transported are exempted from this 76.2-cm (30-inch) separation requirement. All deviations from the CS controls and mass limits listed in Section 3.0 will require individual criticality safety analyses on a case-by-case basis for each of them to confirm their criticality safety prior to their deployment and implementation.« less

Department of Energy: Fundamental Reassessment Needed to Address Major Mission, Structure, and Accountability Problems

DTIC Science & Technology

2001-12-01

addition, the Defense Nuclear Facilities Safety Board warned in 1997 that, given likely future reductions in DOE’s budget, the department needed to...future leaders of the acquisition workforce. The Defense Nuclear Facilities Safety Board’s 2000 report credited DOE with taking steps to improve the...technical capabilities of personnel at its defense nuclear facilities , but pointed out the need for DOE’s leadership to pay increased attention to this

Progress on plutonium stabilization

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hurt, D.

1996-05-01

The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE`s stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities.

42 CFR 483.400 - Basis and purpose.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 42 Public Health 5 2012-10-01 2012-10-01 false Basis and purpose. 483.400 Section 483.400 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION REQUIREMENTS FOR STATES AND LONG TERM CARE FACILITIES Conditions of Participation for Intermediate Care Facilities for...

42 CFR 483.400 - Basis and purpose.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 42 Public Health 5 2013-10-01 2013-10-01 false Basis and purpose. 483.400 Section 483.400 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION REQUIREMENTS FOR STATES AND LONG TERM CARE FACILITIES Conditions of Participation for Intermediate Care Facilities for...

42 CFR 483.400 - Basis and purpose.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 42 Public Health 5 2014-10-01 2014-10-01 false Basis and purpose. 483.400 Section 483.400 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION REQUIREMENTS FOR STATES AND LONG TERM CARE FACILITIES Conditions of Participation for Intermediate Care Facilities for...

42 CFR 442.1 - Basis and purpose.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 42 Public Health 4 2012-10-01 2012-10-01 false Basis and purpose. 442.1 Section 442.1 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL ASSISTANCE PROGRAMS STANDARDS FOR PAYMENT TO NURSING FACILITIES AND INTERMEDIATE CARE FACILITIES FOR INDIVIDUALS WITH INTELLECTUAL DISABILITIES...

42 CFR 442.1 - Basis and purpose.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 42 Public Health 4 2013-10-01 2013-10-01 false Basis and purpose. 442.1 Section 442.1 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL ASSISTANCE PROGRAMS STANDARDS FOR PAYMENT TO NURSING FACILITIES AND INTERMEDIATE CARE FACILITIES FOR INDIVIDUALS WITH INTELLECTUAL DISABILITIES...

18 CFR 1317.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 18 Conservation of Power and Water Resources 2 2010-04-01 2010-04-01 false Comparable facilities... facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities provided for students of one sex shall be comparable to such facilities provided...

Safety analysis in test facility design

NASA Astrophysics Data System (ADS)

Valk, A.; Jonker, R. J.

1990-09-01

The application of safety analysis techniques as developed in, for example nuclear and petrochemical industry, can be very beneficial in coping with the increasing complexity of modern test facility installations and their operations. To illustrate the various techniques available and their phasing in a project, an overview of the most commonly used techniques is presented. Two case studies are described: the hazard and operability study techniques and safety zoning in relation to the possible presence of asphyxiating atmospheres.

CERT tribal internship program. Final intern report: Lewis Yellowrobe, 1995

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1998-09-01

The purpose of this internship was to present state legislators with the history and an overview of the Department of Energy`s policies towards occupational health and safety during cleanup of nuclear weapons production facilities. The approach used library research and phone and personal interviews to acquire information on DOE policies. This intern report contains the final report to legislators entitled ``Environmental restoration and waste management: Worker health and safety concerns during nuclear facility cleanup.`` It presents the current status of DOE occupational health and safety at production facilities, Congressional intent, past DOE occupational policies, and options for state legislators tomore » use to get involved with DOE policy direction.« less

76 FR 73570 - Pipeline Safety: Miscellaneous Changes to Pipeline Safety Regulations

Federal Register 2010, 2011, 2012, 2013, 2014

2011-11-29

... pipeline facilities to facilitate the removal of liquids and other materials from the gas stream. These... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts... Changes to Pipeline Safety Regulations AGENCY: Pipeline and Hazardous Materials Safety Administration...

