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

Cold Vacuum Drying facility civil structural system design description (SYS 06)

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

PITKOFF, C.C.

This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document.

School Safety and Security.

ERIC Educational Resources Information Center

California State Dept. of Education, Sacramento.

This document offers additional guidelines for school facilities in California in the areas of safety and security, lighting, and cleanliness. It also offers a description of technology resources available on the World Wide Web. On the topic of safety and security, the document offers guidelines in the areas of entrances, doors, and controlled…

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

Waste Sampling & Characterization Facility (WSCF) Complex Safety Analysis

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

MELOY, R.T.

2002-04-01

This document was prepared to analyze the Waste Sampling and Characterization Facility for safety consequences by: Determining radionuclide and highly hazardous chemical inventories; Comparing these inventories to the appropriate regulatory limits; Documenting the compliance status with respect to these limits; and Identifying the administrative controls necessary to maintain this status. The primary purpose of the Waste Sampling and Characterization Facility (WSCF) is to perform low-level radiological and chemical analyses on various types of samples taken from the Hanford Site. These analyses will support the fulfillment of federal, Washington State, and Department of Energy requirements.

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7

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

Not Available

1994-04-01

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining themore » facility and executing the mission of the High-Level Waste Storage Tank Farms.« less

Safety analysis report for the Waste Storage Facility. Revision 2

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

Bengston, S.J.

1994-05-01

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

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...

Nuclear criticality safety assessment of the low level radioactive waste disposal facility trenches

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

Kahook, S.D.

1994-04-01

Results of the analyses performed to evaluate the possibility of nuclear criticality in the Low Level Radioactive Waste Disposal Facility (LLRWDF) trenches are documented in this report. The studies presented in this document are limited to assessment of the possibility of criticality due to existing conditions in the LLRWDF. This document does not propose nor set limits for enriched uranium (EU) burial in the LLRWDF and is not a nuclear criticality safety evaluation nor analysis. The calculations presented in the report are Level 2 calculations as defined by the E7 Procedure 2.31, Engineering Calculations.

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

Facility effluent monitoring plan for the plutonium uranium extraction facility

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

Wiegand, D.L.

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

Research, development, and implementation of pedestrian safety facilities in the United Kingdom

DOT National Transportation Integrated Search

1999-12-01

This report is one in a series of pedestrian safety synthesis reports prepared for the Federal Highway Administration to document pedestrian safety in other countries. This report reviews recent research on pedestrian safety carried out in the United...

State Requirements for Educational Facilities, 1997.

ERIC Educational Resources Information Center

Florida State Dept. of Education, Tallahassee. Office of Educational Facilities.

This document updates Florida's deregulation of construction of educational facilities guidelines, while keeping as the primary focus the safety of the students in pre-K through community college facilities. Organized by the sequence of steps required in the facilities procurement process, it covers general definitions, property…

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.

Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

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

Beaulieu, R. A.

The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE-STD-3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do notmore » involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.« 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

Occupational Safety Review of High Technology Facilities

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

Lee Cadwallader

2005-01-31

This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.

76 FR 7628 - Petition for Waiver of Compliance

Federal Register 2010, 2011, 2012, 2013, 2014

2011-02-10

... constructed by European manufacturer and meet European safety standards for crashworthiness and related safety... Engineering Task Force report to the Passenger Safety Working Group of the Railroad Safety Advisory Committee... business hours (9 a.m.-5 p.m.) at the above facility. All documents in the public docket are also available...

Seismic assessment of Technical Area V (TA-V).

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

Medrano, Carlos S.

The Technical Area V (TA-V) Seismic Assessment Report was commissioned as part of Sandia National Laboratories (SNL) Self Assessment Requirement per DOE O 414.1, Quality Assurance, for seismic impact on existing facilities at Technical Area-V (TA-V). SNL TA-V facilities are located on an existing Uniform Building Code (UBC) Seismic Zone IIB Site within the physical boundary of the Kirtland Air Force Base (KAFB). The document delineates a summary of the existing facilities with their safety-significant structure, system and components, identifies DOE Guidance, conceptual framework, past assessments and the present Geological and Seismic conditions. Building upon the past information and themore » evolution of the new seismic design criteria, the document discusses the potential impact of the new standards and provides recommendations based upon the current International Building Code (IBC) per DOE O 420.1B, Facility Safety and DOE G 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and Non-Nuclear Facilities.« less

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.

Standards for material handling and facilities equipment proofload testing

NASA Technical Reports Server (NTRS)

Bonn, S. P.

1970-01-01

Document provides information on verifying the safety of material handling and facilities equipment /MH/FE/, ranging from monorail systems to ladders and non-powered mobile equipment. Seven catagories of MH/FE equipment are defined.

40 CFR 265.16 - Personnel training.

Code of Federal Regulations, 2010 CFR

2010-07-01

... successfully complete a program of classroom instruction or on-the-job training that teaches them to perform... facility employees that receive emergency response training pursuant to Occupational Safety and Health... documents and records at the facility: (1) The job title for each position at the facility related to...

Office of Safety and Mission Assurance Review Report

NASA Technical Reports Server (NTRS)

2000-01-01

This document summarizes questions and concerns raised during the 1999 IV&V Facility's Annual Review Presentation to the Office of Safety and Mission Assurance (OSMA). Recommendations are provided for issues and action items identified.

Test Plan for the Wake Steering Experiment at the Scaled Wind Farm Technology (SWiFT) Facility.

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

Naughton, Brian Thomas

This document is a test plan describing the objectives, configuration, procedures, reporting, roles, and responsibilities for conducting the joint Sandia National Laboratories and National Renewable Energy Laboratory Wake Steering Experiment at the Sandia Scaled Wind Farm Technology (SWiFT) facility near Lubbock, Texas in 2016 and 2017 . The purpose of this document is to ensure the test objectives and procedures are sufficiently detailed such that al l involved personnel are able to contribute to the technical success of the test. This document is not intended to address safety explicitly which is addressed in a separate document listed in the referencesmore » titled Sandia SWiFT Facility Site Operations Manual . Both documents should be reviewed by all test personnel.« 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

Additional nuclear criticality safety calculations for small-diameter containers

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

Hone, M.J.

This report documents additional criticality safety analysis calculations for small diameter containers, which were originally documented in Reference 1. The results in Reference 1 indicated that some of the small diameter containers did not meet the criteria established for criticality safety at the Portsmouth facility (K{sub eff} +2{sigma}<.95) when modeled under various contingency assumptions of reflection and moderation. The calculations performed in this report reexamine those cases which did not meet the criticality safety criteria. In some cases, unnecessary conservatism is removed, and in other cases mass or assay limits are established for use with the respective containers.

76 FR 387 - Atomic Safety and Licensing Board; AREVA Enrichment Services, LLC (Eagle Rock Enrichment Facility)

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-04

... and Licensing Board; AREVA Enrichment Services, LLC (Eagle Rock Enrichment Facility) December 17, 2010... construction and operation of a gas centrifuge uranium enrichment facility--denoted as the Eagle Rock... site at http://www.nrc.gov/materials/fuel-cycle-fac/arevanc.html . These and other documents relating...

76 FR 54531 - Pipeline Safety: Potential for Damage to Pipeline Facilities Caused by the Passage of Hurricanes

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-01

... production and processing is prone to disruption by hurricanes. In 2005, Hurricanes Katrina and Rita caused... Hurricanes AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice... the passage of Hurricanes. ADDRESSES: This document can be viewed on the Office of Pipeline Safety...

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...

Nuclear Criticality Safety Data Book

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

Hollenbach, D. F.

The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

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

Reference Mission Operational Analysis Document (RMOAD) for the Life Sciences Research Facilities

NASA Technical Reports Server (NTRS)

1987-01-01

The space station will be constructed during the next decade as an orbiting, low-gravity, permanent facility. The facility will provide a multitude of research opportunities for many different users. The pressurized research laboratory will allow life scientists to study the effects of long-term exposure to microgravity on humans, animals, and plants. The results of these studies will increase our understanding of this foreign environment on basic life processes and ensure the safety of man's long-term presence in space. This document establishes initial operational requirements for the use of the Life Sciences Research Facility (LSRF) during its construction.

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

Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

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

DAVIS, S.J.

2000-05-25

This document identifies critical characteristics of components to be dedicated for use in Safety Class (SC) or Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common radiation area monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF), in safety class, safety significant systems. System modifications are to be performed in accordance with the instructions provided on ECN 658230. Components for this change are commercially available and interchangeablemore » with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications.« less

TA-55 change control manual

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

Blum, T.W.; Selvage, R.D.; Courtney, K.H.

This manual is the guide for initiating change at the Plutonium Facility, which handles the processing of plutonium as well as research on plutonium metallurgy. It describes the change and work control processes employed at TA-55 to ensure that all proposed changes are properly identified, reviewed, approved, implemented, tested, and documented so that operations are maintained within the approved safety envelope. All Laboratory groups, their contractors, and subcontractors doing work at TA-55 follow requirements set forth herein. This manual applies to all new and modified processes and experiments inside the TA-55 Plutonium Facility; general plant project (GPP) and line itemmore » funded construction projects at TA-55; temporary and permanent changes that directly or indirectly affect structures, systems, or components (SSCs) as described in the safety analysis, including Facility Control System (FCS) software; and major modifications to procedures. This manual does not apply to maintenance performed on process equipment or facility SSCs or the replacement of SSCs or equipment with documented approved equivalents.« less

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

A Technology Solution Strengthens Comprehensive Environmental Management

DTIC Science & Technology

2012-05-23

General Navigation  Chemical Approval Example  NEPA Coordination Example  Safety PPE Example  Summary Marine Corps Support Facility...coordination, completion and documentation through automated workflows of various business processes  Chemical Approval  NEPA Coordination  Safety ...Completion Diagram Government Employee/M CMC MCMC Chemical Manager MCMC HS&E Specialist IMO Chemical Safety Specialist IMO Chemical Environmental

Tank waste remediation system nuclear criticality safety program management review

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

BRADY RAAP, M.C.

1999-06-24

This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999.

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

Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

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

Not Available

1989-06-01

The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportationmore » safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included.« less

Spent nuclear fuel project cold vacuum drying facility operations manual

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

IRWIN, J.J.

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of themore » CVDF until the CVDF final ORR is approved.« less

Human factors engineering in oil and gas--a review of industry guidance.

PubMed

Robb, Martin; Miller, Gerald

2012-01-01

Oil and gas exploration and production activities are carried out in hazardous environments in many parts of the world. Recent events in the Gulf of Mexico highlight those risks and underline the importance of considering human factors during facility design. Ergonomic factors such as machinery design, facility and accommodation layout and the organization of work activities have been systematically considered over the past twenty years on a limited number of offshore facility design projects to a) minimize the occupational risks to personnel, b) support operations and maintenance tasks and c) improve personnel wellbeing. During this period, several regulators and industry bodies such as the American Bureau of Shipping (ABS), the American Society of Testing and Materials (ASTM), the UK's Health and Safety Executive (HSE), Oil and Gas Producers (OGP), and Norway's Petroleum Safety Authority (PSA) have developed specific HFE design standards and guidance documents for the application of Human Factors Engineering (HFE) to the design and operation of Oil and Gas projects. However, despite the existence of these guidance and recommended design practise documents, and documented proof of their value in enhancing crew safety and efficiency, HFE is still not well understood across the industry and application across projects is inconsistent. This paper summarizes the key Oil and Gas industry bodies' HFE guidance documents, identifies recurring themes and current trends in the use of these standards, provides examples of where and how these HFE standards have been used on past major offshore facility design projects, and suggests criteria for selecting the appropriate HFE strategy and tasks for future major oil and gas projects. It also provides a short history of the application of HFE to the offshore industry, beginning with the use of ASTM F 1166 to a major operator's Deepwater Gulf of Mexico facility in 1990 and the application of HFE to diverse world regions. This latter point highlights the need to consider user populations when selecting HFE design criteria, an aspect strongly emphasized in current industry guidance.

Environmental Management Guide for Educational Facilities

ERIC Educational Resources Information Center

APPA: Association of Higher Education Facilities Officers, 2017

2017-01-01

Since 1996, APPA and CSHEMA, the Campus Safety Health and Environmental Management Association, have collaborated to produce guidance documents to help educational facilities get ahead of the moving target that is environmental compliance. This new 2017 edition will help you identify which regulations pertain to your institution, and assist in…

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...

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

Data Quality Objectives for Regulatory Requirements for Hazardous and Radioactive Air Emissions Sampling and Analysis

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

MULKEY, C.H.

1999-07-06

This document describes the results of the data quality objective (DQO) process undertaken to define data needs for state and federal requirements associated with toxic, hazardous, and/or radiological air emissions under the jurisdiction of the River Protection Project (RPP). Hereafter, this document is referred to as the Air DQO. The primary drivers for characterization under this DQO are the regulatory requirements pursuant to Washington State regulations, that may require sampling and analysis. The federal regulations concerning air emissions are incorporated into the Washington State regulations. Data needs exist for nonradioactive and radioactive waste constituents and characteristics as identified through themore » DQO process described in this document. The purpose is to identify current data needs for complying with regulatory drivers for the measurement of air emissions from RPP facilities in support of air permitting. These drivers include best management practices; similar analyses may have more than one regulatory driver. This document should not be used for determining overall compliance with regulations because the regulations are in constant change, and this document may not reflect the latest regulatory requirements. Regulatory requirements are also expected to change as various permits are issued. Data needs require samples for both radionuclides and nonradionuclide analytes of air emissions from tanks and stored waste containers. The collection of data is to support environmental permitting and compliance, not for health and safety issues. This document does not address health or safety regulations or requirements (those of the Occupational Safety and Health Administration or the National Institute of Occupational Safety and Health) or continuous emission monitoring systems. This DQO is applicable to all equipment, facilities, and operations under the jurisdiction of RPP that emit or have the potential to emit regulated air pollutants.« less

K-Basins S/RIDS

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

Watson, D.J.

1995-09-22

The Standards/Requirements Identification Document(S/RID) is a list of the Environmental, Safety, and Health (ES&H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility

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

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.

K-Basins S/RIDS

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

Watson, D.J.

The Standards/Requirements Identification Document (S/RID) is a list of the Environmental, Safety, and Health (ES{ampersand}H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility.

PSD Source Classification for Safety Kleen's Lubricating Oil Recovery Facility

EPA Pesticide Factsheets

This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

Medical surveillance and programs on industrial hygiene at RCRA facilities

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

Murphy, T.E.

1994-12-31

Some special areas where much progress in industrial hygiene and safety has been made in the past few years are; training, personal protective equipment, uniforms, personal monitoring, area monitoring, and medical surveillance. Before one can begin to construct programs for worker protection, some knowledge of potential exposures must be gained. The best place to start is the Waste Analysis Plan, and the list of wastes that a particular site is authorized to receive. Waste Codes are listed within a facility`s Part A and Part B permits. Actual facility receipt of wastes are well documented within Load Records and other documentation.more » A facility`s training program forms the heart of a health and safety program. Every TSD facility should have developed a matrix of job titles and required training. Every facility must also make a commitment to providing a wide range of personal protective equipment, including a wide array of disposables. Some facilities will benefit from the occasional use of the newer respirator quantitative fit-testing devices. All facilities are urged to rent or borrow this type of equipment periodically. Quantitative respirator fit-testers are capable of revealing important deficiencies in a respirator program. Providing uniforms is a newer means of protecting workers. The use of uniforms is an effective means for addressing the idea of carry-home-waste. The use of disposables including boots, must be integrated into a Uniform Program if the program is to be effective. In addition, employees must strictly understand that uniforms must not leave the facility at any time, including lunch time.« less

School Facilities Report: The Results of a Statewide Survey To Determine the Physical Condition and Capacity of Wisconsin's Public Schools.

ERIC Educational Resources Information Center

Soldner, Bob

This report documents survey results in three areas concerning Wisconsin public schools: data on the physical structure and mechanical features of the school building; data on school safety issues; and information on the educational appropriateness and suitability of the school buildings. Appendices provide the school facility survey; and lists of…

Calibration Laboratory Capabilities Listing as of April 2009

NASA Technical Reports Server (NTRS)

Kennedy, Gary W.

2009-01-01

This document reviews the Calibration Laboratory capabilities for various NASA centers (i.e., Glenn Research Center and Plum Brook Test Facility Kennedy Space Center Marshall Space Flight Center Stennis Space Center and White Sands Test Facility.) Some of the parameters reported are: Alternating current, direct current, dimensional, mass, force, torque, pressure and vacuum, safety, and thermodynamics parameters. Some centers reported other parameters.

Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

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

Culbert, W.H.

1985-10-01

This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliancemore » with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.« less

The use of NUREGs 1199 and 1200 in the Illinois LLW licensing program

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

Klinger, J.G.; Harmon, D.F.

1991-12-31

This paper will describe how the LLW licensing staff of the Illinois Department of Nuclear Safety used NRC`s NUREG 1199, NUREG 1200, NUREG 1300 and Regulatory Guide 4.18 in its licensing program for reviewing and evaluating a LLW disposal facility license application. The paper will discuss how Illinois guidance documents were prepared based on modifications made to these NRC documents which were necessary to take into account site and facility specific considerations, as well as changes required by Illinois statutes and regulatory codes. The paper will review the recent revisions (January 1991) to NUREG 1199 and 1200 and the importancemore » of these revisions. The paper will also discuss recommended modifications to these NRC documents and provide an update on the status of the Department`s review and evaluation of an application for a license to site, construct and operate a LLW disposal facility in Illinois.« less

[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.

Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

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

NONE

1994-10-01

This document is the second volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, exceptmore » for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of failure modes and effects analysis; accident analysis; operational safety requirements; quality assurance program; ES&H management program; environmental, safety, and health systems critical to safety; summary of waste-management program; environmental monitoring program; facility expansion, decontamination, and decommissioning; summary of emergency response plan; summary plan for employee training; summary plan for operating procedures; glossary; and appendices A and B.« less

Supporting calculations and assumptions for use in WESF safetyanalysis

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

Hey, B.E.

This document provides a single location for calculations and assumptions used in support of Waste Encapsulation and Storage Facility (WESF) safety analyses. It also provides the technical details and bases necessary to justify the contained results.

76 FR 66723 - Food Safety Modernization Act Domestic and Foreign Facility Reinspections, Recall, and Importer...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-27

...The Food and Drug Administration (FDA) is extending the comment period to November 30, 2011, for the notice entitled, ``Food Safety Modernization Act Domestic and Foreign Facility Reinspections, Recall, and Importer Reinspection User Fee Rates for Fiscal Year 2012'' that appeared in the Federal Register of August 1, 2011 (76 FR 45820). In that document, FDA announced the establishment of a docket to obtain comments that would be considered in establishing the fee rates for fiscal year (FY) 2013. In particular, the Agency provided the current FY 2012 fees and requested public comments to the document and intends to consider such comments, as well as experience and additional data gained in implementing these fees in FY 2012, in establishing the fee rates for FY 2013. The Agency is taking this action in response to requests for an extension to allow interested persons additional time to submit comments.

Organizational safety culture/climate and worker compliance with hazardous drug guidelines: lessons from the blood-borne pathogen experience.

PubMed

McDiarmid, Melissa A; Condon, Marian

2005-07-01

The health risks posed to health care workers (HCW) handling antineoplastic and other hazardous drugs (HDs) are well established. However, despite nearly 20 years of professional practice standards, compliance with safe handling procedures is poor. We present documentation of undercompliance with recommended safety procedures for HDs. Then, we examine a similar problem, HCW compliance with blood-borne pathogen universal precautions (UP) and its partial solution tied to the strength of a facility's safety culture. Lessons learned here may be applicable to the HD issue. It is proposed that analyzing a facility's safety culture may enlarge our understanding of the barriers contributing to HD under-compliance and suggest strategies to improve it. The Safety Culture paradigm offers many targets for intervention to enhance and promote worker compliance with safe HD handling practices thus mitigating internal exposure.

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

Safety analysis report for packaging (onsite) multicanister overpack cask

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

Edwards, W.S.

1997-07-14

This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the MUlticanister Overpack (MCO) and MCO Cask for a highway route controlled quantity, Type B fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.

Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

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

DAVIS, S.J.

2000-12-28

This document identifies critical characteristics of components to be dedicated for use in Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common, radiation area, monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF) for use in safety significant systems. System modifications are to be performed in accordance with the approved design. Components for this change are commercially available and interchangeable with the existing alarm configuration This documentmore » focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications.« less

Hazard Analysis for Building 34 Vacuum Glove Box Assembly

NASA Technical Reports Server (NTRS)

Meginnis, Ian

2014-01-01

One of the characteristics of an effective safety program is the recognition and control of hazards before mishaps or failures occur. Conducting potentially hazardous tests necessitates a thorough hazard analysis in order to prevent injury to personnel, and to prevent damage to facilities and equipment. The primary purpose of this hazard analysis is to define and address the potential hazards and controls associated with the Building 34 Vacuum Glove Box Assembly, and to provide the applicable team of personnel with the documented results. It is imperative that each member of the team be familiar with the hazards and controls associated with his/her particular tasks, assignments and activities while interfacing with facility test systems, equipment and hardware. In fulfillment of the stated purposes, the goal of this hazard analysis is to identify all hazards that have the potential to harm personnel, damage the facility or its test systems or equipment, test articles, Government or personal property, or the environment. This analysis may also assess the significance and risk, when applicable, of lost test objectives when substantial monetary value is involved. The hazards, causes, controls, verifications, and risk assessment codes have been documented on the hazard analysis work sheets in Appendix A of this document. The preparation and development of this report is in accordance with JPR 1700.1, "JSC Safety and Health Handbook" and JSC 17773 Rev D "Instructions for Preparation of Hazard Analysis for JSC Ground Operations".

Defense Nuclear Facilities Safety Board: Improvements Needed to Strengthen Internal Control and Promote Transparency

DTIC Science & Technology

2015-01-01

results of those steps. GAO reviewed relevant federal laws, regulations , and guidance; analyzed DNFSB documents, including records of internal...agencies’ regulations on Sunshine Act meetings.11 We also interviewed a representative of the Sunlight Foundation, an organization focused on...Secretary’s role as operator and regulator of DOE’s defense nuclear facilities—to ensure adequate protection of public health and safety at these

Functions and requirements for tank farm restoration and safe operations, Project W-314. Revision 3

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

Garrison, R.C.

1995-02-01

This Functions and Requirements document (FRD) establishes the basic performance criteria for Project W-314, in accordance with the guidance outlined in the letter from R.W. Brown, RL, to President, WHC, ``Tank Waste Remediation System (TWRS) Project Documentation Methodology,`` 94-PRJ-018, dated 3/18/94. The FRD replaces the Functional Design Criteria (FDC) as the project technical baseline documentation. Project W-314 will improve the reliability of safety related systems, minimize onsite health and safety hazards, and support waste retrieval and disposal activities by restoring and/or upgrading existing Tank Farm facilities and systems. The scope of Project W-314 encompasses the necessary restoration upgrades of themore » Tank Farms` instrumentation, ventilation, electrical distribution, and waste transfer systems.« less

Manned space flight nuclear system safety. Volume 3: Reactor system preliminary nuclear safety analysis. Part 1: Reference Design Document (RDD)

NASA Technical Reports Server (NTRS)

1972-01-01

The Reference Design Document, of the Preliminary Safety Analysis Report (PSAR) - Reactor System provides the basic design and operations data used in the nuclear safety analysis of the Rector Power Module as applied to a Space Base program. A description of the power module systems, facilities, launch vehicle and mission operations, as defined in NASA Phase A Space Base studies is included. Each of two Zirconium Hydride Reactor Brayton power modules provides 50 kWe for the nominal 50 man Space Base. The INT-21 is the prime launch vehicle. Resupply to the 500 km orbit over the ten year mission is provided by the Space Shuttle. At the end of the power module lifetime (nominally five years), a reactor disposal system is deployed for boost into a 990 km high altitude (long decay time) earth orbit.

Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 3

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

LORENZ, B.D.

In February 1995, the US Department of Energy (DOE) approved the Spent Nuclear Fuel (SNF) Project's ''Path Forward'' recommendation for resolution of the safety and environmental concerns associated with the deteriorating SNF stored in the Hanford Site's K Basins (Hansen 1995). The recommendation included an aggressive series of projects to design, construct, and operate systems and facilitates to permit the safe retrieval, packaging, transport, conditions, and interim storage of the K Basins' SNF. The facilities are the Cold VAcuum Drying Facility (CVDF) in the 100 K Area of the Hanford Site and the Canister Storage building (CSB) in the 200more » East Area. The K Basins' SNF is to be cleaned, repackaged in multi-canister overpacks (MCOs), removed from the K Basins, and transported to the CVDF for initial drying. The MCOs would then be moved to the CSB and weld sealed (Loscoe 1996) for interim storage (about 40 years). One of the major tasks associated with the initial Path Forward activities is the development and maintenance of the safety documentation. In addition to meeting the construction needs for new structures, the safety documentation for each must be generated.« less

Plutonium storage criteria

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

Chung, D.; Ascanio, X.

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less thanmore » 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.« less

Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

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

NONE

1994-10-01

This document is the first volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, exceptmore » for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of an introduction, summary/conclusion, site description and assessment, description of facility, and description of operation.« 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

10 CFR 1707.201 - General prohibition.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false General prohibition. 1707.201 Section 1707.201 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.201 General prohibition. No...

10 CFR 1707.201 - General prohibition.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false General prohibition. 1707.201 Section 1707.201 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.201 General prohibition. No...

10 CFR 1707.206 - Final determination.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Final determination. 1707.206 Section 1707.206 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.206 Final determination. The...

10 CFR 1707.201 - General prohibition.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false General prohibition. 1707.201 Section 1707.201 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.201 General prohibition. No...

10 CFR 1707.206 - Final determination.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Final determination. 1707.206 Section 1707.206 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.206 Final determination. The...

10 CFR 1707.206 - Final determination.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Final determination. 1707.206 Section 1707.206 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.206 Final determination. The...

