77 FR 55232 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-03; Compliance With...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-09-07

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0067] Japan Lessons-Learned Project Directorate Interim...-Learned Project Directorate Interim Staff Guidance; issuance. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing the Final Japan Lessons-Learned Project Directorate (JLD...

78 FR 40199 - Draft Spent Fuel Storage and Transportation Interim Staff Guidance

Federal Register 2010, 2011, 2012, 2013, 2014

2013-07-03

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0140] Draft Spent Fuel Storage and Transportation Interim... Spent Fuel Storage and Transportation Interim Staff Guidance No. 24 (SFST-ISG-24), Revision 0, ``The Use of a Demonstration Program as Confirmation of Integrity for Continued Storage of High Burnup Fuel...

77 FR 15818 - License Renewal Interim Staff Guidance LR-ISG-2011-05: Ongoing Review of Operating Experience

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-16

...-05: Ongoing Review of Operating Experience AGENCY: Nuclear Regulatory Commission. ACTION: Interim... License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2011-05, ``Ongoing Review of Operating Experience... industry-wide operating experience as an attribute of aging management programs used at nuclear power...

76 FR 60937 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-02; Aging Management Program for Steam...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-30

...-2011-02; Aging Management Program for Steam Generators AGENCY: Nuclear Regulatory Commission. ACTION... License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2011-02, ``Aging Management Program for Steam... using Revision 3 of NEI 97-06 to manage steam generator aging. The Draft LR-ISG revises the NRC staff's...

The Impact of Operating Parameters and Correlated Parameters for Extended BWR Burnup Credit

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

Ade, Brian J.; Marshall, William B. J.; Ilas, Germina

Applicants for certificates of compliance for spent nuclear fuel (SNF) transportation and dry storage systems perform analyses to demonstrate that these systems are adequately subcritical per the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Parts 71 and 72. For pressurized water reactor (PWR) SNF, these analyses may credit the reduction in assembly reactivity caused by depletion of fissile nuclides and buildup of neutron-absorbing nuclides during power operation. This credit for reactivity reduction during depletion is commonly referred to as burnup credit (BUC). US Nuclear Regulatory Commission (NRC) staff review BUC analyses according to the guidancemore » in the Division of Spent Fuel Storage and Transportation Interim Staff Guidance (ISG) 8, Revision 3, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks.« less

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

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-03

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

76 FR 58311 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-05; Ongoing Review of Operating Experience

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-20

... nuclear power plants. In response to a request from the Nuclear Energy Institute (NEI), the NRC is... NUCLEAR REGULATORY COMMISSION [NRC-2011-0191] Draft License Renewal Interim Staff Guidance LR-ISG-2011-05; Ongoing Review of Operating Experience AGENCY: Nuclear Regulatory Commission. ACTION: Draft...

Interim Stabilization Equipment Essential and Support Drawing Plan

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

KOCH, M.R.

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings.

Staff Reactions to Interim Leadership in a Student Affairs Organization

ERIC Educational Resources Information Center

Jones, Robin D.

2011-01-01

Interim leadership appointments in higher education are a common strategy used to fill leadership gaps in executive positions. Because student affairs executives are particularly vulnerable to high turnover rates, interim appointments are becoming more widespread. Even with the prevalence of this trend, little attention has been given to the…

Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia

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

Wolff, Dietmar; Voelzke, Holger; Weber, Wolfgang

2007-07-01

The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted wastemore » monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of Economics and Labour (BMWi). On the Russian side the Kurchatov Institute holds the project management of the long-term interim storage facility in Sayda Bay, whilst the Nerpa Shipyard, which is about 25 km away from the storage facility, is dismantling the submarines and preparing the reactor compartments for long-term interim storage. The technical monitoring of the German part of this project, being implemented by BMWi, is the responsibility of the Federal Institute for Materials Research and Testing (BAM). This paper gives an overview of the German-Russian project and a brief description of solutions for nuclear submarine disposal in other countries. At Nerpa shipyard, being refurbished with logistic and technical support from Germany, the reactor compartments are sealed by welding, provided with biological shielding, subjected to surface treatment and conservation measures. Using floating docks, a tugboat tows the reactor compartments from Nerpa shipyard to the interim storage facility at Sayda Bay where they will be left on the on-shore concrete storage space to allow the radioactivity to decay. For transport of reactor compartments at the shipyard, at the dock and at the storage facility, hydraulic keel blocks, developed and supplied by German subcontractors, are used. In July 2006 the first stage of the reactor compartment storage facility was commissioned and the first seven reactor compartments have been delivered from Nerpa shipyard. Following transports of reactor compartments to the storage facility are expected in 2007. (authors)« less

Interim Guidance: Municipal Solid Waste Exemption under Superfund

EPA Pesticide Factsheets

Interim guidance discusses the statutory provisions of CERCLA § 107(p) and identifies some factors to be considered by EPA and DOJ staff in exercising their enforcement discretion of MSW at an NPL site.

Interim Safe Storage of Plutonium Production Reactors at the US DOE Hanford Site - 13438

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

Schilperoort, Daryl L.; Faulk, Darrin

2013-07-01

Nine plutonium production reactors located on DOE's Hanford Site are being placed into an Interim Safe Storage (ISS) period that extends to 2068. The Environmental Impact Statement (EIS) for ISS [1] was completed in 1993 and proposed a 75-year storage period that began when the EIS was finalized. Remote electronic monitoring of the temperature and water level alarms inside the safe storage enclosure (SSE) with visual inspection inside the SSE every 5 years are the only planned operational activities during this ISS period. At the end of the ISS period, the reactor cores will be removed intact and buried inmore » a landfill on the Hanford Site. The ISS period allows for radioactive decay of isotopes, primarily Co-60 and Cs-137, to reduce the dose exposure during disposal of the reactor cores. Six of the nine reactors have been placed into ISS by having an SSE constructed around the reactor core. (authors)« less

40 CFR 57.803 - Issuance of tentative determination; notice.

Code of Federal Regulations, 2013 CFR

2013-07-01

... determination. (1) The EPA staff shall formulate and prepare: (i) A “Staff Computational Analysis,” using the... Computational Analysis, discussing the estimated cost of interim controls, and assessing the effect upon the...

40 CFR 57.803 - Issuance of tentative determination; notice.

Code of Federal Regulations, 2012 CFR

2012-07-01

... determination. (1) The EPA staff shall formulate and prepare: (i) A “Staff Computational Analysis,” using the... Computational Analysis, discussing the estimated cost of interim controls, and assessing the effect upon the...

40 CFR 57.803 - Issuance of tentative determination; notice.

Code of Federal Regulations, 2014 CFR

2014-07-01

... determination. (1) The EPA staff shall formulate and prepare: (i) A “Staff Computational Analysis,” using the... Computational Analysis, discussing the estimated cost of interim controls, and assessing the effect upon the...

40 CFR 57.803 - Issuance of tentative determination; notice.

Code of Federal Regulations, 2011 CFR

2011-07-01

... determination. (1) The EPA staff shall formulate and prepare: (i) A “Staff Computational Analysis,” using the... Computational Analysis, discussing the estimated cost of interim controls, and assessing the effect upon the...

78 FR 48503 - Proposed Revision to Missiles Generated by Extreme Winds

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-08

...-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR..., ``Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants,'' and Interim Staff Guidance DC... and Hurricane Missiles for Nuclear Power Plants'' (ADAMS, Accession No. ML110940300), and Interim...

Executive Director Fred Spilhaus Steps Down; Interim Leader Takes AGU Reins

NASA Astrophysics Data System (ADS)

Weiss, Peter

2009-02-01

After 39 years as AGU executive director, Fred Spilhaus has stepped down from his post; he will become executive director emeritus. At a 27 January 2009 staff meeting at AGU headquarters, in Washington, D. C., three of the Union officers introduced Robert T. Van Hook, who will serve as interim executive director while AGU conducts a worldwide search for a new executive director. The search is expected to start in the summer of 2009 and to take from 6 to 18 months. ``AGU is a growing, vibrant organization that wishes to thoughtfully chart its course for the coming decades,'' Van Hook said. ``I am a professional interim executive, here to build on Fred Spilhaus's legacy. I want to help this extraordinary Union of researchers, teachers, and students take careful stock of where it is today, where it wants to go tomorrow, and what kind of staff leader it needs to help it get there,'' he said. ``My job is to get you ready for the next executive director,'' Van Hook told AGU staff, noting that he is not a candidate for the position himself.

75 FR 35510 - License Renewal Interim Staff Guidance Process, Revision 2 Notice of Availability

Federal Register 2010, 2011, 2012, 2013, 2014

2010-06-22

... Related Regulatory Functions.'' An electronic copy of the revised LR-ISG process is available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML100920158. The revised LR-ISG... interim changes to certain NRC license renewal guidance documents. These guidance documents facilitate the...

French Interim MALE UAV Program

DTIC Science & Technology

2003-09-02

MINISTÈRE DE LA DÉFENSE June, 13th 2002 Lcl Monsterleet FAF Staff J. Caron EADS S&DE-ISR FRENCH INTERIM MALE UAV PROGRAM 4 INDUSTRIAL STATUS Report...2003 2. REPORT TYPE N/A 3. DATES COVERED - 4. TITLE AND SUBTITLE French Interim Male UAV Program 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c...PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING ORGANIZATION NAME(S) AND ADDRESS(ES) EADS

78 FR 25487 - Final License Renewal Interim Staff Guidance LR-ISG-2012-01: Wall Thinning Due to Erosion Mechanisms

Federal Register 2010, 2011, 2012, 2013, 2014

2013-05-01

....'' This LR-ISG revises an NRC staff-recommended aging management program (AMP) in NUREG-1801, Revision 2, ``Generic Aging Lessons Learned (GALL) Report,'' and the NRC staff's aging management review procedure and... for piping and components within the scope of the Requirements for Renewal of Operating Licenses for...

75 FR 23821 - Final License Renewal Interim Staff Guidance LR-ISG-2009-01: Aging Management of Spent Fuel Pool...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-05-04

... approach acceptable to the NRC staff for meeting the requirements of 10 CFR part 54. On December 1, 2009... nuclear power plant spent fuel pool neutron-absorbing materials for compliance with part 54... Regulations (10 CFR part 54). The final LR-ISG revises the NRC staff's aging management recommendations...

Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2011

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

David W. Nigg; Devin A. Steuhm

2011-09-01

Legacy computational reactor physics software tools and protocols currently used for support of Advanced Test Reactor (ATR) core fuel management and safety assurance and, to some extent, experiment management are obsolete, inconsistent with the state of modern nuclear engineering practice, and are becoming increasingly difficult to properly verify and validate (V&V). Furthermore, the legacy staff knowledge required for application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. In 2009 the Idaho National Laboratory (INL) initiated a focused effort to address this situation through the introduction of modern high-fidelitymore » computational software and protocols, with appropriate V&V, within the next 3-4 years via the ATR Core Modeling and Simulation and V&V Update (or 'Core Modeling Update') Project. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF). The ATR Core Modeling Update Project, targeted for full implementation in phase with the anticipated ATR Core Internals Changeout (CIC) in the 2014 time frame, began during the last quarter of Fiscal Year 2009, and has just completed its first full year. Key accomplishments so far have encompassed both computational as well as experimental work. A new suite of stochastic and deterministic transport theory based reactor physics codes and their supporting nuclear data libraries (SCALE, KENO-6, HELIOS, NEWT, and ATTILA) have been installed at the INL under various permanent sitewide license agreements and corresponding baseline models of the ATR and ATRC are now operational, demonstrating the basic feasibility of these code packages for their intended purpose. Furthermore, a capability for rigorous sensitivity analysis and uncertainty quantification based on the TSUNAMI system is being implemented and initial computational results have been obtained. This capability will have many applications in 2011 and beyond as a tool for understanding the margins of uncertainty in the new models as well as for validation experiment design and interpretation. Finally we note that although full implementation of the new computational models and protocols will extend over a period 3-4 years as noted above, interim applications in the much nearer term have already been demonstrated. In particular, these demonstrations included an analysis that was useful for understanding the cause of some issues in December 2009 that were triggered by a larger than acceptable discrepancy between the measured excess core reactivity and a calculated value that was based on the legacy computational methods. As the Modeling Update project proceeds we anticipate further such interim, informal, applications in parallel with formal qualification of the system under the applicable INL Quality Assurance procedures and standards.« less

Training forensic staff.

PubMed

Hall-McGee, P

1997-01-01

The author provides a training package for forensic staff on how to handle prisoner patients who are being treated at a healthcare facility. She covers such topics as fire and evacuation plans, interim life safety measures, blood and bloodborne pathogens exposure, universal precautions, respiratory protection and TB, and voluntary medical immobilization and protection devices.

78 FR 21980 - Aging Management of Internal Surfaces, Service Level III and Other Coatings, Atmospheric Storage...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-12

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0068] Aging Management of Internal Surfaces, Service Level... Interim Staff Guidance (LR-ISG), LR-ISG-2012-02, ``Aging Management of Internal Surfaces, Service Level... proposes to revise NRC staff-recommended aging management programs (AMP) and aging management review (AMR...

76 FR 72006 - Draft Interim Staff Guidance: Evaluations of Uranium Recovery Facility Surveys of Radon and Radon...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-11-21

.... Discussion Uranium recovery facility licensees, including in-situ recovery facilities and conventional... Recovery Facility Surveys of Radon and Radon Progeny in Air and Demonstrations of Compliance AGENCY... Staff Guidance, ``Evaluations of Uranium Recovery Facility Surveys of Radon and Radon Progeny in Air and...

Impact investigation of reactor fuel operating parameters on reactivity for use in burnup credit applications

NASA Astrophysics Data System (ADS)

Sloma, Tanya Noel

When representing the behavior of commercial spent nuclear fuel (SNF), credit is sought for the reduced reactivity associated with the net depletion of fissile isotopes and the creation of neutron-absorbing isotopes, a process that begins when a commercial nuclear reactor is first operated at power. Burnup credit accounts for the reduced reactivity potential of a fuel assembly and varies with the fuel burnup, cooling time, and the initial enrichment of fissile material in the fuel. With regard to long-term SNF disposal and transportation, tremendous benefits, such as increased capacity, flexibility of design and system operations, and reduced overall costs, provide an incentive to seek burnup credit for criticality safety evaluations. The Nuclear Regulatory Commission issued Interim Staff Guidance 8, Revision 2 in 2002, endorsing burnup credit of actinide composition changes only; credit due to actinides encompasses approximately 30% of exiting pressurized water reactor SNF inventory and could potentially be increased to 90% if fission product credit were accepted. However, one significant issue for utilizing full burnup credit, compensating for actinide and fission product composition changes, is establishing a set of depletion parameters that produce an adequately conservative representation of the fuel's isotopic inventory. Depletion parameters can have a significant effect on the isotopic inventory of the fuel, and thus the residual reactivity. This research seeks to quantify the reactivity impact on a system from dominant depletion parameters (i.e., fuel temperature, moderator density, burnable poison rod, burnable poison rod history, and soluble boron concentration). Bounding depletion parameters were developed by statistical evaluation of a database containing reactor operating histories. The database was generated from summary reports of commercial reactor criticality data. Through depletion calculations, utilizing the SCALE 6 code package, several light water reactor assembly designs and in-core locations are analyzed in establishing a combination of depletion parameters that conservatively represent the fuel's isotopic inventory as an initiative to take credit for fuel burnup in criticality safety evaluations for transportation and storage of SNF.