Safety in Academic Chemistry Laboratories. Fourth Edition.

ERIC Educational Resources Information Center

American Chemical Society, Washington, DC.

This booklet provides guidelines for safety in the chemical laboratory. Part I, "Guides for Instructors and Administrators," includes safety rules, safety practices and facilities, preparation for emergencies, safety committees, accident reporting, fire insurance, and listings of some hazardous chemicals. Part II, "Student Guide to…

76 FR 15348 - Proposed Extension of the Approval of Information Collection Requirements

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-21

... property to be used for housing migrant agricultural workers shall not permit such housing to be occupied... conducted the housing safety and health inspection is posted at the site of the facility or real property. The certificate attests that the facility or real property meets applicable safety and health...

76 FR 56458 - Proposed Data Collections Submitted for Public Comment and Recommendations

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-13

... Registered Nurse (Infection 6,000 1 5/60 500 Preventionist). 57.101: Facility Contact Information Registered Nurse (Infection 6,000 1 10/60 1,000 Preventionist). 57.103: Patient Safety Component--Annual Registered Nurse (Infection 6,000 1 30/60 3,000 Facility Survey. Preventionist). 57.104: Patient Safety Component...

Laboratory Safety Needs of Kentucky School-Based Agricultural Mechanics Teachers

ERIC Educational Resources Information Center

Saucier, P. Ryan; Vincent, Stacy K.; Anderson, Ryan G.

2014-01-01

The frequency and severity of accidents that occur in the agricultural mechanics laboratory can be reduced when these facilities are managed by educators who are competent in the area of laboratory safety and facility management (McKim & Saucier, 2011). To ensure teachers are technically competent and prepared to manage an agricultural…

10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...

10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...

10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...

10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...

Techniques employed by the NASA White Sands Test Facility to ensure oxygen system component safety

NASA Technical Reports Server (NTRS)

Stradling, J. S.; Pippen, D. L.; Frye, G. W.

1983-01-01

Methods of ascertaining the safety and suitability of a variety of oxygen system components are discussed. Additionally, qualification and batch control requirements for soft goods in oxygen systems are presented. Current oxygen system component qualification test activities in progress at White Sands Test Facility are described.

78 FR 67344 - Sunshine Act Meeting; New Time and Date of Proceeding

Federal Register 2010, 2011, 2012, 2013, 2014

2013-11-12

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting; New Time and Date of Proceeding AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of Public Meeting and Hearing; New Time... the postponement in the Federal Register due to the shutdown. The Board has now decided on a new time...

77 FR 75676 - Standard Review Plan for Review of Fuel Cycle Facility License Applications

Federal Register 2010, 2011, 2012, 2013, 2014

2012-12-21

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0220] Standard Review Plan for Review of Fuel Cycle... Review of a License Application for a Fuel Cycle Facility.'' The NRC is extending the public comment... of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2012...

10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.

Code of Federal Regulations, 2010 CFR

2010-01-01

... assurance program will be implemented; (26) The applicant's organizational structure, allocations or... presents a safety analysis of the structures, systems, and components of the facility as a whole. The final... contain an analysis and evaluation of the major structures, systems, and components of the facility that...

30 CFR 71.500 - Sanitary toilet facilities at surface work sites; installation requirements.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Sanitary toilet facilities at surface work sites; installation requirements. 71.500 Section 71.500 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND...

75 FR 9196 - Letter From Secretary of Energy Accepting Defense Nuclear Facilities Safety Board (Board...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-01

... capability for non- vital laboratory room electrical loads that provides an engineered control to reduce..., approximately two orders of magnitude higher than our evaluation guideline for selecting safety class controls. Approval of the DSA included recognition of weaknesses in the facility's control set and the need to...

77 FR 74587 - Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers

Federal Register 2010, 2011, 2012, 2013, 2014

2012-12-17

... 1625-AA00 Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers AGENCY: Coast Guard, DHS... inbound and outbound grain-shipment vessels involved in commerce with the Columbia Grain facility on the Willamette River in Portland, OR, and the United Grain Corporation facility on the Columbia River in...