10 CFR 1707.206 - Final determination.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Final determination. 1707.206 Section 1707.206 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.206 Final determination. The...

10 CFR 1707.201 - General prohibition.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false General prohibition. 1707.201 Section 1707.201 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.201 General prohibition. No...

10 CFR 1707.206 - Final determination.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Final determination. 1707.206 Section 1707.206 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.206 Final determination. The...

10 CFR 1707.201 - General prohibition.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false General prohibition. 1707.201 Section 1707.201 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.201 General prohibition. No...

Age Learning Factors Affecting Pilot Education.

ERIC Educational Resources Information Center

Torbert, Brison

This document, intended for pilot education and flight safety specialists, consists chiefly of a review of the literature on physiological factors that affect pilot education and an examination of environmental factors that should be scrutinized in order to improve the effectiveness of aviation learning facilities. The physiological factors…

75 FR 52996 - Areva Enrichment Services, LLC (Eagle Rock Enrichment Facility); Notice of Atomic Safety and...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-30

... correspondence, documents, and other materials shall continue to be filed in accordance with the NRC E-Filing rule. See 10 CFR 2.302 et seq. Issued at Rockville, Maryland, this 24th day of August 2010. E. Roy...

Manual for Public School Facilities Fire Prevention and Fire Inspections. [Revised].

ERIC Educational Resources Information Center

New York State Education Dept., Albany.

Designed to provide instruction for New York State inspectors and school administrators completing the annual "Fire Safety Report," this document provides information regarding: (1) the Regulation and Code requirements; (2) inspection and enforcement processes; (3) disputes and procedures for appeal; and (4) financial considerations…

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.

Proposed Risk-Informed Seismic Hazard Periodic Reevaluation Methodology for Complying with DOE Order 420.1C

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

Kammerer, Annie

Department of Energy (DOE) nuclear facilities must comply with DOE Order 420.1C Facility Safety, which requires that all such facilities review their natural phenomena hazards (NPH) assessments no less frequently than every ten years. The Order points the reader to Standard DOE-STD-1020-2012. In addition to providing a discussion of the applicable evaluation criteria, the Standard references other documents, including ANSI/ANS-2.29-2008 and NUREG-2117. These documents provide supporting criteria and approaches for evaluating the need to update an existing probabilistic seismic hazard analysis (PSHA). All of the documents are consistent at a high level regarding the general conceptual criteria that should bemore » considered. However, none of the documents provides step-by-step detailed guidance on the required or recommended approach for evaluating the significance of new information and determining whether or not an existing PSHA should be updated. Further, all of the conceptual approaches and criteria given in these documents deal with changes that may have occurred in the knowledge base that might impact the inputs to the PSHA, the calculated hazard itself, or the technical basis for the hazard inputs. Given that the DOE Order is aimed at achieving and assuring the safety of nuclear facilities—which is a function not only of the level of the seismic hazard but also the capacity of the facility to withstand vibratory ground motions—the inclusion of risk information in the evaluation process would appear to be both prudent and in line with the objectives of the Order. The purpose of this white paper is to describe a risk-informed methodology for evaluating the need for an update of an existing PSHA consistent with the DOE Order. While the development of the proposed methodology was undertaken as a result of assessments for specific SDC-3 facilities at Idaho National Laboratory (INL), and it is expected that the application at INL will provide a demonstration of the methodology, there is potential for general applicability to other facilities across the DOE complex. As such, both a general methodology and a specific approach intended for INL are described in this document. The general methodology proposed in this white paper is referred to as the “seismic hazard periodic review methodology,” or SHPRM. It presents a graded approach for SDC-3, SDC-4 and SDC-5 facilities that can be applied in any risk-informed regulatory environment by once risk-objectives appropriate for the framework are developed. While the methodology was developed for seismic hazard considerations, it can also be directly applied to other types of natural hazards.« less

Proposed Risk-Informed Seismic Hazard Periodic Reevaluation Methodology for Complying with DOE Order 420.1C

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

Kammerer, Annie

Department of Energy (DOE) nuclear facilities must comply with DOE Order 420.1C Facility Safety, which requires that all such facilities review their natural phenomena hazards (NPH) assessments no less frequently than every ten years. The Order points the reader to Standard DOE-STD-1020-2012. In addition to providing a discussion of the applicable evaluation criteria, the Standard references other documents, including ANSI/ANS-2.29-2008 and NUREG-2117. These documents provide supporting criteria and approaches for evaluating the need to update an existing probabilistic seismic hazard analysis (PSHA). All of the documents are consistent at a high level regarding the general conceptual criteria that should bemore » considered. However, none of the documents provides step-by-step detailed guidance on the required or recommended approach for evaluating the significance of new information and determining whether or not an existing PSHA should be updated. Further, all of the conceptual approaches and criteria given in these documents deal with changes that may have occurred in the knowledge base that might impact the inputs to the PSHA, the calculated hazard itself, or the technical basis for the hazard inputs. Given that the DOE Order is aimed at achieving and assuring the safety of nuclear facilities—which is a function not only of the level of the seismic hazard but also the capacity of the facility to withstand vibratory ground motions—the inclusion of risk information in the evaluation process would appear to be both prudent and in line with the objectives of the Order. The purpose of this white paper is to describe a risk-informed methodology for evaluating the need for an update of an existing PSHA consistent with the DOE Order. While the development of the proposed methodology was undertaken as a result of assessments for specific SDC-3 facilities at Idaho National Laboratory (INL), and it is expected that the application at INL will provide a demonstration of the methodology, there is potential for general applicability to other facilities across the DOE complex. As such, both a general methodology and a specific approach intended for INL are described in this document. The general methodology proposed in this white paper is referred to as the “seismic hazard periodic review methodology,” or SHPRM. It presents a graded approach for SDC-3, SDC-4 and SDC-5 facilities that can be applied in any risk-informed regulatory environment once risk-objectives appropriate for the framework are developed. While the methodology was developed for seismic hazard considerations, it can also be directly applied to other types of natural hazards.« less

SLUDGE TREATMENT PROJECT KOP CONCEPTUAL DESIGN CONTROL DECISION REPORT

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

CARRO CA

2010-03-09

This control decision addresses the Knock-Out Pot (KOP) Disposition KOP Processing System (KPS) conceptual design. The KPS functions to (1) retrieve KOP material from canisters, (2) remove particles less than 600 {micro}m in size and low density materials from the KOP material, (3) load the KOP material into Multi-Canister Overpack (MCO) baskets, and (4) stage the MCO baskets for subsequent loading into MCOs. Hazard and accident analyses of the KPS conceptual design have been performed to incorporate safety into the design process. The hazard analysis is documented in PRC-STP-00098, Knock-Out Pot Disposition Project Conceptual Design Hazard Analysis. The accident analysismore » is documented in PRC-STP-CN-N-00167, Knock-Out Pot Disposition Sub-Project Canister Over Lift Accident Analysis. Based on the results of these analyses, and analyses performed in support of MCO transportation and MCO processing and storage activities at the Cold Vacuum Drying Facility (CVDF) and Canister Storage Building (CSB), control decision meetings were held to determine the controls required to protect onsite and offsite receptors and facility workers. At the conceptual design stage, these controls are primarily defined by their safety functions. Safety significant structures, systems, and components (SSCs) that could provide the identified safety functions have been selected for the conceptual design. It is anticipated that some safety SSCs identified herein will be reclassified based on hazard and accident analyses performed in support of preliminary and detailed design.« less

Documentation: Records and Reports.

PubMed

Akers, Michael J

2017-01-01

This article deals with documentation to include the beginning of documentation, the requirements of Good Manufacturing Practice reports and records, and the steps that can be taken to minimize Good Manufacturing Practice documentation problems. It is important to remember that documentation for 503a compounding involves the Formulation Record, Compounding Record, Standard Operating Procedures, Safety Data Sheets, etc. For 503b outsourcing facilities, compliance with Current Good Manufacturing Practices is required, so this article is applicable to them. For 503a pharmacies, one can see the development and modification of Good Manufacturing Practice and even observe changes as they are occurring in 503a documentation requirements and anticipate that changes will probably continue to occur. Copyright© by International Journal of Pharmaceutical Compounding, Inc.

Nuclear criticality safety evaluation of SRS 9971 shipping package

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

Vescovi, P.J.

1993-02-01

This evaluation is requested to revise the criticality evaluation used to generate Chapter 6 (Criticality Evaluation) of the Safety Analysis Report for Packaging (SARP) for shipment Of UO{sub 3} product from the Uranium Solidification Facility (USF) in the SRS 9971 shipping package. The pertinent document requesting this evaluation is included as Attachment I. The results of the evaluation are given in Attachment II which is written as Chapter 6 of a NRC format SARP.

10 CFR 1707.202 - Factors DNFSB will consider.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Factors DNFSB will consider. 1707.202 Section 1707.202 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.202 Factors DNFSB...

10 CFR 1707.202 - Factors DNFSB will consider.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Factors DNFSB will consider. 1707.202 Section 1707.202 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.202 Factors DNFSB...

10 CFR 1707.207 - Restrictions that apply to testimony.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Restrictions that apply to testimony. 1707.207 Section 1707.207 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.207...

10 CFR 1707.207 - Restrictions that apply to testimony.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Restrictions that apply to testimony. 1707.207 Section 1707.207 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.207...

10 CFR 1707.202 - Factors DNFSB will consider.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Factors DNFSB will consider. 1707.202 Section 1707.202 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.202 Factors DNFSB...

10 CFR 1707.208 - Restrictions that apply to released records.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Restrictions that apply to released records. 1707.208 Section 1707.208 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.202 - Factors DNFSB will consider.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Factors DNFSB will consider. 1707.202 Section 1707.202 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.202 Factors DNFSB...

10 CFR 1707.207 - Restrictions that apply to testimony.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Restrictions that apply to testimony. 1707.207 Section 1707.207 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.207...

10 CFR 1707.208 - Restrictions that apply to released records.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Restrictions that apply to released records. 1707.208 Section 1707.208 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.208 - Restrictions that apply to released records.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Restrictions that apply to released records. 1707.208 Section 1707.208 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.208 - Restrictions that apply to released records.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Restrictions that apply to released records. 1707.208 Section 1707.208 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.207 - Restrictions that apply to testimony.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Restrictions that apply to testimony. 1707.207 Section 1707.207 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.207...

10 CFR 1707.208 - Restrictions that apply to released records.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Restrictions that apply to released records. 1707.208 Section 1707.208 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.207 - Restrictions that apply to testimony.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Restrictions that apply to testimony. 1707.207 Section 1707.207 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.207...

10 CFR 1707.202 - Factors DNFSB will consider.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Factors DNFSB will consider. 1707.202 Section 1707.202 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707.202 Factors DNFSB...

Documents | Office of Marine and Aviation Operations

Science.gov Websites

; Facilities Public & Legislative Affairs Publication Regulation Report Safety Security Specifications ) 2007 NOAA Diving Program Annual Report This report highlights the significant achievements of the NOAA Program, Office of Marine and Aviation Operation, Report Download from OMAO OMAO (2008) 2008 NOAA Diving

OSHA: Implications for Higher Education.

ERIC Educational Resources Information Center

National Association of College and University Business Officers, Washington, DC.

Presented in this document are several articles concerning recommendations about the Occupational Safety and Health Act of 1970 (OSHA) and its implications for higher education. It is time for an educated look at facilities and programs and the beginning of plans which, in the long run, will bring colleges and universities into compliance with…

Possible safety hazards associated with the operation of the 0.3-m transonic cryogenic tunnel at the NASA Langley Research Center

NASA Technical Reports Server (NTRS)

Webster, T. J.

1982-01-01

The 0.3 m Transonic Cryogenic Tunnel (TCT) at the NASA Langley Research Center was built in 1973 as a facility intended to be used for no more than 60 hours in order to verify the validity of the cryogenic wind tunnel concept at transonic speeds. The role of the 0.3 m TCT has gradually changed until now, after over 3000 hours of operation, it is classified as a major NASA research facility and, under the administration of the Experimental Techniques Branch, it is used extensively for the testing of airfoils at high Reynolds numbers and for the development of various technologies related to the efficient operation and use of cryogenic wind tunnels. The purpose of this report is to document the results of a recent safety analysis of the 0.3 m TCT facility. This analysis was made as part of an on going program with the Experimental Techniques Branch designed to ensure that the existing equipment and current operating procedures of the 0.3 m TCT facility are acceptable in terms of today's standards of safety for cryogenic systems.

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

Tendera, P.

At present there are two NPPs equipped with PWR units in Czech Republic. The Dukovany NPP is about ten years in operation (four units 440 MW - WWER model 213) and Temelin NPP is under construction (two units 1000 MW-WWER model 320). Both NPPs were built to Soviet design and according to Soviet regulations and standards but most of equipment for primary circuits was supplied by home manufactures. The objective for the Czech LBB programme is to prove the LBB status of the primary piping systems of these NPPs and the LBB concept is a part of strategy to meetmore » western style safety standards. The reason for the Czech LBB project is a lack of some standard safety facilities, too. For both Dukovany and Temolin NPPs a full LBB analysis should be carried out. The application of LBB to the piping system should be also a cost effective means to avoid installations of pipe whip restraints and jet shields. The Czech regulatory body issued non-mandatory requirement {open_quotes}Leak Before Break{close_quotes} which is in compliance with national legal documents and which is based on the US NRC Regulatory Procedures and US standards (ASME, CODE, ANSI). The requirement has been published in the document {open_quotes}Safety of Nuclear Facilities{close_quotes} No. 1/1991 as {open_quotes}Requirements on the Content and Format of Safety Reports and their Supplements{close_quotes} and consists of two parts (1) procedure for obtaining proof of evidence {open_quotes}Leak Before Break{close_quotes} (2) leak detection systems for the pressurized reactor primary circuit. At present some changes concerning both parts of the above document will be introduced. The reasons for this modifications will be presented.« less

Safety and environmental health handbook

USGS Publications Warehouse

,

1989-01-01

This Safety Handbook (445-1-H.) supplements the Geological Survey Safety Management Program objectives set forth in Survey Manual 445.1. Specifically, it provides a compact source of basic information to assist management and employees in preventing motor vehicle accidents, personal injuries, occupational diseases, fire, and other property damage or loss. All work situations incidental to the Geological Survey cannot be discussed in a handbook, and such complete coverage is not intended in this document. However, a wide range of subjects are covered in which a "common sense" approach to safety has been expressed. These subjects have been organized such that Chapters 1-5 address administrative issues, Chapters 6-12 address activities usually conducted within a facility, and Chapters 13-20 address field activities. No information contained in the Handbook is intended to alter any provision of any Federal law or executive order, Department of the Interior or Survey directive, or collective bargaining agreement. Questions or suggestions regarding the content of the Safety Handbook may be directed to the Survey Safety Manager, Administrative Division, Office of Facilities and Management Services, National Center, Reston, Virginia, Mail Stop 246. The previous edition of the Safety Handbook is superseded.

New food safety law: effectiveness on the ground.

PubMed

Drew, Christa A; Clydesdale, Fergus M

2015-01-01

The demand for safety in the US food supply from production to consumption necessitates a scientific, risk-based strategy for the management of microbiological, chemical, and physical hazards in food. The key to successful management is an increase in systematic collaboration and communication and in enforceable procedures with all domestic and international stakeholders. The enactment of the Food Safety Modernization Act (FSMA) aims to prevent or reduce large-scale food-borne illness outbreaks through stricter facility registration and records standards, mandatory prevention-based controls, increased facility inspections in the United States and internationally, mandatory recall authority, import controls, and increased consumer communication. The bill provisions are expected to cost $1.4 billion over the next four years. Effective implementation of the FSMA's 50 rules, reports, studies, and guidance documents in addition to an increased inspection burden requires further funding appropriations. Additional full-time inspectors and unprecedented foreign compliance is necessary for the full and effective implementation of the FSMA.

Hazard Analysis for Pneumatic Flipper Suitport/Z-1 Manned Evaluation, Chamber B, Building 32. Revision: Basic

NASA Technical Reports Server (NTRS)

2012-01-01

One of the characteristics of an effective safety program is the recognition and control of hazards before mishaps or failures occur. Conducting potentially hazardous tests necessitates a thorough hazard analysis in order to protect our personnel from injury and our equipment from damage. The purpose of this hazard analysis is to define and address the potential hazards and controls associated with the Z1 Suit Port Test in Chamber B located in building 32, and to provide the applicable team of personnel with the documented results. It is imperative that each member of the team be familiar with the hazards and controls associated with his/her particular tasks, assignments, and activities while interfacing with facility test systems, equipment, and hardware. The goal of this hazard analysis is to identify all hazards that have the potential to harm personnel and/or damage facility equipment, flight hardware, property, or harm the environment. This analysis may also assess the significance and risk, when applicable, of lost test objectives when substantial monetary value is involved. The hazards, causes, controls, verifications, and risk assessment codes have been documented on the hazard analysis work sheets in appendix A of this document. The preparation and development of this report is in accordance with JPR 1700.1, JSC Safety and Health Handbook.

Nuclear criticality safety evaluation of SRS 9971 shipping package. [SRS (Savannah River Site)

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

Vescovi, P.J.

1993-02-01

This evaluation is requested to revise the criticality evaluation used to generate Chapter 6 (Criticality Evaluation) of the Safety Analysis Report for Packaging (SARP) for shipment Of UO[sub 3] product from the Uranium Solidification Facility (USF) in the SRS 9971 shipping package. The pertinent document requesting this evaluation is included as Attachment I. The results of the evaluation are given in Attachment II which is written as Chapter 6 of a NRC format SARP.

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

10 CFR 1707.210 - Procedure in the event of an adverse ruling.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Procedure in the event of an adverse ruling. 1707.210 Section 1707.210 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.210 - Procedure in the event of an adverse ruling.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Procedure in the event of an adverse ruling. 1707.210 Section 1707.210 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.210 - Procedure in the event of an adverse ruling.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Procedure in the event of an adverse ruling. 1707.210 Section 1707.210 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.210 - Procedure in the event of an adverse ruling.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Procedure in the event of an adverse ruling. 1707.210 Section 1707.210 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

10 CFR 1707.210 - Procedure in the event of an adverse ruling.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Procedure in the event of an adverse ruling. 1707.210 Section 1707.210 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS Requests for Testimony and Production of Documents § 1707...

25 CFR 170.209 - How will IRRHPP applications be ranked and funded?

Code of Federal Regulations, 2013 CFR

2013-04-01

... IRR transportation facility up to a maximum of $1 million per application. (c) A project submitted as... 25 Indians 1 2013-04-01 2013-04-01 false How will IRRHPP applications be ranked and funded? 170... and the following criteria: (1) Existence of safety hazards with documented fatality and injury...

25 CFR 170.209 - How will IRRHPP applications be ranked and funded?

Code of Federal Regulations, 2014 CFR

2014-04-01

... IRR transportation facility up to a maximum of $1 million per application. (c) A project submitted as... 25 Indians 1 2014-04-01 2014-04-01 false How will IRRHPP applications be ranked and funded? 170... and the following criteria: (1) Existence of safety hazards with documented fatality and injury...

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

Brunett, A. J.; Fei, T.; Strons, P. S.

The Transient Reactor Test Facility (TREAT), located at Idaho National Laboratory (INL), is a test facility designed to evaluate the performance of reactor fuels and materials under transient accident conditions. The facility, an air-cooled, graphite-moderated reactor designed to utilize fuel containing high-enriched uranium (HEU), has been in non-operational standby status since 1994. Currently, in support of the missions of the Department of Energy (DOE) National Nuclear Security Administration (NNSA) Material Management and Minimization (M3) Reactor Conversion Program, a new core design is being developed for TREAT that will utilize low-enriched uranium (LEU). The primary objective of this conversion effort ismore » to design an LEU core that is capable of meeting the performance characteristics of the existing HEU core. Minimal, if any, changes are anticipated for the supporting systems (e.g. reactor trip system, filtration/cooling system, etc.); therefore, the LEU core must also be able to function with the existing supporting systems, and must also satisfy acceptable safety limits. In support of the LEU conversion effort, a range of ancillary safety analyses are required to evaluate the LEU core operation relative to that of the existing facility. These analyses cover neutronics, shielding, and thermal hydraulic topics that have been identified as having the potential to have reduced safety margins due to conversion to LEU fuel, or are required to support the required safety analyses documentation. The majority of these ancillary tasks have been identified in [1] and [2]. The purpose of this report is to document the ancillary safety analyses that have been performed at Argonne National Laboratory during the early stages of the LEU design effort, and to describe ongoing and anticipated analyses. For all analyses presented in this report, methodologies are utilized that are consistent with, or improved from, those used in analyses for the HEU Final Safety Analysis Report (FSAR) [3]. Depending on the availability of historical data derived from HEU TREAT operation, results calculated for the LEU core are compared to measurements obtained from HEU TREAT operation. While all analyses in this report are largely considered complete and have been reviewed for technical content, it is important to note that all topics will be revisited once the LEU design approaches its final stages of maturity. For most safety significant issues, it is expected that the analyses presented here will be bounding, but additional calculations will be performed as necessary to support safety analyses and safety documentation. It should also be noted that these analyses were completed as the LEU design evolved, and therefore utilized different LEU reference designs. Preliminary shielding, neutronic, and thermal hydraulic analyses have been completed and have generally demonstrated that the various LEU core designs will satisfy existing safety limits and standards also satisfied by the existing HEU core. These analyses include the assessment of the dose rate in the hodoscope room, near a loaded fuel transfer cask, above the fuel storage area, and near the HEPA filters. The potential change in the concentration of tramp uranium and change in neutron flux reaching instrumentation has also been assessed. Safety-significant thermal hydraulic items addressed in this report include thermally-induced mechanical distortion of the grid plate, and heating in the radial reflector.« less

Embracing Safe Ground Test Facility Operations and Maintenance

NASA Technical Reports Server (NTRS)

Dunn, Steven C.; Green, Donald R.

2010-01-01

Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

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

Association between health worker motivation and healthcare quality efforts in Ghana

PubMed Central

2013-01-01

Background 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. Purpose 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. Methods 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. Results 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). Conclusion 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. PMID:23945073

Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

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

NONE

1994-10-01

This document is the third volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, exceptmore » for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of appendices C through U of the report« less

Aeronautical engineering: A continuing bibliography with indexes (supplement 280)

NASA Technical Reports Server (NTRS)

1992-01-01

This bibliography lists 647 reports, articles, and other documents introduced into the NASA scientific and technical information system in June, 1991. Subject coverage includes: aerodynamics, air transportation safety, aircraft communication and navigation, aircraft design and performance, aircraft instrumentation, aircraft propulsion, aircraft stability and control, research facilities, astronautics, chemistry and materials, engineering, geosciences, computer sciences, physics, and social sciences.

Poster - 28: Shielding of X-ray Rooms in Ontario in the Absence of Best Practice

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

Frimeth, Jeff; Richer, Jeff; Nesbitt, James

This poster will be strictly based on the Healing Arts Radiation Protection (HARP) Act, Regulation 543 under this Act (X-ray Safety Code), and personal communication the presenting author has had. In Ontario, the process of approval of an X-ray machine installation by the Director of the X-ray Inspection Service (XRIS) follows a certain protocol. Initially, the applicant submits a series of forms, including recommended shielding amounts, in order to satisfy the law. This documentation is then transferred to a third-party vendor (i.e. a professional engineer – P.Eng.) outsourced by the Ministry of Health and Long-term Care (MOHLTC). The P.Eng. thenmore » evaluates the submitted documentation for appropriate fulfillment of the HARP Act and Reg. 543 requirements. If the P.Eng.’s evaluation of the documentation is to their satisfaction, the XRIS is then notified. Finally, the Director will then issue a letter of approval to install the equipment at the facility. The methodology required to be used by the P.Eng. in order to determine the required amounts of protective barriers, and recommended to be used by the applicant, is contained within Safety Code 20A. However, Safety Code 35 has replaced the obsolete Safety Code 20A document and employs best practices in shielding design. This talk will focus further on specific intentions and limitations of Safety Code 20A. Furthermore, this talk will discuss the definition of the “practice of professional engineering” in Ontario. COMP members who are involved in shielding design are strongly encouraged to attend.« less

Improving tractor safety warnings: readability is missing.

PubMed

Tebeaux, E

2010-07-01

Research on tractor safety has not focused on user manuals. This study focuses on tractor operator manuals, specifically safety warnings, selected from the files of the Tractor Test facility at University of Nebraska-Lincoln. Analysis of many common warnings, based on readability and legibility research, shows that many warnings contain excessive information, confusing visuals and safety icons, poor document design, and illegible typefaces. The result is unreadable warnings that do not communicate quickly and correctly, and discourage readers rather than clarify critical information. Many tractor operator warnings are cluttered, "over-written," and contain information needed to protect the manufacturer rather than to inform operators. What is needed is a careful analysis and revision of many safety warnings with the goal of encouraging operators to read the warnings and follow their message.

Plutonium Oxide Containment and the Potential for Water-Borne Transport as a Consequence of ARIES Oxide Processing Operations

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

Wayne, David Matthew; Rowland, Joel C.