Approach for validating actinide and fission product compositions for burnup credit criticality safety analyses

DOE PAGES

Radulescu, Georgeta; Gauld, Ian C.; Ilas, Germina; ...

2014-11-01

This paper describes a depletion code validation approach for criticality safety analysis using burnup credit for actinide and fission product nuclides in spent nuclear fuel (SNF) compositions. The technical basis for determining the uncertainties in the calculated nuclide concentrations is comparison of calculations to available measurements obtained from destructive radiochemical assay of SNF samples. Probability distributions developed for the uncertainties in the calculated nuclide concentrations were applied to the SNF compositions of a criticality safety analysis model by the use of a Monte Carlo uncertainty sampling method to determine bias and bias uncertainty in effective neutron multiplication factor. Application ofmore » the Monte Carlo uncertainty sampling approach is demonstrated for representative criticality safety analysis models of pressurized water reactor spent fuel pool storage racks and transportation packages using burnup-dependent nuclide concentrations calculated with SCALE 6.1 and the ENDF/B-VII nuclear data. Furthermore, the validation approach and results support a recent revision of the U.S. Nuclear Regulatory Commission Interim Staff Guidance 8.« less

76 FR 58846 - Final Interim Staff Guidance: Review of Evaluation To Address Gas Accumulation Issues in Safety...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-22

... of the comments. A document comparing the version of the ISG that went out for public comment and the final version of the ISG can be found under ADAMS Accession No. ML111170302. ADDRESSES: Publicly... its issued staff guidance in the agency external web page ( http://www.nrc.gov/reading-rm/doc...

76 FR 63676 - Final Division of Safety Systems Interim Staff Guidance DSS-ISG-2010-01: Staff Guidance Regarding...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-13

... learned based on recent submittals. FOR FURTHER INFORMATION CONTACT: Mr. Kent Wood, Division of Safety...-0001; telephone: 301-415-4120; or e- mail: [email protected] . ADDRESSES: You can access publicly... are available online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . From this page...

77 FR 46127 - Interim Staff Guidance on Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-08-02

... Aging Lessons Learned (GALL) Report Revision 2 AMP XI.M41, ``Buried and Underground Piping and Tanks... AMPs in NUREG-1801, Revision 2, ``Generic Aging Lessons Learned (GALL) Report,'' and the NRC staff's... issues LR-ISG to communicate insights and lessons learned and to address emergent issues not covered in...

Developing a concept for a national used fuel interim storage facility in the United States

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

Lewis, Donald Wayne

2013-07-01

In the United States (U.S.) the nuclear waste issue has plagued the nuclear industry for decades. Originally, spent fuel was to be reprocessed but with the threat of nuclear proliferation, spent fuel reprocessing has been eliminated, at least for now. In 1983, the Nuclear Waste Policy Act of 1982 [1] was established, authorizing development of one or more spent fuel and high-level nuclear waste geological repositories and a consolidated national storage facility, called a 'Monitored Retrievable Storage' facility, that could store the spent nuclear fuel until it could be placed into the geological repository. Plans were under way to buildmore » a geological repository, Yucca Mountain, but with the decision by President Obama to terminate the development of Yucca Mountain, a consolidated national storage facility that can store spent fuel for an interim period until a new repository is established has become very important. Since reactor sites have not been able to wait for the government to come up with a storage or disposal location, spent fuel remains in wet or dry storage at each nuclear plant. The purpose of this paper is to present a concept developed to address the DOE's goals stated above. This concept was developed over the past few months by collaboration between the DOE and industry experts that have experience in designing spent nuclear fuel facilities. The paper examines the current spent fuel storage conditions at shutdown reactor sites, operating reactor sites, and the type of storage systems (transportable versus non-transportable, welded or bolted). The concept lays out the basis for a pilot storage facility to house spent fuel from shutdown reactor sites and then how the pilot facility can be enlarged to a larger full scale consolidated interim storage facility. (authors)« less

A nurse led model of chronic disease care - an interim report.

PubMed

Eley, Diann S; Del Mar, Chris B; Patterson, Elizabeth; Synnott, Robyn L; Baker, Peter G; Hegney, Desley

2008-12-01

Chronic condition management in general practice is projected to account for 50% of all consultations by 2051. General practices under present workforce conditions will be unable to meet this demand. Nurse led collaborative care models of chronic disease management have been successful overseas and are proposed as one solution. This article provides an interim report on a prospective randomised trial to investigate the acceptability, cost effectiveness and feasibility of a nurse led model of care for chronic conditions in Australian general practice. A qualitative study focused on the impact of this model of care through the perceptions of practice staff from one urban and one regional practice in Queensland, and one Victorian rural practice. Primary benefits of the collaborative care model focused on increased efficiency and communication between practice staff and patients. The increased degree of patient self responsibility was noted by all and highlights the motivational aspect of chronic disease management.

Interim MELCOR Simulation of the Fukushima Daiichi Unit 2 Accident Reactor Core Isolation Cooling Operation

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

Ross, Kyle W.; Gauntt, Randall O.; Cardoni, Jeffrey N.

2013-11-01

Data, a brief description of key boundary conditions, and results of Sandia National Laboratories’ ongoing MELCOR analysis of the Fukushima Unit 2 accident are given for the reactor core isolation cooling (RCIC) system. Important assumptions and related boundary conditions in the current analysis additional to or different than what was assumed/imposed in the work of SAND2012-6173 are identified. This work is for the U.S. Department of Energy’s Nuclear Energy University Programs fiscal year 2014 Reactor Safety Technologies Research and Development Program RC-7: RCIC Performance under Severe Accident Conditions.

77 FR 71019 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-04; Guidance on...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-11-28

... Insights from the Fukushima Dai-ichi Accident,'' dated March 12, 2012 (ADAMS Accession No. ML12053A340... resulting nuclear accident, at the Fukushima Dai-ichi nuclear power plant in March 2011. Enclosure 1 to the...

76 FR 75771 - Emergency Planning Guidance for Nuclear Power Plants

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-05

... Guidance for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of NUREG... Support of Nuclear Power Plants;'' NSIR/DPR-ISG-01, ``Interim Staff Guidance Emergency Planning for Nuclear Power Plants;'' and NUREG/CR-7002, ``Criteria for Development of Evacuation Time Estimate Studies...

Hanford Site 100-N Area In Situ Bioremediation of UPR-100-N-17, Deep Petroleum Unplanned Release - 13245

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

Saueressig, Daniel G.

2013-07-01

In 1965 and 1966, approximately 303 m{sup 3} of Number 2 diesel fuel leaked from a pipeline used to support reactor operations at the Hanford Site's N Reactor. N Reactor was Hanford's longest operating reactor and served as the world's first dual purpose reactor for military and power production needs. The Interim Action Record of Decision for the 100-N Area identified in situ bioremediation as the preferred alternative to remediate the deep vadose zone contaminated by this release. A pilot project supplied oxygen into the vadose zone to stimulate microbial activity in the soil. The project monitored respiration rates asmore » an indicator of active biodegradation. Based on pilot study results, a full-scale system is being constructed and installed to remediate the vadose zone contamination. (authors)« less

Field trial of gravel stabilization methods : Route 1, Cyr-Van Buren, ME : 2nd interim report.

DOT National Transportation Integrated Search

1995-02-01

This experimental construction project was developed, designed, and inspected by personnel from the University of Maine, Civil Engineering Staff. The experimental project was constructed on and as a part of Project #2586 00. This was a complete recon...

Field trial of gravel stabilization methods : Route 1, Cyr-Van Buren, ME : 1st interim report.

DOT National Transportation Integrated Search

1993-05-01

This experimental construction project was developed, designed, and inspected by personnel from the University of Maine, Civil Engineering Staff. The experimental project was constructed on and as a part of Project #2586.00. This was a complete recon...

Preliminary Concept of Operations for the Spent Fuel Management System--WM2017

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

Cumberland, Riley M; Adeniyi, Abiodun Idowu; Howard, Rob L

The Nuclear Fuels Storage and Transportation Planning Project (NFST) within the U.S. Department of Energy s Office of Nuclear Energy is tasked with identifying, planning, and conducting activities to lay the groundwork for developing interim storage and transportation capabilities in support of an integrated waste management system. The system will provide interim storage for commercial spent nuclear fuel (SNF) from reactor sites and deliver it to a repository. The system will also include multiple subsystems, potentially including; one or more interim storage facilities (ISF); one or more repositories; facilities to package and/or repackage SNF; and transportation systems. The project teammore » is analyzing options for an integrated waste management system. To support analysis, the project team has developed a Concept of Operations document that describes both the potential integrated system and inter-dependencies between system components. The goal of this work is to aid systems analysts in the development of consistent models across the project, which involves multiple investigators. The Concept of Operations document will be updated periodically as new developments emerge. At a high level, SNF is expected to travel from reactors to a repository. SNF is first unloaded from reactors and placed in spent fuel pools for wet storage at utility sites. After the SNF has cooled enough to satisfy loading limits, it is placed in a container at reactor sites for storage and/or transportation. After transportation requirements are met, the SNF is transported to an ISF to store the SNF until a repository is developed or directly to a repository if available. While the high level operation of the system is straightforward, analysts must evaluate numerous alternative options. Alternative options include the number of ISFs (if any), ISF design, the stage at which SNF repackaging occurs (if any), repackaging technology, the types of containers used, repository design, component sizing, and timing of events. These alternative options arise due to technological, economic, or policy considerations. As new developments regularly emerge, the operational concepts will be periodically updated. This paper gives an overview of the different potential alternatives identified in the Concept of Operations document at a conceptual level.« less

76 FR 8366 - Science Advisory Board Staff Office; Request for Nominations; SAB Environmental Justice Technical...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-02-14

... Nominations; SAB Environmental Justice Technical Panel AGENCY: Environmental Protection Agency (EPA). ACTION... experts to serve on the SAB Environmental Justice Technical (EJT) Panel. DATES: Nominations should be...) released the Interim Guidance on Considering Environmental Justice During the Development of an Action...

Patterns and Trends in UK Higher Education 2016

ERIC Educational Resources Information Center

Universities UK, 2016

2016-01-01

This report provides an interim update to the Universities UK "Patterns" series, before the publication of the full "Patterns and Trends" publication in spring 2017. It includes updates of the main charts included in the 2015 publication, covering trends in student and staff numbers and finances of the UK higher education…

76 FR 9381 - Notice of Availability of Interim Staff Guidance Documents for Spent Fuel Storage Casks

Federal Register 2010, 2011, 2012, 2013, 2014

2011-02-17

.... FOR FURTHER INFORMATION CONTACT: Matthew Gordon, Structural Mechanics and Materials Branch, Division... a fee. Comments and questions on ISG-23 should be directed to Matthew Gordon, Structural Mechanics..., 2011. For the U.S. Nuclear Regulatory Commission. Michele Sampson, Acting Chief, Structural Mechanics...

Classification Structures for Career Information. Occupational Statements, Volume I. Part 1. SOC Numbers 1099 to 4490. Interim Edition.

ERIC Educational Resources Information Center

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

"Classification Structures for Career Information" was created to provide Career Information Delivery Systems (CIDS) staff with pertinent and useful occupational information arranged according to the Standard Occupational Classification (SOC) structure. Through this publication, the National Occupational Information Coordinating…

Classification Structures for Career Information. Occupational Statements, Volume I. Part 2. SOC Numbers 4499 to 6560. Interim Edition.

ERIC Educational Resources Information Center

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

"Classification Structures for Career Information" was created to provide Career Information Delivery Systems (CIDS) staff with pertinent and useful occupational information arranged according to the Standard Occupational Classification (SOC) structure. Through this publication, the National Occupational Information Coordinating…

Classification Structures for Career Information. Occupational Statements, Volume I. Part 3. SOC Numbers 6699 to 9900. Interim Edition.

ERIC Educational Resources Information Center

Ohio State Univ., Columbus. National Center for Research in Vocational Education.

"Classification Structures for Career Information" was created to provide Career Information Delivery Systems (CIDS) staff with pertinent and useful occupational information arranged according to the Standard Occupational Classification (SOC) structure. Through this publication, the National Occupational Information Coordinating…

76 FR 74831 - Aging Management of Stainless Steel Structures and Components in Treated Borated Water

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-01

... exposed to treated borated water. In response to a request from the Nuclear Energy Institute (NEI), the... NUCLEAR REGULATORY COMMISSION [NRC-2011-0256] Aging Management of Stainless Steel Structures and Components in Treated Borated Water AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff...

78 FR 44523 - Burned Area Emergency Response, Forest Service

Federal Register 2010, 2011, 2012, 2013, 2014

2013-07-24

..., Fish, Wildlife, Air and Rare Plants, Mail Stop 1121, 1400 Independence Ave. SW., Washington, DC 20250... interim directive may do so in the Office of the Director, Watershed, Fish, Wildlife, Air and Rare Plants..., Fish Wildlife, Air and Rare Plants Staff, 333 Broadway SE., Albuquerque, NM 87102, 505-842-3141 or...

Baltimore Community Schools: Promise & Progress

ERIC Educational Resources Information Center

Durham, Rachel E.; Connolly, Faith

2016-01-01

This report documents the interim progress of the Baltimore Community School (CommSch) strategy by examining outcomes for the 2014-15 school year. Results show that CommSch parents more often reported being connected with community resources by school staff compared to parents at other schools. They also were more likely to report that school…

Home Start Evaluation Study. Interim Case Studies IIa.

ERIC Educational Resources Information Center

Fein, Robert

This formative evaluation study of Home Start uses a case study approach. A brief case study focuses on the administrative structure and staff resources and responsibilities of National Home Start. Also included are reports on seven local programs developed after two field visits had been made to each program. In the first visit, objectives chosen…

78 FR 6149 - Final Interim Staff Guidance Assessing the Radiological Consequences of Accidental Releases of...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-29

... Accidental Releases of Radioactive Materials From Liquid Waste Tanks in Ground and Surface Waters for... Radioactive Materials from Liquid Waste Tanks in Ground and Surface Waters for Combined License Applications... Radioactive Materials from Liquid Waste Tanks in Ground and Surface Waters for Combined License Applications...

78 FR 49782 - Interim Staff Guidance on Changes During Construction

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-15

... seven comments on the Draft ISG from the Nuclear Energy Institute (NEI) (ADAMS Accession No. ML12089A019... construction impacts evaluation and the 10 CFR 50.59- like review (including applicability determination..., the construction impacts evaluation and the 10 CFR 50.59 and 10 CFR 50-59-like evaluation (including...

A Case Study of Technical Assistance to Demonstration Programs for Young Handicapped Children. Part I.

ERIC Educational Resources Information Center

Behr, Shirley K.; And Others

The interim report presents an evaluation of TADS (Technical Assistance Development System) through case studies of TADS technical assistance to the staffs of two demonstration programs for preschool handicapped children and their families. Purposes of the study included obtaining indepth descriptions of the technical assistance process to…

Geographic information system development in the CARETS project

USGS Publications Warehouse

Mitchell, William B.; Fegeas, Robin G.; Fitzpatrick, Katherine A.; Hallam, Cheryl A.