Seismic risk management solution for nuclear power plants

DOE PAGES

Coleman, Justin; Sabharwall, Piyush

2014-12-01

Nuclear power plants should safely operate during normal operations and maintain core-cooling capabilities during off-normal events, including external hazards (such as flooding and earthquakes). Management of external hazards to expectable levels of risk is critical to maintaining nuclear facility and nuclear power plant safety. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components). Seismic isolation (SI) is one protective measure showing promise to minimize seismic risk. Current SI designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefitmore » of SI application in the nuclear industry is being recognized and SI systems have been proposed in American Society of Civil Engineer Standard 4, ASCE-4, to be released in the winter of 2014, for light water reactors facilities using commercially available technology. The intent of ASCE-4 is to provide criteria for seismic analysis of safety related nuclear structures such that the responses to design basis seismic events, computed in accordance with this standard, will have a small likelihood of being exceeded. The U.S. nuclear industry has not implemented SI to date; a seismic isolation gap analysis meeting was convened on August 19, 2014, to determine progress on implementing SI in the U.S. nuclear industry. The meeting focused on the systems and components that could benefit from SI. As a result, this article highlights the gaps identified at this meeting.« less

Optimizing Characterization of Site Hydrology in Support of New Reactor Licensing at the U.S. Nuclear Regulatory Commission (Invited)

NASA Astrophysics Data System (ADS)

Nicholson, T. J.; Raione, R.; Ahn, H.; Barnhurst, D.; Giacinto, J.; McBride, M.; Tiruneh, N. D.

2009-12-01

The NRC regulates the civilian use of radioactive materials and facilities in an open and transparent manner. The NRC regulatory criteria are designed to protect human health and safety, and the environment by regulating nuclear facilities. During review of new reactor licensing applications, NRC staff reviews and independently verifies hydrogeologic information submitted by the applicant in several topical areas such as development and testing of Conceptual Site Models (CSM) which may involve perched aquifers; engineered water level fluctuations of surface-water reservoirs; ground-water collector wells and local ground-water uses; design-basis ground-water levels for structural analysis; analysis of scenarios for potential release of radionuclides to the subsurface; deep well injection of effluents; and monitoring to detect radionuclide releases. This information is reviewed in a systematic manner in accordance with NRC requirements and guidance to evaluate safety and environmental impacts and reduce the uncertainties for these impacts. NRC licensing staff is reviewing 14 applications for siting new reactors. Experience gained through these licensing activities has shown the value of using site-specific data to evaluate the CSM and its use to assess design and operational issues. Optimizing the information flow process through a systemically and thorough review process creates efficiencies. Through an iterative process of evaluating various geographical settings and associated ground-water conditions, NRC staff has developed methods to minimize prediction uncertainty through the use of confirmatory analyses performed under conservative, hierarchal approaches.

40 CFR 170.135 - Posted pesticide safety information.

Code of Federal Regulations, 2011 CFR

2011-07-01

..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...

40 CFR 170.135 - Posted pesticide safety information.

Code of Federal Regulations, 2012 CFR

2012-07-01

..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...

40 CFR 170.135 - Posted pesticide safety information.

Code of Federal Regulations, 2014 CFR

2014-07-01

..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...

40 CFR 170.135 - Posted pesticide safety information.

Code of Federal Regulations, 2010 CFR

2010-07-01

..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...

40 CFR 170.135 - Posted pesticide safety information.

Code of Federal Regulations, 2013 CFR

2013-07-01

..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...

49 CFR 193.2189-193.2233 - [Reserved

Code of Federal Regulations, 2010 CFR

2010-10-01

... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Lng Storage Tanks §§ 193.2189-193.2233 [Reserved] ...

49 CFR 193.2121-193.2153 - [Reserved

Code of Federal Regulations, 2010 CFR

2010-10-01

... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Design of Components and Buildings §§ 193.2121-193...

10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

Code of Federal Regulations, 2011 CFR

2011-01-01

... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...

10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

Code of Federal Regulations, 2013 CFR

2013-01-01

... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...

10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

Code of Federal Regulations, 2012 CFR

2012-01-01

... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...

10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

Code of Federal Regulations, 2014 CFR

2014-01-01

... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...

49 CFR 193.2019 - Mobile and temporary LNG facilities.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 49 Transportation 3 2011-10-01 2011-10-01 false Mobile and temporary LNG facilities. 193.2019... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance...

28 CFR 54.410 - Comparable facilities.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Comparable facilities. 54.410 Section 54... in Education Programs or Activities Prohibited § 54.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities...