2015-02-01

The question of oxide containment during processing and storage has become a primary concern when considering the continued operability of the Plutonium Facility (PF-4) at Los Alamos National Laboratory (LANL). An Evaluation of the Safety of the Situation (ESS), “Potential for Criticality in a Glovebox Due to a Fire” (TA55-ESS-14-002-R2, since revised to R3) first issued in May, 2014 summarizes these concerns: “The safety issue of fire water potentially entering a glovebox is: the potential for the water to accumulate in the bottom of a glovebox and result in an inadvertent criticality due to the presence of fissionable materials inmore » the glovebox locations and the increased reflection and moderation of neutrons from the fire water accumulation.” As a result, the existing documented safety analysis (DSA) was judged inadequate and, while it explicitly considered the potential for criticality resulting from water intrusion into gloveboxes, criticality safety evaluation documents (CSEDs) for the affected locations did not evaluate the potential for fire water intrusion into a glovebox.« less

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

Lightning Protection System for HE Facilities at LLNL - Certification Template

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

Clancy, T J; Ong, M M; Brown, C G

2005-12-08

This document is meant as a template to assist in the development of your own lighting certification process. Aside from this introduction and the mock representative name of the building (Building A), this document is nearly identical to a lightning certification report issued by the Engineering Directorate at Lawrence Livermore National Laboratory. At the date of this release, we have certified over 70 HE processing and storage cells at our Site 300 facilities. In Chapters 1 and 2 respectively, we address the need and methods of lightning certification for HE processing and storage facilities at LLNL. We present the preferredmore » method of lightning protection in Chapter 3, as well as the likely building modifications that are needed to comply with this method. In Chapter 4, we present the threat assessment and resulting safe work areas within a cell. After certification, there may be changes to operations during a lightning alert, and this is discussed in Chapter 5. Chapter 6 lists the maintenance requirements for the continuation of lighting certification status. Appendices of this document are meant as an aid in developing your own certification process, and they include a bonding list, an inventory of measurement equipment, surge suppressors in use at LLNL, an Integrated Work and Safety form (IWS), and a template certification sign-off sheet. The lightning certification process involves more that what is spelled out in this document. The first steps involve considerable planning, the securing of funds, and management and explosives safety buy-in. Permits must be obtained, measurement equipment must be assembled and tested, and engineers and technicians must be trained in their use. Cursory building inspections are also recommended, and surge suppression for power systems must be addressed. Upon completion of a certification report and its sign-off by management, additional work is required. Training will be needed in order to educate workers and facility managers of the requirements of lightning certification. Operating procedures will need to be generated and/or modified with additional controls. Engineering controls may also be implemented requiring the modification of cells. Careful planning should bring most of these issues to light, making it clear where this document is helpful and were additional assistance may be necessary.« less

Review of the Constellation Level II Safety, Reliability, and Quality Assurance (SR&QA) Requirements Documents during Participation in the Constellation Level II SR&QA Forum

NASA Technical Reports Server (NTRS)

Cameron, Kenneth D.; Gentz, Steven J.; Beil, Robert J.; Minute, Stephen A.; Currie, Nancy J.; Scott, Steven S.; Thomas, Walter B., III; Smiles, Michael D.; Schafer, Charles F.; Null, Cynthia H.;

RDS - A systematic approach towards system thermal hydraulics input code development for a comprehensive deterministic safety analysis

NASA Astrophysics Data System (ADS)

Salim, Mohd Faiz; Roslan, Ridha; Ibrahim, Mohd Rizal Mamat @

2014-02-01

Deterministic Safety Analysis (DSA) is one of the mandatory requirements conducted for Nuclear Power Plant licensing process, with the aim of ensuring safety compliance with relevant regulatory acceptance criteria. DSA is a technique whereby a set of conservative deterministic rules and requirements are applied for the design and operation of facilities or activities. Computer codes are normally used to assist in performing all required analysis under DSA. To ensure a comprehensive analysis, the conduct of DSA should follow a systematic approach. One of the methodologies proposed is the Standardized and Consolidated Reference Experimental (and Calculated) Database (SCRED) developed by University of Pisa. Based on this methodology, the use of Reference Data Set (RDS) as a pre-requisite reference document for developing input nodalization was proposed. This paper shall describe the application of RDS with the purpose of assessing its effectiveness. Two RDS documents were developed for an Integral Test Facility of LOBI-MOD2 and associated Test A1-83. Data and information from various reports and drawings were referred in preparing the RDS. The results showed that by developing RDS, it has made possible to consolidate all relevant information in one single document. This is beneficial as it enables preservation of information, promotes quality assurance, allows traceability, facilitates continuous improvement, promotes solving of contradictions and finally assisting in developing thermal hydraulic input regardless of whichever code selected. However, some disadvantages were also recognized such as the need for experience in making engineering judgments, language barrier in accessing foreign information and limitation of resources. Some possible improvements are suggested to overcome these challenges.

Report on the oversight assessment of the operational readiness review of the Replacement Tritium Facility at Savannah River Site

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

Lee, B.T.

1993-03-01

This report presents the results of an oversight assessment (OA) conducted by the US Department of Energy's (DOE) Office of Environment, Safety and Health (EH) of operational readiness review (ORR) activities for the Replacement Tritium Facility (RTF) located at Savannah River Site (SRS). The EH OA of this facility took place concurrently with an ORR conducted by the DOE Office of Defense Programs (DP). The DP ORR was conducted from January 19 through February 5, 1993. The EH OA was performed in accordance with the protocol and procedures specified in EH Program for Oversight Assessment of Operational Readiness Evaluations formore » Startups and Restarts,'' dated September 15, 1992. The EH OA Team evaluated the DP ORR to determine whether it was thorough and demonstrated sufficient inquisitiveness to verify that the implementation of programs and procedures adequately ensures the protection of worker safety and health. The EH OA Team performed its evaluation of the DP ORR in the following technical areas: occupational safety, industrial hygiene, and respiratory protection; fire protection; and chemical safety. In the areas of fire protection and chemical safety, the EH OA Team conducted independent vertical-slice reviews to confirm DP ORR results. Within each technical area, the EH OA Team reviewed the DP ORR Plan, including the Criteria Review and Approach Documents (CRADs); the qualifications of individual DP ORR team members; the performance of planned DP ORR activities; and the results of the DP ORR.« less

Report on the oversight assessment of the operational readiness review of the Replacement Tritium Facility at Savannah River Site

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

Lee, B.T.

1993-03-01

This report presents the results of an oversight assessment (OA) conducted by the US Department of Energy`s (DOE) Office of Environment, Safety and Health (EH) of operational readiness review (ORR) activities for the Replacement Tritium Facility (RTF) located at Savannah River Site (SRS). The EH OA of this facility took place concurrently with an ORR conducted by the DOE Office of Defense Programs (DP). The DP ORR was conducted from January 19 through February 5, 1993. The EH OA was performed in accordance with the protocol and procedures specified in ``EH Program for Oversight Assessment of Operational Readiness Evaluations formore » Startups and Restarts,`` dated September 15, 1992. The EH OA Team evaluated the DP ORR to determine whether it was thorough and demonstrated sufficient inquisitiveness to verify that the implementation of programs and procedures adequately ensures the protection of worker safety and health. The EH OA Team performed its evaluation of the DP ORR in the following technical areas: occupational safety, industrial hygiene, and respiratory protection; fire protection; and chemical safety. In the areas of fire protection and chemical safety, the EH OA Team conducted independent vertical-slice reviews to confirm DP ORR results. Within each technical area, the EH OA Team reviewed the DP ORR Plan, including the Criteria Review and Approach Documents (CRADs); the qualifications of individual DP ORR team members; the performance of planned DP ORR activities; and the results of the DP ORR.« less

Safety analysis, risk assessment, and risk acceptance criteria

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

Jamali, K.; Stack, D.W.; Sullivan, L.H.

1997-08-01

This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities andmore » that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, `ensuring` plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is `safe.` Use of RACs requires quantitative estimates of consequence frequency and magnitude.« less

Hazard Analysis for the Mark III Space Suit Assembly (SSA) Used in One-g Operations

NASA Technical Reports Server (NTRS)

Mitchell, Kate; Ross, Amy; Blanco, Raul; Wood, Art

2012-01-01

This Hazard Analysis document encompasses the Mark III Space Suit Assembly (SSA) and associated ancillary equipment. It has been prepared using JSC17773, "Preparing Hazard Analyses for JSC Ground Operation", as a guide. The purpose of this document is to present the potential hazards involved in ground (23 % maximum O2, One-g) operations of the Mark III and associated ancillary support equipment system. The hazards listed in this document are specific to suit operations only; each supporting facility (Bldg. 9, etc.) is responsible for test specific Hazard Analyses. A "hazard" is defined as any condition that has the potential for harming personnel or equipment. This analysis was performed to document the safety aspects associated with manned use of the Mark III for pressurized and unpressurized ambient, ground-based, One-g human testing. The hazards identified herein represent generic hazards inherent to all standard JSC test venues for nominal ground test configurations. Non-standard test venues or test specific configurations may warrant consideration of additional hazards analysis prior to test. The cognizant suit engineer is responsible for the safety of the astronaut/test subject, space suit, and suit support personnel. The test requester, for the test supported by the suit test engineer and suited subject, is responsible for overall safety and any necessary Test Readiness Reviews (TRR).

What if? The one question every administrator should ask. Use HIPAA rules as a blueprint for broader safety, security.

PubMed

Redling, Bob

2007-08-01

Are you doing enough to control security and privacy at your practice? Could you cope if your organization suffered a disaster that destroyed facilities, business documents and patient records? Although Health Insurance Portability and Accountability Act (HIPAA) security and privacy rules focus on patient health information, they also point the way to a more comprehensive approach to managing risk. By using HIPAA rules as a blueprint, you can design policies and procedures to address everything from safeguarding financial information to protecting the personal safety of patients, physicians and staff.

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.

The NUITM-KEMRI P3 Laboratory in Kenya: Establishment, Features, Operation and Maintenance

PubMed Central

Inoue, Shingo; Wandera, Ernest; Miringu, Gabriel; Bundi, Martin; Narita, Chika; Ashur, Salame; Kwallah, Allan; Galata, Amina; Abubakar, Mwajuma; Suka, Sora; Mohamed, Shah; Karama, Mohamed; Horio, Masahiro; Shimada, Masaaki; Ichinose, Yoshio

2013-01-01

A biocontainment facility is a core component in any research setting due to the services it renders towards comprehensive biosafety observance. The NUITM-KEMRI P3 facility was set up in 2007 and has been actively in use since 2010 by researchers from this and other institutions. A number of hazardous agents have been handled in the laboratory among them MDR-TB and yellow fever viruses. The laboratory has the general physical and operational features of a P3 laboratory in addition to a number of unique features, among them the water-air filtration system, the eco-mode operation feature and automation of the pressure system that make the facility more efficient. It is equipped with biosafety and emergency response equipments alongside common laboratory equipments, maintained regularly using daily, monthly and yearly routines. Security and safety is strictly observed within the facility, enhanced by restricted entry, strict documentation and use of safety symbols. Training is also engrained within the operation of the laboratory and is undertaken and evaluated annually. Though the laboratory is in the process of obtaining accreditation, it is fully certified courtesy of the manufactures’ and constructed within specified standards. PMID:23533023

Implementing personal digital assistant documentation of pharmacist interventions in a military treatment facility.

PubMed

Ford, Stephen; Illich, Stan; Smith, Lisa; Franklin, Arthur

2006-01-01

To describe the use of personal digital assistants (PDAs) in documenting pharmacists' clinical interventions. Evans Army Community Hospital (EACH), a 78-bed military treatment facility, in Colorado Springs. Pharmacists on staff at EACH. All pharmacists at EACH used PDAs with the pilot software to record interventions for 1 month. The program underwent final design changes and then became the sole source for recording pharmacist interventions. The results of this project are being evaluated every 3 months for the first year and yearly thereafter. Visual CE (Syware Inc. Cambridge, Mass.) software was selected to develop fields for the documentation tool. This software is simple and easy to use, and users can retrieve reports of interventions from both inpatient and outpatient sections. The software needed to be designed so that data entry would only take a few minutes and ad hoc reports could be produced easily. Number of pharmacist interventions reported, time spent in clinical interventions, and outcome of clinical intervention. Implementing a PDA-based system for documenting pharmacist interventions across ambulatory, inpatient, and clinical services dramatically increased reporting during the first 6 months after implementation (August 2004-February 2005). After initial fielding, clinical pharmacists in advanced practice settings (such as disease management clinic, anticoagulation clinic) recognized a need to tailor the program to their specific activities, which resulted in a spin-off program unique to their practice roles. A PDA-based system for documenting clinical interventions at a military treatment facility increased reporting of interventions across all pharmacy points of service. Pharmacy leadership used these data to document the impact of pharmacist interventions on safety and quality of pharmaceutical care provided.

Range Flight Safety Requirements

NASA Technical Reports Server (NTRS)

Loftin, Charles E.; Hudson, Sandra M.

2018-01-01

The purpose of this NASA Technical Standard is to provide the technical requirements for the NPR 8715.5, Range Flight Safety Program, in regards to protection of the public, the NASA workforce, and property as it pertains to risk analysis, Flight Safety Systems (FSS), and range flight operations. This standard is approved for use by NASA Headquarters and NASA Centers, including Component Facilities and Technical and Service Support Centers, and may be cited in contract, program, and other Agency documents as a technical requirement. This standard may also apply to the Jet Propulsion Laboratory or to other contractors, grant recipients, or parties to agreements to the extent specified or referenced in their contracts, grants, or agreements, when these organizations conduct or participate in missions that involve range flight operations as defined by NPR 8715.5.1.2.2 In this standard, all mandatory actions (i.e., requirements) are denoted by statements containing the term “shall.”1.3 TailoringTailoring of this standard for application to a specific program or project shall be formally documented as part of program or project requirements and approved by the responsible Technical Authority in accordance with NPR 8715.3, NASA General Safety Program Requirements.

Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

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

Dionne, B.J.; Morris, S.C. III; Baum, J.W.

1998-01-01

The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example ofmore » a risk-based decision technique. This document contains the Appendices for the report.« less

Safety skills of mental health workers: empirical evidence of a risk management strategy.

PubMed

Flannery, Raymond B; Walker, Andrew P

2003-01-01

To reduce violence in the workplace, health care facilities invest time and resources in risk management strategies such as photo identification and controlled access and surveillance. Studies of assaultive psychiatric patients continue to document that mental health workers (MHWs) are the most frequent targets of the patient violence. Unexamined in these findings is the role skilled MHWs contribute in restoring safety and order in the aftermath of these assaults. This six-year, empirical retrospective study examined the safety skills of MHWs in containing violence. Although they were 28% of the workforce, MHWs restored order in the majority of single assault incidents and restraint procedures. Their skills appear to be a risk management strategy in their own right. The implications are discussed.

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

Evolution in performance assessment modeling as a result of regulatory review

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

Rowat, J.H.; Dolinar, G.M.; Stephens, M.E.

1995-12-31

AECL is planning to build the IRUS (Intrusion Resistant Underground Structure) facility for near-surface disposal of LLRW. The PSAR (preliminary safety assessment report) was subject to an initial regulatory review during mid-1992. The regulatory authority provided comments on many aspects of the safety assessment documentation including a number of questions on specific PA (Performance Assessment) modelling assumptions. As a result of these comments as well as a separate detailed review of the IRUS disposal concept, changes were made to the conceptual and mathematical models. The original disposal concept included a non-sorbing vault backfill, with a strong reliance on the wasteformmore » as a barrier. This concept was altered to decrease reliance on the wasteform by replacing the original backfill with a sand/clinoptilolite mix, which is a better sorber of metal cations. This change lead to changes in the PA models which in turn altered the safety case for the facility. This, and other changes that impacted performance assessment modelling are the subject of this paper.« less

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

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

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

Roadmap to a Sustainable Structured Trusted Employee Program

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

Coates, Cameron W; Eisele, Gerhard R

2013-08-01

Organizations (facility, regulatory agency, or country) have a compelling interest in ensuring that individuals who occupy sensitive positions affording access to chemical biological, radiological and nuclear (CBRN) materials facilities and programs are functioning at their highest level of reliability. Human reliability and human performance relate not only to security but also focus on safety. Reliability has a logical and direct relationship to trustworthiness for the organization is placing trust in their employees to conduct themselves in a secure, safe, and dependable manner. This document focuses on providing an organization with a roadmap to implementing a successful and sustainable Structured Trustedmore » Employee Program (STEP).« less

Meteorological Support at the Savanna River Site

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

Addis, Robert P.

2005-10-14

The Department of Energy (DOE) operates many nuclear facilities on large complexes across the United States in support of national defense. The operation of these many and varied facilities and processes require meteorological support for many purposes, including: for routine operations, to respond to severe weather events, such as lightning, tornadoes and hurricanes, to support the emergency response functions in the event of a release of materials to the environment, for engineering baseline and safety documentation, as well as hazards assessments etc. This paper describes a program of meteorological support to the Savannah River Site, a DOE complex located inmore » South Carolina.« less

Evaluation of Agency Non-Code Layered Pressure Vessels (LPVs) . Volume 2; Appendices

NASA Technical Reports Server (NTRS)

Prosser, William H.

2014-01-01

In coordination with the Office of Safety and Mission Assurance and the respective Center Pressure System Managers (PSMs), the NASA Engineering and Safety Center (NESC) was requested to formulate a consensus draft proposal for the development of additional testing and analysis methods to establish the technical validity, and any limitation thereof, for the continued safe operation of facility non-code layered pressure vessels. The PSMs from each NASA Center were asked to participate as part of the assessment team by providing, collecting, and reviewing data regarding current operations of these vessels. This document contains the appendices to the main report.

Closeout of IE Bulletin 83-06: Nonconforming materials supplied by Tube-Line Corporation Facilities at Long Island City, New York; Houston, Texas; and Carol Stream, Illinois

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

Dean, R.S.; Foley, W.J.; Hennick, A.

1989-05-01

Documentation is provided in this report for the closeout of IE Bulletin 83-06 regarding nonconformities of certain materials which were obtained directly or indirectly from the Tube-Line Corporation (T-L) for use in safety-related systems. Closeout is based on the implementation and verification of four (4) required actions by licensees and holders of construction permits of nuclear power reactor and nuclear fuel facilities. From evaluation of responses and NRC/Region inspection reports, it is concluded that the concerns of the bulletin have been resolved. The bulletin is closed for all of the 120 power reactor facilities and for both of the twomore » nuclear fuel facilities to which it was issued for action. Background information is supplied in the Introduction and Appendix A. 3 refs., 5 tabs.« less

Criticality Safety Evaluation for the TACS at DAF

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

Percher, C. M.; Heinrichs, D. P.

2011-06-10

Hands-on experimental training in the physical behavior of multiplying systems is one of ten key areas of training required for practitioners to become qualified in the discipline of criticality safety as identified in DOE-STD-1135-99, Guidance for Nuclear Criticality Safety Engineer Training and Qualification. This document is a criticality safety evaluation of the training activities and operations associated with HS-3201-P, Nuclear Criticality 4-Day Training Course (Practical). This course was designed to also address the training needs of nuclear criticality safety professionals under the auspices of the NNSA Nuclear Criticality Safety Program1. The hands-on, or laboratory, portion of the course will utilizemore » the Training Assembly for Criticality Safety (TACS) and will be conducted in the Device Assembly Facility (DAF) at the Nevada Nuclear Security Site (NNSS). The training activities will be conducted by Lawrence Livermore National Laboratory following the requirements of an Integrated Work Sheet (IWS) and associated Safety Plan. Students will be allowed to handle the fissile material under the supervision of an LLNL Certified Fissile Material Handler.« less

Canister Storage Building (CSB) Hazard Analysis Report

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

POWERS, T.B.

2000-03-16

This report describes the methodology used in conducting the Canister Storage Building (CSB) Hazard Analysis to support the final CSB Safety Analysis Report and documents the results. This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis process identified hazardous conditions and material-at-risk, determined causes for potential accidents, identified preventive and mitigative features, and qualitatively estimated the frequencies and consequences of specific occurrences. The hazard analysis was performed by a team of cognizant CSB operations and design personnel, safetymore » analysts familiar with the CSB, and technical experts in specialty areas. The material included in this report documents the final state of a nearly two-year long process. Attachment A provides two lists of hazard analysis team members and describes the background and experience of each. The first list is a complete list of the hazard analysis team members that have been involved over the two-year long process. The second list is a subset of the first list and consists of those hazard analysis team members that reviewed and agreed to the final hazard analysis documentation. The material included in this report documents the final state of a nearly two-year long process involving formal facilitated group sessions and independent hazard and accident analysis work. The hazard analysis process led to the selection of candidate accidents for further quantitative analysis. New information relative to the hazards, discovered during the accident analysis, was incorporated into the hazard analysis data in order to compile a complete profile of facility hazards. Through this process, the results of the hazard and accident analyses led directly to the identification of safety structures, systems, and components, technical safety requirements, and other controls required to protect the public, workers, and environment.« less

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

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

FFTF Passive Safety Test Data for Benchmarks for New LMR Designs

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

Wootan, David W.; Casella, Andrew M.

Liquid Metal Reactors (LMRs) continue to be considered as an attractive concept for advanced reactor design. Software packages such as SASSYS are being used to im-prove new LMR designs and operating characteristics. Significant cost and safety im-provements can be realized in advanced liquid metal reactor designs by emphasizing inherent or passive safety through crediting the beneficial reactivity feedbacks associ-ated with core and structural movement. This passive safety approach was adopted for the Fast Flux Test Facility (FFTF), and an experimental program was conducted to characterize the structural reactivity feedback. The FFTF passive safety testing pro-gram was developed to examine howmore » specific design elements influenced dynamic re-activity feedback in response to a reactivity input and to demonstrate the scalability of reactivity feedback results to reactors of current interest. The U.S. Department of En-ergy, Office of Nuclear Energy Advanced Reactor Technology program is in the pro-cess of preserving, protecting, securing, and placing in electronic format information and data from the FFTF, including the core configurations and data collected during the passive safety tests. Benchmarks based on empirical data gathered during operation of the Fast Flux Test Facility (FFTF) as well as design documents and post-irradiation examination will aid in the validation of these software packages and the models and calculations they produce. Evaluation of these actual test data could provide insight to improve analytical methods which may be used to support future licensing applications for LMRs« less

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

Engaging staff to improve quality and safety in an austere medical environment: a case-control study in two Sierra Leonean hospitals.

PubMed

Rosen, Michael A; Chima, Adaora M; Sampson, John B; Jackson, Eric V; Koka, Rahul; Marx, Megan K; Kamara, Thaim B; Ogbuagu, Onyebuchi U; Lee, Benjamin H

2015-08-01

Inadequate observance of basic processes in patient care such as patient monitoring and documentation practices are potential impediments to the timely diagnoses and management of patients. These gaps exist in low resource settings such as Sierra Leone and can be attributed to a myriad of factors such as workforce and technology deficiencies. In the study site, only 12.4% of four critical vital signs were documented in the pre-intervention period. Implement a failure mode and effects analysis (FMEA) to improve documentation of four patient vital signs: temperature, blood pressure, pulse rate and respiratory rate. FMEA was implemented among a subpopulation of health workers who are involved in monitoring and documenting patient vital signs. Pre- and post-FMEA monitoring and documentation practice were compared with a control site. Participants identified a four-step process to monitoring and documenting vital signs, three categories of failure modes and four potential solutions. Based on 2100 patient days of documentation compliance data from 147 patients between July and November 2012, staff members at the study site were 1.79 times more likely to document all four patient vital signs in the post-implementation period (95% CI [1.35, 2.38]). FMEA is a feasible and effective strategy for improving quality and safety in an austere medical environment. Documentation compliance improved at the intervention facility. To evaluate the scalability and sustainability of this approach, programs targeting the development of these types of process improvement skills in local staff should be evaluated. © The Author 2015. Published by Oxford University Press in association with the International Society for Quality in Health Care; all rights reserved.

Study of status of safe injection practice and knowledge regarding injection safety among primary health care workers in Baglung district, western Nepal.

PubMed

Gyawali, Sudesh; Rathore, Devendra S; Kc, Bhuvan; Shankar, P Ravi

2013-01-03

Unsafe injection practices and injection overuse are widespread in developing countries harming the patient and inviting risks to the health care workers. In Nepal, there is a dearth of documented information about injection practices so the present study was carried out: a) to determine whether the selected government health facilities satisfy the conditions for safe injections in terms of staff training, availability of sterile injectable equipment and their proper disposal after use and b) to assess knowledge and attitudes of healthcare workers in these health care facilities with regard to injection safety. A descriptive cross-sectional mixed type (qualitative and quantitative) survey was carried out from 18th May to 16th June 2012. In-depth interviews with the in-charges were conducted using a semi-structured questionnaire. Observation of the health facilities using a structured observation tool was done. The data were analysed manually by summarizing, tabulating and presenting in various formats. The in-charges (eight males, two females) who participated in the study ranged in age from 30 to 50 years with a mean age of 37.8 years. Severe infection followed by pain was the most important cause for injection use with injection Gentamicin being most commonly prescribed. New single use (disposable) injections and auto-disable syringes were used to inject curative drugs and vaccines respectively. Sufficient safety boxes were also supplied to dispose the used syringe. All health care workers had received full course of Hepatitis B vaccine and were knowledgeable about at least one pathogen transmitted through unsafe injection practices. Injection safety management policy and waste disposal guideline was not available for viewing in any of the facilities. The office staff who disposed the bio-medical wastes did so without taking any safety measures. Moreover, none of these staff had received any formal training in waste management. Certain safe injection practices were noticed in the studied health care facilities but there remain a number of grey areas where unsafe practices still persists placing patient and health workers at risk of associated hazards. Training concentrating on injection safety, guidelines to dispose biomedical waste and monitoring of the activity is needed.