1977-01-01

Experience in the development of a geographic information system to support the CARETS project has confirmed the considerable advantages that may accrue by paralleling the system development with a rational and balanced system production effort which permits the integration of the education and training of users with interim deliverable products to them. Those advantages include support for a long-term staff plan that recognizes substantial staff changes through system development and implementation, a fiscal plan that provides continuity in resources necessary for total system development, and a feedback system which allows the user to communicate his experiences in using the system. Thus far balance between system development and system production has not been achieved because of continuing large-scale spatial data processing requirements coupled with strong and insistent demands from users for immediately deliverable products from the system. That imbalance has refocussed staffing and fiscal plans from long-term system development to short- and near-term production requirements, continuously extends total system development time, and increases the possibility that later system development may reduce the usefulness of current interim products.

Shielding calculation and criticality safety analysis of spent fuel transportation cask in research reactors.

PubMed

Mohammadi, A; Hassanzadeh, M; Gharib, M

2016-02-01

In this study, shielding calculation and criticality safety analysis were carried out for general material testing reactor (MTR) research reactors interim storage and relevant transportation cask. During these processes, three major terms were considered: source term, shielding, and criticality calculations. The Monte Carlo transport code MCNP5 was used for shielding calculation and criticality safety analysis and ORIGEN2.1 code for source term calculation. According to the results obtained, a cylindrical cask with body, top, and bottom thicknesses of 18, 13, and 13 cm, respectively, was accepted as the dual-purpose cask. Furthermore, it is shown that the total dose rates are below the normal transport criteria that meet the standards specified. Copyright © 2015 Elsevier Ltd. All rights reserved.

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions

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

Radulescu, Georgeta; Gauld, Ian C; Ilas, Germina

2011-01-01

The expanded use of burnup credit in the United States (U.S.) for storage and transport casks, particularly in the acceptance of credit for fission products, has been constrained by the availability of experimental fission product data to support code validation. The U.S. Nuclear Regulatory Commission (NRC) staff has noted that the rationale for restricting the Interim Staff Guidance on burnup credit for storage and transportation casks (ISG-8) to actinide-only is based largely on the lack of clear, definitive experiments that can be used to estimate the bias and uncertainty for computational analyses associated with using burnup credit. To address themore » issues of burnup credit criticality validation, the NRC initiated a project with the Oak Ridge National Laboratory to (1) develop and establish a technically sound validation approach for commercial spent nuclear fuel (SNF) criticality safety evaluations based on best-available data and methods and (2) apply the approach for representative SNF storage and transport configurations/conditions to demonstrate its usage and applicability, as well as to provide reference bias results. The purpose of this paper is to describe the isotopic composition (depletion) validation approach and resulting observations and recommendations. Validation of the criticality calculations is addressed in a companion paper at this conference. For isotopic composition validation, the approach is to determine burnup-dependent bias and uncertainty in the effective neutron multiplication factor (keff) due to bias and uncertainty in isotopic predictions, via comparisons of isotopic composition predictions (calculated) and measured isotopic compositions from destructive radiochemical assay utilizing as much assay data as is available, and a best-estimate Monte Carlo based method. This paper (1) provides a detailed description of the burnup credit isotopic validation approach and its technical bases, (2) describes the application of the approach for representative pressurized water reactor and boiling water reactor safety analysis models to demonstrate its usage and applicability, (3) provides reference bias and uncertainty results based on a quality-assurance-controlled prerelease version of the Scale 6.1 code package and the ENDF/B-VII nuclear cross section data.« less

Neutronic, steady-state, and transient analyses for the Kazakhstan VVR-K reactor with LEU fuel: ANL independent verification results

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

Hanan, Nelson A.; Garner, Patrick L.

Calculations have been performed for steady state and postulated transients in the VVR-K reactor at the Institute of Nuclear Physics (INP), Kazakhstan. (The reactor designation in Cyrillic is BBP-K; transliterating characters to English gives VVR-K but translating words gives WWR-K.) These calculations have been performed at the request of staff of the INP who are performing similar calculations. The selection of the transients considered started during working meetings and email correspondence between Argonne National Laboratory (ANL) and INP staff. In the end the transient were defined by the INP staff. Calculations were performed for the fresh low-enriched uranium (LEU) coremore » and for four subsequent cores as beryllium is added to maintain critically during the first 15 cycles. These calculations have been performed independently from those being performed by INP and serve as one step in the verification process.« less

75 FR 53353 - Notice of Availability of Final Interim Staff Guidance Document No. 25 “Pressure and Helium...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-31

... Guidance Document No. 25 ``Pressure and Helium Leakage Testing of the Confinement Boundary of Spent Fuel...: The Division of Spent Fuel Storage and Transportation (SFST) of the Office of Nuclear Materials Safety... Helium Leakage Testing of the Confinement Boundary of Spent Fuel Dry Storage Systems.'' This ISG...

Evaluation and Assessment Processes in Nebraska Public Schools. A Staff Report. Education Interim Study LR 181.

ERIC Educational Resources Information Center

Nebraska Legislative Council, Lincoln. Legislative Research Div.

During the spring of 1987, the National Conference of State Legislatures awarded the Nebraska Legislature a cost-sharing award to study local school evaluation processes. Embodied in Legislative Resolution 181, which has the purpose of studying school evaluation procedures, the study attempts to provide legislators, educators, local school…

77 FR 33777 - Interim Staff Guidance JLD-ISG-2012-02; Compliance With Order EA-12-050, Order Modifying Licenses...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-07

... feet) in height that inundated the Fukushima Dai-ichi nuclear power plant site. The earthquake and... infrastructure and industry in the northeastern coastal areas of Japan. When the earthquake occurred, Fukushima... earthquake appears to have been normal. Following the events at the Fukushima Dai-ichi nuclear power plant...

77 FR 73057 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-05; Performance of...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-12-07

... height that inundated the Fukushima Dai-ichi nuclear power plant site. The earthquake and tsunami... industry in the northeastern coastal areas of Japan. When the earthquake occurred, Fukushima Dai-ichi Units... loss of cooling capabilities. Following the events at the Fukushima Dai-ichi nuclear power plant, the...

76 FR 72725 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-05: Ongoing Review of Operating Experience

Federal Register 2010, 2011, 2012, 2013, 2014

2011-11-25

... Experience.'' This LR-ISG provides guidance and clarification concerning ongoing review of plant-specific and... plants. As noticed on September 20, 2011 (76 FR 58311), the public comment period was extended and, as of... to communicate insights and lessons learned and to address emergent issues not covered in license...

Comparative risk assessments for the production and interim storage of glass and ceramic waste forms: Defense waste processing facility

NASA Astrophysics Data System (ADS)

Huang, J. C.; Wright, W. V.

1982-04-01

The Defense Waste Processing Facility (DWPF) for immobilizing nuclear high level waste (HLW) is scheduled to be built. High level waste is produced when reactor components are subjected to chemical separation operations. Two candidates for immobilizing this HLW are borosilicate glass and crystalline ceramic, either being contained in weld sealed stainless steel canisters. A number of technical analyses are being conducted to support a selection between these two waste forms. The risks associated with the manufacture and interim storage of these two forms in the DWPF are compared. Process information used in the risk analysis was taken primarily from a DWPF processibility analysis. The DWPF environmental analysis provided much of the necessary environmental information.

Interim waste storage for the Integral Fast Reactor

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

Benedict, R.W.; Phipps, R.D.; Condiff, D.W.

1991-01-01

The Integral Fast Reactor (IFR), which Argonne National Laboratory is developing, is an innovative liquid metal breeder reactor that uses metallic fuel and has a close coupled fuel recovery process. A pyrochemical process is used to separate the fission products from the actinide elements. These actinides are used to make new fuel for the reactor. As part of the overall IFR development program, Argonne has refurbished an existing Fuel Cycle Facility at ANL-West and is installing new equipment to demonstrate the remote reprocessing and fabrication of fuel for the Experimental Breeder Reactor II (EBR-II). During this demonstration the wastes thatmore » are produced will be treated and packaged to produce waste forms that would be typical of future commercial operations. These future waste forms would, assuming Argonne development goals are fulfilled, be essentially free of long half-life transuranic isotopes. Promising early results indicate that actinide extraction processes can be developed to strip these isotopes from waste stream and return them to the IFR type reactors for fissioning. 1 fig.« less

Thermal-Mechanical Stress Analysis of PWR Pressure Vessel and Nozzles under Grid Load-Following Mode: Interim Report on the Effect of Cyclic Hardening Material Properties and Pre-existing Cracks on Stress Analysis Results

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

Mohanty, Subhasish; Soppet, William; Majumdar, Saurin

This report provides an update on an assessment of environmentally assisted fatigue for light water reactor components under extended service conditions. This report is a deliverable under the work package for environmentally assisted fatigue as part of DOE’s Light Water Reactor Sustainability Program. In a previous report (September 2015), we presented tensile and fatigue test data and related hardening material properties for 508 low-alloys steel base metal and other reactor metals. In this report, we present thermal-mechanical stress analysis of the reactor pressure vessel and its hot-leg and cold-leg nozzles based on estimated material properties. We also present results frommore » thermal and thermal-mechanical stress analysis under reactor heat-up, cool-down, and grid load-following conditions. Analysis results are given with and without the presence of preexisting cracks in the reactor nozzles (axial or circumferential crack). In addition, results from validation stress analysis based on tensile and fatigue experiments are reported.« less

78 FR 48201 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2013-01; Guidance for...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-07

... following the earthquake and shutdown of the operating units, however, the first large tsunami wave inundated the site, followed by additional waves. The tsunami caused extensive damage to site facilities and..., and after some period of time at the other units. Unit 6 retained the function of one air-cooled EDG...

78 FR 3039 - Japan Lessons-Learned Project Directorate Interim Staff Guidance JLD-ISG-2012-06; Performing a...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-15

... following the earthquake and shutdown of the operating units, however, the first large tsunami wave inundated the site, followed by additional waves. The tsunami caused extensive damage to site facilities and..., and after some period of time at the other units. Unit 6 retained the function of one air-cooled EDG...

76 FR 50284 - Request for Public Comments on Interim Review of Eligibility of Cote d'Ivoire, Guinea, and Niger...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-08-12

... Eligibility of Cote d'Ivoire, Guinea, and Niger for Benefits Under the African Growth and Opportunity Act.... SUMMARY: The African Growth and Opportunity Act Implementation Subcommittee of the Trade Policy Staff... eligibility of Cote d'Ivoire, Guinea, and Niger to receive the benefits of the African Growth and Opportunity...

School Capital Manual. An Interim Guide for School Boards, Administrators, Facility Planners and Consultants Who Engage in School Building Projects.

ERIC Educational Resources Information Center

Alberta Dept. of Education, Edmonton.

This manual is intended for use by the Alberta, Canada, school boards, administrators, consultants, education staff, and other individuals involved in school building projects. The purpose of the School Capital Plan, funding, and Alberta Education's funding framework are detailed. The school building project components of the School Capital Plan…

Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

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

Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.

2009-10-09

The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected tomore » come from increasingly diverse educational and experiential backgrounds.« less

77 FR 33780 - Interim Staff Guidance JLD-ISG-2012-03; Compliance with Order EA-12-051, Order Modifying Licenses...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-07

... Fukushima Dai-ichi nuclear power plant in March 2011. Order EA-12-051 requires all licensees and... complying with Order EA-12-051. Following the events at the Fukushima Dai-ichi nuclear power plant, the NRC... agency should make additional improvements to these programs in light of the events at Fukushima Dai-ichi...

77 FR 33779 - Interim Staff Guidance JLD-ISG-2012-01; Compliance With Order EA-12-049, Order Modifying Licenses...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-07

..., estimated to have exceeded 14 meters (45 feet) in height that inundated the Fukushima Dai-ichi nuclear power... earthquake occurred, Fukushima Dai-ichi Units 1, 2, and 3, were in operation and Units 4, 5, and 6, were shut... facility response to the earthquake appears to have been normal. Following the events at the Fukushima Dai...

76 FR 52995 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-05: Ongoing Review of Operating...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-08-24

...- 2011-0191. Address questions about NRC dockets to Carol Gallagher, telephone: 301-492-3668; e-mail...): Publicly available documents created or received at the NRC are available online in the NRC Library at http...-800-397-4209, 301-415-4737, or by e-mail to [email protected] . The draft LR-ISG proposes to revise...

Health Education Needs: A Survey of Rural Adults in Northumberland County, Pennsylvania, 1975. An Interim Report. Rural Health Staff Papers - Paper Number 6.

ERIC Educational Resources Information Center

Leadley, Samuel M.

In June 1975, 53 men and 56 women living on commercial farms in Northumberland County, Pennsylvania were interviewed regarding their behaviors, beliefs, and attitudes related to preventing cancer and coronary heart disease. Respondents represented about 23% of all adults living on commercial farms in the county. A commercial farm was defined as…

76 FR 77025 - Office of New Reactors; Notice of Availability of the Final Staff Guidance Section 1.0, Revision...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-09

... the Final Staff Guidance Section 1.0, Revision 2 on Introduction and Interfaces AGENCY: Nuclear... Plants: LWR Edition,'' Section 1.0, Revision 2 on ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112730393). The NRC staff issues revisions to SRP...

Low-temperature catalytic gasification of food processing wastes. 1995 topical report

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

Elliott, D.C.; Hart, T.R.

The catalytic gasification system described in this report has undergone continuing development and refining work at Pacific Northwest National Laboratory (PNNL) for over 16 years. The original experiments, performed for the Gas Research Institute, were aimed at developing kinetics information for steam gasification of biomass in the presence of catalysts. From the fundamental research evolved the concept of a pressurized, catalytic gasification system for converting wet biomass feedstocks to fuel gas. Extensive batch reactor testing and limited continuous stirred-tank reactor tests provided useful design information for evaluating the preliminary economics of the process. This report is a follow-on to previousmore » interim reports which reviewed the results of the studies conducted with batch and continuous-feed reactor systems from 1989 to 1994, including much work with food processing wastes. The discussion here provides details of experiments on food processing waste feedstock materials, exclusively, that were conducted in batch and continuous- flow reactors.« less

Exploring approaches to the administration of a long-term care facility: The application of a community planning and development process.

PubMed

Caldwell, W J

1996-01-01

This article outlines the approaches taken to the management of two long-term care facilities by the County of Huron in southwestern Ontario in 1994. Lay-offs, a move to new facilities, loss of local political confidence, changes in key administrative personnel and low staff morale prompted the county to ask an interim administrative team to develop and implement an appropriate response. The article explains how community development and planning principles and techniques were applied to the management of the homes to achieve an overall improvement in communication, staff morale and attitude. These approaches may prove helpful to other administrations facing major change.

Health Education Needs: A Survey of Rural Adults in Armstrong County, Pennsylvania, 1975. An Interim Report. Rural Health Staff Papers - Paper Number 8.

ERIC Educational Resources Information Center

Leadley, Samuel M.; Taranto, Angelo A.

In July and August 1975, 138 rural residents of Armstrong County, Pennsylvania were interviewed as to their behaviors, beliefs, and attitudes regarding the prevention of cancer and coronary heart disease. Respondents were selected by interviewing an adult living on a commercial farm (a farm that either sold $10,000 or more produce per year or the…

Health Education Needs: A Survey of Rural Adults in Juniata County, Pennsylvania, 1975. An Interim Report. Rural Health Staff Papers - Paper Number 4.