The Worker Exposure Failure Modes and Effects Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Lee C. Cadwallader

2004-09-01

This paper documents the activities of the US-Japan exchange in the area of personnel safety at magnetic and laser fusion experiments. A near-miss event with a visiting scientist to the US in 1992 was the impetus for forming the Joint Working Group on Fusion Safety. This exchange has been under way for over ten years and has provided many safety insights for both US and Japanese facility personnel at national institutes and at universities. The background and activities of the Joint Working Group are described, including the facilities that have been visited for safety walkthroughs, the participants from both countries,more » and the main safety issues examined during visits. Based on these visits, some operational safety ideas to enhance experiment safety are given. The near-term future plans of the Safety Monitor Joint Working Group are also discussed.« less

The role and working conditions of Movement Science students employed in sport and recreational facilities: An Italian multicenter study.

PubMed

Gallè, Francesca; Di Onofrio, Valeria; Arpesella, Marisa; Bacci, Silvia; Bianco, Antonino; Brandi, Giorgio; Bruno, Stefania; Anastasi, Daniela; Carraro, Elisabetta; Flacco, Maria Elena; Giampaoli, Saverio; Izzotti, Alberto; Leoni, Erica; Bertoncello, Chiara; Minelli, Liliana; Napoli, Christian; Nobile, Carmelo; Pasquarella, Cesira; Liguori, Giorgio; Romano Spica, Vincenzo

2015-01-01

In Italy, students from Movement Science (MS) Degree Courses often work in sport and recreational facilities before graduation. The employment conditions of Movement Science students working in sport/recreational facilities were investigated, and the management and structural features of the facilities were evaluated, including safety policies. Regional differences were also considered. Questionnaires were administered to undergraduate and graduate students (N = 4,217) in 17 Universities. Students' perceptions of the quality of the facilities where they had been employed was evaluated using multivariate analysis. A latent class model with covariates was used to evaluate how variables relating to participants, employment facilities or regions influence their opinions. A high proportion of MS students were employed in sporting facilities (undergraduate level: 33% ; graduate level: 55%), in most cases without any formal employment contracts. Both the structural and hygienic features, as well as the professional knowledge of the staff, were considered good to excellent by the majority of participants (about 70%). Communication of the basic behavioral rules was considered adequate by 61-63% of undergraduate students and 71-75% of graduate students, while nearly half of the participants were dissatisfied with the staff safety training. Correlations between the perceived good structural/hygienic conditions, the presence of regulations and training programs for the staff were investigated. Differences regarding occupational level and safety training among different regions of Italy were also observed. Italian students in Movement Science were easily employed in sport/recreational facilities, but frequently without a formal contract. This is a consequence of the lack of specific regulations in the field of recreational/leisure employment and could have negative implications, especially in terms of safety.

Association between health worker motivation and healthcare quality efforts in Ghana.

PubMed

Alhassan, Robert Kaba; Spieker, Nicole; van Ostenberg, Paul; Ogink, Alice; Nketiah-Amponsah, Edward; de Wit, Tobias F Rinke

2013-08-14

Ghana is one of the sub-Saharan African countries making significant progress towards universal access to quality healthcare. However, it remains a challenge to attain the 2015 targets for the health related Millennium Development Goals (MDGs) partly due to health sector human resource challenges including low staff motivation. This paper addresses indicators of health worker motivation and assesses associations with quality care and patient safety in Ghana. The aim is to identify interventions at the health worker level that contribute to quality improvement in healthcare facilities. The study is a baseline survey of health workers (n = 324) in 64 primary healthcare facilities in two regions in Ghana. Data collection involved quality care assessment using the SafeCare Essentials tool, the National Health Insurance Authority (NHIA) accreditation data and structured staff interviews on workplace motivating factors. The Spearman correlation test was conducted to test the hypothesis that the level of health worker motivation is associated with level of effort by primary healthcare facilities to improve quality care and patient safety. The quality care situation in health facilities was generally low, as determined by the SafeCare Essentials tool and NHIA data. The majority of facilities assessed did not have documented evidence of processes for continuous quality improvement and patient safety. Overall, staff motivation appeared low although workers in private facilities perceived better working conditions than workers in public facilities (P <0.05). Significant positive associations were found between staff satisfaction levels with working conditions and the clinic's effort towards quality improvement and patient safety (P <0.05). As part of efforts towards attainment of the health related MDGs in Ghana, more comprehensive staff motivation interventions should be integrated into quality improvement strategies especially in government-owned healthcare facilities where working conditions are perceived to be the worst.