Study of status of safe injection practice and knowledge regarding injection safety among primary health care workers in Baglung district, western Nepal

PubMed Central

2013-01-01

Background Unsafe injection practices and injection overuse are widespread in developing countries harming the patient and inviting risks to the health care workers. In Nepal, there is a dearth of documented information about injection practices so the present study was carried out: a) to determine whether the selected government health facilities satisfy the conditions for safe injections in terms of staff training, availability of sterile injectable equipment and their proper disposal after use and b) to assess knowledge and attitudes of healthcare workers in these health care facilities with regard to injection safety. Methodology A descriptive cross-sectional mixed type (qualitative and quantitative) survey was carried out from 18th May to 16th June 2012. In-depth interviews with the in-charges were conducted using a semi-structured questionnaire. Observation of the health facilities using a structured observation tool was done. The data were analysed manually by summarizing, tabulating and presenting in various formats. Results The in-charges (eight males, two females) who participated in the study ranged in age from 30 to 50 years with a mean age of 37.8 years. Severe infection followed by pain was the most important cause for injection use with injection Gentamicin being most commonly prescribed. New single use (disposable) injections and auto-disable syringes were used to inject curative drugs and vaccines respectively. Sufficient safety boxes were also supplied to dispose the used syringe. All health care workers had received full course of Hepatitis B vaccine and were knowledgeable about at least one pathogen transmitted through unsafe injection practices. Injection safety management policy and waste disposal guideline was not available for viewing in any of the facilities. The office staff who disposed the bio-medical wastes did so without taking any safety measures. Moreover, none of these staff had received any formal training in waste management. Conclusions Certain safe injection practices were noticed in the studied health care facilities but there remain a number of grey areas where unsafe practices still persists placing patient and health workers at risk of associated hazards. Training concentrating on injection safety, guidelines to dispose biomedical waste and monitoring of the activity is needed. PMID:23286907

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

Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

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

NONE

1995-08-01

The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S and M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S and M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, andmore » the technical approach for the project. A companion document, the EFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has adopted the strategy of deactivating the simple facilities first, to reduce the scope of the project and to gain experience before addressing more difficult facilities. A decision support system is being developed to identify the activities that best promote the project mission and result in the largest cost savings. This work plan will be reviewed and revised annually. Deactivation of EFDP Facilities was initiated in FY 1994 and will be completed in FY 2000. The schedule for deactivation of facilities is shown. The total cost of the project is estimated to be $51M. The costs are summarized. Upon completion of deactivation, annual S and M costs of these facilities will be reduced from the current level of $5M per year to less than $1M per year.« 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

Type A Accident Investigation Board report on the January 17, 1996, electrical accident with injury in Technical Area 21 Tritium Science and Fabrication Facility Los Alamos National Laboratory. Final report

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

NONE

1996-04-01

An electrical accident was investigated in which a crafts person received serious injuries as a result of coming into contact with a 13.2 kilovolt (kV) electrical cable in the basement of Building 209 in Technical Area 21 (TA-21-209) in the Tritium Science and Fabrication Facility (TSFF) at Los Alamos National Laboratory (LANL). In conducting its investigation, the Accident Investigation Board used various analytical techniques, including events and causal factor analysis, barrier analysis, change analysis, fault tree analysis, materials analysis, and root cause analysis. The board inspected the accident site, reviewed events surrounding the accident, conducted extensive interviews and document reviews,more » and performed causation analyses to determine the factors that contributed to the accident, including any management system deficiencies. Relevant management systems and factors that could have contributed to the accident were evaluated in accordance with the guiding principles of safety management identified by the Secretary of Energy in an October 1994 letter to the Defense Nuclear Facilities Safety Board and subsequently to Congress.« less

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.

Computer Aided Method for System Safety and Reliability Assessments

DTIC Science & Technology

2008-09-01

program between 1998 and 2003. This tool was not marketed in the public domain after the CRV program ended. The other tool is called eXpress, and it...support Government reviewed and approved analyses methodologies which can 5 then be shared with other government agencies and industry partners...Documented for B&R, UP&L, EPRI 30 DEC 80 GO IBM Version Enhanced at UCC , Dallas, Descriptors, Facility to Alter Array Sizes, Explanation of Use 1 SEP 82

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...

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...

Runway Safety Monitor Algorithm for Single and Crossing Runway Incursion Detection and Alerting

NASA Technical Reports Server (NTRS)

Green, David F., Jr.

2006-01-01

The Runway Safety Monitor (RSM) is an aircraft based algorithm for runway incursion detection and alerting that was developed in support of NASA's Runway Incursion Prevention System (RIPS) research conducted under the NASA Aviation Safety and Security Program's Synthetic Vision System project. The RSM algorithm provides warnings of runway incursions in sufficient time for pilots to take evasive action and avoid accidents during landings, takeoffs or when taxiing on the runway. The report documents the RSM software and describes in detail how RSM performs runway incursion detection and alerting functions for NASA RIPS. The report also describes the RIPS flight tests conducted at the Reno/Tahoe International Airport (RNO) and the Wallops Flight Facility (WAL) during July and August of 2004, and the RSM performance results and lessons learned from those flight tests.

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...

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.

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...

APSIC Guidelines for environmental cleaning and decontamination.

PubMed

Ling, Moi Lin; Apisarnthanarak, Anucha; Thu, Le Thi Anh; Villanueva, Victoria; Pandjaitan, Costy; Yusof, Mohamad Yasim

2015-01-01

This document is an executive summary of APSIC Guidelines for Environmental Cleaning and Decontamination. It describes best practices in routine cleaning and decontamination in healthcare facilities as well as in specific settings e.g. management of patients with isolation precautions, food preparation areas, construction and renovation, and following a flood. It recommends the implementation of environmental hygiene program to keep the environment safe for patients, staff and visitors visiting a healthcare facility. Objective assessment of cleanliness and quality is an essential component of this program as a method for identifying quality improvement opportunities. Recommendations for safe handling of linen and bedding; as well as occupational health and safety issues are included in the guidelines. A training program is vital to ensure consistent adherence to best practices.

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

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...

Microgravity Combustion Research: 1999 Program and Results

NASA Technical Reports Server (NTRS)

Friedman, Robert (Editor); Gokoglu, Suleyman A. (Editor); Urban, David L. (Editor)

1999-01-01

The use of the microgravity environment of space to expand scientific knowledge and to enable the commercial development of space for enhancing the quality of life on Earth is particularly suitable to the field of combustion. This document reviews the current status of microgravity combustion research and derived information. It is the fourth in a series of timely surveys, all published as NASA Technical Memoranda, and it covers largely the period from 1995 to early 1999. The scope of the review covers three program areas: fundamental studies, applications to fire safety and other fields. and general measurements and diagnostics. The document also describes the opportunities for Principal Investigator participation through the NASA Research Announcement program and the NASA Glenn Research Center low-gravity facilities available to researchers.

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.

System safety checklist Skylab program report

NASA Technical Reports Server (NTRS)

Mcnail, E. M.

1974-01-01

Design criteria statement applicable to a wide variety of flight systems, experiments and other payloads, associated ground support equipment and facility support systems are presented. The document reflects a composite of experience gained throughout the aerospace industry prior to Skylab and additional experience gained during the Skylab Program. It has been prepared to provide current and future program organizations with a broad source of safety-related design criteria and to suggest methods for systematic and progressive application of the criteria beginning with preliminary development of design requirements and specifications. Recognizing the users obligation to shape the checklist to his particular needs, a summary of the historical background, rationale, objectives, development and implementation approach, and benefits based on Skylab experience has been included.

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...

33 CFR 96.250 - What documents and reports must a safety management system have?

Code of Federal Regulations, 2010 CFR

2010-07-01

...) Safety management system document and data maintenance (1) Procedures which establish and maintain control of all documents and data relevant to the safety management system. (2) Documents are available at... safety management system have? 96.250 Section 96.250 Navigation and Navigable Waters COAST GUARD...

Nevada State plan; final approval determination. Occupational Safety and Health Administration (OSHA), U.S. Department of Labor. Final State plan approval--Nevada.

PubMed

2000-04-18

This document amends OSHA's regulations to reflect the Assistant Secretary's decision granting final approval to the Nevada State plan. As a result of this affirmative determination under section 18(e) of the Occupational Safety and Health Act of 1970, Federal OSHA's standards and enforcement authority no longer apply to occupational safety and health issues covered by the Nevada plan, and authority for Federal concurrent jurisdiction is relinquished. Federal enforcement jurisdiction is retained over any private sector maritime employment, private sector employers on Indian land, and any contractors or subcontractors on any Federal establishment where the land is exclusive Federal jurisdiction. Federal jurisdiction remains in effect with respect to Federal government employers and employees. Federal OSHA will also retain authority for coverage of the United States Postal Service (USPS), including USPS employees, contract employees, and contractor-operated facilities engaged in USPS mail operations.

Radiotherapy and Nuclear Medicine Project for an Integral Oncology Center at the Oaxaca High Specialization Regional Hospital

NASA Astrophysics Data System (ADS)

De Jesús, M.; Trujillo-Zamudio, F. E.

2010-12-01

A building project of Radiotherapy & Nuclear Medicine services (diagnostic and therapy), within an Integral Oncology Center (IOC), requires interdisciplinary participation of architects, biomedical engineers, radiation oncologists and medical physicists. This report focus on the medical physicist role in designing, building and commissioning stages, for the final clinical use of an IOC at the Oaxaca High Specialization Regional Hospital (HRAEO). As a first step, during design stage, the medical physicist participates in discussions about radiation safety and regulatory requirements for the National Regulatory Agency (called CNSNS in Mexico). Medical physicists propose solutions to clinical needs and take decisions about installing medical equipment, in order to fulfill technical and medical requirements. As a second step, during the construction stage, medical physicists keep an eye on building materials and structural specifications. Meanwhile, regulatory documentation must be sent to CNSNS. This documentation compiles information about medical equipment, radioactivity facility, radiation workers and nuclear material data, in order to obtain the license for the linear accelerator, brachytherapy and nuclear medicine facilities. As a final step, after equipment installation, the commissioning stage takes place. As the conclusion, we show that medical physicists are essentials in order to fulfill with Mexican regulatory requirements in medical facilities.

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...

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

10 CFR 830.206 - Preliminary documented safety analysis.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Preliminary documented safety analysis. 830.206 Section 830.206 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Safety Basis Requirements § 830.206 Preliminary documented safety analysis. If construction begins after December 11, 2000, the contractor...

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

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

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

1993-09-01

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

New health and safety initiatives at the Department of Energy (DOE)

NASA Technical Reports Server (NTRS)

Ziemer, Paul L.

1993-01-01

This document touches on some of the more important lessons learned and the more noteworthy initiatives DOE has put into motion in the last three years to protect the health and safety of our contractor employees. What we have learned in the process should come as no surprise to those of you who have been working in the field: (1) that management commitment to safety and health is critical to a successful program; (2) that meaningful employee participation in all aspects of the program enhances its effectiveness at every level; and (3) that the dedication and expertise of medical and occupational safety and health professionals are needed if the challenging problems presented by the complex and technologically advanced environment at DOE facilities are to be overcome. I believe that we have made a good beginning in the long and arduous task of building an Occupational Safety and Health Program that will serve as a model for others, and I can assure you that we intend to continue our efforts to protect every worker within the complex from occupational injury and disease.

Evaluating the Performance of the NASA LaRC CMF Motion Base Safety Devices

NASA Technical Reports Server (NTRS)

Gupton, Lawrence E.; Bryant, Richard B., Jr.; Carrelli, David J.

2006-01-01

This paper describes the initial measured performance results of the previously documented NASA Langley Research Center (LaRC) Cockpit Motion Facility (CMF) motion base hardware safety devices. These safety systems are required to prevent excessive accelerations that could injure personnel and damage simulator cockpits or the motion base structure. Excessive accelerations may be caused by erroneous commands or hardware failures driving an actuator to the end of its travel at high velocity, stepping a servo valve, or instantly reversing servo direction. Such commands may result from single order failures of electrical or hydraulic components within the control system itself, or from aggressive or improper cueing commands from the host simulation computer. The safety systems must mitigate these high acceleration events while minimizing the negative performance impacts. The system accomplishes this by controlling the rate of change of valve signals to limit excessive commanded accelerations. It also aids hydraulic cushion performance by limiting valve command authority as the actuator approaches its end of travel. The design takes advantage of inherent motion base hydraulic characteristics to implement all safety features using hardware only solutions.

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...

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

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

Not Available

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

Exposure of farm laborers and dairy cattle to formaldehyde from footbath use at a dairy farm in New York State.

PubMed

Doane, M; Sarenbo, S

2014-07-15

Formalin footbaths are commonly used in the dairy industry to prevent cattle hoof diseases. Although formalin is a well-documented disinfectant, it is also a carcinogen and irritant. The aim of this study was to estimate the exposure of farm workers and dairy cattle to formaldehyde from footbaths located in a milking facility and a heifer facility at a dairy farm in western New York, USA. The dairy farm included approximately 3900 dairy cattle including young stock; of these, 1670 cows were milked three times per day in a 60-stall carousel milking parlor, and approximately 800 heifers were located at the heifer facility where footbaths with formalin were in use. The formaldehyde concentration of the air was measured using a Formaldemeter™ htV approximately 50cm above the 3% formalin footbaths in the milking (one footbath location) and heifer (three footbath locations) facilities on three consecutive days. The measured formaldehyde concentrations varied between 0.00 and 2.28ppm, falling within the safety guidelines established by the Occupation Safety and Health Administration (OSHA) of the United States. Significant differences were found in the formaldehyde concentrations at the different footbath locations in the heifer facility, potentially due to the varying levels of ventilation at each location. Changes in the ambient temperature during the 3-day sampling period did not significantly affect the concentrations. We believe that the substantial ventilation at both the heifer and milking facilities ensured that the formaldehyde concentrations did not exceed OSHA guidelines, thus permitting the safe use of formalin footbaths in this farm. Copyright © 2014 Elsevier B.V. All rights reserved.

Microgravity Experiments Safety and Integration Requirements Document Tree

NASA Technical Reports Server (NTRS)

Hogan, Jean M.

1995-01-01

This report is a document tree of the safety and integration documents required to develop a space experiment. Pertinent document information for each of the top level (tier one) safety and integration documents, and their applicable and reference (tier two) documents has been identified. This information includes: document title, revision level, configuration management, electronic availability, listed applicable and reference documents, source for obtaining the document, and document owner. One of the main conclusions of this report is that no single document tree exists for all safety and integration documents, regardless of the Shuttle carrier. This document also identifies the need for a single point of contact for customers wishing to access documents. The data in this report serves as a valuable information source for the NASA Lewis Research Center Project Documentation Center, as well as for all developers of space experiments.

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...

Annual Report to Congress of the Atomic Energy Commission for 1965

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

Seaborg, Glenn T.

1966-01-31

The document represents the 1965 Annual Report of the Atomic Energy Commission (AEC) to Congress. The report opens with a Foreword - a letter from President Lyndon B. Johnson. The main portion is divided into 3 major sections for 1965, plus 10 appendices and the index. Section names and chapters are as follows. Part One reports on Developmental and Promotional Activities with the following chapters: (1) The Atomic Energy Program - 1965; (2) The Industrial Base ; (3) Industrial Relations; (4) Operational Safety; (5) Source and Special Nuclear Materials Production; (6) The Nuclear Defense Effort; (7) Civilian Nuclear Power; (8)more » Nuclear Space Applications; (9) Auxiliary Electrical Power for Land and Sea; (10) Military Reactors; (11) Advanced Reactor Technology and Nuclear Safety Research; (12) The Plowshare Program; (13) Isotopes and Radiation Development; (14) Facilities and Projects for Basic Research; (15) International Cooperation; and, (16) Nuclear Education and Information. Part Two reports on Regulatory Activities with the following chapters: (1) Licensing and Regulating the Atom; (2) Reactors and other Nuclear Facilities; and, (3) Control of Radioactive Materials. Part Three reports on Adjudicatory Activities.« less

The NTF Inlet Guide Vanes Thermal Gradient Problem and Its Mitigation

NASA Technical Reports Server (NTRS)

Venkat, Venki S.; Paryz, Roman W.; Bissett, Owen W.; Kilgore, W.

2013-01-01

The National Transonic Facility (NTF) utilizes Inlet Guide Vanes (IGV) to provide precise, quick response Mach number control for the tunnel. During cryogenic operations, the massive IGV structure can experience large thermal gradients, measured as "Delta T or (Delta)T", between the IGV ring and its support structure called the transfer case. If these temperature gradients are too large, the IGV structure can be stressed beyond its safety limit and cease operation. In recent years, (Delta)T readings exceeding the prescribed safety limits were observed frequently during cryogenic operations, particularly during model access. The tactical operation methods of the tunnel to minimize (Delta)T did not always succeed. One obvious option to remedy this condition is to warm up the IGV structure by disabling the main drive operation, but this "natural" warm up method can takes days in some cases, resulting in productivity loss. This paper documents the thermal gradient problem associated with the IGV structure during cryogenic operation and how the facility has recently achieved an acceptable mitigation which has resulted in improved efficiency of operations.

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

Safety of Rural Nursing Home-to-Emergency Department Transfers: Improving Communication and Patient Information Sharing Across Settings.

PubMed

Tupper, Judith B; Gray, Carolyn E; Pearson, Karen B; Coburn, Andrew F

2015-01-01

The "siloed" approach to healthcare delivery contributes to communication challenges and to potential patient harm when patients transfer between settings. This article reports on the evaluation of a demonstration in 10 rural communities to improve the safety of nursing facility (NF) transfers to hospital emergency departments by forming interprofessional teams of hospital, emergency medical service, and NF staff to develop and implement tools and protocols for standardizing critical interfacility communication pathways and information sharing. We worked with each of the 10 teams to document current communication processes and information sharing tools and to design, implement, and evaluate strategies/tools to increase effective communication and sharing of patient information across settings. A mixed methods approach was used to evaluate changes from baseline in documentation of patient information shared across settings during the transfer process. Study findings showed significant improvement in key areas across the three settings, including infection status and baseline mental functioning. Improvement strategies and performance varied across settings; however, accurate and consistent information sharing of advance directives and medication lists remains a challenge. Study results demonstrate that with neutral facilitation and technical support, collaborative interfacility teams can assess and effectively address communication and information sharing problems that threaten patient safety.

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.

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...

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

Functional safety for the Advanced Technology Solar Telescope

NASA Astrophysics Data System (ADS)

Bulau, Scott; Williams, Timothy R.

2012-09-01

Since inception, the Advanced Technology Solar Telescope (ATST) has planned to implement a facility-wide functional safety system to protect personnel from harm and prevent damage to the facility or environment. The ATST will deploy an integrated safety-related control system (SRCS) to achieve functional safety throughout the facility rather than relying on individual facility subsystems to provide safety functions on an ad hoc basis. The Global Interlock System (GIS) is an independent, distributed, facility-wide, safety-related control system, comprised of commercial off-the-shelf (COTS) programmable controllers that monitor, evaluate, and control hazardous energy and conditions throughout the facility that arise during operation and maintenance. The GIS has been designed to utilize recent advances in technology for functional safety plus revised national and international standards that allow for a distributed architecture using programmable controllers over a local area network instead of traditional hard-wired safety functions, while providing an equivalent or even greater level of safety. Programmable controllers provide an ideal platform for controlling the often complex interrelationships between subsystems in a modern astronomical facility, such as the ATST. A large, complex hard-wired relay control system is no longer needed. This type of system also offers greater flexibility during development and integration in addition to providing for expanded capability into the future. The GIS features fault detection, self-diagnostics, and redundant communications that will lead to decreased maintenance time and increased availability of the facility.

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

Building 9401-2 Plating Shop Surveillance and Maintenance Plan

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

None

1999-05-01

This document provides a plan for implementing surveillance and maintenance (S and M) activities to ensure that Building 9401-2 Plating Shop is maintained in a cost effective and environmentally secure configuration until subsequent closure during the final disposition phase of decommissioning. U.S. Department of Energy (DOE) G430.1A-2, Surveillance and Maintenance During Facility Disposition (1997), was used as guidance in the development of this plan. The S and M Plan incorporates DOE O 430.1A, Life Cycle Asset Management (LCAM) (1998a) direction to provide for conducting surveillance and maintenance activities required to maintain the facility and remaining hazardous and radioactive materials, wastes,more » and contamination in a stable and known condition pending facility disposition. Recommendations in the S and M plan have been made that may not be requirement-based but would reduce the cost and frequency of surveillance and maintenance activities. During the course of S and M activities, the facility's condition may change so as to present an immediate or developing hazard or unsatisfactory condition. Corrective action should be coordinated with the appropriate support organizations using the requirements and guidance stated in procedure Y10-202, Rev. 1, Integrated Safety Management Program, (Lockheed Martin Energy Systems, Inc. (LMES), 1998a) implemented at the Oak Ridge Y-12 Plant and the methodology of the Nuclear Operations Conduct of Operations Manual (LMES, 1999) for the Depleted Uranium Operations (DUO) organization. The key S and M objectives applicable to the Plating Shop are to: Ensure adequate containment of remaining residual material in exhaust stacks and outside process piping, stored chemicals awaiting offsite shipment, and items located in the Radioactive Material Area (RMA); Provide access control into the facility and physical safety to S and M personnel; Maintain the facility in a manner that will protect the public, the environment, and the S and M personnel; Provide an S and M plan which identifies and complies with applicable environmental, safety, and health safeguards and security requirements; and Provide a cost effective S and M program for the plating shop, Building 9401-2.« less

Environment, Health, and Safety - Construction Subcontractors Documents |

Science.gov Websites

NREL Environment, Health, and Safety - Construction Subcontractors Documents Environment , Health, and Safety - Construction Subcontractors Documents The purpose of this page is to ensure NREL Environment, Health and Safety (EH&S) requirements are understood by construction subcontractors and

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

Better Oversight Needed for Safety and Health Activities at DOE’s Nuclear Facilities.

DTIC Science & Technology

1981-08-04

States Acca !3ion Tor Kl. ; BRA&I DTIC TAi \\ • inounced Jusl Lfii I "• ’ DiStril on/ r\\ D i Avai3 i - ’•ity Coi a j...m*d——I—^1 I —* Even DOE’s audit report tracking system failed to adequately document corrective actions taken or planned. This system was...designed by DOE to ensure that corrective actions on audit report recommendations are responsive, timely and complete. Audit re- ports, such as ours

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...

How to develop a Standard Operating Procedure for sorting unfixed cells

PubMed Central

Schmid, Ingrid

2012-01-01

Written Standard Operating Procedures (SOPs) are an important tool to assure that recurring tasks in a laboratory are performed in a consistent manner. When the procedure covered in the SOP involves a high-risk activity such as sorting unfixed cells using a jet-in-air sorter, safety elements are critical components of the document. The details on sort sample handling, sorter set-up, validation, operation, troubleshooting, and maintenance, personal protective equipment (PPE), and operator training, outlined in the SOP are to be based on careful risk assessment of the procedure. This review provides background information on the hazards associated with sorting of unfixed cells and the process used to arrive at the appropriate combination of facility design, instrument placement, safety equipment, and practices to be followed. PMID:22381383

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

Voluntarily Stopping Eating and Drinking: A Practical Approach for Long-Term Care Facilities.

PubMed

Gruenewald, David A

2018-06-05

Some residents of long-term care (LTC) facilities with lethal or serious chronic illnesses may express a wish to hasten their death by voluntarily stopping eating and drinking (VSED). LTC facility clinicians, administrators, and staff must balance resident safety, moral objections to hastened death, and other concerns with resident rights to autonomy, self-determination, and bodily integrity. Initially, requests for hastened death, including VSED must be treated as opportunities to uncover underlying concerns. After a concerted effort to address root causes of suffering, some residents will continue to request hastened death. Rigorous resident assessment, interdisciplinary care planning, staff training, and clear and complete documentation are mandatory. In addition, an independent second opinion from a consultant with palliative care and/or hospice expertise is indicated to help determine the most appropriate response. When VSED is the only acceptable option to relieve suffering of residents with severe chronic and lethal illnesses, facilitating VSED requests honors resident-centered care. The author offers practice suggestions and a checklist for LTC facilities and staff caring for residents requesting and undergoing VSED.

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.

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.

Car manufacturers and global road safety: a word frequency analysis of road safety documents.

PubMed

Roberts, I; Wentz, R; Edwards, P

2006-10-01

The World Bank believes that the car manufacturers can make a valuable contribution to road safety in poor countries and has established the Global Road Safety Partnership (GRSP) for this purpose. However, some commentators are sceptical. The authors examined road safety policy documents to assess the extent of any bias. Word frequency analyses of road safety policy documents from the World Health Organization (WHO) and the GRSP. The relative occurrence of key road safety terms was quantified by calculating a word prevalence ratio with 95% confidence intervals. Terms for which there was a fourfold difference in prevalence between the documents were tabulated. Compared to WHO's World report on road traffic injury prevention, the GRSP road safety documents were substantially less likely to use the words speed, speed limits, child restraint, pedestrian, public transport, walking, and cycling, but substantially more likely to use the words school, campaign, driver training, and billboard. There are important differences in emphasis in road safety policy documents prepared by WHO and the GRSP. Vigilance is needed to ensure that the road safety interventions that the car industry supports are based on sound evidence of effectiveness.

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

Poster - Thur Eve - 07: CNSC Update: "What's New in Class II".

PubMed

Heimann, M

2012-07-01

The Accelerators and Class II Facilities Division (ACFD) of the Canadian Nuclear Safety Commission (CNSC), is responsible for the oversight of radiotherapy facilities containing Class II prescribed equipment in Canada. This poster will highlight a number of new initiatives that the CNSC has implemented recently that have an impact on radiotherapy facility licensees. The presentation will discuss the recent policy decision to regulate particle accelerators of above 1 MeV. Challenges and progress with respect to the implementation of the policy will be presented. Other initiatives which will be described include: • The new ACFD webspace on the CNSC website, with direct links to relevant information on licensing, compliance and Class II prescribed equipment • The improved structure of the Appendix of Licence Documents that is part of every Class II licence • Updated licence application guides • Changes to Annual Compliance reporting requirements and progress on the ACR-Online initiative • Changes to some regulatory expectations related to medical accelerator facilities • Consolidation of Class II facility licences The poster will also include other initiatives that may be of particular interest to COMP membership. © 2012 American Association of Physicists in Medicine.

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

30 CFR 585.632 - What documents must I submit before I may construct and install facilities under my approved COP?

Code of Federal Regulations, 2014 CFR

2014-07-01

... construct and install facilities under my approved COP? 585.632 Section 585.632 Mineral Resources BUREAU OF... Approved Cop § 585.632 What documents must I submit before I may construct and install facilities under my approved COP? (a) You must submit to BOEM the documents listed in the following table: Document...