ERIC Educational Resources Information Center

Leadley, Samuel M.

In June 1975, 62 men and 64 women living on commercial farms in Juniata County, Pennsylvania were interviewed regarding their behaviors, beliefs, and attitudes related to preventing cancer and coronary heart disease. Respondents represented about 22% of all adults living on commercial farms in the county. A commercial farm was defined as one that…

Health Education Needs: A Survey of Rural Adults in Fulton County, Pennsylvania, 1975. An Interim Report. Rural Health Staff Papers - Paper Number 5.

ERIC Educational Resources Information Center

Leadley, Samuel M.

In June 1975, 47 men and 43 women living on commercial farms in Fulton County, Pennsylvania were interviewed regarding their behaviors, beliefs, and attitudes related to preventing cancer and coronary heart disease. Respondents represented about 39% of all adults living on commercial farms in the county. A commercial farm was defined as one that…

An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (keff) Predictions

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

Scaglione, John M; Mueller, Don; Wagner, John C

2011-01-01

One of the most significant remaining challenges associated with expanded implementation of burnup credit in the United States is the validation of depletion and criticality calculations used in the safety evaluation - in particular, the availability and use of applicable measured data to support validation, especially for fission products. Applicants and regulatory reviewers have been constrained by both a scarcity of data and a lack of clear technical basis or approach for use of the data. U.S. Nuclear Regulatory Commission (NRC) staff have noted that the rationale for restricting their Interim Staff Guidance on burnup credit (ISG-8) to actinide-only ismore » based largely on the lack of clear, definitive experiments that can be used to estimate the bias and uncertainty for computational analyses associated with using burnup credit. To address the issue of validation, the NRC initiated a project with the Oak Ridge National Laboratory to (1) develop and establish a technically sound validation approach (both depletion and criticality) for commercial spent nuclear fuel (SNF) criticality safety evaluations based on best-available data and methods and (2) apply the approach for representative SNF storage and transport configurations/conditions to demonstrate its usage and applicability, as well as to provide reference bias results. The purpose of this paper is to describe the criticality (k{sub eff}) validation approach, and resulting observations and recommendations. Validation of the isotopic composition (depletion) calculations is addressed in a companion paper at this conference. For criticality validation, the approach is to utilize (1) available laboratory critical experiment (LCE) data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments and the French Haut Taux de Combustion (HTC) program to support validation of the principal actinides and (2) calculated sensitivities, nuclear data uncertainties, and the limited available fission product LCE data to predict and verify individual biases for relevant minor actinides and fission products. This paper (1) provides a detailed description of the approach and its technical bases, (2) describes the application of the approach for representative pressurized water reactor and boiling water reactor safety analysis models to demonstrate its usage and applicability, (3) provides reference bias results based on the prerelease SCALE 6.1 code package and ENDF/B-VII nuclear cross-section data, and (4) provides recommendations for application of the results and methods to other code and data packages.« less

75 FR 69709 - Office of New Reactors; Notice of Availability of the Final Staff Guidance; Standard Review Plan...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-15

... the Final Staff Guidance; Standard Review Plan, Section 13.6.6, Revision 0 on Cyber Security Plan... Reports for Nuclear Power Plants,'' Section 13.6.6, Revision 0 on ``Cyber Security Plan'' (Agencywide.... Disposition: On May 13, 2010, the NRC staff issued the proposed Revision 0 on SRP Section 13.6.6 on ``Cyber...

Addressing Fission Product Validation in MCNP Burnup Credit Criticality Calculations

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

Mueller, Don; Bowen, Douglas G; Marshall, William BJ J

2015-01-01

The US Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation issued Interim Staff Guidance (ISG) 8, Revision 3 in September 2012. This ISG provides guidance for NRC staff members’ review of burnup credit (BUC) analyses supporting transport and dry storage of pressurized water reactor spent nuclear fuel (SNF) in casks. The ISG includes guidance for addressing validation of criticality (k eff) calculations crediting the presence of a limited set of fission products and minor actinides (FP&MAs). Based on previous work documented in NRC Regulatory Guide (NUREG) Contractor Report (CR)-7109, the ISG recommends that NRC staff members acceptmore » the use of either 1.5 or 3% of the FP&MA worth—in addition to bias and bias uncertainty resulting from validation of k eff calculations for the major actinides in SNF—to conservatively account for the bias and bias uncertainty associated with the specified unvalidated FP&MAs. The ISG recommends (1) use of 1.5% of the FP&MA worth if a modern version of SCALE and its nuclear data are used and (2) 3% of the FP&MA worth for well qualified, industry standard code systems other than SCALE with the Evaluated Nuclear Data Files, Part B (ENDF/B),-V, ENDF/B-VI, or ENDF/B-VII cross sections libraries. The work presented in this paper provides a basis for extending the use of the 1.5% of the FP&MA worth bias to BUC criticality calculations performed using the Monte Carlo N-Particle (MCNP) code. The extended use of the 1.5% FP&MA worth bias is shown to be acceptable by comparison of FP&MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII–based nuclear data. The comparison supports use of the 1.5% FP&MA worth bias when the MCNP code is used for criticality calculations, provided that the cask design is similar to the hypothetical generic BUC-32 cask model and that the credited FP&MA worth is no more than 0.1 Δk eff (ISG-8, Rev. 3, Recommendation 4).« less

Interim Status Report for Risk Management for SFRs

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

Jankovsky, Zachary Kyle; Denman, Matthew R.; Groth, Katrina

2015-10-01

Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of passive, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the system's design to take advantage of natural phenomena to manage the accident. Inherently and passively safe designs are laudable, but nonetheless extreme boundary conditions can interfere with the design attributes which facilitate inherent safety, thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a variety of beyondmore » design basis events with the intent of exploring the utility of a Dynamic Bayesian Network to infer the state of the reactor to inform the operator's corrective actions. These inferences also serve to identify the instruments most critical to informing an operator's actions as candidates for hardening against radiation and other extreme environmental conditions that may exist in an accident. This reduction in uncertainty serves to inform ongoing discussions of how small sodium reactors would be licensed and may serve to reduce regulatory risk and cost for such reactors.« less

Assessment of Program Impact Through First Grade, Volume I: The Context, Conceptual Approach and Methods of the Evaluation. An Evaluation of Project Developmental Continuity. Interim Report X.

ERIC Educational Resources Information Center

Rosario, Jose; And Others

This volume is the first of a series reporting evaluation findings on the impact of Project Developmental Continuity (PDC) on institutions, classroom staff, parents and children from the time the children entered Head Start through the first grade. PDC was begun in 1974 with the purpose of ensuring that disadvantaged children receive continuous…

Health Education Needs: A Survey of Rural Adults in Butler County, Pennsylvania, 1975. An Interim Report. Rural Health Staff Papers - Paper Number 7.

ERIC Educational Resources Information Center

Leadley, Samuel M.; Taranto, Angelo A.

In July and August 1975, 17 men and 63 women living in rural areas in Butler County, Pennsylvania were interviewed as to their behaviors, beliefs, and attitudes related to preventing cancer and coronary heart disease. Respondents represented about 12% of all adults living on commercial farms and 5% of all rural nonfarm adults in the county. A…

Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

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

Favalli, Andrea; Vo, D.; Grogan, Brandon R.

The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuelmore » assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/ 137Cs, 134Cs/ 137Cs, 106Ru/ 137Cs, and 144Ce/ 137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. Furthermore, the results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.« less

Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

DOE PAGES

Favalli, Andrea; Vo, D.; Grogan, Brandon R.; ...

2016-02-26

The purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuelmore » assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/ 137Cs, 134Cs/ 137Cs, 106Ru/ 137Cs, and 144Ce/ 137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. Furthermore, the results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.« less

78 FR 28896 - Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components

Federal Register 2010, 2011, 2012, 2013, 2014

2013-05-16

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0095] Design Limits and Loading Combinations for Metal... Regulatory Guide (RG) 1.57, ``Design Limits and Loading Combinations for Metal Primary Reactor Containment... the NRC staff considers acceptable for design limits and loading combinations for metal primary...

10 CFR 2.337 - Evidence at a hearing.

Code of Federal Regulations, 2010 CFR

2010-01-01

... the proffered evidence. If the excluded evidence is in written form, a copy must be marked for... proceeding in compliance with section 182(b) of the Act, any safety evaluation prepared by the NRC staff, and... chapter by the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or...

77 FR 5063 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Thermal...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-01

... Subcommittee on Thermal-Hydraulics Phenomena; Notice of Meeting The ACRS Subcommittee on Thermal-Hydraulics... Regulatory Guide (1.79), ``Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water... Water Reactors.'' The Subcommittee will hear presentations by and hold discussions with the NRC staff...

Planning for progress, productivity, and performance.

PubMed

Benedict, J M

1983-10-01

A project is described for the interim renovation of a labor intensive existing foodservice facility. The renovated area will provide effective food management during the hospital's redevelopment period, including a new foodservice. Objectives of the interim project were to conserve labor while emphasizing control and centralization, provide economic foodservices with improved quality, and incorporate one tray distribution system throughout the hospital complex. Immediate measures were necessary in order to generate funds to proceed. Renovations had to occur without disrupting food-service to patients. The project was planned over a three year period and included an ingredient control area, two patient tray service centres, a renewed production kitchen and test kitchen facility. Each phase has been financed on the understanding that the costs of construction and equipment will be repaid within one fiscal year of operating the renovated facility. Positive results are being achieved, attributable to the support and encouragement received from staff during the change process.

Interim reliability evaluation program, Browns Ferry 1

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

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.

1981-01-01

Probabilistic risk analysis techniques, i.e., event tree and fault tree analysis, were utilized to provide a risk assessment of the Browns Ferry Nuclear Plant Unit 1. Browns Ferry 1 is a General Electric boiling water reactor of the BWR 4 product line with a Mark 1 (drywell and torus) containment. Within the guidelines of the IREP Procedure and Schedule Guide, dominant accident sequences that contribute to public health and safety risks were identified and grouped according to release categories.

Fostering community understanding of sufficient benefit and early stopping for a phase 2B HIV prevention clinical trial in Africa.

PubMed

White, Rhonda; Chileshe, Modesta; Dawson, Liza; Donnell, Deborah; Hillier, Sharon; Morar, Neetha; Noguchi, Lisa; Dixon, Dennis

2011-02-01

Most trials of interventions are designed to address the traditional null hypothesis of no benefit. VOICE, a phase 2B HIV prevention trial funded by NIH and conducted in Africa, is designed to assess if the intervention will prevent a substantial fraction of infections. Planned interim analysis may provide conclusive evidence against the traditional null hypothesis without establishing substantial benefit. At this interim point, the Data and Safety Monitoring Board would then face the dilemma of knowing the product has some positive effect, but perhaps not as great an effect as the protocol has declared necessary. In March 2008, NIH program staff recommended that the VOICE protocol team discuss the stopping rules with stakeholders prior to initiating the protocol. The goals of the workshop were to inform community representatives about the potential ethical dilemma associated with stopping rules and engage in dialogue about these issues. We describe the resulting community consultation and summarize the outcomes. A 2-day workshop was convened with the goal of having a clear and transparent consultation with the stakeholders around the question, 'Given emerging evidence that a product could prevent some infections, would the community support a decision to continue accruing to the trial?' Participants included research staff and community stakeholders. Lectures with visual aids, discussions, and exercises using interactive learning tasks were used, with a focus on statistics and interpreting data from trials, particularly interim data. Results of oral and written evaluations by participants were reviewed. The feedback was mostly positive, with some residual confusion regarding statistical concepts. However, discussions with attendees later revealed that not all felt prepared to engage fully in the workshop. This was the presenters' first experience facilitating a formal discussion with an audience that had no advanced science, research, or mathematics training. Community representatives' concern regarding speaking for their communities without consulting them also created a challenge for the workshop. Open discussion around trial stopping rules requires that all discussants have an understanding of trial design concepts and feel a sense of empowerment to ask and answer questions. The VOICE CWG workshop was a first step toward the goal of open discussion regarding trial stopping rules and interim results for the study; however, ongoing education and dialogue must occur to ensure that all stakeholders fully participate in the process.

10 CFR 2.809 - Participation by the Advisory Committee on Reactor Safeguards.

Code of Federal Regulations, 2010 CFR

2010-01-01

... will give its reasons for doing so. Both the ACRS recommendation and the Commission's response will be... under development by the NRC Staff, the Staff will ensure that the ACRS is given an opportunity to provide advice at appropriate stages and to identify issues to be considered during rulemaking hearings...

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

Craig, D.F.

The division was formed in 1946 at the suggestion of Dr. Eugene P. Wigner to attack the problem of the distortion of graphite in the early reactors due to exposure to reactor neutrons, and the consequent radiation damage. It was called the Metallurgy Division and assembled the metallurgical and solid state physics activities of the time which were not directly related to nuclear weapons production. William A. Johnson, a Westinghouse employee, was named Division Director in 1946. In 1949 he was replaced by John H Frye Jr. when the Division consisted of 45 people. He was director during most ofmore » what is called the Reactor Project Years until 1973 and his retirement. During this period the Division evolved into three organizational areas: basic research, applied research in nuclear reactor materials, and reactor programs directly related to a specific reactor(s) being designed or built. The Division (Metals and Ceramics) consisted of 204 staff members in 1973 when James R. Weir, Jr., became Director. This was the period of the oil embargo, the formation of the Energy Research and Development Administration (ERDA) by combining the Atomic Energy Commission (AEC) with the Office of Coal Research, and subsequent formation of the Department of Energy (DOE). The diversification process continued when James O. Stiegler became Director in 1984, partially as a result of the pressure of legislation encouraging the national laboratories to work with U.S. industries on their problems. During that time the Division staff grew from 265 to 330. Douglas F. Craig became Director in 1992.« less

Navy Nuclear-Powered Surface Ships: Background, Issues, and Options for Congress

DTIC Science & Technology

2010-03-29

246 of H.R. 2647 would require DOD to submit to the congressional defense committees a study on the use of thorium -liquid fueled nuclear reactors ...Congressional Research Service 19 SEC. 246. STUDY ON THORIUM -LIQUID FUELED REACTORS FOR NAVAL FORCES. (a) Study Required- The Secretary of Defense and...the Chairman of the Joint Chiefs of Staff shall jointly carry out a study on the use of thorium -liquid fueled nuclear reactors for naval power

Navy Nuclear-Powered Surface Ships: Background, Issues, and Options for Congress

DTIC Science & Technology

2009-07-17

thorium -liquid fueled nuclear reactors for Navy surface ships. Section 1012 of the FY2010 defense authorization bill (S. 1390) as reported by the Senate...to the congressional defense committees a study on the use of thorium -liquid fueled nuclear reactors for Navy surface ships. The text of Section...STUDY ON THORIUM -LIQUID FUELED REACTORS FOR NAVAL FORCES. (a) Study Required- The Secretary of Defense and the Chairman of the Joint Chiefs of Staff

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

Cummins, G.D.

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of thismore » waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.« less

Using evidence-based leadership initiatives to create a healthy nursing work environment.