Infection prevention and control in the design of healthcare facilities.

PubMed

Farrow, Tye S; Black, Stephen M

2009-01-01

The lead paper, "Healthcare-Associated Infections as Patient Safety Indicators," written by Gardam, Lemieux, Reason, van Dijk and Goel, puts forward the design of healthcare facilities as one of many strategies to improve patient safety with respect to healthcare-associated infections. This commentary explores some of the issues in balancing infection prevention and control priorities with other needs and values brought to the design process. This balance is challenged not only by a lack of supporting evidence but also by the superficial nature in which infection prevention and control are often discussed within a design context. For the physical environment to support any patient safety initiative, the design of the processes must be developed in conjunction with that of the physical environment so that compliance can be natural and convenient. Finally, consideration is given to the value of documenting decision-making related to infection prevention and control in facility design and ongoing assessments of existing facilities.

The Department of Energy Nuclear Criticality Safety Program

NASA Astrophysics Data System (ADS)

Felty, James R.

2005-05-01

This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

48 CFR 923.7001 - Nuclear safety.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Nuclear safety. 923.7001... Efficiency, Renewable Energy Technologies, and Occupational Safety Programs 923.7001 Nuclear safety. The DOE regulates the nuclear safety of its major facilities under its own statutory authority derived from the...

75 FR 65151 - Marine Vapor Control Systems

Federal Register 2010, 2011, 2012, 2013, 2014

2010-10-21

...The Coast Guard proposes to increase maritime domain safety by revising existing safety regulations for facility and vessel vapor control systems (VCSs). The proposed changes would make VCS requirements more compatible with new Federal and State environmental requirements, reflect industry advancements in VCS technology, and codify the standards for the design and operation of a VCS at tank barge cleaning facilities. These changes would increase the safety of operations by regulating the design, installation, and use of VCSs, but would not require anyone to install or use VCSs.

Facilities Maintenance in the U.S. Navy

DTIC Science & Technology

1986-01-01

Row’a9IVI s..Nl,I I~de 14. 11111116104 It. safeI MeAI. 5,124 AN (:lgnd) JOHN SMITH I765 IIf Figure 111-1 Work Request is EMIROENCY/SERVICE WORK...Eliminate fire, health and active life of less than 3 years safety hazards o Infrequently or only partially o Patch and reinforce instead used of...safety or health hazards and to permit reactivation within the period prescribed under mobili- zation plans o Surplus facilities a Fliminate fire, safety

76 FR 14590 - Defense Federal Acquisition Regulation Supplement; Safety of Facilities, Infrastructure, and...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-17

... facilities, infrastructure, and equipment that are intended for use by military or civilian personnel of the..., maintenance, or operation of facilities, infrastructure, and equipment for use by DoD military or civilian... facilities. This includes contracts for facilities, infrastructure, and equipment configured for occupancy...

2011 Annual Criticality Safety Program Performance Summary

DOE Office of Scientific and Technical Information (OSTI.GOV)