30 CFR 585.632 - What documents must I submit before I may construct and install facilities under my approved COP?

Code of Federal Regulations, 2013 CFR

2013-07-01

... construct and install facilities under my approved COP? 585.632 Section 585.632 Mineral Resources BUREAU OF... Approved Cop § 585.632 What documents must I submit before I may construct and install facilities under my approved COP? (a) You must submit to BOEM the documents listed in the following table: Document...

30 CFR 585.632 - What documents must I submit before I may construct and install facilities under my approved COP?

Code of Federal Regulations, 2012 CFR

2012-07-01

... construct and install facilities under my approved COP? 585.632 Section 585.632 Mineral Resources BUREAU OF... Approved Cop § 585.632 What documents must I submit before I may construct and install facilities under my approved COP? (a) You must submit to BOEM the documents listed in the following table: Document...

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

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...

78 FR 55282 - Federal Housing Administration (FHA) Healthcare Facility Documents: Notice of Information...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-10

... HUD has determined must be submitted with original signatures, in hard copy format. These documents... facility documents, in addition to being presented in an unmarked format, were presented in redline/strikeout format so that reviewers could see the changes proposed to the existing healthcare facility...

NIST Document Sharing Test Facility

Science.gov Websites

NIST Document Sharing Test Facility This site supports the IHE effort in Document Sharing as part . This test facility is based on the IHE IT Infrastructure Technical Framework. All testing done against that Patient IDs be pre-registered before submitting metadata about them. To allocate new patient IDs

78 FR 16279 - HUD Healthcare Facility Documents: Notice Announcing Final Approved Documents and Assignment of...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-03-14

... DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT [Docket No. FR-5623-N-03] HUD Healthcare Facility... notice announces that the healthcare facility documents have completed the notice and comment processes... of Healthcare Programs, Office of Housing, Department of Housing and Urban Development, 451 7th...

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4

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

Greene, N.M.; Petrie, L.M.; Westfall, R.M.

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system hasmore » been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries.« less

Integration Process for Payloads in the Fluids and Combustion Facility

NASA Technical Reports Server (NTRS)

Free, James M.; Nall, Marsha M.

2001-01-01

The Fluids and Combustion Facility (FCF) is an ISS research facility located in the United States Laboratory (US Lab), Destiny. The FCF is a multi-discipline facility that performs microgravity research primarily in fluids physics science and combustion science. This facility remains on-orbit and provides accommodations to multi-user and Principal investigator (PI) unique hardware. The FCF is designed to accommodate 15 PI's per year. In order to allow for this number of payloads per year, the FCF has developed an end-to-end analytical and physical integration process. The process includes provision of integration tools, products and interface management throughout the life of the payload. The payload is provided with a single point of contact from the facility and works with that interface from PI selection through post flight processing. The process utilizes electronic tools for creation of interface documents/agreements, storage of payload data and rollup for facility submittals to ISS. Additionally, the process provides integration to and testing with flight-like simulators prior to payload delivery to KSC. These simulators allow the payload to test in the flight configuration and perform final facility interface and science verifications. The process also provides for support to the payload from the FCF through the Payload Safety Review Panel (PSRP). Finally, the process includes support in the development of operational products and the operation of the payload on-orbit.

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.

National Wind Technology Center sitewide, Golden, CO: Environmental assessment

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

NONE

1996-11-01

The National Renewable Energy Laboratory (NREL), the nation`s primary solar and renewable energy research laboratory, proposes to expand its wind technology research and development program activities at its National Wind Technology Center (NWTC) near Golden, Colorado. NWTC is an existing wind energy research facility operated by NREL for the US Department of Energy (DOE). Proposed activities include the construction and reuse of buildings and facilities, installation of up to 20 wind turbine test sites, improvements in infrastructure, and subsequent research activities, technology testing, and site operations. In addition to wind turbine test activities, NWTC may be used to support othermore » NREL program activities and small-scale demonstration projects. This document assesses potential consequences to resources within the physical, biological, and human environment, including potential impacts to: air quality, geology and soils, water resources, biological resources, cultural and historic resources, socioeconomic resources, land use, visual resources, noise environment, hazardous materials and waste management, and health and safety conditions. Comment letters were received from several agencies in response to the scoping and predecisional draft reviews. The comments have been incorporated as appropriate into the document with full text of the letters contained in the Appendices. Additionally, information from the Rocky Flats Environmental Technology Site on going sitewide assessment of potential environmental impacts has been reviewed and discussed by representatives of both parties and incorporated into the document as appropriate.« less

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...

Tiger Team Assessment of the Fermi National Accelerator Laboratory

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

Not Available

1992-06-01

This draft report documents the Tiger Team Assessment of the Fermi National Accelerator Laboratory (Fermilab) located in Batavia, Illinois. Fermilab is a program-dedicated national laboratory managed by the Universities Research Association, Inc. (URA) for the US Department of Energy (DOE). The Tiger Team Assessment was conducted from May 11 to June 8, 1992, under the auspices of DOE's Office of Special Projects (OSP) under the Office of the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety and health (ES H), and quality assurance (QA) disciplines; site remediation; facilities management; and waste management operations.more » Compliance with applicable Federal , State of Illinois, and local regulations; applicable DOE Orders; best management practices; and internal Fermilab requirements was addressed. In addition, an evaluation of the effectiveness of DOE and Fermilab management of the ES H/QA and self-assessment programs was conducted. The Fermilab Tiger Team Assessment is part a larger, comprehensive DOE Tiger Team Independent Assessment Program planned for DOE facilities. The objective of the initiative is to provide the Secretary of Energy with information on the compliance status of DOE facilities with regard to ES H requirements, root causes for noncompliance, adequacy of DOE and contractor ES H management programs, response actions to address the identified problem areas, and DOE-wide ES H compliance trends and root causes.« less

Tiger Team Assessment of the Fermi National Accelerator Laboratory

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

Not Available

1992-06-01

This draft report documents the Tiger Team Assessment of the Fermi National Accelerator Laboratory (Fermilab) located in Batavia, Illinois. Fermilab is a program-dedicated national laboratory managed by the Universities Research Association, Inc. (URA) for the US Department of Energy (DOE). The Tiger Team Assessment was conducted from May 11 to June 8, 1992, under the auspices of DOE`s Office of Special Projects (OSP) under the Office of the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety and health (ES&H), and quality assurance (QA) disciplines; site remediation; facilities management; and waste management operations. Compliancemore » with applicable Federal , State of Illinois, and local regulations; applicable DOE Orders; best management practices; and internal Fermilab requirements was addressed. In addition, an evaluation of the effectiveness of DOE and Fermilab management of the ES&H/QA and self-assessment programs was conducted. The Fermilab Tiger Team Assessment is part a larger, comprehensive DOE Tiger Team Independent Assessment Program planned for DOE facilities. The objective of the initiative is to provide the Secretary of Energy with information on the compliance status of DOE facilities with regard to ES&H requirements, root causes for noncompliance, adequacy of DOE and contractor ES&H management programs, response actions to address the identified problem areas, and DOE-wide ES&H compliance trends and root causes.« less

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

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

Coenenberg, J.G.

1997-08-15

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit applicationmore » guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating text. 38 39 Information provided in this Liquid Effluent Retention Facility and 40 200 Area Effluent Treatment Facility permit application documentation is 41 current as of June 1, 1997.« less

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.

Tiger Team Assessment of the National Institute for Petroleum and Energy Research

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

Not Available

1992-05-01

This report documents the Tiger Team Assessment of the National Institute for Petroleum and Energy Research (NIPER) and the Bartlesville Project Office (BPO) of the Department of Energy (DOE), co-located in Bartlesville, Oklahoma. The assessment investigated the status of the environmental, safety, and health (ES H) programs of the two organizations. The Tiger Team Assessment was conducted from April 6 to May 1, 1992, under the auspices of DOE's Office of Special Projects (OSP) in the Office of the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety, and health issues; management practices; qualitymore » assurance; and NIPER and BPO self-assessments. Compliance with Federal, state, and local regulations; DOE Orders; best management practices; and internal IITRI requirements was assessed. In addition, an evaluation was conducted of the adequacy and effectiveness of BPO and IITRI management of the ES H and self-assessment processes. The NIPER/BPO Tiger Team Assessment is part of a larger, comprehensive DOE Tiger Team Independent Assessment Program planned for DOE facilities. The objective of the initiative is to provide the Secretary with information on the compliance status of DOE facilities with regard to ES H requirements, root causes for noncompliance, adequacy of DOE and contractor ES H management programs, response actions to address the identified problem areas, and DOE-wide ES H compliance trends and root causes.« less

Tiger Team Assessment of the National Institute for Petroleum and Energy Research

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

Not Available

1992-05-01

This report documents the Tiger Team Assessment of the National Institute for Petroleum and Energy Research (NIPER) and the Bartlesville Project Office (BPO) of the Department of Energy (DOE), co-located in Bartlesville, Oklahoma. The assessment investigated the status of the environmental, safety, and health (ES&H) programs of the two organizations. The Tiger Team Assessment was conducted from April 6 to May 1, 1992, under the auspices of DOE`s Office of Special Projects (OSP) in the Office of the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety, and health issues; management practices; quality assurance;more » and NIPER and BPO self-assessments. Compliance with Federal, state, and local regulations; DOE Orders; best management practices; and internal IITRI requirements was assessed. In addition, an evaluation was conducted of the adequacy and effectiveness of BPO and IITRI management of the ES&H and self-assessment processes. The NIPER/BPO Tiger Team Assessment is part of a larger, comprehensive DOE Tiger Team Independent Assessment Program planned for DOE facilities. The objective of the initiative is to provide the Secretary with information on the compliance status of DOE facilities with regard to ES&H requirements, root causes for noncompliance, adequacy of DOE and contractor ES&H management programs, response actions to address the identified problem areas, and DOE-wide ES&H compliance trends and root causes.« 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...

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

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...

Using resources for scientific-driven pharmacovigilance: from many product safety documents to one product safety master file.

PubMed

Furlan, Giovanni

2012-08-01

Current regulations require a description of the overall safety profile or the specific risks of a drug in multiple documents such as the Periodic and Development Safety Update Reports, Risk Management Plans (RMPs) and Signal Detection Reports. In a resource-constrained world, the need for preparing multiple documents reporting the same information results in shifting the focus from a thorough scientific and medical evaluation of the available data to maintaining compliance with regulatory timelines. Since the aim of drug safety is to understand and characterize product issues to take adequate risk minimization measures rather than to comply with bureaucratic requirements, there is the need to avoid redundancy. In order to identify core drug safety activities that need to be undertaken to protect patient safety and reduce the number of documents reporting the results of these activities, the author has reviewed the main topics included in the drug safety guidelines and templates. The topics and sources that need to be taken into account in the main regulatory documents have been found to greatly overlap and, in the future, as a result of the new Periodic Safety Update Report structure and requirements, in the author's opinion this overlap is likely to further increase. Many of the identified inter-document differences seemed to be substantially formal. The Development Safety Update Report, for example, requires separate presentation of the safety issues emerging from different sources followed by an overall evaluation of each safety issue. The RMP, instead, requires a detailed description of the safety issues without separate presentation of the evidence derived from each source. To some extent, however, the individual documents require an in-depth analysis of different aspects; the RMP, for example, requires an epidemiological description of the indication for which the drug is used and its risks. At the time of writing this article, this is not specifically required by other documents. The author has identified signal detection (intended not only as adverse event disproportionate reporting, but including non-clinical, laboratory, clinical analysis data and literature screening) and characterization as the basis for the preparation of all drug safety documents, which can be viewed as different ways of presenting the results of this activity. Therefore, the author proposes to merge all the aggregate reports required by current regulations into a single document - the Drug Safety Master File. This report should contain all the available information, from any source, regarding the potential and identified risks of a drug. It should be a living document updated and submitted to regulatory authorities on an ongoing basis.

Designing an Alternate Mission Operations Control Room

NASA Technical Reports Server (NTRS)

Montgomery, Patty; Reeves, A. Scott

2014-01-01

The Huntsville Operations Support Center (HOSC) is a multi-project facility that is responsible for 24x7 real-time International Space Station (ISS) payload operations management, integration, and control and has the capability to support small satellite projects and will provide real-time support for SLS launches. The HOSC is a serviceoriented/ highly available operations center for ISS payloads-directly supporting science teams across the world responsible for the payloads. The HOSC is required to endure an annual 2-day power outage event for facility preventive maintenance and safety inspection of the core electro-mechanical systems. While complete system shut-downs are against the grain of a highly available sub-system, the entire facility must be powered down for a weekend for environmental and safety purposes. The consequence of this ground system outage is far reaching: any science performed on ISS during this outage weekend is lost. Engineering efforts were focused to maximize the ISS investment by engineering a suitable solution capable of continuing HOSC services while supporting safety requirements. The HOSC Power Outage Contingency (HPOC) System is a physically diversified compliment of systems capable of providing identified real-time services for the duration of a planned power outage condition from an alternate control room. HPOC was designed to maintain ISS payload operations for approximately three continuous days during planned HOSC power outages and support a local Payload Operations Team, International Partners, as well as remote users from the alternate control room located in another building. This paper presents the HPOC architecture and lessons learned during testing and the planned maiden operational commissioning. Additionally, this paper documents the necessity of an HPOC capability given the unplanned HOSC Facility power outage on April 27th, 2011, as a result of the tornado outbreak that damaged the electrical grid to such a degree that significantly inhibited the Tennessee Valley Authority's ability to transmit electricity throughout the North Alabama region.

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

Pandemic influenza guidance for corporations.

PubMed

2011-06-01

The purpose of this guidance document is to assist members of the American College of Occupational and Environmental Medicine (ACOEM), and the organizations for which they work, in managing the impact of a pandemic of influenza or other contagious respiratory disease on patients, employees, and business. This guidance document outlines actions to take before and during an influenza pandemic on the basis of two main strategies: (1) reducing the spread of the virus within facilities; and (2) providing medical care and medical surveillance to client/patient populations. Facilities in which ACOEM members serve include government agencies and the military, universities, and corporations, which generally have multiple locations/sites and their own medical staff, with members responsible for medical care and disease control. This guidance is for organizations with outpatient occupational medicine services, to be used as appropriate. Medical centers should also use guidance that addresses additional employee and external patient care needs.1–3 The ACOEM fully supports implementation of occupational influenza programs that conform with guidance from the Centers for Disease Control and Prevention (CDC), with other guidance from the US Department of Health and Human Services (DHHS), and Occupational Safety and Health Administration (OSHA) regulations and guidance.

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

How to develop a standard operating procedure for sorting unfixed cells.

PubMed

Schmid, Ingrid

2012-07-01

Written standard operating procedures (SOPs) are an important tool to assure that recurring tasks in a laboratory are performed in a consistent manner. When the procedure covered in the SOP involves a high-risk activity such as sorting unfixed cells using a jet-in-air sorter, safety elements are critical components of the document. The details on sort sample handling, sorter set-up, validation, operation, troubleshooting, and maintenance, personal protective equipment (PPE), and operator training, outlined in the SOP are to be based on careful risk assessment of the procedure. This review provides background information on the hazards associated with sorting of unfixed cells and the process used to arrive at the appropriate combination of facility design, instrument placement, safety equipment, and practices to be followed. Copyright © 2012 Elsevier Inc. All rights reserved.

Health care workers in danger zones: a special report on safety and security in a changing environment.

PubMed

Redwood-Campbell, Lynda J; Sekhar, Sharonya N; Persaud, Christine R

2014-10-01

Violence against humanitarian health care workers and facilities in situations of armed conflict is a serious humanitarian problem. Targeting health care workers and destroying or looting medical facilities directly or indirectly impacts the delivery of emergency and life-saving medical assistance, often at a time when it is most needed. Attacks may be intentional or unintentional and can take a range of forms from road blockades and check points which delay or block transport, to the direct targeting of hospitals, attacks against medical personnel, suppliers, patients, and armed entry into health facilities. Lack of access to vital health care services weakens the entire health system and exacerbates existing vulnerabilities, particularly among communities of women, children, the elderly, and the disabled, or anyone else in need of urgent or chronic care. Health care workers, especially local workers, are often the target. This report reviews the work being spearheaded by the Red Cross and Red Crescent Movement on the Health Care in Danger initiative, which aims to strengthen the protections for health care workers and facilities in armed conflicts and ensure safe access for patients. This includes a review of internal reports generated from the expert workshops on a number of topics as well as a number of public sources documenting innovative coping mechanisms adopted by National Red Cross and Red Crescent Societies. The work of other organizations is also briefly examined. This is followed by a review of security mechanisms within the humanitarian sector to ensure the safety and security of health care personnel operating in armed conflicts. From the existing literature, a number of gaps have been identified with current security frameworks that need to be addressed to improve the safety of health care workers and ensure the protection and access of vulnerable populations requiring assistance. A way forward for policy, research, and practice is proposed for consideration. While there is work being done to improve conditions for health care personnel and patients, there need to be concerted actions to stigmatize attacks against workers, facilities, and patients to protect the neutrality of the medical mission.

DUF6 Conversion Facility EISs

Science.gov Websites

Conversion EIS Documents News FAQs Internet Resources Glossary Home » Conversion Facility EISs EIS Logo Guide | DU Uses | DUF6 Management | DUF6 Conversion Facility EISs | Documents News | FAQs | Internet

Safety of sports facilities and training of graduates in physical education.

PubMed

Romano Spica, V; Giampaoli, S; Di Onofrio, V; Liguori, G

2015-01-01

Post-industrial societies have to face the problem of physical inactivity and inappropriate lifestyles. Programs to promote physical activity are strongly supported by supranational, national and local institutions and organizations. These programs can be developed in sport facilities but also in places that are not institutionally dedicated to sport. The use of urban and working sites has the advantage of better reach the various segments of the population, but at the same time requires coordination between various professionals in structuring an effective intervention. Bibliographical research in the historical archives of the library of the University of Rome Foro Italico, online databases, paleoigiene (wikigiene), documents archives (GSMS-SItI, WHO, ISS, OsEPi, INAIL, ISTAT, national laws). Several guidelines and regulations face the problem of safety in sport environments. The context is in rapid evolution and directions are provided by public health authorities. Graduates in Sport and Physical Activity, represent an additional resource in terms of: prevention and safety in the workplace, health education, application of preventive and adapted physical activities in the territory. These tasks can be integrated in all prevention stages: e.g. childhood and primary prevention programs in school, adapted physical activity for the elderly. The contribution of public health specialists is strategic in the surveillance and coordination of integrated projects. At the same time, graduates in Physical Education appear to be pivots for health promotion and qualified resources for institutions in the territory. Their training should always include contents related to prevention and safety, regulations on sport and working environments, along with bases of preventive medicine related to the context of physical activity.

Proposal for continued research in intelligent machines at the Center for Engineering Systems Advanced Research (CESAR) for FY 1988 to FY 1991

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

Weisbin, C.R.

1987-03-01

This document reviews research accomplishments achieved by the staff of the Center for Engineering Systems Advanced Research (CESAR) during the fiscal years 1984 through 1987. The manuscript also describes future CESAR objectives for the 1988-1991 planning horizon, and beyond. As much as possible, the basic research goals are derived from perceived Department of Energy (DOE) needs for increased safety, productivity, and competitiveness in the United States energy producing and consuming facilities. Research areas covered include the HERMIES-II Robot, autonomous robot navigation, hypercube computers, machine vision, and manipulators.

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS

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

MACKEY, T.C.

2006-03-17

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double shell waste tanks. The analysis is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raise by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review (in April and May 2001) of work being performed on the double-shell tank farms, and the operation of the aging waste facility (AWF) primary tank ventilation system.

Validation of MCNP6 Version 1.0 with the ENDF/B-VII.1 Cross Section Library for Plutonium Metals, Oxides, and Solutions on the High Performance Computing Platform Moonlight

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

Chapman, Bryan Scott; Gough, Sean T.

This report documents a validation of the MCNP6 Version 1.0 computer code on the high performance computing platform Moonlight, for operations at Los Alamos National Laboratory (LANL) that involve plutonium metals, oxides, and solutions. The validation is conducted using the ENDF/B-VII.1 continuous energy group cross section library at room temperature. The results are for use by nuclear criticality safety personnel in performing analysis and evaluation of various facility activities involving plutonium materials.

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.

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...

Effects of increased nurses' workload on quality documentation of patient information at selected Primary Health Care facilities in Vhembe District, Limpopo Province.

PubMed

Shihundla, Rhulani C; Lebese, Rachel T; Maputle, Maria S

2016-05-13

Recording of information on multiple documents increases professional nurses' responsibilities and workload during working hours. There are multiple registers and books at Primary Health Care (PHC) facilities in which a patient's information is to be recorded for different services during a visit to a health professional. Antenatal patients coming for the first visit must be recorded in the following documents: tick register; Prevention of Mother-ToChild Transmission (PMTCT) register; consent form for HIV and AIDS testing; HIV Counselling and Testing (HCT) register (if tested positive for HIV and AIDS then this must be recorded in the Antiretroviral Therapy (ART) wellness register); ART file with an accompanying single file, completion of which is time-consuming; tuberculosis (TB) suspects register; blood specimen register; maternity case record book and Basic Antenatal Care (BANC) checklist. Nurses forget to record information in some documents which leads to the omission of important data. Omitting information might lead to mismanagement of patients. Some of the documents have incomplete and inaccurate information. As PHC facilities in Vhembe District render twenty four hour services through a call system, the same nurses are expected to resume duty at 07:00 the following morning. They are expected to work effectively and when tired a nurse may record illegible information which may cause problems when the document is retrieved by the next person for continuity of care. The objective of this study was to investigate and describe the effects of increased nurses' workload on quality documentation of patient information at PHC facilities in Vhembe District, Limpopo Province. The study was conducted in Vhembe District, Limpopo Province, where the effects of increased nurses' workload on quality documentation of information is currently experienced. The research design was explorative, descriptive and contextual in nature. The population consisted of all nurses who work at PHC facilities in Vhembe District. Purposive sampling was used to select nurses and three professional nurses were sampled from each PHC facility. An in-depth face-to-face interview was used to collect data using an interview guide. PHC facilities encountered several effects due to increased nurses' workload where incomplete patient information is documented. Unavailability of patient information was observed, whilst some documented information was found to be illegible, inaccurate and incomplete. Documentation of information at PHC facilities is an evidence of effective communication amongst professional nurses. There should always be active follow-up and mentoring of the nurses' documentation to ensure that information is accurately and fully documented in their respective facilities. Nurses find it difficult to cope with the increased workload associated with documenting patient information on the multiple records that are utilized at PHC facilities, leading to incomplete information. The number of nurses at facilities should be increased to reduce the increased workload.

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...

36 CFR 1232.16 - What documentation must an agency create before it transfers records to a records storage facility?

Code of Federal Regulations, 2010 CFR

2010-07-01

... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false What documentation must an agency create before it transfers records to a records storage facility? 1232.16 Section 1232.16 Parks... RECORDS TO RECORDS STORAGE FACILITIES § 1232.16 What documentation must an agency create before it...

Radiation predictions and shielding calculations for RITS-6

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

Maenchen, John Eric; O'Malley, John; Kensek, Ronald Patrick

2005-06-01

The mission of Radiographic Integrated Test Stand-6 (RITS-6) facility is to provide the underlying science and technology for pulsed-power-driven flash radiographic X-ray sources for the National Nuclear Security Administration (NNSA). Flash X-ray radiography is a penetrating diagnostic to discern the internal structure in dynamic experiments. Short (~50 nanosecond (ns) duration) bursts of very high intensity Xrays from mm-scale source sizes are required at a variety of voltages to address this mission. RITS-6 was designed and is used to both develop the accelerator technology needed for these experiments and serves as the principal test stand to develop the high intensity electronmore » beam diodes that generate the required X-ray sources. RITS is currently in operation with three induction cavities (RITS-3) with a maximum voltage output of 5.5 MV and is classified as a low hazard non-nuclear facility in accordance with CPR 400.1.1, Chapter 13, Hazards Identification/Analysis and Risk Management. The facility will be expanded from three to six cavities (RITS-6) effectively doubling the operating voltage. The increase in the operating voltage to above 10 MV has resulted in RITS-6 being classified as an accelerator facility. RITS-6 will come under DOE Order 420.2B, Safety of Accelerator Facilities. The hazards of RITS are detailed in the "Safety Assessment Document for the Radiographic Integrated Test Stand Facility." The principal non-industrial hazard is prompt x-ray radiation. As the operating voltage is increased, both the penetration power and the total amount (dose) of x-rays are increased, thereby increasing the risk to local personnel. Fixed site shielding (predominantly concrete walls and a steel/lead skyshine shield) is used to attenuate these x-rays and mitigate this risk. This SAND Report details the anticipated x-ray doses, the shielding design, and the anticipated x-ray doses external to this shielding structure both in areas where administrative access control restricts occupation and in adjacent uncontrolled areas.« less

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.

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

Safety and Security of Radioactive Sealed and Disused/Orphan Sources in Ukraine - German Contribution - 13359

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

Brasser, Thomas; Hertes, Uwe; Meyer, Thorsten

2013-07-01

Within the scope of 'Nuclear Security of Radioactive Sources', the German government implemented the modernization of Ukrainian State Production Company's transport and storage facility for radioactive sources (TSF) in Kiev. The overall management of optimizing the physical protection of the storage facility (including the construction of a hot cell for handling the radioactive sources) is currently carried out by the German Federal Foreign Office (AA). AA jointly have assigned Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Germany's leading expert institution in the area of nuclear safety and waste management, to implement the project and to ensure transparency by financial andmore » technical monitoring. Sealed radioactive sources are widely used in industry, medicine and research. Their life cycle starts with the production and finally ends with the interim/long-term storage of the disused sources. In Ukraine, IZOTOP is responsible for all radioactive sources throughout their life cycle. IZOTOP's transport and storage facility (TSF) is the only Ukrainian storage facility for factory-fresh radioactive sources up to an activity of about 1 million Ci (3.7 1016 Bq). The TSF is specially designed for the storage and handling of radioactive sources. Storage began in 1968, and is licensed by the Ukrainian state authorities. Beside the outdated state of TSF's physical protection and the vulnerability of the facility linked with it, the lack of a hot cell for handling and repacking radioactive sources on the site itself represents an additional potential hazard. The project, financed by the German Federal Foreign Office, aims to significantly improve the security of radioactive sources during their storage and handling at the TSF site. Main tasks of the project are a) the modernization of the physical protection of the TSF itself in order to prevent any unauthorized access to radioactive sources as well as b) the construction of a hot cell to reduce the number of transports of radioactive sources within the city of Kiev. In future, the new established hot cell at IZOTOP's transport and storage facility will be useful for identification and characterization of orphan/disused radioactive sources. The projects implemented are performed in accordance with international recommendations (e. g. IAEA) and national normative documents and will make a crucial contribution towards an improved safety and security management of radioactive sources in Ukraine. (authors)« less

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

Loftin, B.; Abramczyk, G.; Koenig, R.