PubMed

Nayback-Beebe, Ann M; Forsythe, Tanya; Funari, Tamara; Mayfield, Marie; Thoms, William; Smith, Kimberly K; Bradstreet, Harry; Scott, Pamela

2013-01-01

In an effort to create a healthy nursing work environment in a military hospital Intermediate Care Unit (IMCU), a facility-level Evidence Based Practice working group composed of nursing.Stakeholders brainstormed and piloted several unit-level evidence-based leadership initiatives to improve the IMCU nursing work environment. These initiatives were guided by the American Association of Critical Care Nurses Standards for Establishing and Sustaining Healthy Work Environments which encompass: (1) skilled communication, (2) true collaboration, (3) effective decision making, (4) appropriate staffing, (5) meaningful recognition, and (6) authentic leadership. Interim findings suggest implementation of these six evidence-based, relationship-centered principals, when combined with IMCU nurses' clinical expertise, management experience, and personal values and preferences, improved staff morale, decreased staff absenteeism, promoted a healthy nursing work environment, and improved patient care.

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

Sklenka, L.; Rataj, J.; Frybort, J.

Research reactors play an important role in providing key personnel of nuclear power plants a hands-on experience from operation and experiments at nuclear facilities. Training of NPP (Nuclear Power Plant) staff is usually deeply theoretical with an extensive utilisation of simulators and computer visualisation. But a direct sensing of the reactor response to various actions can only improve the personnel awareness of important aspects of reactor operation. Training Reactor VR-1 and its utilization for training of NPP operators and other professionals from Czech Republic and Slovakia is described. Typical experimental exercises and good practices in organization of a training programmore » are demonstrated. (authors)« less

Installation Development Environmental Assessment at Joint Base Andrews-Naval Air Facility Washington Prince George’s County, Maryland

DTIC Science & Technology

2013-04-01

and seven additional aircraft by fiscal year (FY) 16. As an interim solution, temporary trailers totaling 4,000 square feet (SF) are being used on a...hangar floor to accommodate office space and aircrew flight equipment workshop needs. However, the use of trailers comes at a direct cost to the...facility would have 18 classrooms, a gross motor room, a lobby with reception area, a conference room, administrative offices, a staff lounge, a full-service

78 FR 33132 - Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research and Test...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-06-03

... Fuel Elements for Use in Research and Test Reactors AGENCY: Nuclear Regulatory Commission. ACTION... Research and Test Reactors.'' This guide describes a method that the staff of the NRC considers acceptable... assurance program for verifying the quality of plate-type uranium-aluminum fuel elements used in research...

77 FR 27487 - License Amendment Request From The State University of New York, University of Buffalo Reactor...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-05-10

... State University of New York, University of Buffalo Reactor Facility AGENCY: Nuclear Regulatory... staff at 1-800-397-4209, 301-415- 4737, or by email to [email protected] . The University of Buffalo... license amendment application from the State University of New York, University of Buffalo requesting...

How safe is safe enough. The relation of environmental characteristics and economic competitiveness in fusion-reactor design

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

Holdren, J.P.

The need for fusion energy depends strongly on fusion's potential to achieve ambitious safety goals more completely or more economically than fission can. The history and present complexion of public opinion about environment and safety gives little basis for expecting either that these concerns will prove to be a passing fad or that the public will make demands for zero risk that no energy source can meet. Hazard indices based on ''worst case'' accidents and exposures should be used as design tools to promote combinations of fusion-reactor materials and configurations that bring the worst cases down to levels small comparedmore » to the hazards people tolerate from electricity at the point of end use. It may well be possible, by building such safety into fusion from the ground up, to accomplish this goal at costs competitive with other inexhaustible electricity sources. Indeed, the still rising and ultimately indeterminate costs of meeting safety and environmental requirements in nonbreeder fission reactors and coal-burning power plants mean that fusion reactors meeting ambitious safety goals may be able to compete economically with these ''interim'' electricity sources as well.« less

(Boiling water reactor (BWR) CORA experiments)

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

Ott, L.J.

To participate in the 1990 CORA Workshop at Kernforschungszentrum Karlsruhe (KfK) GmbH, Karlsruhe, FRG, on October 1--4, and to participate in detailed discussions on October 5 with the KfK CORA Boiling Water Reactor (BWR) experiments. The traveler attended the 1990 CORA Workshop at KfK, FRG. Participation included the presentation of a paper on work performed by the Boiling Water Reactor Core Melt Progression Phenomena Program at Oak Ridge National Laboratory (ORNL) on posttest analyses of CORA BWR experiments. The Statement of Work (November 1989) for the BWR Core Melt Progression Phenomena Program provides for pretest and posttest analyses of themore » BWR CORA experiments performed at KfK. Additionally, it is intended that ORNL personnel participate in the planning process for future CORA BWR experiments. For these purposes, meetings were held with KfK staff to discuss such topics as (1) experimental test schedule, (2) BWR test conduct, (3) perceived BWR experimental needs, and (4) KfK operational staff needs with respect to ORNL support. 19 refs.« less

75 FR 32972 - Office of New Reactors: Notice of Availability of the Final Staff Guidance; Section 14.3.12 on...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-06-10

... the Final Staff Guidance; Section 14.3.12 on Physical Security Hardware Inspections, Tests, Analyses...: The NRC is issuing its Final Revision 1 to NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 14.3.12 on ``Physical Security Hardware...

75 FR 68009 - Office of New Reactors; Notice of Availability of the Final Staff Guidance Standard Review Plan...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-04

... the Final Staff Guidance Standard Review Plan Section 13.6.3, Revision 1 on Physical Security--Early... NRC is issuing its Final Revision 1 to NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 13.6.3, Revision 1 on Physical Security...

75 FR 68009 - Office of New Reactors; Notice of Availability of the Final Staff Guidance Standard Review Plan...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-04

... the Final Staff Guidance Standard Review Plan Section 13.6.2, Revision 1 on Physical Security--Design... issuing its Final Revision 1 to NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 13.6.2, Revision 1 on Physical Security--Design Certification...

75 FR 68009 - Office of New Reactors; Notice of Availability of the Final Staff Guidance Standard Review Plan...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-11-04

... the Final Staff Guidance Standard Review Plan, Section 13.6.1, Revision 1 on Physical Security... Availability. SUMMARY: The NRC is issuing its Final Revision 1 to NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 13.6.1, Revision 1 on...

Sustainable production of green feed from carbon dioxide and hydrogen.

PubMed

Landau, Miron V; Vidruk, Roxana; Herskowitz, Moti

2014-03-01

Carbon dioxide hydrogenation to form hydrocarbons was conducted on two iron-based catalysts, prepared according to procedures described in the literature, and on a new iron spinel catalyst. The CO2 conversion measured in a packed-bed reactor was limited to about 60% because of excessive amounts of water produced in this process. Switching to a system of three packed-bed reactors in series with interim removal of water and condensed hydrocarbons increased CO2 conversion to as much as 89%. The pure spinel catalyst displayed a significantly higher activity and selectivity than those of the other iron catalysts. This process produces a product called green feed, which is similar in composition to the product of a high-temperature, iron-based Fischer–Tropsch process from syngas. The green feed can be readily converted into renewable fuels by well-established technologies.

Supporting the Federal Emergency Management Agency Rescuers: a variation of critical incident stress management.

PubMed

Garcia, Evangeline; Horton, Denise A

2003-02-01

The purpose of this article was to document the efforts of two military installations in facilitating Critical Incident Stress Management teams for Federal Emergency Management Agency Rescue and Recovery Units following the attacks on the World Trade Center on September 11, 2001. McGuire Air Force Base accepted the mission to support the rotating task forces with emotional support, and Fort Dix offered temporary lodging while the teams were in-bound and out-bound to the "Ground Zero" site. A team, comprised of staff from both installations due to the configuration of professional and support staffs, does the Critical Incident Stress Management work. Both installations are within commuting distance of New York City and could provide adequate safety, security, and logistics to the teams. The classic crisis management models were not called into play, as that service was not asked for; however, it was clear to the McGuire Air Force Base/Fort Dix Critical Incident Stress Management team members that the rescue and recovery teams needed their physical presence. Many rescue organizations have their own "debriefing teams," yet it is believed that "outside teams" may be helpful as interim measures to demonstrate the universality of the process of coping with traumatic stress and grief management. It is hoped that this article honors the workers who came together to help in a very difficult time for our country. This article documents the interim measures that were taken for a group of people moving through crisis.

Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

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

Belles, Randy; Jain, Prashant K.; Powers, Jeffrey J.

The Oak Ridge National Laboratory (ORNL) has a rich history of support for light water reactor (LWR) and non-LWR technologies. The ORNL history involves operation of 13 reactors at ORNL including the graphite reactor dating back to World War II, two aqueous homogeneous reactors, two molten salt reactors (MSRs), a fast-burst health physics reactor, and seven LWRs. Operation of the High Flux Isotope Reactor (HFIR) has been ongoing since 1965. Expertise exists amongst the ORNL staff to provide non-LWR training; support evaluation of non-LWR licensing and safety issues; perform modeling and simulation using advanced computational tools; run laboratory experiments usingmore » equipment such as the liquid salt component test facility; and perform in-depth fuel performance and thermal-hydraulic technology reviews using a vast suite of computer codes and tools. Summaries of this expertise are included in this paper.« less

BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

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

Bevard, Bruce Balkcom; Mertyurek, Ugur; Belles, Randy

The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been storedmore » on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is utilized or referenced, justification has been provided as to why the data can be utilized for BWR fuel.« less

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

Stillman, J. A.; Feldman, E. E.; Jaluvka, D.

This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members in the Research and Test Reactor Department at the Argonne National Laboratory (ANL) and the MURR Facility. MURR LEU conversion is part of an overall effort to develop and qualify high-density fuel within the U.S. High Performance Research Reactor Conversion (USHPRR) program conducted by the U.S. Department of Energy National Nuclearmore » Security Administration’s Office of Material Management and Minimization (M 3).« less

Expanded scope of training and education programs at the UFTR

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

Vernetson, W.G.; Whaley, P.M.

1985-01-01

Historically, the University of Florida Training Reactor (UFTR) has been used to train both hot and cold license reactor operator candidates in intensive two- and three-week training programs consisting of a correlated set of classroom lectures, hands-on reactor operations, and laboratory exercises. These training programs provide nuclear plant operating staff with fundamental operational experience in understanding, controlling, and evaluating subcritical multiplication, reactivity effects, reactivity manipulations, and reactor operations; a sufficient number of startups and shutdowns is also assured. The UDTR is also used in a nuclear engineering course entitled ''Principles of Nuclear Reactor Operations.'' The purpose of this paper ismore » to report the results of efforts to redirect and refine tractor operations educational and training programs at the UFTR.« less

Neutron radiation characteristics of the IVth generation reactor spent fuel

NASA Astrophysics Data System (ADS)

Bedenko, Sergey; Shamanin, Igor; Grachev, Victor; Knyshev, Vladimir; Ukrainets, Olesya; Zorkin, Andrey

2018-03-01

Exploitation of nuclear power plants as well as construction of new generation reactors lead to great accumulation of spent fuel in interim storage facilities at nuclear power plants, and in spent fuel «wet» and «dry» long-term storages. Consequently, handling the fuel needs more attention. The paper is focused on the creation of an efficient computational model used for developing the procedures and regulations of spent nuclear fuel handling in nuclear fuel cycle of the new generation reactor. A Thorium High-temperature Gas-Cooled Reactor Unit (HGTRU, Russia) was used as an object for numerical research. Fuel isotopic composition of HGTRU was calculated using the verified code of the MCU-5 program. The analysis of alpha emitters and neutron radiation sources was made. The neutron yield resulting from (α,n)-reactions and at spontaneous fission was calculated. In this work it has been shown that contribution of (α,n)-neutrons is insignificant in case of such (Th,Pu)-fuel composition and HGTRU operation mode, and integral neutron yield can be approximated by the Watt spectral function. Spectral and standardized neutron distributions were achieved by approximation of the list of high-precision nuclear data. The distribution functions were prepared in group and continuous form for further use in calculations according to MNCP, MCU, and SCALE.

Planning and supervision of reactor defueling using discrete event techniques

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

Garcia, H.E.; Imel, G.R.; Houshyar, A.

1995-12-31

New fuel handling and conditioning activities for the defueling of the Experimental Breeder Reactor II are being performed at Argonne National Laboratory. Research is being conducted to investigate the use of discrete event simulation, analysis, and optimization techniques to plan, supervise, and perform these activities in such a way that productivity can be improved. The central idea is to characterize this defueling operation as a collection of interconnected serving cells, and then apply operational research techniques to identify appropriate planning schedules for given scenarios. In addition, a supervisory system is being developed to provide personnel with on-line information on themore » progress of fueling tasks and to suggest courses of action to accommodate changing operational conditions. This paper provides an introduction to the research in progress at ANL. In particular, it briefly describes the fuel handling configuration for reactor defueling at ANL, presenting the flow of material from the reactor grid to the interim storage location, and the expected contributions of this work. As an example of the studies being conducted for planning and supervision of fuel handling activities at ANL, an application of discrete event simulation techniques to evaluate different fuel cask transfer strategies is given at the end of the paper.« less

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

Stillman, J. A.; Feldman, E. E.; Wilson, E. H.

This report contains the results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. This report contains themore » results of reactor accident analyses for the University of Missouri Research Reactor (MURR). The calculations were performed as part of the conversion from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL), the MURR Facility, and the Nuclear Engineering Program – College of Engineering, University of Missouri-Columbia. The core conversion to LEU is being performed with financial support from the U. S. government. In the framework of non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MURR. This report presents the results of a study of core behavior under a set of accident conditions for MURR cores fueled with HEU U-Alx dispersion fuel or LEU monolithic U-Mo alloy fuel with 10 wt% Mo (U-10Mo).« less

Strange bedfellows: The curious case of STAR and Moata

NASA Astrophysics Data System (ADS)

Smith, A. M.; Levchenko, V. A.; Malone, G.

2013-01-01

The 2 MV tandem accelerator named ‘STAR’ was installed at ANSTO in 2003 and commissioned in 2004. It is used for ion beam analysis (IBA) and for radiocarbon measurements by accelerator mass spectrometry (AMS). Convenient space for the accelerator was found in the same building occupied by the decommissioned Argonaut-class nuclear reactor ‘Moata’; the name derives from the aboriginal word for ‘fire stick’ or ‘gentle fire’, appropriate for a 100 kW research reactor. This reactor operated between 1961 and 1995. In 2007 ANSTO’s Engineering Division assembled a team to dismantle and remove the reactor structure, along with its 12.1 tonnes of graphite reflector. The removal and remediation was completed in November 2010 and has won the team a number of prestigious awards. The entire operation was conducted inside a negatively-pressurised double-walled vinyl tent. An air curtain was positioned around the reactor core. The exhaust air from the tent passed through 2-stage HEPA filters before venting through an external stack. Neither ANSTO staff nor contractors received any significant radiation dose during the operation. Given the sensitivity of STAR for detection of 14C/12C (∼10-16) and the numerous routes for production of 14C in the reactor such as 13C(n, γ)14C, 14N(n, p)14C and 17O(n, α)14C there was the potential to directly contaminate the STAR environment with 14C. Furthermore, there was concern that reactor-14C could find its way from this building into the building where the radiocarbon sample preparation laboratories are located. This necessitated restrictions on staff movement between the buildings. We report on 14C control measurements made during and after the operation. These involved direct measurements on the reactor graphite and concrete bioshield, blank targets that were exposed in the building, swipe samples taken inside the tent and around the building and aerosol samples that were collected inside the building throughout the operation.