Andrea Hoffman

The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection,more » an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The TSR limits fuel plate bundles to 1085 grams U-235, which is the maximum loading of an ATR fuel element. The overloaded fuel plate bundle contained 1097 grams U-235 and was assembled under an 1100 gram U-235 limit in 1982. In 2003, the limit was reduced to 1085 grams citing a new criticality safety evaluation for ATR fuel elements. The fuel plate bundle inventories were not checked for compliance prior to implementing the reduced limit. A subsequent review of the NMIS inventory did not identify further violations. Requirements Management - The INL Criticality Safety program is organized and well documented. The source requirements for the INL Criticality Safety Program are from 10 CFR 830.204, DOE Order 420.1B, Chapter III, 'Nuclear Criticality Safety,' ANSI/ANS 8-series Industry Standards, and DOE Standards. These source requirements are documented in LRD-18001, 'INL Criticality Safety Program Requirements Manual.' The majority of the criticality safety source requirements are contained in DOE Order 420.1B because it invokes all of the ANSI/ANS 8-Series Standards. DOE Order 420.1B also invokes several DOE Standards, including DOE-STD-3007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities.' DOE Order 420.1B contains requirements for DOE 'Heads of Field Elements' to approve the criticality safety program and specific elements of the program, namely, the qualification of criticality staff and the method for preparing criticality safety evaluations. This was accomplished by the approval of SAR-400, 'INL Standardized Nuclear Safety Basis Manual,' Chapter 6, 'Prevention of Inadvertent Criticality.' Chapter 6 of SAR-400 contains sufficient detail and/or reference to the specific DOE and contractor documents that adequately describe the INL Criticality Safety Program per the elements specified in DOE Order 420.1B. The Safety Evaluation Report for SAR-400 specifically recognizes that the approval of SAR-400 approves the INL Criticality Safety Program. No new source requirements were released in 2011. A revision to LRD-18001 is planned for 2012 to clarify design requirements for criticality alarms. Training - Criticality Safety Engineering has developed training and provides training for many employee positions, including fissionable material handlers, facility managers, criticality safety officers, firefighters, and criticality safety engineers. Criticality safety training at the INL is a program strength. A revision to the training module developed in 2010 to supplement MFC certified fissionable material handlers (operators) training was prepared and presented in August of 2011. This training, 'Applied Science of Criticality Safety,' builds upon existing training and gives operators a better understanding of how their criticality controls are derived. Improvements to 00INL189, 'INL Criticality Safety Principles' are planned for 2012 to strengthen fissionable material handler training.« less

The assessment of exploitation process of power for access control system

NASA Astrophysics Data System (ADS)

Wiśnios, Michał; Paś, Jacek

2017-10-01

The safety of public utility facilities is a function not only of effectiveness of the electronic safety systems, used for protection of property and persons, but it also depends on the proper functioning of their power supply systems. The authors of the research paper analysed the power supply systems, which are used in buildings for the access control system that is integrated with the closed-circuit TV. The Access Control System is a set of electronic, electromechanical and electrical devices and the computer software controlling the operation of the above-mentioned elements, which is aimed at identification of people, vehicles allowed to cross the boundary of the reserved area, to prevent from crossing the reserved area and to generate the alarm signal informing about the attempt of crossing by an unauthorised entity. The industrial electricity with appropriate technical parameters is a basis of proper functioning of safety systems. Only the electricity supply to the systems is not equivalent to the operation continuity provision. In practice, redundant power supply systems are used. In the carried out reliability analysis of the power supply system, various power circuits of the system were taken into account. The reliability and operation requirements for this type of system were also included.

Findings of Phlebotomy Practices in Kenya in 2010: Need for Action

PubMed Central

Kimani, Daniel; Kamau, Rachel; Gadde, Renuka; Selenic, Dejana; Maina, Stephen; Marum, Lawrence; Hongjiang, Gao; Mwalili, Samuel; Marfin, Anthony; Mwangi, Jane

2016-01-01

Background. Phlebotomy, a commonly performed medical procedure in healthcare, is essential for disease diagnosis and patient management. However, poorly performed phlebotomy can compromise patient safety, healthcare worker (HCW) safety, and specimen quality. We carried out a study between June and July 2010 to assess knowledge, quality and safety of phlebotomy before implementation of a public-private partnership between Becton, Dickinson and Company and the US President's Emergency Plan for AIDS Relief. Methods. This was a cross-sectional observational study in 8 healthcare facilities within 4 regions of Kenya. HCWs were observed conducting venous and capillary blood collections, and pre- and posttests were offered during HCW training. Results. Of 283 blood samples obtained, 194 were venous draws conducted by 72 HCWs and 89 were capillary draws performed by 33 HCWs. Based on 12 preset quality-associated criteria, none of the 194 observed phlebotomies met the standard. In total, 91 HCWs were trained in phlebotomy. The mean knowledge increase between pre- and posttraining test was 41%, ranging from 39% to 45% (95% confidence interval, 29.3%–53.5%; P < .001). Conclusions. Inadequate knowledge and imperfect phlebotomy procedures were noted. This formed the basis for the safe phlebotomy partnership to address these deficiencies. To ensure sustainability, safe phlebotomy practices were integrated into preservice training. PMID:27025699

49 CFR 25.410 - Comparable facilities.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 49 Transportation 1 2011-10-01 2011-10-01 false Comparable facilities. 25.410 Section 25.410... Education Programs or Activities Prohibited § 25.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities provided for students...