Radioactive materials are stored in a variety of locations throughout the DOE complex. At the Savannah River Site (SRS), materials are stored within dedicated facilities. Each of those facilities has a documented safety analysis (DSA) that describes accidents that the facility and the materials within it may encounter. Facilities at the SRS are planning on utilizing the certified Model 9977 Shipping Package as a long term storage package and one of these facilities required ballistics testing. Specifically, in order to meet the facility DSA, the radioactive materials (RAM) must be contained within the storage package after impact by a .223more » caliber round. In order to qualify the Model 9977 Shipping Package for storage in this location, the package had to be tested under these conditions. Over the past two years, the Model 9977 Shipping Package has been subjected to a series of ballistics tests. The purpose of the testing was to determine if the 9977 would be suitable for use as a storage package at a Savannah River Site facility. The facility requirements are that the package must not release any of its contents following the impact in its most vulnerable location by a .223 caliber round. A package, assembled to meet all of the design requirements for a certified 9977 shipping configuration and using simulated contents, was tested at the Savannah River Site in March of 2011. The testing was completed and the package was examined. The results of the testing and examination are presented in this paper.« 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.

30 CFR 285.632 - What documents must I submit before I may construct and install facilities under my approved COP?

Code of Federal Regulations, 2011 CFR

2011-07-01

... construct and install facilities under my approved COP? 285.632 Section 285.632 Mineral Resources BUREAU OF... Requirements Activities Under An Approved Cop § 285.632 What documents must I submit before I may construct and install facilities under my approved COP? (a) You must submit to MMS the documents listed in the following...

Arts Education Facilities Planner for Grades 9-12.

ERIC Educational Resources Information Center

North Carolina State Dept. of Public Instruction, Raleigh. Div. of School Support.

This document suggests facilities necessary to conduct instruction in arts programs in grades 9-12 and conveys essential features that should be present. As a reference document for school facilities designers, it describes arts education programs and the facilities that support them, with some sections focusing on the concepts and features common…

Cold Vacuum Drying (CVD) Facility Acceptance for Beneficial Use

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

BRISBIN, S.A.

2000-01-05

This document provides a checklist of the items required for turnover of the Cold Vacuum Drying Facility from the Construction Projects organization to the Operations organization. This document will be updated periodically to document completion of additional deliverables.

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...

The Nuclear Energy Advanced Modeling and Simulation Enabling Computational Technologies FY09 Report

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

Diachin, L F; Garaizar, F X; Henson, V E

2009-10-12

In this document we report on the status of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Enabling Computational Technologies (ECT) effort. In particular, we provide the context for ECT In the broader NEAMS program and describe the three pillars of the ECT effort, namely, (1) tools and libraries, (2) software quality assurance, and (3) computational facility (computers, storage, etc) needs. We report on our FY09 deliverables to determine the needs of the integrated performance and safety codes (IPSCs) in these three areas and lay out the general plan for software quality assurance to meet the requirements of DOE andmore » the DOE Advanced Fuel Cycle Initiative (AFCI). We conclude with a brief description of our interactions with the Idaho National Laboratory computer center to determine what is needed to expand their role as a NEAMS user facility.« less

Program on immunization and cold chain monitoring: the status in eight health districts in Cameroon.

PubMed

Ateudjieu, Jérôme; Kenfack, Bruno; Nkontchou, Blaise Wakam; Demanou, Maurice

2013-03-16

Cold chain monitoring is a precondition to ensure immunization quality, efficacy and safety. In Cameroon, the Expanded Program on Immunization (EPI) has National Standard Operating Procedure (SOP) that describes the vaccines, the cold chain system and equipment, its use and recommended procedures to control and monitor the temperatures and the cold chain. This study was conducted to assess the status of cold chain in eight health districts in Cameroon. The study was carried out in eight health districts out of fifty with poor immunization coverage rate. Data were collected using a validated form by observation and consultation of related documents. District Health Services (DHS) and four Integrated. Health Centers (IHC) randomly selected were targeted per health district. Forty health facilities were included. Twenty eight (70.0%) had at least one functional refrigerator for EPI activities. The power supply was reported to be permanent in 7 (20.6%) out of 34. (85.0%) health facilities with access to power supply. The temperature monitoring chart was pasted on 27 (96.4%) of the cold chain equipment. On 16 (59.3%) of these charts, the temperature was recorded twice daily as recommended. Seven (25.9%) of 27 refrigerators assessed had temperature out of the recommended range of 2 to 8°C. Almost 23.30% of health centers did not received any supervision on cold chain monitoring during a vaccination campaign. This study documents failure of the cold chain maintenance and questions the efficacy and safety of vaccines administered during EPI activities in Cameroun. These findings indicate that appropriate actions are needed to ensure monitoring of EPI cold chain in the country.

Challenges for Nurses Caring for Patients With Peripherally Inserted Central Catheters in Skilled Nursing Facilities

PubMed Central

Harrod, Molly; Montoya, Ana; Mody, Lona; McGuirk, Helen; Winter, Suzanne; Chopra, Vineet

2016-01-01

Objectives To understand frontline nurses’ (registered nurses and licensed practical nurses), unit nurse managers’ and skilled nursing facility (SNF) administrators’ perceived preparedness in providing care for patients with peripherally inserted central catheters (PICCs) in SNFs. Design An exploratory, qualitative pilot study. Setting Two community based SNFs. Participants Patients, frontline nurses (registered nurses and licensed practical nurses), unit nurse managers and SNF administrators. Methods Over 36-weeks, we observed and conducted informal interviews with 56 patients with PICCs and their nurses focusing on PICC care practices and documentation. In addition, we collected baseline PICC data including placement indication (e.g., antimicrobial administration), placement setting (hospital vs. SNF), and dwell time. We then conducted focus groups with frontline nurses and unit nurse managers and semi-structured interviews with SNF administrators to evaluate perceived preparedness for PICC care. Data were analyzed using a descriptive analysis approach. Results During weekly informal interviews and observations variations in documentation were observed. Differences between patient-reported PICC concerns (quality-of-life) and those described by frontline nurses were noted. Deficiencies in communication between hospitals and SNFs with respect to device care, date of last dressing change and PICC removal time were also noted. During focus group sessions, perceived inadequacy of information at the time of care transitions, limited availability of resources to care for PICCs and gaps in training and education were highlighted as barriers in improving practice and safety. Conclusion Our study suggests that practices for PICC care in SNFs can be improved. Multimodal strategies that enhance staff education, improve information exchange during care transitions and increase resource availability in SNFs appear necessary to enhance PICC care and patient safety. PMID:27603747

Challenges for Nurses Caring for Individuals with Peripherally Inserted Central Catheters in Skilled Nursing Facilities.

PubMed

Harrod, Molly; Montoya, Ana; Mody, Lona; McGuirk, Helen; Winter, Suzanne; Chopra, Vineet

2016-10-01

To understand the perceived preparedness of frontline nurses (registered nurses (RNs), licensed practical nurses (LPNs)), unit nurse managers, and skilled nursing facility (SNF) administrators in providing care for residents with peripherally inserted central catheters (PICCs) in SNFs. Exploratory, qualitative pilot study. Two community based SNFs. Residents with PICCs, frontline nurses (RNs, LPNs), unit nurse managers, and SNF administrators. Over 36 weeks, 56 residents with PICCs and their nurses were observed and informally interviewed, focusing on PICC care practices and documentation. In addition, baseline PICC data were collected on placement indication (e.g., antimicrobial administration), placement setting (hospital vs SNF), and dwell time. Focus groups were then conducted with frontline nurses and unit nurse managers, and semistructured interviews were conducted with SNF administrators to evaluate perceived preparedness for PICC care. Data were analyzed using a descriptive analysis approach. Variations in documentation were observed during weekly informal interviews and observations. Differences were noted between resident self-reported PICC concerns (quality of life) and those described by frontline nurses. Deficiencies in communication between hospitals and SNFs with respect to device care, date of last dressing change, and PICC removal time were also noted. During focus group sessions, perceived inadequacy of information at the time of care transitions, limited availability of resources to care for PICCs, and gaps in training and education were highlighted as barriers to improving practice and safety. Practices for PICC care in SNFs can be improved. Multimodal strategies that enhance staff education, improve information exchange during care transitions, and increase resource availability in SNFs appear necessary to enhance PICC care and safety. © 2016, Copyright the Authors Journal compilation © 2016, The American Geriatrics Society.

Program on immunization and cold chain monitoring: the status in eight health districts in Cameroon

PubMed Central

2013-01-01

Background Cold chain monitoring is a precondition to ensure immunization quality, efficacy and safety. In Cameroon, the Expanded Program on Immunization (EPI) has National Standard Operating Procedure (SOP) that describes the vaccines, the cold chain system and equipment, its use and recommended procedures to control and monitor the temperatures and the cold chain. This study was conducted to assess the status of cold chain in eight health districts in Cameroon. Findings The study was carried out in eight health districts out of fifty with poor immunization coverage rate. Data were collected using a validated form by observation and consultation of related documents. District Health Services (DHS) and four Integrated. Health Centers (IHC) randomly selected were targeted per health district. Forty health facilities were included. Twenty eight (70.0%) had at least one functional refrigerator for EPI activities. The power supply was reported to be permanent in 7 (20.6%) out of 34. (85.0%) health facilities with access to power supply. The temperature monitoring chart was pasted on 27 (96.4%) of the cold chain equipment. On 16 (59.3%) of these charts, the temperature was recorded twice daily as recommended. Seven (25.9%) of 27 refrigerators assessed had temperature out of the recommended range of 2 to 8°C. Almost 23.30% of health centers did not received any supervision on cold chain monitoring during a vaccination campaign. Conclusion This study documents failure of the cold chain maintenance and questions the efficacy and safety of vaccines administered during EPI activities in Cameroun. These findings indicate that appropriate actions are needed to ensure monitoring of EPI cold chain in the country. PMID:23497720

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...

78 FR 47805 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-06

... Documents Access and Management System (ADAMS): You may access publicly available documents online in the... Management Plans for Digital Computer Software used in Safety Systems of Nuclear Power Plants,'' issued for... Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Revision...

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...

Composite Overwrapped Pressure Vessels: Database Extension Task 3.0 and Impact Damage Effects Control Task 8.0

NASA Technical Reports Server (NTRS)

Beeson, Harold D.; Davis, Dennis D.; Ross, William L., Sr.; Tapphorn, Ralph M.

2002-01-01

This document represents efforts accomplished at the NASA Johnson Space Center White Sands Test Facility (WSTF) in support of the Enhanced Technology for Composite Overwrapped Pressure Vessels (COPV) Program, a joint research and technology effort among the U.S. Air Force, NASA, and the Aerospace Corporation. WSTF performed testing for several facets of the program. Testing that contributed to the Task 3.0 COPV database extension objective included baseline structural strength, failure mode and safe-life, impact damage tolerance, sustained load/impact effect, and materials compatibility. WSTF was also responsible for establishing impact protection and control requirements under Task 8.0 of the program. This included developing a methodology for establishing an impact control plan. Seven test reports detail the work done at WSTF. As such, this document contributes to the database of information regarding COPV behavior that will ensure performance benefits and safety are maintained throughout vessel service life.

Guidelines for generators to meet HWHF acceptance requirements for hazardous, radioactive, and mixed wastes at Berkeley Lab. Revision 3

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

Albert, R.

1996-06-01

This document provides performance standards that one, as a generator of hazardous chemical, radioactive, or mixed wastes at the Berkeley Lab, must meet to manage their waste to protect Berkeley Lab staff and the environment, comply with waste regulations and ensure the continued safe operation of the workplace, have the waste transferred to the correct Waste Handling Facility, and enable the Environment, Health and Safety (EH and S) Division to properly pick up, manage, and ultimately send the waste off site for recycling, treatment, or disposal. If one uses and generates any of these wastes, one must establish a Satellitemore » Accumulation Area and follow the guidelines in the appropriate section of this document. Topics include minimization of wastes, characterization of the wastes, containers, segregation, labeling, empty containers, and spill cleanup and reporting.« less

TECHNICAL GUIDANCE DOCUMENT: QUALITY ASSURANCE AND QUALITY CONTROL FOR WASTE CONTAINMENT FACILITIES

EPA Science Inventory

This Technical Guidance Document provides comprehensive guidance on procedures for quality assurance and quality control for waste containment facilities. he document includes a discussion of principles and concepts, compacted soil liners, soil drainage systems, geosynthetic drai...

TECHNICAL GUIDANCE DOCUMENT: QUALITY ASSURANCE AND QUALITY CONTROL FOR WASTE CONTAINMENT FACILITIES

EPA Science Inventory

This Technical Guidance Document provides comprehensive guidance on procedures for quality assurance and quality control for waste containment facilities. The document includes a discussion of principles and concepts, compacted soil liners, soil drainage systems, geosynthetic dr...

[Patient safety in home care - A review of international recommendations].

PubMed

Czakert, Judith; Lehmann, Yvonne; Ewers, Michael

2018-06-08

In recent years there has been a growing trend towards nursing care at home in general as well as towards intensive home care being provided by specialized home care services in Germany. However, resulting challenges for patient safety have rarely been considered. Against this background we aimed to explore whether international recommendations for patient safety in home care in general and in intensive home care in particular already exist and how they can stimulate further practice development in Germany. A review of online English documents containing recommendations for patient safety in intensive home care was conducted. Available documents were analyzed and compared in terms of their form and content. Overall, a small number of relevant documents could be identified. None of these documents exclusively refer to the intensive home care sector. Despite their differences, however, the analysis of four selected documents showed similarities, e. g., regarding specific topics of patient safety (communication, involvement of patients and their relatives, risk assessment, medication management, qualification). Furthermore, strengths and weaknesses of the documents became apparent: e. g., an explicit understanding of patient safety, a literature-based introduction to safety topics or an adaptation of the recommendations to the specific features of home care were occasionally lacking. This document analysis provides interesting input to the formal and content-related development of specific recommendations and to practice development in Germany to improve patient safety in home care. Copyright © 2018. Published by Elsevier GmbH.

2001 Safety belt usage survey in Kentucky

DOT National Transportation Integrated Search

2001-08-01

The objective of this study was to establish 2001 safety belt and child safety seat usage rates in Kentucky. The 2001 survey continues to document the results after enactment of a statewide mandatory safety belt law in 1994. It also documented the lo...

Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255

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

Rogers, Ben C.; Heacker, Fred K.; Shannon, Christopher

2013-07-01

The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sitesmore » and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct and install the necessary integrated systems to process the accumulated MVST Facilities SL inventory at the TWPC thus enabling safe and effective disposal of the waste. This BCP does not include work to support current MVST Facility Surveillance and Maintenance programs or the ORNL Building 3019 U-233 Disposition project, since they are not currently part of the TWPC prime contract. The purpose of the environmental compliance strategy is to identify the environmental permits and other required regulatory documents necessary for the construction and operation of the SL- PFB at the TWPC, Oak Ridge, TN. The permits and other regulatory documents identified are necessary to comply with the environmental laws and regulations of DOE Orders, and other requirements documented in the SL-PFB, Safety Design Strategy (SDS), SL-A-AD-002, R0 draft, and the Systems, Function and Requirements Document (SFRD), SL-X-AD-002, R1 draft. This compliance strategy is considered a 'living strategy' and it is anticipated that it will be revised as design progresses and more detail is known. The design basis on which this environmental permitting and compliance strategy is based is the Wastren Advantage, Inc., (WAI), TWPC, SL-PFB (WAI-BL-B.01.06) baseline. (authors)« less

Waste Technology Engineering Laboratory (324 building)

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

Kammenzind, D.E.

The 324 Facility Standards/Requirements Identification Document (S/RID) is comprised of twenty functional areas. Two of the twenty functional areas (Decontamination and Decommissioning and Environmental Restoration) were determined as nonapplicable functional areas and one functional area (Research and Development and Experimental Activities) was determined applicable, however, requirements are found in other functional areas and will not be duplicated. Each functional area follows as a separate chapter, either containing the S/RID or a justification for nonapplicability. The twenty functional areas listed below follow as chapters: 1. Management Systems; 2. Quality Assurance; 3. Configuration Management; 4. Training and Qualification; 5. Emergency Management; 6.more » Safeguards and Security; 7. Engineering Program; 8. Construction; 9. Operations; 10. Maintenance; 11. Radiation Protection; 12. Fire Protection; 13. Packaging and Transportation; 14. Environmental Restoration; 15. Decontamination and Decommissioning; 16. Waste Management; 17. Research and Development and Experimental Activities; 18. Nuclear Safety; 19. Occupational Safety and Health; 20. Environmental Protection.« 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

Accidental fires in clinical laboratories.

PubMed

Hoeltge, G A; Miller, A; Klein, B R; Hamlin, W B

1993-12-01

The National Fire Protection Association, Quincy, Mass, estimates that 169 fires have occurred annually in health care, medical, and chemical laboratories. On the average, there are 13 civilian injuries and $1.5 million per year in direct property damage. Most fires in which the cause or ignition source can be identified originate in malfunctioning electrical equipment (41.6%) or in the facility's electrical distribution system (14.7%). The prevalence of fire safety deficiencies was measured in the College of American Pathologists Laboratory Accreditation Program. Of the 1732 inspected laboratories, 5.5% lacked records of electrical receptacle polarity and ground checks in the preceding year. Of these inspected laboratories, 4.7% had no or incomplete documentation of electrical safety checks on laboratory instruments. There was no evidence of quarterly fire exit drills in 9% of the laboratories. Deficiencies were also found in precautionary labeling (6.8%), in periodic review of safe work practices (4.2%), in the use of safety cans (3.7%), and in venting of flammable liquid storage areas (2.8%). Fire preparedness would be improved if all clinical laboratories had smoke detectors and automatic fire-extinguishing systems. In-service training courses in fire safety should be targeted to the needs of specific service areas.

Report on SARS backfit evaluation, Exxon Donor Solvent Plant, Baytown, Texas

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

Meyer, A.F. Jr.

1980-07-02

This report provides information on observations, findings, and conclusions arising from a site visit to the Exxon Donor Solvent Plant, Baytown, Texas. That visit was to provide technical assistance and professional services to the DOE/ASFE/OPTA Project Officer regarding verification of his initial determination that this pilot plant is exempt from the SARS backfit requirement (DOE Order 5481.1). A secondary purpose was to obtain further information regarding the occupational safety and health plans and procedures at this new pilot plant facility. It is concluded that a well planned and implemented occupational safety and health program exists at the Exxon Donor Solventmore » Plant. Excellent manuals regarding general safety requirements and protection against carcinogens have been prepared and distributed. A Safe Operations Committee is in effect as is a Risk Management Committee. Adequate safety and industrial hygiene staff has been assigned and an excellent medical surveillance program has been established. Adequate compliance with environmental codes, standards, and regulations is being achieved. Although this plant is not subject to SARS because of the nature of the contract, adequate documentation exists in any case to exempt it from the SARS backfit requirement.« less

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...

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.

Accident analysis and control options in support of the sludge water system safety analysis

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

HEY, B.E.

A hazards analysis was initiated for the SWS in July 2001 (SNF-8626, K Basin Sludge and Water System Preliminary Hazard Analysis) and updated in December 2001 (SNF-10020 Rev. 0, Hazard Evaluation for KE Sludge and Water System - Project A16) based on conceptual design information for the Sludge Retrieval System (SRS) and 60% design information for the cask and container. SNF-10020 was again revised in September 2002 to incorporate new hazards identified from final design information and from a What-if/Checklist evaluation of operational steps. The process hazards, controls, and qualitative consequence and frequency estimates taken from these efforts have beenmore » incorporated into Revision 5 of HNF-3960, K Basins Hazards Analysis. The hazards identification process documented in the above referenced reports utilized standard industrial safety techniques (AIChE 1992, Guidelines for Hazard Evaluation Procedures) to systematically guide several interdisciplinary teams through the system using a pre-established set of process parameters (e.g., flow, temperature, pressure) and guide words (e.g., high, low, more, less). The teams generally included representation from the U.S. Department of Energy (DOE), K Basins Nuclear Safety, T Plant Nuclear Safety, K Basin Industrial Safety, fire protection, project engineering, operations, and facility engineering.« 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

Tiger Team Assessment of the Princeton Plasma Physics Laboratory

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

Not Available

1991-03-01

This report documents the Tiger Team Assessment of the Princeton Plasma Physics Laboratory (PPPL) conducted from February 11 to March 12, 1991. The PPPL is operated for the US Department of Energy (DOE) by Princeton University. The assessment was conducted under the auspices of the Headquarters, DOE, Office of Special Projects which is under the Assistant Secretary for Environment, Safety and Health. Activities of the Tiger Team Assessment resulted in identification of compliance findings or concerns and noteworthy practices and an analysis as to the root causes for noncompliance. The PPPL Tiger Team Assessment is one component of a larger,more » comprehensive DOE Tiger Team Assessment program for DOE facilities that will eventually encompass over 100 of the Department's operating facilities. The objective of the initiative is to provide the Secretary with information on the compliance status of DOE facilities with regard to ES H requirements; root causes for noncompliances; adequacy of DOE and contractor ES H management programs; response actions to address the identified problems areas; and DOE-wide ES H compliance trends and root causes.« less

Main steam line break accident simulation of APR1400 using the model of ATLAS facility

NASA Astrophysics Data System (ADS)

Ekariansyah, A. S.; Deswandri; Sunaryo, Geni R.

2018-02-01

A main steam line break simulation for APR1400 as an advanced design of PWR has been performed using the RELAP5 code. The simulation was conducted in a model of thermal-hydraulic test facility called as ATLAS, which represents a scaled down facility of the APR1400 design. The main steam line break event is described in a open-access safety report document, in which initial conditions and assumptionsfor the analysis were utilized in performing the simulation and analysis of the selected parameter. The objective of this work was to conduct a benchmark activities by comparing the simulation results of the CESEC-III code as a conservative approach code with the results of RELAP5 as a best-estimate code. Based on the simulation results, a general similarity in the behavior of selected parameters was observed between the two codes. However the degree of accuracy still needs further research an analysis by comparing with the other best-estimate code. Uncertainties arising from the ATLAS model should be minimized by taking into account much more specific data in developing the APR1400 model.

Plant observation report and evaluation, Pennwalt Corporation, secondary and tertiary aliphatic monoamines

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

Not Available

1980-08-27

A site visit was made to the amine manufacturing facility of the Pennwalt Corporation, Wyandotte, Michigan, to evaluate the facility in regard to the Secondary and Tertiary Aliphatic Monoamines Criteria Document. A total of 21 people were directly in contact with the amine production process. Two to four of the maintenance personnel may also come in contact with the process. Maintenance workers ran the risk of exposure not only to primary, secondary and tertiary amine compounds, but also to several other chemicals being used in the process. The processes used to unload raw materials are described, along with reactor operations,more » decanter and recycling operations, distillation operations, product storage and shipping. Medical monitoring at the facility included chest x-ray, respiratory function tests, sight screening, urinalysis, and back x-rays. Restricted and potentially hazardous area signs were clearly posted. Employees wore hard hats and safety glasses on the job as well as gloves, rubber boots, face shields, goggles, and respirators as necessary. Emergency procedures are described, including fire protection. Sanitation and personal hygiene are discussed, along with monitoring of the workplace conditions.« less

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...

Documenting and determining distributions, trends, and relations in truck times at international border crossing facilities.

DOT National Transportation Integrated Search

2017-01-20

Documenting the times trucks incur when crossing an international border facility is valuable both to the private freight industry and to gateway facility operators and planners. : Members of the project team previously developed and implemented an a...

Environmental Radiation Monitoring at the Areas of the Former Military Technical Bases at the Russian Far East - 12445

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

Kiselev, Sergey M.; Shandala, Nataliya K.; Titov, Alexey V.

After termination of operation at the serviced facilities of the nuclear fleet of the former Soviet Union, the Military Technical Base in Sysoeva Bay has been reorganized to the site for SNF and RW temporary storage (STS). The main activities of STS are receipt, storage and transmission to radioactive waste reprocessing. Establishment of the RW management regional centre in the Far-Eastern region at the STS in Sysoeva Bay implies intensification of SNF and RW management in this region that can result in increasing ecological load to the adjacent areas and settlements. Regulatory supervision of the radiation safety at the areasmore » of the Former Military Technical Bases at the Russian Far East is one of the regulatory functions of the Federal Medical Biological Agency (FMBA of Russia). To regulate SNF an RW management and provide the effective response to changing radiation situation, the environmental radiation monitoring system is arranged. For this purpose, wide range of environmental media examinations at the Sysoeva Bay STS was performed by Burnasyan Federal Medical Biophysical Centre - a technical support organization of FMBA of Russia in collaboration with the Federal State Geological Enterprise 'Hydrospecgeology' (Federal Agency for Entrails). Regulation during the RW and SNF management is continuous process, which the FMBA of Russia implements in close cooperation with other Russian responsible authorities - the State Atomic Energy Corporation 'Rosatom' and Federal Agency for Entrails. The Environmental radiation monitoring findings served as a basis for the associated databank arrangement. The radio ecological monitoring system was arranged at the facilities under inspection for the purpose of the dynamic control of the radiation situation. It presupposes regular radiometry inspections in-situ, their analysis and assessment of the radiation situation forecast in the course of the STS remediation main stages. Some new data on the radiation situation at the facilities will appear in future and the prognostic assessment will become more precise. The mentioned natural, practical and theoretical works is a base for the development of the set of regulatory documents to assure radiation protection and safety of workers, public and environment, as well as development of documents to regulate SNF and RW management at the STS facilities. (authors)« less

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

Evaluation of nuclear-facility decommissioning projects. Summary report: Ames Laboratory Research Reactor

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

Link, B.W.; Miller, R.L.