Manufacture and Testing of an Activation Foil Package for Use in AFIDS

DTIC Science & Technology

2005-03-01

Miller. Nuclides and Isotopes , 16th ed. Lockheed Martin, 2002. 4. Broadhead, Bryan. Sr. Development Staff, Reactor and Fuel Cycle Analysis ...alternative, the concept of using liquid nitrous oxide inside a reactor to simulate large volumes of air was investigated. Simulation using the...weapon. We analyzed whether N2O could replicate large volumes of air in neutron transport experiments since one cubic centimeter of liquid N2O

Optimizing Characterization of Site Hydrology in Support of New Reactor Licensing at the U.S. Nuclear Regulatory Commission (Invited)

NASA Astrophysics Data System (ADS)

Nicholson, T. J.; Raione, R.; Ahn, H.; Barnhurst, D.; Giacinto, J.; McBride, M.; Tiruneh, N. D.

2009-12-01

The NRC regulates the civilian use of radioactive materials and facilities in an open and transparent manner. The NRC regulatory criteria are designed to protect human health and safety, and the environment by regulating nuclear facilities. During review of new reactor licensing applications, NRC staff reviews and independently verifies hydrogeologic information submitted by the applicant in several topical areas such as development and testing of Conceptual Site Models (CSM) which may involve perched aquifers; engineered water level fluctuations of surface-water reservoirs; ground-water collector wells and local ground-water uses; design-basis ground-water levels for structural analysis; analysis of scenarios for potential release of radionuclides to the subsurface; deep well injection of effluents; and monitoring to detect radionuclide releases. This information is reviewed in a systematic manner in accordance with NRC requirements and guidance to evaluate safety and environmental impacts and reduce the uncertainties for these impacts. NRC licensing staff is reviewing 14 applications for siting new reactors. Experience gained through these licensing activities has shown the value of using site-specific data to evaluate the CSM and its use to assess design and operational issues. Optimizing the information flow process through a systemically and thorough review process creates efficiencies. Through an iterative process of evaluating various geographical settings and associated ground-water conditions, NRC staff has developed methods to minimize prediction uncertainty through the use of confirmatory analyses performed under conservative, hierarchal approaches.

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

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

Boing, L.E.; Henley, D.R.; Manion, W.J.

1989-12-01

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document inmore » their evaluation process. 73 refs., 26 figs., 69 tabs.« less

Production of aluminum--silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. First interim technical report, Phase B, September 1--November 30, 1978

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

Bruno, M.J.

1978-12-01

The parameters of charge content, reaction temperatures and residence time were studied in a bench reactor concerning the production of Al--Si and Fe--Si alloys. Results confirmed that minimum final stage reaction temperature is 1950 to 2000/sup 0/C. Residence time varied with initial charge concentration. Fe/sub 2/O/sub 3/ additions to the charge produced a significant increase in metallic yield. A burden preparation procedure was developed for making acceptable agglomerates containing Fe/sub 2/O/sub 3/, bauxite, clay and coke. Particle size distribution of starting materials was correlated with agglomerate strength. A new bench scale reactor was designed and built to facilitate semi-continuous operation,more » using O/sub 2/ injection to burn coke supporting the burden, resulting in burden movement. In a number of runs bridging of the burden material occurred due to condensation of volatilized sub-oxides in the cooler zones of the reactor. The reactor operated smoothly as an iron blast furnace at 1500/sup 0/C, demonstrating the validity of the equipment and test procedures. Initial construction of pilot reactor VSR-1 was completed. Bench scale fractional crystallizer runs were continued to determine the impurity effects of Fe up to 6.9% and Ti up to 1.25% on alloy product concentration and yield. High levels of impurities formed intermetallic complexes with Al and reduced product yield.« less

Final Report for the “WSU Neutron Capture Therapy Facility Support”

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

Gerald E. Tripard; Keith G. Fox

2006-08-24

The objective for the cooperative research program for which this report has been written was to provide separate NCT facility user support for the students, faculty and scientists who would be doing the U.S. Department of Energy Office (DOE) of Science supported advanced radiotargeted research at the WSU 1 megawatt TRIGA reactor. The participants were the Idaho National laboratory (INL, P.I., Dave Nigg), the Veterinary Medical Research Center of Washington State University (WSU, Janean Fidel and Patrick Gavin), and the Washington State University Nuclear Radiation Center (WSU, P.I., Gerald Tripard). A significant number of DOE supported modifications were made tomore » the WSU reactor in order to create an epithermal neutron beam while at the same time maintaining the other activities of the 1 MW reactor. These modifications were: (1) Removal of the old thermal column. (2) Construction and insertion of a new epithermal filter, collimator and shield. (3) Construction of a shielded room that could accommodate the very high radiation field created by an intense neutron beam. (4) Removal of the previous reactor core fuel cluster arrangement. (5) Design and loading of the new reactor core fuel cluster arrangement in order to optimize the neutron flux entering the epithermal neutron filter. (6) The integration of the shielded rooms interlocks and radiological controls into the SCRAM chain and operating electronics of the reactor. (7) Construction of a motorized mechanism for moving and remotely controlling the position of the entire reactor bridge. (8) The integration of the reactor bridge control electronics into the SCRAM chain and operating electronics of the reactor. (9) The design, construction and attachment to the support structure of the reactor of an irradiation box that could be inserted into position next to the face of the reactor. (Necessitated by the previously mentioned core rearrangement). All of the above modifications were successfully completed and tested. The resulting epithermal beam of 1 x 10{sup 9} n/sec-cm{sup 2} was measured by Idaho National Laboratory with assistance from WSU's Neutron Activation Analysis Group. The beam is as good as our initial proposals for the project had predicted. In addition to all of the design, construction and insertion of the hardware, shielding, electronics and radiation monitoring systems there was considerable manpower and effort put into changes in the Technical Specifications of the reactor and implementing procedures for use of the new facility. This staff involvement is one of the reasons we requested special facility support from the DOE. Once the facility was competed and all of the recalibrations and measurements made to characterize the differences between this reactor core and the previous core we began to assist INL in making their beam measurements with foils and phantoms. Although we proposed support for only one additional staff position to support this new NCT facility the staff support provided by the WSU Nuclear Radiation Center was greater than had been anticipated by our initial proposal. INL was also assisted in the testing of a heavy water (deuterated water) bladder that can be inserted into the collimator in order to produce an intense, external thermal neutron beam. The external epithermal and/or thermal neutron beam capability remains available for use, if funding becomes available for future research projects.« less

Addressing the underperformance of faculty and staff.

PubMed

Kenner, Carole; Pressler, Jana L

2006-01-01

Many new nursing leaders assuming work as deans, assistant deans, or interim deans have limited education, experience, or background to prepare them for the job. To assist new deans and those aspiring to be deans, the authors of this department, both deans, offer survival tips based on their personal experiences and insights. They address common issues, challenges, and opportunities that face academic executive teams, such as negotiating an executive contract, obtaining faculty lines, building effective work teams, managing difficult employees, and creating nimble organizational structure to respond to changing consumer, healthcare delivery, and community needs. The authors welcome counterpoint discussions with readers.

Needs and Requirements for Future Research Reactors (ORNL Perspectives)

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

Ilas, Germina; Bryan, Chris; Gehin, Jess C.

2016-02-10

The High Flux Isotope Reactor (HFIR) is a vital national and international resource for neutron science research, production of radioisotopes, and materials irradiation. While HFIR is expected to continue operation for the foreseeable future, interest is growing in understanding future research reactors features, needs, and requirements. To clarify, discuss, and compile these needs from the perspective of Oak Ridge National Laboratory (ORNL) research and development (R&D) missions, a workshop, titled “Needs and Requirements for Future Research Reactors”, was held at ORNL on May 12, 2015. The workshop engaged ORNL staff that is directly involved in research using HFIR to collectmore » valuable input on the reactor’s current and future missions. The workshop provided an interactive forum for a fruitful exchange of opinions, and included a mix of short presentations and open discussions. ORNL staff members made 15 technical presentations based on their experience and areas of expertise, and discussed those capabilities of the HFIR and future research reactors that are essential for their current and future R&D needs. The workshop was attended by approximately 60 participants from three ORNL directorates. The agenda is included in Appendix A. This document summarizes the feedback provided by workshop contributors and participants. It also includes information and insights addressing key points that originated from the dialogue started at the workshop. A general overview is provided on the design features and capabilities of high performance research reactors currently in use or under construction worldwide. Recent and ongoing design efforts in the US and internationally are briefly summarized, followed by conclusions and recommendations.« less

Preparation macroconstants to simulate the core of VVER-1000 reactor

NASA Astrophysics Data System (ADS)

Seleznev, V. Y.

2017-01-01

Dynamic model is used in simulators of VVER-1000 reactor for training of operating staff and students. As a code for the simulation of neutron-physical characteristics is used DYNCO code that allows you to perform calculations of stationary, transient and emergency processes in real time to a different geometry of the reactor lattices [1]. To perform calculations using this code, you need to prepare macroconstants for each FA. One way of getting macroconstants is to use the WIMS code, which is based on the use of its own 69-group macroconstants library. This paper presents the results of calculations of FA obtained by the WIMS code for VVER-1000 reactor with different parameters of fuel and coolant, as well as the method of selection of energy groups for further calculation macroconstants.

The Concentration Of Tritium In Urine And Internal Radiation Dose Estimation Of PTNBR Radiation Workers

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

Tjahaja, Poppy Intan; Sukmabuana, Putu; Aisyah, Neneng Nur

2010-12-23

The operation of Triga 2000 reactor in Nuclear Technology Center for Materials and Radiometry (PTNBR BATAN) normally produce tritium radionuclide which is the activation product of deuterium atom in reactor primary cooling water. According to previous monitoring, tritium was detected with the concentration of 8.236{+-}0.677 kBq/L and 1.704{+-}0.046 Bq/L in the primary cooling water and in reactor hall air, respectively. The tritium in reactor hall air chronically can be inhaled by the workers. In this research, tritium content in radiation workers' urine was determined to estimate the internal radiation doses received by the workers. About 50-100 mL of urine samplesmore » were collected from 48 PTNBR workers that is classified as 24 radiation workers and 24 administration staffs as a control. Urine samples of 25 mL were then prepared by active charcoal and KMnO{sub 4} addition and followed with complete distillation. The 2 mL of distillate was added with 13 mL scintillator, shaked vigorously and remained in cool and dark condition for about 24 hours. The tritium in the samples was then measured using liquid scintillation counter (LSC) for 1 hour. From the measurement results it was obtained that the tritium concentration in the urine of radiation workers were in the range of not detected and 5.191 Bq/mL, whereas in the administration staffs the concentration were between not detected and 4.607 Bq/mL. Internally radiation doses were calculated using the tritium concentration data, and it was found the averages about 0.602 {mu}Sv/year and 0.532 {mu}Sv/year for radiation workers and administration staffs, respectively. The doses received by the workers were lower than that of the permissible doses from tritium, i.e. 40 {mu}Sv/year.« less

Study of dietary supplements compositions by neutron activation analysis at the VR-1 training reactor

NASA Astrophysics Data System (ADS)

Stefanik, Milan; Rataj, Jan; Huml, Ondrej; Sklenka, Lubomir

2017-11-01

The VR-1 training reactor operated by the Czech Technical University in Prague is utilized mainly for education of students and training of various reactor staff; however, R&D is also carried out at the reactor. The experimental instrumentation of the reactor can be used for the irradiation experiments and neutron activation analysis. In this paper, the neutron activation analysis (NAA) is used for a study of dietary supplements containing the zinc (one of the essential trace elements for the human body). This analysis includes the dietary supplement pills of different brands; each brand is represented by several different batches of pills. All pills were irradiated together with the standard activation etalons in the vertical channel of the VR-1 reactor at the nominal power (80 W). Activated samples were investigated by the nuclear gamma-ray spectrometry technique employing the semiconductor HPGe detector. From resulting saturated activities, the amount of mineral element (Zn) in the pills was determined using the comparative NAA method. The results show clearly that the VR-1 training reactor is utilizable for neutron activation analysis experiments.

Summary of the 1987 soil sampling effort at the Idaho National Engineering Laboratory Test Reactor Area Paint Shop Ditch

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

Wood, T.R.; Knight, J.L.; Hertzler, C.L.

1989-08-01

Sampling of the Test Reactor Area (TRA) Paint Shop Ditch at the Idaho National Engineering Laboratory was initiated in compliance with the Interim Agreement between the Department of Energy (DOE) and the Environmental Protection Agency (EPA). Sampling of the TRA Paint Shop Ditch was done as part of the Action Plan to achieve and maintain compliance with the Resource Conservation and Recovery Act (RCRA) and applicable regulations. It is the purpose of this document to provide a summary of the July 6, 1987 sampling activities that occurred in ditch west of Building TRA-662, which housed the TRA Paint Shop inmore » 1987. This report will give a narrative description of the field activities, locations of collected samples, discuss the sampling procedures and the chemical analyses. Also included in the scope of this report is to bring together data and reports on the TRA Paint Shop Ditch for archival purposes. 6 refs., 10 figs., 8 tabs.« less

Key metrics for HFIR HEU and LEU models

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

Ilas, Germina; Betzler, Benjamin R.; Chandler, David

This report compares key metrics for two fuel design models of the High Flux Isotope Reactor (HFIR). The first model represents the highly enriched uranium (HEU) fuel currently in use at HFIR, and the second model considers a low-enriched uranium (LEU) interim design fuel. Except for the fuel region, the two models are consistent, and both include an experiment loading that is representative of HFIR's current operation. The considered key metrics are the neutron flux at the cold source moderator vessel, the mass of 252Cf produced in the flux trap target region as function of cycle time, the fast neutronmore » flux at locations of interest for material irradiation experiments, and the reactor cycle length. These key metrics are a small subset of the overall HFIR performance and safety metrics. They were defined as a means of capturing data essential for HFIR's primary missions, for use in optimization studies assessing the impact of HFIR's conversion from HEU fuel to different types of LEU fuel designs.« less

Remaining Sites Verification Package for the 100-F-26:15 Miscellaneous Pipelines Associated with the 132-F-6, 1608-F Waste Water Pumping Station, Waste Site Reclassification Form 2007-031

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

L. M. Dittmer

2008-03-18

The 100-F-26:15 waste site consisted of the remnant portions of underground process effluent and floor drain pipelines that originated at the 105-F Reactor. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

Dreamers, Rebels, And Others.

ERIC Educational Resources Information Center

Gilbert, Michael

1992-01-01

Clinical psychologist Taibi Kahler's Process Communication Model is based on six personality types (dreamers, persisters, promoters, reactors, rebels, and workaholics). By satisfying people's individual communication needs, the model helps improve student motivation and achievement, enhances staff morale, and reduces the need for discipline. (MLH)

Interim Reliability Evaluation Program: analysis of the Browns Ferry, Unit 1, nuclear plant. Main report

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

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.

1982-07-01

A probabilistic risk assessment (PRA) was made of the Browns Ferry, Unit 1, nuclear plant as part of the Nuclear Regulatory Commission's Interim Reliability Evaluation Program (IREP). Specific goals of the study were to identify the dominant contributors to core melt, develop a foundation for more extensive use of PRA methods, expand the cadre of experienced PRA practitioners, and apply procedures for extension of IREP analyses to other domestic light water reactors. Event tree and fault tree analyses were used to estimate the frequency of accident sequences initiated by transients and loss of coolant accidents. External events such as floods,more » fires, earthquakes, and sabotage were beyond the scope of this study and were, therefore, excluded. From these sequences, the dominant contributors to probable core melt frequency were chosen. Uncertainty and sensitivity analyses were performed on these sequences to better understand the limitations associated with the estimated sequence frequencies. Dominant sequences were grouped according to common containment failure modes and corresponding release categories on the basis of comparison with analyses of similar designs rather than on the basis of detailed plant-specific calculations.« less

340B Drug Pricing Program Ceiling Price and Manufacturer Civil Monetary Penalties Regulation. Final rule; further delay of effective date.

PubMed

2017-05-19

The Health Resources and Services Administration (HRSA) administers section 340B of the Public Health Service Act (PHSA), referred to as the "340B Drug Pricing Program" or the "340B Program." HRSA published a final rule on January 5, 2017, that set forth the calculation of the ceiling price and application of civil monetary penalties. The final rule applied to all drug manufacturers that are required to make their drugs available to covered entities under the 340B Program. In accordance with a January 20, 2017, memorandum from the Assistant to the President and Chief of Staff, entitled "Regulatory Freeze Pending Review," HRSA issued an interim final rule that delayed the effective date of the final rule published in the Federal Register (82 FR 1210, (January 5, 2017)) to May 22, 2017. HHS invited commenters to provide their views on whether a longer delay of the effective date to October 1, 2017, would be more appropriate. After consideration of the comments received on the interim final rule, HHS is delaying the effective date of the January 5, 2017 final rule, to October 1, 2017.

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

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

Phillips, S.J.; Phillips, M.; Etheridge, D.

2012-07-01

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

75 FR 44819 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Siting

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-29

...--8:30 a.m. Until 5 p.m. The Subcommittee will review the MOX Fuel Fabrication Facility (Shaw-Areva... presentations by and hold discussions with representatives of the NRC staff, Shaw-Areva, LLC, and other...

HFBR handbook. Revised

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

Shapiro, S.; Rorer, D.C.; Kuper, H.

1983-08-01

This manual is intended primarily to acquaint outside users and new Brookhaven staff members with the research facilities available at the HFBR. In addition to describing the beam lines and major instruments, general information is also provided on the reactor and on services available at the Laboratory.

Dry transfer system for spent fuel: Project report, A system designed to achieve the dry transfer of bare spent fuel between two casks. Final report

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

Dawson, D.M.; Guerra, G.; Neider, T.

1995-12-01

This report describes the system developed by EPRI/DOE for the dry transfer of spent fuel assemblies outside the reactor spent fuel pool. The system is designed to allow spent fuel assemblies to be removed from a spent fuel pool in a small cask, transported to the transfer facility, and transferred to a larger cask, either for off-site transportation or on-site storage. With design modifications, this design is capable of transferring single spent fuel assemblies from dry storage casks to transportation casks or visa versa. One incentive for the development of this design is that utilities with limited lifting capacity ormore » other physical or regulatory constraints are limited in their ability to utilize the current, more efficient transportation and storage cask designs. In addition, DOE, in planning to develop and implement the multi-purpose canister (MPC) system for the Civilian Radioactive Waste Management System, included the concept of an on-site dry transfer system to support the implementation of the MPC system at reactors with limitations that preclude the handling of the MPC system transfer casks. This Dry Transfer System can also be used at reactors wi decommissioned spent fuel pools and fuel in dry storage in non-MPC systems to transfer fuel into transportation casks. It can also be used at off-reactor site interim storage facilities for the same purpose.« less

78 FR 59981 - Proposed Revision to Physical Security-Standard Design Certification and Operating Reactors

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-30

... the Standard Review Plan (SRP), concerning the physical security reviews of design certification... NRC staff with the physical security review of applications for design certifications, incorporate... NUCLEAR REGULATORY COMMISSION [NRC-2013-0225] Proposed Revision to Physical Security--Standard...

Interim Results of a National Test of the Rapid Assessment of Hospital Procurement Barriers in Donation (RAPiD)

PubMed Central

Traino, H. M.; Alolod, G. P.; Shafer, T.; Siminoff, L. A.

2012-01-01

Organ donation remains a major public health challenge with over 114 000 people on the waitlist in the United States. Among other factors, extant research highlights the need to improve the identification and timely referral of potential donors by hospital health-care providers (HCPs) to organ procurement organizations (OPOs). We implemented a national test of the Rapid Assessment of hospital Procurement barriers in Donation (RAPiD) to identify assets and barriers to the organ donation and patient referral processes; assess hospital–OPO relationships and offer tailored recommendations for improving these processes. Having partnered with seven OPOs, data were collected at 70 hospitals with high donor potential in the form of direct observations and interviews with 2358 HCPs. We found that donation attitudes and knowledge among HCPs were high, but use of standard referral criteria was lacking. Significant differences were found in the donation-related attitudes, knowledge and behaviors of physicians and emergency department staff as compared to other staff in intensive care units with high organ donor potential. Also, while OPO staff were generally viewed positively, they were often perceived as outsiders rather than members of healthcare teams. Recommendations for improving the referral and donation processes are discussed. PMID:22900761

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

Stevens, D.L.; Simonen, F.A.; Strosnider, J. Jr.

The VISA (Vessel Integrity Simulation Analysis) code was developed as part of the NRC staff evaluation of pressurized thermal shock. VISA uses Monte Carlo simulation to evaluate the failure probability of a pressurized water reactor (PWR) pressure vessel subjected to a pressure and thermal transient specified by the user. Linear elastic fracture mechanics are used to model crack initiation and propagation. parameters for initial crack size, copper content, initial RT/sub NDT/, fluence, crack-initiation fracture toughness, and arrest fracture toughness are treated as random variables. This report documents the version of VISA used in the NRC staff report (Policy Issue frommore » J.W. Dircks to NRC Commissioners, Enclosure A: NRC Staff Evaluation of Pressurized Thermal Shock, November 1982, SECY-82-465) and includes a user's guide for the code.« less

Safety evaluation report on Tennessee Valley Authority: Browns Ferry nuclear performance plan

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

Not Available

1989-10-01

This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory commission staff. The Browns Ferry Nuclear Plant consists of three boiling-water reactors at a site in Limestone County, Alabama. The plan addresses the plant-specific concerns requiring resolution before the startup of Unit 2. The staff will inspect implementation of those TVA programs that address these concerns. Where systems are common to Units 1 and 2 or to Units 2more » and 3, the staff safety evaluations of those systems are included herein. 85 refs.« less

Tuberculosis among prison staff in Rio Grande do Sul.

PubMed

Busatto, Caroline; Nunes, Luciana de Souza; Valim, Andréia Rosane de Moura; Valença, Mariana Soares; Krug, Suzane Frantz; Becker, Daniela; Allgayer, Manuela Filter; Possuelo, Lia Gonçalves

2017-04-01

to evaluate the risk of infection and illness caused by Mycobacterium tuberculosis among health care and security staff in prisons in two regions of Rio Grande do Sul (RS). cross-sectional study involving prison staff. An interview and sputum smear microscopy and culture were performed. Latent infection was evaluated according to the result of the tuberculin test (TT), self-referred. among staff who had a TT, 10 (83.3%) in the central region and 2 (16.7%) in the southern region were considered reactors. Length of employment among prison officers who reacted to TT was 15.3 years, and among health care workers, 4.1 years (p = 0.01). No cases of active tuberculosis (TB) were identified. prevalence of latent TB was 27.9%. Length of employment between different professional categories and their working regions was considered a risk factor for latent TB.

76 FR 5218 - Advisory Committee on Reactor Safeguards

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-28

..., October 21, 2010 (74 FR 65038-65039). Thursday, February 10, 2011, Conference Room T2-B1, 11545 Rockville... Evaluation Report Associated with the License Renewal Application for the Palo Verde Nuclear Generating... NRC staff and Arizona Public Service Company regarding the final Safety Evaluation Report associated...

77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-27

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0182] Terrestrial Environmental Studies for Nuclear Power... Environmental Studies for Nuclear Power Stations.'' This guide provides technical guidance that the NRC staff... nuclear power reactors. ADDRESSES: Please refer to Docket ID NRC-2011-0182 when contacting the NRC about...

Education and career progression of imaging administrators.

PubMed

South-Winter, Carole

2014-01-01

The advancement into leadership positions for many administrators began as staff technologists moving up via interim management opportunities. New managers must develop supervisory skills while simultaneously assuming responsibility for the operation of the department. Mobility today is based primarily on a formal educational background. A transferable set of skills must be augmented with higher education. Those in the imaging sciences realize that an administrative position requires business and management acumen as well as technical skills. A shortage of imaging administrators is predicted due to an aging population and the rapid advancement of technology in healthcare. Institutes of higher education need to address and support the curricula and programs needed, which includes the CRA credential, for this growing field.

75 FR 28074 - Advisory Committee on Reactor Safeguards

Federal Register 2010, 2011, 2012, 2013, 2014

2010-05-19

..., 2009, (74 FR 52829-52830). Wednesday, June 9, 2010, Conference Room T2-B1, Two White Flint North... Regulatory Guide (RG) 1.216, ``Containment Structural Integrity Evaluation for Internal Pressure Loadings... representatives of the NRC staff regarding draft final RG 1.216, ``Containment Structural Integrity Evaluation for...

77 FR 16278 - Advisory Committee on Reactor Safeguards: Notice of Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-20

..., 11545 Rockville Pike, Rockville, Maryland. Thursday, April 12, 2012, Conference Room T2-B1, 11545....: Selected Chapters of the Safety Evaluation Report (SER) with Open Items Associated with the Calvert Cliffs... chapters of the NRC staff's Safety Evaluation Report (SER) with open items associated with the Calvert...

10 CFR 2.102 - Administrative review of application.

Code of Federal Regulations, 2010 CFR

2010-01-01

... Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF... proceeding to confer with the NRC staff informally. In the case of docketed application for a limited work... completion of its review. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New...

77 FR 10786 - Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Reliability...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-02-23

... Modeling Application Guide.'' The Subcommittee will hear presentations by and hold discussions with the NRC staff and other interested persons regarding this matter. The Subcommittee will gather information.../acrs . Information regarding topics to be discussed, changes to the agenda, whether the meeting has...

Lithium vapor/aerosol studies. Interim summary report

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

Whitlow, G.A.; Bauerle, J.E.; Down, M.G.

1979-04-01

The temperature/cover gas pressure regime, in which detectable lithium aerosol is formed in a static system has been mapped for argon and helium cover gases using a portable He--Ne laser device. At 538/sup 0/C (1000/sup 0/F), lithium aerosol particles were observed over the range 0.5 to 20 torr and 2 to 10 torr for argon and helium respectively. The experimental conditions in this study were more conducive to aerosol formation than in a fusion reactor. In the real reactor system, very high intensity mechanical and thermal disturbances will be made to the liquid lithium. These disturbances, particularly transient increases inmore » lithium vapor pressure appear to be capable of producing high concentrations of optically-dense aerosol. A more detailed study is, therefore, proposed using the basic information generated in these preliminary experiments, as a starting point. Areas recommended include the kinetics of aerosol formation and the occurrence of supersaturated vapor during rapid vapor pressure transients, and also the effect of lithium agitation (falls, jets, splashing, etc.) on aerosol formation.« less

Technical and economic assessment of different options for minor actinide transmutation: the French case

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

Chabert, C.; Coquelet-Pascal, C.; Saturnin, A.

Studies have been performed to assess the industrial perspectives of partitioning and transmutation of long-lived elements. These studies were carried out in tight connection with GEN-IV systems development. The results include the technical and economic evaluation of fuel cycle scenarios along with different options for optimizing the processes between the minor actinide transmutation in fast neutron reactors, their interim storage and geological disposal of ultimate waste. The results are analysed through several criteria (impacts on waste, on waste repository, on fuel cycle plants, on radiological exposure of workers, on costs and on industrial risks). These scenario evaluations take place inmore » the French context which considers the deployment of the first Sodium-cooled Fast Reactor (SFR) in 2040. 3 management options of minor actinides have been studied: no transmutation, transmutation in SFR and transmutation in an accelerator-driven system (ADS). Concerning economics the study shows that the cost overrun related to the transmutation process could vary between 5 to 9% in SFR and 26 % in the case of ADS.« less

VVER Reactor Safety in Eastern Europe and Former Soviet Union

NASA Astrophysics Data System (ADS)

Papadopoulou, Demetra

2012-02-01

VVER Soviet-designed reactors that operate in Eastern Europe and former Soviet republics have heightened international concern for years due to major safety deficiencies. The governments of countries with VVER reactors have invested millions of dollars toward improving the safety of their nuclear power plants. Most of these reactors will continue to operate for the foreseeable future since they provide urgently-needed electrical power. Given this situation, this paper assesses the radiological consequences of a major nuclear accident in Eastern Europe. The paper also chronicles the efforts launched by the international nuclear community to improve the safety of the reactors and notes the progress made so far through extensive collaborative efforts in Armenia, Bulgaria, the Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine to reduce the risks of nuclear accidents. Western scientific and technical staff collaborated with these countries to improve the safety of their reactor operations by strengthening the ability of the regulator to perform its oversight function, installing safety equipment and technologies, investing time in safety training, and working diligently to establish an enduring safety culture. Still, continued safety improvement efforts are necessary to ensure safe operating practices and achieve timely phase-out of older plants.

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

Not Available

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation,more » boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.« less

324 Building B-Cell Pressurized Water Reactor Spent Fuel Packaging & Shipment RL Readiness Assessment Final Report [SEC 1 Thru 3

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

HUMPHREYS, D C

A parallel readiness assessment (RA) was conducted by independent Fluor Hanford (FH) and U. S. Department of Energy, Richland Operations Office (RL) team to verify that an adequate state of readiness had been achieved for activities associated with the packaging and shipping of pressurized water reactor fuel assemblies from B-Cell in the 324 Building to the interim storage area at the Canister Storage Building in the 200 Area. The RL review was conducted in parallel with the FH review in accordance with the Joint RL/FH Implementation Plan (Appendix B). The RL RA Team members were assigned a FH RA Teammore » counterpart for the review. With this one-on-one approach, the RL RA Team was able to assess the FH Team's performance, competence, and adherence to the implementation plan and evaluate the level of facility readiness. The RL RA Team agrees with the FH determination that startup of the 324 Building B-Cell pressurized water reactor spent nuclear fuel packaging and shipping operations can safely proceed, pending completion of the identified pre-start items in the FH final report (see Appendix A), completion of the manageable list of open items included in the facility's declaration of readiness, and execution of the startup plan to operations.« less

Experimental validation of the DARWIN2.3 package for fuel cycle applications

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

San-Felice, L.; Eschbach, R.; Bourdot, P.