1983-07-01

This document summarizes the available information concerning the decommissioning of the Ames Laboratory Research Reactor (ALRR), a five-megawatt heavy water moderated and cooled research reactor. The data were placed in a computerized information retrieval/manipulation system which permits its future utilization for purposes of comparative analysis. This information is presented both in detail in its computer output form and also as a manually assembled summarization which highlights the more important aspects of the decommissioning program. Some comparative information with reference to generic decommissioning data extracted from NUREG/CR 1756, Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors, is included.

Safer Liquid Natural Gas

NASA Technical Reports Server (NTRS)

1976-01-01

After the disaster of Staten Island in 1973 where 40 people were killed repairing a liquid natural gas storage tank, the New York Fire Commissioner requested NASA's help in drawing up a comprehensive plan to cover the design, construction, and operation of liquid natural gas facilities. Two programs are underway. The first transfers comprehensive risk management techniques and procedures which take the form of an instruction document that includes determining liquid-gas risks through engineering analysis and tests, controlling these risks by setting up redundant fail safe techniques, and establishing criteria calling for decisions that eliminate or accept certain risks. The second program prepares a liquid gas safety manual (the first of its kind).

Component Selection for Sterile Compounding.

PubMed

Dilzer, Richard H

2017-01-01

This article describes the factors to consider, as well as the process of proper component selection, for use in preparing compounded sterile preparations. Special emphasis is placed on individual chemical factors that may impact a preparation's accuracy and potency. Values reported in a typical certificate of analysis are discussed, including methods of identifying any required adjustments to a master formulation or compounding record during the compounding of sterile preparations. Proper screening of the certificate of analysis, the Safety Data Sheet, procedural documentation, and the filing of all certificates of conformance are crucial to the operation of a sterile compounding facility. Copyright© by International Journal of Pharmaceutical Compounding, Inc.

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...

77 FR 37074 - License Amendment Request From the Alan J. Blotcky Reactor Facility

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-20

... the Alan J. Blotcky Reactor Facility AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... section of this document. FOR FURTHER INFORMATION CONTACT: Theodore Smith, Project Manager, Reactor... provided the first time that a document is referenced. The Alan J. Blotcky Reactor Facility Decommissioning...

HyRAM V1.0 User Guide

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

Groth, Katrina M.; Zumwalt, Hannah Ruth; Clark, Andrew Jordan

2016-03-01

Hydrogen Risk Assessment Models (HyRAM) is a prototype software toolkit that integrates data and methods relevant to assessing the safety of hydrogen fueling and storage infrastructure. The HyRAM toolkit integrates deterministic and probabilistic models for quantifying accident scenarios, predicting physical effects, and characterizing the impact of hydrogen hazards, including thermal effects from jet fires and thermal pressure effects from deflagration. HyRAM version 1.0 incorporates generic probabilities for equipment failures for nine types of components, and probabilistic models for the impact of heat flux on humans and structures, with computationally and experimentally validated models of various aspects of gaseous hydrogen releasemore » and flame physics. This document provides an example of how to use HyRAM to conduct analysis of a fueling facility. This document will guide users through the software and how to enter and edit certain inputs that are specific to the user-defined facility. Description of the methodology and models contained in HyRAM is provided in [1]. This User’s Guide is intended to capture the main features of HyRAM version 1.0 (any HyRAM version numbered as 1.0.X.XXX). This user guide was created with HyRAM 1.0.1.798. Due to ongoing software development activities, newer versions of HyRAM may have differences from this guide.« less

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...

Safety and Health Training Resources.

ERIC Educational Resources Information Center

Federal Safety Advisory Council, Washington, DC.

Information obtained from a survey of safety and health training activities undertaken by Federal agencies is provided in the document which serves as a resource guide and directory of agency safety programs. The document, intended to help Federal managers meet their safety training needs with available government resources, is divided into four…

Hydrogen Fuel Cell Engines and Related Technologies

NASA Astrophysics Data System (ADS)

2001-12-01

The Hydrogen Fuel Cell Engines and Related Technologies report documents the first training course ever developed and made available to the transportation community and general public on the use hydrogen fuel cells in transportation. The course is designed to train a new generation of technicians in gaining a more complete understanding of the concepts, procedures, and technologies involved with hydrogen fuel cell use in transportation purposes. The manual contains 11 modules (chapters). The first eight modules cover (1) hydrogen properties, use and safety; and (2) fuel cell technology and its systems, fuel cell engine design and safety, and design and maintenance of a heavy duty fuel cell bus engine. The different types of fuel cells and hybrid electric vehicles are presented, however, the system descriptions and maintenance procedures focus on proton-exchange-membrane (PEM) fuel cells with respect to heavy duty transit applications. Modules 9 and 10 are intended to provide a better understanding of the acts, codes, regulations and guidelines concerning the use of hydrogen, as well as the safety guidelines for both hydrogen maintenance and fueling facilities. Module 11 presents a glossary and conversions.

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

Safety and fitness electronic records (SAFER) system : logical architecture document : working draft

DOT National Transportation Integrated Search

1997-01-31

This Logical Architecture Document includes the products developed during the functional analysis of the Safety and Fitness Electronic Records (SAFER) System. This document, along with the companion Operational Concept and Physical Architecture Docum...

Nuclear criticality safety staff training and qualifications at Los Alamos National Laboratory

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

Monahan, S.P.; McLaughlin, T.P.

1997-05-01

Operations involving significant quantities of fissile material have been conducted at Los Alamos National Laboratory continuously since 1943. Until the advent of the Laboratory`s Nuclear Criticality Safety Committee (NCSC) in 1957, line management had sole responsibility for controlling criticality risks. From 1957 until 1961, the NCSC was the Laboratory body which promulgated policy guidance as well as some technical guidance for specific operations. In 1961 the Laboratory created the position of Nuclear Criticality Safety Office (in addition to the NCSC). In 1980, Laboratory management moved the Criticality Safety Officer (and one other LACEF staff member who, by that time, wasmore » also working nearly full-time on criticality safety issues) into the Health Division office. Later that same year the Criticality Safety Group, H-6 (at that time) was created within H-Division, and staffed by these two individuals. The training and education of these individuals in the art of criticality safety was almost entirely self-regulated, depending heavily on technical interactions between each other, as well as NCSC, LACEF, operations, other facility, and broader criticality safety community personnel. Although the Los Alamos criticality safety group has grown both in size and formality of operations since 1980, the basic philosophy that a criticality specialist must be developed through mentoring and self motivation remains the same. Formally, this philosophy has been captured in an internal policy, document ``Conduct of Business in the Nuclear Criticality Safety Group.`` There are no short cuts or substitutes in the development of a criticality safety specialist. A person must have a self-motivated personality, excellent communications skills, a thorough understanding of the principals of neutron physics, a safety-conscious and helpful attitude, a good perspective of real risk, as well as a detailed understanding of process operations and credible upsets.« 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.

77 FR 26304 - Federal Housing Administration (FHA) Healthcare Facility Documents: Proposed Revisions and...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-05-03

...Consistent with the Paperwork Reduction Act of 1995 (PRA), HUD is publishing for public comment a comprehensive set of closing and other documents used in connection with transactions involving healthcare facilities (excluding hospitals) that are insured pursuant to section 232 of the National Housing Act (Section 232). In addition to meeting PRA requirements, this notice seeks public comment for the purpose of enlisting input from the lending industry and other interested parties in the development, updating, and adoption of a set of instruments (collectively, healthcare facility documents) that offer the requisite protection to all parties in these FHA-insured mortgage transactions, consistent with modern real estate and mortgage lending laws and practices. The healthcare facility documents, which are the subject of this notice, can be viewed on HUD's Web site: www.hud.gov/232forms. HUD is also publishing today a proposed rule that will submit for public comment certain revisions to FHA's Section 232 regulations for the purpose of ensuring consistency between the program regulations and the revised healthcare facility documents.

Intranet-based safety documentation in management of major hazards and occupational health and safety.

PubMed

Leino, Antti

2002-01-01

In the European Union, Council Directive 96/82/EC requires operators producing, using, or handling significant amounts of dangerous substances to improve their safety management systems in order to better manage the major accident potentials deriving from human error. A new safety management system for the Viikinmäki wastewater treatment plant in Helsinki, Finland, was implemented in this study. The system was designed to comply with both the new safety liabilities and the requirements of OHSAS 18001 (British Standards Institute, 1999). During the implementation phase experiences were gathered from the development processes in this small organisation. The complete documentation was placed in the intranet of the plant. Hyperlinks between documents were created to ensure convenience of use. Documentation was made accessible for all workers from every workstation.

An error taxonomy system for analysis of haemodialysis incidents.

PubMed

Gu, Xiuzhu; Itoh, Kenji; Suzuki, Satoshi

2014-12-01

This paper describes the development of a haemodialysis error taxonomy system for analysing incidents and predicting the safety status of a dialysis organisation. The error taxonomy system was developed by adapting an error taxonomy system which assumed no specific specialty to haemodialysis situations. Its application was conducted with 1,909 incident reports collected from two dialysis facilities in Japan. Over 70% of haemodialysis incidents were reported as problems or complications related to dialyser, circuit, medication and setting of dialysis condition. Approximately 70% of errors took place immediately before and after the four hours of haemodialysis therapy. Error types most frequently made in the dialysis unit were omission and qualitative errors. Failures or complications classified to staff human factors, communication, task and organisational factors were found in most dialysis incidents. Device/equipment/materials, medicine and clinical documents were most likely to be involved in errors. Haemodialysis nurses were involved in more incidents related to medicine and documents, whereas dialysis technologists made more errors with device/equipment/materials. This error taxonomy system is able to investigate incidents and adverse events occurring in the dialysis setting but is also able to estimate safety-related status of an organisation, such as reporting culture. © 2014 European Dialysis and Transplant Nurses Association/European Renal Care Association.

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

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...

Information Scanning and Processing at the Nuclear Safety Information Center.

ERIC Educational Resources Information Center

Parks, Celia; Julian, Carol

This report is a detailed manual of the information specialist's duties at the Nuclear Safety Information Center. Information specialists scan the literature for documents to be reviewed, procure the documents (books, journal articles, reports, etc.), keep the document location records, and return the documents to the plant library or other…

76 FR 10295 - Implementing a Nationwide, Broadband, Interoperable Public Safety Network in the 700 MHz Band

Federal Register 2010, 2011, 2012, 2013, 2014

2011-02-24

... Docket 07-100; FCC 11-6] Implementing a Nationwide, Broadband, Interoperable Public Safety Network in the... framework for the nationwide public safety broadband network. This document considers and proposes... broadband networks operating in the 700 MHz band. This document addresses public safety broadband network...

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,…

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

NONE

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatorymore » Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.« less

Development and Assessment of a Medication Safety Measurement Program in a Long-Term Care Pharmacy.

PubMed

Hertig, John B; Hultgren, Kyle E; Parks, Scott; Rondinelli, Rick

2016-02-01

Medication errors continue to be a major issue in the health care system, including in long-term care facilities. While many hospitals and health systems have developed methods to identify, track, and prevent these errors, long-term care facilities historically have not invested in these error-prevention strategies. The objective of this study was two-fold: 1) to develop a set of medication-safety process measures for dispensing in a long-term care pharmacy, and 2) to analyze the data from those measures to determine the relative safety of the process. The study was conducted at In Touch Pharmaceuticals in Valparaiso, Indiana. To assess the safety of the medication-use system, each step was documented using a comprehensive flowchart (process flow map) tool. Once completed and validated, the flowchart was used to complete a "failure modes and effects analysis" (FMEA) identifying ways a process may fail. Operational gaps found during FMEA were used to identify points of measurement. The research identified a set of eight measures as potential areas of failure; data were then collected on each one of these. More than 133,000 medication doses (opportunities for errors) were included in the study during the research time frame (April 1, 2014, and ended on June 4, 2014). Overall, there was an approximate order-entry error rate of 15.26%, with intravenous errors at 0.37%. A total of 21 errors migrated through the entire medication-use system. These 21 errors in 133,000 opportunities resulted in a final check error rate of 0.015%. A comprehensive medication-safety measurement program was designed and assessed. This study demonstrated the ability to detect medication errors in a long-term pharmacy setting, thereby making process improvements measureable. Future, larger, multi-site studies should be completed to test this measurement program.

MO-AB-201-02: The RSO and The RSC: Challenges and Opportunities

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

Dimock, C.

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatorymore » Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.« less

MO-AB-201-03: The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections

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

Kroger, L.

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatorymore » Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.« 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.

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...

3 CFR - Federal Support for the Randolph-Sheppard Vending Facility Program

Code of Federal Regulations, 2013 CFR

2013-01-01

... 3 The President 1 2013-01-01 2013-01-01 false Federal Support for the Randolph-Sheppard Vending Facility Program Presidential Documents Other Presidential Documents Memorandum of January 20, 2012 Federal Support for the Randolph-Sheppard Vending Facility Program Memorandum for the Heads of Executive Departments and Agencies Thousands of American...

Information security management system planning for CBRN facilities

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

Lenaeu, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.

The focus of this document is to provide guidance for the development of information security management system planning documents at chemical, biological, radiological, or nuclear (CBRN) facilities. It describes a risk-based approach for planning information security programs based on the sensitivity of the data developed, processed, communicated, and stored on facility information systems.

Assessment of documentation requirements under DOE 5481. 1, Safety Analysis and Review System (SARS)

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

Browne, E.T.

1981-03-01

This report assesses the requirements of DOE Order 5481.1, Safety Analysis and Review System for DOE Operations (SARS) in regard to maintaining SARS documentation. Under SARS, all pertinent details of the entire safety analysis and review process for each DOE operation are to be traceable from the initial identification of a hazard. This report is intended to provide assistance in identifying the points in the SARS cycle at which documentation is required, what type of documentation is most appropriate, and where it ultimately should be maintained.

Traceability of Software Safety Requirements in Legacy Safety Critical Systems

NASA Technical Reports Server (NTRS)

Hill, Janice L.

2007-01-01

How can traceability of software safety requirements be created for legacy safety critical systems? Requirements in safety standards are imposed most times during contract negotiations. On the other hand, there are instances where safety standards are levied on legacy safety critical systems, some of which may be considered for reuse for new applications. Safety standards often specify that software development documentation include process-oriented and technical safety requirements, and also require that system and software safety analyses are performed supporting technical safety requirements implementation. So what can be done if the requisite documents for establishing and maintaining safety requirements traceability are not available?

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

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).

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.

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...

16 CFR 1203.3 - Referenced documents.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Referenced documents. 1203.3 Section 1203.3 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY... international standard, it has become a consensus national standard because all recent major voluntary standards...

Aeropropulsion facilities configuration control: Procedures manual

NASA Technical Reports Server (NTRS)

Lavelle, James J.

1990-01-01

Lewis Research Center senior management directed that the aeropropulsion facilities be put under configuration control. A Configuration Management (CM) program was established by the Facilities Management Branch of the Aeropropulsion Facilities and Experiments Division. Under the CM program, a support service contractor was engaged to staff and implement the program. The Aeronautics Directorate has over 30 facilities at Lewis of various sizes and complexities. Under the program, a Facility Baseline List (FBL) was established for each facility, listing which systems and their documents were to be placed under configuration control. A Change Control System (CCS) was established requiring that any proposed changes to FBL systems or their documents were to be processed as per the CCS. Limited access control of the FBL master drawings was implemented and an audit system established to ensure all facility changes are properly processed. This procedures manual sets forth the policy and responsibilities to ensure all key documents constituting a facilities configuration are kept current, modified as needed, and verified to reflect any proposed change. This is the essence of the CM program.

Industrial Hygiene Issues

NASA Technical Reports Server (NTRS)

Brisbin, Steven G.

1999-01-01

This breakout session is a traditional conference instrument used by the NASA industrial hygiene personnel as a method to convene personnel across the Agency with common interests. This particular session focused on two key topics, training systems and automation of industrial hygiene data. During the FY 98 NASA Occupational Health Benchmarking study, the training system under development by the U.S. Environmental Protection Agency (EPA) was deemed to represent a "best business practice." The EPA has invested extensively in the development of computer based training covering a broad range of safety, health and environmental topics. Currently, five compact disks have been developed covering the topics listed: Safety, Health and Environmental Management Training for Field Inspection Activities; EPA Basic Radiation Training Safety Course; The OSHA 600 Collateral Duty Safety and Health Course; and Key program topics in environmental compliance, health and safety. Mr. Chris Johnson presented an overview of the EPA compact disk-based training system and answered questions on its deployment and use across the EPA. This training system has also recently been broadly distributed across other Federal Agencies. The EPA training system is considered "public domain" and, as such, is available to NASA at no cost in its current form. Copies of the five CD set of training programs were distributed to each NASA Center represented in the breakout session. Mr. Brisbin requested that each NASA Center review the training materials and determine whether there is interest in using the materials as it is or requesting that EPA tailor the training modules to suit NASA's training program needs. The Safety, Health and Medical Services organization at Ames Research Center has completed automation of several key program areas. Mr. Patrick Hogan, Safety Program Manager for Ames Research Center, presented a demonstration of the automated systems, which are described by the following: (1) Safety, Health and Environmental Training. This system includes an assessment of training needs for every NASA Center organization, course descriptions, schedules and automated course scheduling, and presentation of training program metrics; (2) Safety and Health Inspection Information. This system documents the findings from each facility inspection, tracks abatement status on those findings and presents metrics on each department for senior management review; (3) Safety Performance Evaluation Profile. The survey system used by NASA to evaluate employee and supervisory perceptions of safety programs is automated in this system; and (4) Documentation Tracking System. Electronic archive and retrieval of all correspondence and technical reports generated by the Safety, Health and Medical Services Office are provided by this system.

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...

Using a 3D CAD plant model to simplify process hazard reviews

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

Tolpa, G.

A Hazard and Operability (HAZOP) review is a formal predictive procedure used to identify potential hazard and operability problems associated with certain processes and facilities. The HAZOP procedure takes place several times during the life cycle of the facility. Replacing plastic models, layout and detail drawings with a 3D CAD electronic model, provides access to process safety information and a detailed level of plant topology that approaches the visualization capability of the imagination. This paper describes the process that is used for adding the use of a 3D CAD model to flowsheets and proven computer programs for the conduct ofmore » hazard and operability reviews. Using flowsheets and study nodes as a road map for the review the need for layout and other detail drawings is all but eliminated. Using the 3D CAD model again for a post-P and ID HAZOP supports conformance to layout and safety requirements, provides superior visualization of the plant configuration and preserves the owners equity in the design. The response from the review teams are overwhelmingly in favor of this type of review over a review that uses only drawings. Over the long term the plant model serves more than just process hazards analysis. Ongoing use of the model can satisfy the required access to process safety information, OHSA documentation and other legal requirements. In this paper extensive instructions address the logic for the process hazards analysis and the preparation required to assist anyone who wishes to add the use of a 3D model to their review.« less

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

36 CFR 1232.16 - What documentation must an agency create before it transfers records to a records storage facility?

Code of Federal Regulations, 2011 CFR

2011-07-01

... agency create before it transfers records to a records storage facility? 1232.16 Section 1232.16 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION RECORDS MANAGEMENT TRANSFER OF RECORDS TO RECORDS STORAGE FACILITIES § 1232.16 What documentation must an agency create before it...

36 CFR 1232.16 - What documentation must an agency create before it transfers records to a records storage facility?

Code of Federal Regulations, 2014 CFR

2014-07-01

... agency create before it transfers records to a records storage facility? 1232.16 Section 1232.16 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION RECORDS MANAGEMENT TRANSFER OF RECORDS TO RECORDS STORAGE FACILITIES § 1232.16 What documentation must an agency create before it...

36 CFR 1232.16 - What documentation must an agency create before it transfers records to a records storage facility?

Code of Federal Regulations, 2012 CFR

2012-07-01

... agency create before it transfers records to a records storage facility? 1232.16 Section 1232.16 Parks, Forests, and Public Property NATIONAL ARCHIVES AND RECORDS ADMINISTRATION RECORDS MANAGEMENT TRANSFER OF RECORDS TO RECORDS STORAGE FACILITIES § 1232.16 What documentation must an agency create before it...

APPA's New Operational Guidelines for Educational Facilities

ERIC Educational Resources Information Center

Bigger, Alan S.

2011-01-01

Nearly 25 years ago a group of APPA members and facilities managers started to discuss an idea and to plant a seed about the need for a document, or series of documents, that would explain the need for staffing facilities operations and the implication of such staffing on levels of service. As the demand for increased budget cuts reached seismic…

[Current Situation Survey of the Measures to Prevent Medication Errors in the Operating Room: Report of the Japan Society of Anesthesiologists Safety Commission Working Group for Consideration of Recommendations for Color Coding of Prepared Syringe Labels for Prevention of Medication Errors].

PubMed

Shida, Kyoko; Suzuki, Toshiyasu; Sugahara, Kazuhiro; Sobue, Kazuya

2016-05-01

In the case of medication errors which are among the more frequent adverse events that occur in the hospital, there is a need for effective measures to prevent incidence. According to the Japan Society of Anesthesiologists study "Drug incident investigation 2005-2007 years", "Error of a syringe at the selection stage" was the most frequent (44.2%). The status of current measures and best practices implemented in Japanese hospitals was the focus of a subsequent investigation. Representative specialists in anesthesiology certified hospitals across the country were surveyed via a questionnaire sampling that lasted 46 days. Investigation method was via the Web with survey responses anonymous. With respect to preventive measures implemented to mitigate risk of medication errors in perioperative settings, responses included: incident and accident report (215 facilities, 70.3%), use of pre-filled syringes (180 facilities, 58.8%), devised the arrangement of dangerous drugs (154 facilities, 50.3%), use of the product with improper connection preventing mechanism (123 facilities, 40.2%), double-check (116 facilities, 37.9%), use of color barreled syringe (115 facilities, 37.6%), use of color label or color tape (89 facilities, 29.1%), presentation of medication such as placing the ampoule or syringe on a tray by dividing color code for drug class on a tray (54 facilities, 17.6%), the discontinuance of handwritten labels (23 facilities, 7.5%), use of a drug verification system that uses bar code (20 facilities, 6.5%), and facilities that have not implemented any means (11 facilities, 3.6%), others not mentioned (10 facilities, 3.3%), and use of carts that count/account the agents by drug type and record selection and number picked automatically (6 facilities, 2.0%). Drug name identification affixed to the syringe via perforated label torn from the ampoule/vial, etc. (245 facilities, 28.1%), handwriting directly to the syringe (208 facilities, 23.8%), use of the attached label (like that comes with the product) (187 facilities, 21.4%), handwriting on the plain tape (87 facilities, 10.0%), printing labels (62 facilities, 7.1%), printed color labels (44 facilities, 5.0%), handwriting on the color tape (27 facilities, 3.1%), machinery for printing the drug name by scanning bar code of the ampoule, etc.(10 facilities, 1.1%), others (3 facilities, 0.3%), no description on the prepared drug (0 facilities, 0%). The awareness of international standard color code, such as by the International Organization for Standardization (ISO), was only 18.6%. Targeting anesthesiology certified hospitals recognized by the Japan Society of Anesthesiologists, the result of the survey on the measures to prevent medication errors during perioperative procedures indicated that various measures were documented in use. However, many facilities still use hand written labels (a common cause for errors). Confirmation of the need for improved drug name and drug recognition on syringe was documented.

Overview of Design, Lifecycle, and Safety for Computer-Based Systems

NASA Technical Reports Server (NTRS)

Torres-Pomales, Wilfredo

2015-01-01

This document describes the need and justification for the development of a design guide for safety-relevant computer-based systems. This document also makes a contribution toward the design guide by presenting an overview of computer-based systems design, lifecycle, and safety.

Public Involvement Opportunities for the DUF6 Conversion Facility EISs

Science.gov Websites

and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home » Conversion Management | DUF6 Conversion Facility EISs | Documents News | FAQs | Internet Resources | Glossary Help

BSL-3 laboratory practices in the United States: comparison of select agent and non-select agent facilities.

PubMed

Richards, Stephanie L; Pompei, Victoria C; Anderson, Alice

2014-01-01

New construction of biosafety level 3 (BSL-3) laboratories in the United States has increased in the past decade to facilitate research on potential bioterrorism agents. The Centers for Disease Control and Prevention inspect BSL-3 facilities and review commissioning documentation, but no single agency has oversight over all BSL-3 facilities. This article explores the extent to which standard operating procedures in US BSL-3 facilities vary between laboratories with select agent or non-select agent status. Comparisons are made for the following variables: personnel training, decontamination, personal protective equipment (PPE), medical surveillance, security access, laboratory structure and maintenance, funding, and pest management. Facilities working with select agents had more complex training programs and decontamination procedures than non-select agent facilities. Personnel working in select agent laboratories were likely to use powered air purifying respirators, while non-select agent laboratories primarily used N95 respirators. More rigorous medical surveillance was carried out in select agent workers (although not required by the select agent program) and a higher level of restrictive access to laboratories was found. Most select agent and non-select agent laboratories reported adequate structural integrity in facilities; however, differences were observed in personnel perception of funding for repairs. Pest management was carried out by select agent personnel more frequently than non-select agent personnel. Our findings support the need to promote high quality biosafety training and standard operating procedures in both select agent and non-select agent laboratories to improve occupational health and safety.

BSL-3 Laboratory Practices in the United States: Comparison of Select Agent and Non–Select Agent Facilities

PubMed Central

Pompei, Victoria C.; Anderson, Alice

2014-01-01

New construction of biosafety level 3 (BSL-3) laboratories in the United States has increased in the past decade to facilitate research on potential bioterrorism agents. The Centers for Disease Control and Prevention inspect BSL-3 facilities and review commissioning documentation, but no single agency has oversight over all BSL-3 facilities. This article explores the extent to which standard operating procedures in US BSL-3 facilities vary between laboratories with select agent or non–select agent status. Comparisons are made for the following variables: personnel training, decontamination, personal protective equipment (PPE), medical surveillance, security access, laboratory structure and maintenance, funding, and pest management. Facilities working with select agents had more complex training programs and decontamination procedures than non–select agent facilities. Personnel working in select agent laboratories were likely to use powered air purifying respirators, while non–select agent laboratories primarily used N95 respirators. More rigorous medical surveillance was carried out in select agent workers (although not required by the select agent program) and a higher level of restrictive access to laboratories was found. Most select agent and non–select agent laboratories reported adequate structural integrity in facilities; however, differences were observed in personnel perception of funding for repairs. Pest management was carried out by select agent personnel more frequently than non–select agent personnel. Our findings support the need to promote high quality biosafety training and standard operating procedures in both select agent and non–select agent laboratories to improve occupational health and safety. PMID:24552359

Living Away from Home Facilities for Isolated Children. Document 78. A Look at Recent Documents of Educational Significance.

ERIC Educational Resources Information Center

Queensland Dept. of Education, Brisbane (Australia).

The first national study of facilities for isolated Australian children living away from home was undertaken by the Commonwealth Schools Commission in 1981 and released in 1983. This document contains the conclusions, findings, and recommendations of the Commonwealth Schools Commission Working Party report. The results prompted the Commission to…

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...

Documenting quality improvement and patient safety efforts: the quality portfolio. A statement from the academic hospitalist taskforce.

PubMed

Taylor, Benjamin B; Parekh, Vikas; Estrada, Carlos A; Schleyer, Anneliese; Sharpe, Bradley

2014-01-01

Physicians increasingly investigate, work, and teach to improve the quality of care and safety of care delivery. The Society of General Internal Medicine Academic Hospitalist Task Force sought to develop a practical tool, the quality portfolio, to systematically document quality and safety achievements. The quality portfolio was vetted with internal and external stakeholders including national leaders in academic medicine. The portfolio was refined for implementation to include an outlined framework, detailed instructions for use and an example to guide users. The portfolio has eight categories including: (1) a faculty narrative, (2) leadership and administrative activities, (3) project activities, (4) education and curricula, (5) research and scholarship, (6) honors, awards, and recognition, (7) training and certification, and (8) an appendix. The authors offer this comprehensive, yet practical tool as a method to document quality and safety activities. It is relevant for physicians across disciplines and institutions and may be useful as a standalone document or as an adjunct to traditional promotion documents. As the Next Accreditation System is implemented, academic medical centers will require faculty who can teach and implement the systems-based practice requirements. The quality portfolio is a method to document quality improvement and safety activities.

A method for independent modelling in support of regulatory review of dose assessments.

PubMed

Dverstorp, Björn; Xu, Shulan

2017-11-01

Several countries consider geological disposal facilities as the preferred option for spent nuclear fuel due to their potential to provide isolation from the surface environment on very long timescales. In 2011 the Swedish Nuclear Fuel & Waste Management Co. (SKB) submitted a license application for construction of a spent nuclear fuel repository. The disposal method involves disposing spent fuel in copper canisters with a cast iron insert at about 500 m depth in crystalline basement rock, and each canister is surrounded by a buffer of swelling bentonite clay. SKB's license application is supported by a post-closure safety assessment, SR-Site. SR-Site has been reviewed by the Swedish Radiation Safety Authority (SSM) for five years. The main method for review of SKB's license application is document review, which is carried out by SSM's staff and supported by SSM's external experts. The review has proven a challenging task due to its broad scope, complexity and multidisciplinary nature. SSM and its predecessors have, for several decades, been developing independent models to support regulatory reviews of post-closure safety assessments for geological repositories. For the review of SR-Site, SSM has developed a modelling approach with a structured application of independent modelling activities, including replication modelling, use of alternative conceptual models and bounding calculations, to complement the traditional document review. This paper describes this scheme and its application to biosphere and dose assessment modelling. SSM's independent modelling has provided important insights regarding quality and reasonableness of SKB's rather complex biosphere modelling and has helped quantifying conservatisms and highlighting conceptual uncertainty. Copyright © 2017 Elsevier Ltd. All rights reserved.

Electronic Medical Record Documentation of Driving Safety for Veterans with Diagnosed Dementia.

PubMed

Vair, Christina L; King, Paul R; Gass, Julie; Eaker, April; Kusche, Anna; Wray, Laura O

2018-01-01

Many older adults continue to drive following dementia diagnosis, with medical providers increasingly likely to be involved in addressing such safety concerns. This study examined electronic medical record (EMR) documentation of driving safety for veterans with dementia (N = 118) seen in Veterans Affairs primary care and interdisciplinary geriatrics clinics in one geographic region over a 10-year period. Qualitative directed content analysis of retrospective EMR data. Assessment of known risk factors or subjective concerns for unsafe driving were documented in fewer than half of observed cases; specific recommendations for driving safety were evident for a minority of patients, with formal driving evaluation the most frequently documented recommendation by providers. Utilizing data from actual clinical encounters provides a unique snapshot of how driving risk and safety concerns are addressed for veterans with dementia. This information provides a meaningful frame of reference for understanding potential strengths and possible gaps in how this important topic area is being addressed in the course of clinical care. The EMR is an important forum for interprofessional communication, with documentation of driving risk and safety concerns an essential element for continuity of care and ensuring consistency of information delivered to patients and caregivers.

TH-B-12A-01: TG124 “A Guide for Establishing a Credentialing and Privileging Program for Users of Fluoroscopic Equipment in Healthcare Organizations”

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

Moore, M

Fluoroscopy credentialing and privileging programs are being instituted because of recorded patient injuries and the widespread growth in fluoroscopy use by operators whose medical education did not include formal fluoroscopy training. This lack of training is recognized as a patient safety deficiency, and medical physicists and health physicists are finding themselves responsible for helping to establish fluoroscopy credentialing programs. While physicians are very knowledgeable about clinical credentials review and the privileging process, medical physicists and health physicists are not as familiar with the process and associated requirements. To assist the qualified medical physicist (QMP) and the radiation safety officer (RSO)more » with these new responsibilities, TG 124 provides an overview of the credentialing process, guidance for policy development and incorporating trained fluoroscopy users into a facility's established process, as well as recommendations for developing and maintaining a risk-based fluoroscopy safety training program. This lecture will review the major topics addressed in TG124 and relate them to practical situations. Learning Objectives: Understand the difference between credentialing and privileging. Understand the responsibilities, interaction and coordination among key individuals and committees. Understand options for integrating the QMP and/or RSO and Radiation Safety Committee into the credentialing and privileging process. Understand issues related to implementing the fluoroscopy safety training recommendations and with verifying and documenting successful completion.« less

PROCESS KNOWLEDGE DATA GATHERING AND REPORTING IN SUPPORT OF DECOMMISSIONING Health Physics Society Annual Meeting West Palm Beach, Florida June 27, 2011

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

David A. King

2011-06-27

Summary of recent ORAU decommissioning activities at the Oak Ridge National Laboratory (ORNL) and the East Tennessee Technology Park (ETTP). Project objective was to generate approved Waste Lot Profiles for legacy facilities scheduled for demolition and shipment to the Environmental Management Waste Management Facility (EMWMF) or appropriate alternate facility. The form and content of process knowledge (PK) reports were developed with input from the EMWMF Waste Acceptance Criteria (WAC) Attainment Team and regulators. PK may be defined as the knowledge of the design and the history of operations that occurs during the life cycle of a facility (paraphrased from SRNLmore » guidance) - similar to the MARSSIM historical site assessment. Some types of PK data used to decommission ORNL and ETTP facilities include: (1) Design drawings; (2) Historical documents [e.g., History of the Oak Ridge National Laboratory by Thomas (1963) and A Brief History of the Chemical Technical Division (ORNL/M-2733)]; (3) Historical photographs; (4) Radiological survey reports; (5) Facility-specific databases - (a) Spill history, (b) Waste Information Tracking System (WITS), and (c) Hazardous Materials Management Information System (HMMIS); (6) Facility walkdown summary reports; and (7) Living memory data. Facility walkdowns are critical for worker safety planning and to assure on-the-ground-conditions match historical descriptions. For Oak Ridge operations, investigators also document the nature and number of items requiring special handling or disposition planning, such as the following: (1) Items containing polychlorinated biphenyls, asbestos, lead, or refrigerants; (2) Items with physical WAC restriction (e.g., large items, pipes, and concrete); and (3) Too 'hot' for EMWMF. Special emphasis was made to interview facility managers, scientists, technicians, or anyone with direct knowledge of process-related activities. Interviews often led to more contact names and reports but also offered anecdotal accounts of releases, process-related operations, maintenance activities, and other relevant information not addressed in the written record. 'Fun' part of PK data gathering. Often got not-so-useful information such as, 'The operations manager was a jerk and we all hated him.' PK data are used to indicate the presence or absence of contaminants. Multiple lines of investigation are necessary for characterization planning and to help determine which disposal facility is best suited for targeted wastes. The model used by ORAU assisted remediation contractors and EMWMF managers by identifying anomalous waste and items requiring special handling.« less

TA-55 Final Safety Analysis Report Comparison Document and DOE Safety Evaluation Report Requirements

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

Alan Bond

2001-04-01

This document provides an overview of changes to the currently approved TA-55 Final Safety Analysis Report (FSAR) that are included in the upgraded FSAR. The DOE Safety Evaluation Report (SER) requirements that are incorporated into the upgraded FSAR are briefly discussed to provide the starting point in the FSAR with respect to the SER requirements.

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...

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...

Public Involvement Opportunities for the DUF6 Conversion Facility EISs

Science.gov Websites

and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home » Conversion | DU Uses | DUF6 Management | DUF6 Conversion Facility EISs | Documents News | FAQs | Internet

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.

Zoonoses of occupational health importance in contemporary laboratory animal research.

PubMed

Hankenson, F Claire; Johnston, Nancy A; Weigler, Benjamin J; Di Giacomo, Ronald F

2003-12-01

In contemporary laboratory animal facilities, workplace exposure to zoonotic pathogens, agents transmitted to humans from vertebrate animals or their tissues, is an occupational hazard. The primary (e.g., macaques, pigs, dogs, rabbits, mice, and rats) and secondary species (e.g., sheep, goats, cats, ferrets, and pigeons) of animals commonly used in biomedical research, as classified by the American College of Laboratory Animal Medicine, are established or potential hosts for a large number of zoonotic agents. Diseases included in this review are principally those wherein a risk to biomedical facility personnel has been documented by published reports of human cases in laboratory animal research settings, or under reasonably similar circumstances. Diseases are listed alphabetically, and each section includes information about clinical disease, transmission, occurrence, and prevention in animal reservoir species and humans. Our goal is to provide a resource for veterinarians, health-care professionals, technical staff, and administrators that will assist in the design and on-going evaluation of institutional occupational health and safety programs.

MO-AB-201-01: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223

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

Phillips, L.

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatorymore » Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35 requirements as they relate to the everyday practice of Nuclear Medicine and Radiation Oncology. Understand the nature of available guidance documents (e.g., NUREG 1556). Examine the commonalities between TJC and CMS preparedness.« less

29 CFR 1905.7 - Form of documents; subscription; copies.

Code of Federal Regulations, 2010 CFR

2010-07-01

... UNDER THE WILLIAMS-STEIGER OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 General § 1905.7 Form of documents... 29 Labor 5 2010-07-01 2010-07-01 false Form of documents; subscription; copies. 1905.7 Section 1905.7 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION...

Reducing Operating Costs by Optimizing Space in Facilities

DTIC Science & Technology

2012-03-01

Base level 5 engineering units will provide facility floor plans, furniture layouts, and staffing documentation as necessary. One obstacle...due to the quantity and diverse locations. Base level engineering units provided facility floor plans, furniture layouts, and staffing documentation... furniture purchases and placement 5. Follow a quality systematic process in all decisions The per person costs can be better understood with a real

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.

Transit vehicle-to-infrastructure (V2I) applications : near term research and development. Transit bus-pedestrian/cyclist crossing safety application : operational concept.

DOT National Transportation Integrated Search

2013-11-01

This document serves as an Operational Concept for the Transit Bus-Pedestrian/Cyclist Crossing Safety application. The purpose of this document is to provide an operational description of how the Transit Bus-Pedestrian/Cyclist Crossing Safety W...

The National Ignition Facility: alignment from construction to shot operations

NASA Astrophysics Data System (ADS)

Burkhart, S. C.; Bliss, E.; Di Nicola, P.; Kalantar, D.; Lowe-Webb, R.; McCarville, T.; Nelson, D.; Salmon, T.; Schindler, T.; Villanueva, J.; Wilhelmsen, K.

2010-08-01

The National Ignition Facility in Livermore, California, completed it's commissioning milestone on March 10, 2009 when it fired all 192 beams at a combined energy of 1.1 MJ at 351nm. Subsequently, a target shot series from August through December of 2009 culminated in scale ignition target design experiments up to 1.2 MJ in the National Ignition Campaign. Preparations are underway through the first half of of 2010 leading to DT ignition and gain experiments in the fall of 2010 into 2011. The top level requirement for beam pointing to target of 50μm rms is the culmination of 15 years of engineering design of a stable facility, commissioning of precision alignment, and precise shot operations controls. Key design documents which guided this project were published in the mid 1990's, driving systems designs. Precision Survey methods were used throughout construction, commissioning and operations for precision placement. Rigorous commissioning processes were used to ensure and validate placement and alignment throughout commissioning and in present day operations. Accurate and rapid system alignment during operations is accomplished by an impressive controls system to align and validate alignment readiness, assuring machine safety and productive experiments.

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…

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.

Green Propellant Landing Demonstration at U.S. Range

NASA Technical Reports Server (NTRS)

Mulkey, Henry W.; Miller, Joseph T.; Bacha, Caitlin E.

2016-01-01

The Green Propellant Loading Demonstration (GPLD) was conducted December 2015 at Wallops Flight Facility (WFF), leveraging work performed over recent years to bring lower toxicity hydrazine replacement green propellants to flight missions. The objective of this collaboration between NASA Goddard Space Flight Center (GSFC), WFF, the Swedish National Space Board (SNSB), and Ecological Advanced Propulsion Systems (ECAPS) was to successfully accept LMP-103S propellant at a U.S. Range, store the propellant, and perform a simulated flight vehicle propellant loading. NASA GSFC Propulsion (Code 597) managed all aspects of the operation, handling logistics, preparing the procedures, and implementing the demonstration. In addition to the partnership described above, Moog Inc. developed an LMP-103S propellant-compatible titanium rolling diaphragm flight development tank and loaned it to GSFC to act as the GPLD flight vessel. The flight development tank offered the GPLD an additional level of flight-like propellant handling process and procedures. Moog Inc. also provided a compatible latching isolation valve for remote propellant expulsion. The GPLD operation, in concert with Moog Inc. executed a flight development tank expulsion efficiency performance test using LMP-103S propellant. As part of the demonstration work, GSFC and WFF documented Range safety analyses and practices including all elements of shipping, storage, handling, operations, decontamination, and disposal. LMP-103S has not been previously handled at a U.S. Launch Range. Requisite for this activity was an LMP-103S Risk Analysis Report and Ground Safety Plan. GSFC and WFF safety offices jointly developed safety documentation for application into the GPLD operation. The GPLD along with the GSFC Propulsion historical hydrazine loading experiences offer direct comparison between handling green propellant versus safety intensive, highly toxic hydrazine propellant. These described motives initiated the GPLD operation in order to investigate the handling and process safety variances in project resources between LMP-103S and typical in-space propellants. The GPLD risk reduction operation proved successful for many reasons including handling the green propellant at a U.S. Range, loading and pressurizing a flight-like tank, expelling the propellant, measuring the tank expulsion efficiency, and most significantly, GSFC propulsion personnel's new insight into the LMP-103S propellant handling details.

Green Propellant Loading Demonstration at U.S. Range

NASA Technical Reports Server (NTRS)

Mulkey, Henry W.; Miller, Joseph T.; Bacha, Caitlin E.

2016-01-01

The Green Propellant Loading Demonstration (GPLD) was conducted December 2015 at Wallops Flight Facility (WFF), leveraging work performed over recent years to bring lower toxicity hydrazine replacement green propellants to flight missions. The objective of this collaboration between NASA Goddard Space Flight Center (GSFC), WFF, the Swedish National Space Board (SNSB), and Ecological Advanced Propulsion Systems (ECAPS) was to successfully accept LMP-103S propellant at a U.S. Range, store the propellant, and perform a simulated flight vehicle propellant loading. NASA GSFC Propulsion (Code 597) managed all aspects of the operation, handling logistics, preparing the procedures, and implementing the demonstration. In addition to the partnership described above, Moog Inc. developed an LMP-103S propellant-compatible titanium rolling diaphragm flight development tank and loaned it to GSFC to act as the GPLD flight vessel. The flight development tank offered the GPLD an additional level of flight-like propellant handling process and procedures. Moog Inc. also provided a compatible latching isolation valve for remote propellant expulsion. The GPLD operation, in concert with Moog Inc. executed a flight development tank expulsion efficiency performance test using LMP-103S propellant. As part of the demonstration work, GSFC and WFF documented Range safety analyses and practices including all elements of shipping, storage, handling, operations, decontamination, and disposal. LMP-103S has not been previously handled at a U.S. Launch Range. Requisite for this activity was an LMP-103S Risk Analysis Report and Ground Safety Plan. GSFC and WFF safety offices jointly developed safety documentation for application into the GPLD operation. The GPLD along with the GSFC Propulsion historical hydrazine loading experiences offer direct comparison between handling green propellant versus safety intensive, highly toxic hydrazine propellant. These described motives initiated the GPLD operation in order to investigate the handling and process safety variances in project resources between LMP-103S and typical in-space propellants. The GPLD risk reduction operation proved successful for many reasons including handling the green propellant at a U.S. Range, loading and pressurizing a flight-like tank, expelling the propellant, measuring the tank expulsion efficiency, and most significantly, GSFC propulsion personnel's new insight into the LMP-103S propellant handling details.

Measuring and documenting truck activity times at international border crossings.

DOT National Transportation Integrated Search

2014-04-01

Documenting the times trucks incur when crossing an international border facility is : valuable both to the private freight industry and to gateway facility operators and planners. : Members of the project team previously developed and implemented an...

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

Process Evaluation of Two Participatory Approaches: Implementing Total Worker Health® Interventions in a Correctional Workforce

PubMed Central

Dugan, Alicia G.; Farr, Dana A.; Namazi, Sara; Henning, Robert A.; Wallace, Kelly N.; El Ghaziri, Mazen; Punnett, Laura; Dussetschleger, Jeffrey L.; Cherniack, Martin G.

2018-01-01

Background Correctional Officers (COs) have among the highest injury rates and poorest health of all the public safety occupations. The HITEC-2 (Health Improvement Through Employee Control-2) study uses Participatory Action Research (PAR) to design and implement interventions to improve health and safety of COs. Method HITEC-2 compared two different types of participatory program, a CO-only “Design Team” (DT) and “Kaizen Event Teams” (KET) of COs and supervisors, to determine differences in implementation process and outcomes. The Program Evaluation Rating Sheet (PERS) was developed to document and evaluate program implementation. Results Both programs yielded successful and unsuccessful interventions, dependent upon team-, facility-, organizational, state-, facilitator-, and intervention-level factors. Conclusions PAR in corrections, and possibly other sectors, depends upon factors including participation, leadership, continuity and timing, resilience, and financial circumstances. The new PERS instrument may be useful in other sectors to assist in assessing intervention success. PMID:27378470

Waste Isolation Pilot Plant Site Environmental Report for 1998

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

Hooda, Balwan S.; Allen, Vivian L.

This 1998 annual Site Environmental Report (SER) was prepared in accordance with U.S. Department of Energy (DOE) Order 5400.1, ''General Environmental Protection Program''; DOE Order 231.1, ''Environmental Safety and Health Reporting''; the ''Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance'' (DOE/EH-0173T); and the Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an SER to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of the SER is to provide a comprehensive description of operational environmental monitoring activities, an abstract of environmental activities conducted tomore » characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year ( CY) 1998. The content of this SER is not restricted to a synopsis of the required data. Information pertaining to new and continued monitoring and compliance activities during CY 1998 are also included.« less

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

Process evaluation of two participatory approaches: Implementing total worker health® interventions in a correctional workforce.

PubMed

Dugan, Alicia G; Farr, Dana A; Namazi, Sara; Henning, Robert A; Wallace, Kelly N; El Ghaziri, Mazen; Punnett, Laura; Dussetschleger, Jeffrey L; Cherniack, Martin G

2016-10-01

Correctional Officers (COs) have among the highest injury rates and poorest health of all the public safety occupations. The HITEC-2 (Health Improvement Through Employee Control-2) study uses Participatory Action Research (PAR) to design and implement interventions to improve health and safety of COs. HITEC-2 compared two different types of participatory program, a CO-only "Design Team" (DT) and "Kaizen Event Teams" (KET) of COs and supervisors, to determine differences in implementation process and outcomes. The Program Evaluation Rating Sheet (PERS) was developed to document and evaluate program implementation. Both programs yielded successful and unsuccessful interventions, dependent upon team-, facility-, organizational, state-, facilitator-, and intervention-level factors. PAR in corrections, and possibly other sectors, depends upon factors including participation, leadership, continuity and timing, resilience, and financial circumstances. The new PERS instrument may be useful in other sectors to assist in assessing intervention success. Am. J. Ind. Med. 59:897-918, 2016. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

The Paucity Problem: Where Have All the Space Reactor Experiments Gone?

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

Bess, John D.; Marshall, Margaret A.

2016-10-01

The Handbooks of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) together contain a plethora of documented and evaluated experiments essential in the validation of nuclear data, neutronics codes, and modeling of various nuclear systems. Unfortunately, only a minute selection of handbook data (twelve evaluations) are of actual experimental facilities and mockups designed specifically for space nuclear research. There is a paucity problem, such that the multitude of space nuclear experimental activities performed in the past several decades have yet to be recovered and made available in such detail that themore » international community could benefit from these valuable historical research efforts. Those experiments represent extensive investments in infrastructure, expertise, and cost, as well as constitute significantly valuable resources of data supporting past, present, and future research activities. The ICSBEP and IRPhEP were established to identify and verify comprehensive sets of benchmark data; evaluate the data, including quantification of biases and uncertainties; compile the data and calculations in a standardized format; and formally document the effort into a single source of verified benchmark data. See full abstract in attached document.« less

NASA Processes and Requirements for Conducting Human-in-the-Loop Closed Chamber Tests

NASA Technical Reports Server (NTRS)

Barta, Daniel J.; Montz, Michael E.

2004-01-01

NASA has specific processes and requirements that must be followed for tests involving human subjects to be conducted in a safe and effective manner. There are five distinct phases of test operations. Phase one, the test request phase, consists of those activities related to initiating, processing, reviewing, and evaluating the test request. Phase two, the test preparation phase consists of those activities related to planning, coordinating, documenting, and building up the test. Phase three, the test readiness phase consists of those activities related to verifying and reviewing the planned test operations. Phase four, the test activity phase, consists of all pretest operations, functional checkouts, emergency drills, and test operations. Phase five, the post test activity phase, consists of those activities performed once the test is completed, including briefings, documentation of anomalies, data reduction and archiving, and reporting. Project management processes must be followed for facility modifications and major test buildup, which include six phases: initiation and assessment, requirements evaluation, preliminary design, detailed design, use readiness review (URR) and acceptance. Compliance with requirements for safety and quality assurance are documented throughout the test buildup and test operation processes. Tests involving human subjects must be reviewed by the applicable Institutional Review Board (IRB).

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.

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.

Prospective implementation of a software application for pre-disposal L/ILW waste management activities in Romania

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

Fako, Raluca; Sociu, Florin; Stan, Camelia

Romania is actively engaged to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Considering relevant documents to be further updated, about 122,000 m{sup 3} SL-LILW are to be disposed in a near surface facility that will have room, also, for quantities of VLLW. Planned date for commissioning is under revision. Taking into account that in this moment there are initiated several actions for the improvement of the technical capability for LILW treatment and conditioning, several steps for the possible use of SAFRAN software weremore » considered. In view of specific data for Romanian radioactive waste inventory, authors are trying to highlight the expected limitations and unknown data related with the implementation of SAFRAN software for the foreseen pre-disposal waste management activities. There are challenges that have to be faced in the near future related with clear definition of the properties of each room, area and waste management activity. This work has the aim to address several LILW management issues in accordance with national and international regulatory framework for the assurance of nuclear safety. Also, authors intend to develop their institutional capability for the safety demonstration of the existent and future radioactive waste management facilities and activities. (authors)« less

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

18 CFR 5.6 - Pre-application document.

Code of Federal Regulations, 2011 CFR

2011-04-01

... project, including any daily or seasonal ramping rates, flushing flows, reservoir operations, and flood... document must describe the existing and proposed (if any) project facilities and operations, provide...)(viii). (2) Project location, facilities, and operations. The potential applicant must include in the...

30 CFR 285.632 - What documents must I submit before I may construct and install facilities under my approved COP?

Code of Federal Regulations, 2010 CFR

2010-07-01

... construct and install facilities under my approved COP? 285.632 Section 285.632 Mineral Resources MINERALS... FACILITIES ON THE OUTER CONTINENTAL SHELF Plans and Information Requirements Activities Under An Approved Cop... COP? (a) You must submit to MMS the documents listed in the following table: ER29AP09.124 (b) You must...