2012-07-01

The DARWIN package, developed by the CEA and its French partners (AREVA and EDF) provides the required parameters for fuel cycle applications: fuel inventory, decay heat, activity, neutron, {gamma}, {alpha}, {beta} sources and spectrum, radiotoxicity. This paper presents the DARWIN2.3 experimental validation for fuel inventory and decay heat calculations on Pressurized Water Reactor (PWR). In order to validate this code system for spent fuel inventory a large program has been undertaken, based on spent fuel chemical assays. This paper deals with the experimental validation of DARWIN2.3 for the Pressurized Water Reactor (PWR) Uranium Oxide (UOX) and Mixed Oxide (MOX) fuelmore » inventory calculation, focused on the isotopes involved in Burn-Up Credit (BUC) applications and decay heat computations. The calculation - experiment (C/E-1) discrepancies are calculated with the latest European evaluation file JEFF-3.1.1 associated with the SHEM energy mesh. An overview of the tendencies is obtained on a complete range of burn-up from 10 to 85 GWd/t (10 to 60 GWcVt for MOX fuel). The experimental validation of the DARWIN2.3 package for decay heat calculation is performed using calorimetric measurements carried out at the Swedish Interim Spent Fuel Storage Facility for Pressurized Water Reactor (PWR) assemblies, covering a large burn-up (20 to 50 GWd/t) and cooling time range (10 to 30 years). (authors)« less

Safety evaluation report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan

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

Not Available

1991-01-01

This safety evaluation report (SER) was prepared by the US Nuclear Regulatory Commission (NRC) staff and represents the second and last supplement (SSER 2) to the staff's original SER published as Volume 3 of NUREG-1232 in April 1989. Supplement 1 of Volume 3 of NUREG-1232 (SSER 1) was published in October 1989. Like its predecessors, SSER 2 is composed of numerous safety evaluations by the staff regarding specific elements contained in the Browns Ferry Nuclear Performance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the Browns Ferry Nuclear Plant (BFN).more » The Browns Ferry Nuclear Plant consists of three boiling-water reactors (BWRs) at a site in Limestone County, Alabama. The BFNPP describes the corrective action plans and commitments made by TVA to resolve deficiencies with its nuclear programs before the startup of Unit 2. The staff has inspected and will continue to inspect TVA's implementation of these BFNPP corrective action plans that address staff concerns about TVA's nuclear program. SSER 2 documents the NRC staff's safety evaluations and conclusions for those elements of the BFNPP that were not previously addressed by the staff or that remained open as a result of unresolved issues identified by the staff in previous SERs and inspections.« less

Analysis of Transportation Options for Commercial Spent Fuel in the U.S.

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

Kalinina, Elena; Busch, Ingrid Karin

The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S.more » Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage The U.S. Department of Energy (DOE) is laying the groundwork for implementing interim storage and associated transportation of spent nuclear fuel (SNF) highand associated transportation of spent nuclear fuel (SNF) and high and associated transportation of spent nuclear fuel (SNF) highand associated transportation of spent nuclear fuel (SNF) and high and associated transportation of spent nuclear fuel (SNF) highand associated transportation of spent nuclear fuel (SNF) and highand associated transportation of spent nuclear fuel (SNF) and high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) highand associated transportation of spent nuclear fuel (SNF) and high and associated transportation of spent nuclear fuel (SNF) high and associated transportation of spent nuclear fuel (SNF) highand associated transportation of spent nuclear fuel (SNF)...« less

76 FR 23340 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-26

... Thursday, October 21, 2010 (75 FR 65038-65039). Thursday, May 12, 2011, Conference Room T2-B1, 11545... Safety Evaluation Report Associated with the License Renewal Application for the Hope Creek Generating... NRC staff and PSEG Nuclear, LLC regarding the final safety evaluation report (SER) associated with the...

76 FR 64399 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-18

... Thursday, October 21, 2010 (74 FR 65038-65039). Thursday, November 3, 2011, Conference Room T2-B1, 11545... Evaluation of Diversity and Defense-In-Depth in Digital Computer-Based Instrumentation and Control Systems... staff regarding Branch Technical Position 7- 19, ``Guidance for the Evaluation of Diversity and Defense...

10 CFR 52.135 - Filing of applications.

Code of Federal Regulations, 2010 CFR

2010-01-01

... design for a nuclear power reactor of the type described in 10 CFR 50.22 to the NRC staff for its review... 10 Energy 2 2010-01-01 2010-01-01 false Filing of applications. 52.135 Section 52.135 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

76 FR 1376 - Physical Protection of Irradiated Reactor Fuel in Transit Extension of Comment Period

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-10

... dockets to Carol Gallagher, telephone: 301-492- 3668, e-mail: [email protected] . Mail comments to... Adjudications Staff. E-mail comments to: [email protected] . If you do not receive a reply e-mail..., e-mail: [email protected] . SUPPLEMENTARY INFORMATION: Submitting Comments and Accessing...

Radiation Characterization Summary: ACRR Polyethylene-Lead-Graphite (PLG) Bucket Located in the Central Cavity on the 32-Inch Pedestal at the Core Centerline (ACRR-PLG-CC-32-cl).

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

Parma, Edward J.,; Vehar, David W.; Lippert, Lance L.

2015-06-01

This document presents the facility-recommended characterization of the neutron, prompt gamma-ray, and delayed gamma-ray radiation fields in the Annular Core Research Reactor (ACRR) for the polyethylene-lead-graphite (PLG) bucket in the central cavity on the 32-inch pedestal at the core centerline. The designation for this environment is ACRR-PLG-CC-32-cl. The neutron, prompt gamma-ray, and delayed gamma-ray energy spectra, uncertainties, and covariance matrices are presented as well as radial and axial neutron and gamma-ray fluence profiles within the experiment area of the bucket. Recommended constants are given to facilitate the conversion of various dosimetry readings into radiation metrics desired by experimenters. Representative pulsemore » operations are presented with conversion examples. Acknowledgements The authors wish to thank the Annular Core Research Reactor staff and the Radiation Metrology Laboratory staff for their support of this work. Also thanks to David Ames for his assistance in running MCNP on the Sandia parallel machines.« less

Radiation Characterization Summary: ACRR Central Cavity Free-Field Environment with the 32-Inch Pedestal at the Core Centerline (ACRR-FF-CC-32-cl).

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

Vega, Richard Manuel; Parma, Edward J.; Naranjo, Gerald E.

2015-08-01

This document presents the facilit y - recommended characteri zation o f the neutron, prompt gamma - ray, and delayed gamma - ray radiation fields in the Annular Core Research Reactor ( ACRR ) for the cen tral cavity free - field environment with the 32 - inch pedestal at the core centerline. The designation for this environmen t is ACRR - FF - CC - 32 - cl. The neutron, prompt gamma - ray , and delayed gamma - ray energy spectra , uncertainties, and covariance matrices are presented as well as radial and axial neutron and gamma -more » ray fluence profiles within the experiment area of the cavity . Recommended constants are given to facilitate the conversion of various dosimetry readings into radiation metrics desired by experimenters. Representative pulse operations are presented with conversion examples . Acknowledgements The authors wish to th ank the Annular Core Research Reactor staff and the Radiation Metrology Laboratory staff for their support of this work . Also thanks to David Ames for his assistance in running MCNP on the Sandia parallel machines.« less

Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. Second interim technical report, Phase C for the period 1980 April 1-1980 June 30

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

Bruno, M.J.

1980-10-01

Beneficiation of bauxite by high intensity wet magnetic separation to remove Fe and Ti was not successful. Pilot reactor VSR-3 was modified and operated to evaluate the blast-arc reduction process concept. Modifications included a tapered upper shaft section, vertical stroke ram, and CO preheater system. The taper/ram revisions were successful in maintaining bed movement, resulting in several continuous runs in which large quantities of burden were fed and metal product was recovered. Pilot VSR samples were also analyzed. The major phases contained Si and FeSi/sub 2/Al/sub 4/ intermetallics in a matrix of eutectic Al-Si.

Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. Third interim technical report, Phase C for the period 1980 July 1-1980 September 30

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

Bruno, M.J.

1980-10-01

Pilot reactor VSR-3 operation in the third quarter was directed to tapping molten alloy product. Modifications to the hearth region included a tapping furnace to maintain taphole temperature, a graphite ring filter to separate carbides from matal and an alumina liner to eliminate carbiding from reaction of alloy with the graphite hearth walls. Tapping was not successful, however, due to high alloy viscosity from a large concentration of carbides. Three runs were made on the pilot crystallizer to determine the effects of alloy composition, cooling rate, tamping rate, remelt temperature and rate on eutectic Al-Si yield.

Computer modeling with randomized-controlled trial data informs the development of person-centered aged care homes.

PubMed

Chenoweth, Lynn; Vickland, Victor; Stein-Parbury, Jane; Jeon, Yun-Hee; Kenny, Patricia; Brodaty, Henry

2015-10-01

To answer questions on the essential components (services, operations and resources) of a person-centered aged care home (iHome) using computer simulation. iHome was developed with AnyLogic software using extant study data obtained from 60 Australian aged care homes, 900+ clients and 700+ aged care staff. Bayesian analysis of simulated trial data will determine the influence of different iHome characteristics on care service quality and client outcomes. Interim results: A person-centered aged care home (socio-cultural context) and care/lifestyle services (interactional environment) can produce positive outcomes for aged care clients (subjective experiences) in the simulated environment. Further testing will define essential characteristics of a person-centered care home.

76 FR 4369 - Interim Deputation Agreements; Interim BIA Adult Detention Facility Guidelines

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-25

... Adult Detention Facility Guidelines AGENCY: Bureau of Indian Affairs, Interior. ACTION: Notice. SUMMARY: This notice announces the online publication of the Interim BIA Adult Detention Facility Guidelines and... Indian Affairs Web site. DATES: These Interim BIA Adult Detention Facility Guidelines and Interim Model...

24 CFR 35.820 - Interim controls.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Interim controls. 35.820 Section 35...-Possession Multifamily Property § 35.820 Interim controls. HUD shall conduct interim controls in accordance... accordance with § 35.815. Interim controls are considered completed when clearance is achieved in accordance...

24 CFR 35.820 - Interim controls.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 24 Housing and Urban Development 1 2012-04-01 2012-04-01 false Interim controls. 35.820 Section 35...-Possession Multifamily Property § 35.820 Interim controls. HUD shall conduct interim controls in accordance... accordance with § 35.815. Interim controls are considered completed when clearance is achieved in accordance...

76 FR 70778 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Federal Register 2010, 2011, 2012, 2013, 2014

2011-11-15

... Pike, Rockville, Maryland. Thursday, December 1, 2011, Conference Room T2-B1, 11545 Rockville Pike... subsequent COL application for Levy County, Units 1 and 2, and the NRC staff's associated safety evaluation... pursuant to 5 U.S.C. 552b(c)(4).] Friday, December 2, 2011, Conference Room T2-B1, 11545 Rockville Pike...

Rebuilding the Brookhaven high flux beam reactor: A feasibility study

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

Brynda, W.J.; Passell, L.; Rorer, D.C.

1995-01-01

After nearly thirty years of operation, Brookhaven`s High Flux Beam Reactor (HFBR) is still one of the world`s premier steady-state neutron sources. A major center for condensed matter studies, it currently supports fifteen separate beamlines conducting research in fields as diverse as crystallography, solid-state, nuclear and surface physics, polymer physics and structural biology and will very likely be able to do so for perhaps another decade. But beyond that point the HFBR will be running on borrowed time. Unless appropriate remedial action is taken, progressive radiation-induced embrittlement problems will eventually shut it down. Recognizing the HFBR`s value as a nationalmore » scientific resource, members of the Laboratory`s scientific and reactor operations staffs began earlier this year to consider what could be done both to extend its useful life and to assure that it continues to provide state-of-the-art research facilities for the scientific community. This report summarizes the findings of that study. It addresses two basic issues: (i) identification and replacement of lifetime-limiting components and (ii) modifications and additions that could expand and enhance the reactor`s research capabilities.« less

Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. Second interim technical report, Phase B, December 1, 1978-February 28, 1979

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

Bruno, M.J.

1979-03-01

Experimental runs were made to determine the effect of a cooler product reservoir on metal alloy yield and recovery. The reservoir temperature had no significant effect. Difficulties were experienced with operation of an oxygen injected bench scale reactor. Many tests were terminated by burden bridging or flooding of the oxygen tuyeres with metal and slag. Runs were made in which refluxing vapors were condensed in a liquid slag. The addition of CaO decreased the tendency for formation of thick, strong burden bridges but did not completely eliminate bridging. Reduction of flame temperatures did not affect the volatilization rate in themore » bench reactor. Operation of VSR-1 pilot reactor with O injection was achieved after resolving reactor shell leakage problems, by replacing the permeable ceramic shell with impermeable fused silica. Various combustion parameters were investigated, including coke size, burden height and oxygen flow rate. Steady state operation of the oxygen-coke system was attained with smooth burden movement and a 2000/sup 0/C bed temperature in the raceway vicinity. To further reduce heat losses from the raceway area. VSR-1 was redesigned to facilitate locating an induction coil below the oxygen inlets. Further evaluation of effects of impurities on alloy purification in the bench scale unit indicated a 50% decrease in product yield for starting charges containing Fe greater than 5%. Site installation for the entire alloy purification complex was completed. Operations were continued in the bench scale units to obtain design information for the pilot commercial grade Al purification unit. Procurement of construction material was established.« less

75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

Federal Register 2010, 2011, 2012, 2013, 2014

2010-01-07

... Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites AGENCY... Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response... interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer...

NASA Reactor Facility Hazards Summary. Volume 1

NASA Technical Reports Server (NTRS)

1959-01-01

The Lewis Research Center of the National Aeronautics and Space Administration proposes to build a nuclear research reactor which will be located in the Plum Brook Ordnance Works near Sandusky, Ohio. The purpose of this report is to inform the Advisory Committee on Reactor Safeguards of the U. S. Atomic Energy Commission in regard to the design Lq of the reactor facility, the characteristics of the site, and the hazards of operation at this location. The purpose of this research reactor is to make pumped loop studies of aircraft reactor fuel elements and other reactor components, radiation effects studies on aircraft reactor materials and equipment, shielding studies, and nuclear and solid state physics experiments. The reactor is light water cooled and moderated of the MTR-type with a primary beryllium reflector and a secondary water reflector. The core initially will be a 3 by 9 array of MTR-type fuel elements and is designed for operation up to a power of 60 megawatts. The reactor facility is described in general terms. This is followed by a discussion of the nuclear characteristics and performance of the reactor. Then details of the reactor control system are discussed. A summary of the site characteristics is then presented followed by a discussion of the larger type of experiments which may eventually be operated in this facility. The considerations for normal operation are concluded with a proposed method of handling fuel elements and radioactive wastes. The potential hazards involved with failures or malfunctions of this facility are considered in some detail. These are examined first from the standpoint of preventing them or minimizing their effects and second from the standpoint of what effect they might have on the reactor facility staff and the surrounding population. The most essential feature of the design for location at the proposed site is containment of the maximum credible accident.

Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012

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

Nancy J. Lybeck; Vivek Agarwal; Binh T. Pham

The Light Water Reactor Sustainability program at Idaho National Laboratory (INL) is actively conducting research to develop and demonstrate online monitoring (OLM) capabilities for active components in existing Nuclear Power Plants. A pilot project is currently underway to apply OLM to Generator Step-Up Transformers (GSUs) and Emergency Diesel Generators (EDGs). INL and the Electric Power Research Institute (EPRI) are working jointly to implement the pilot project. The EPRI Fleet-Wide Prognostic and Health Management (FW-PHM) Software Suite will be used to implement monitoring in conjunction with utility partners: the Shearon Harris Nuclear Generating Station (owned by Duke Energy for GSUs, andmore » Braidwood Generating Station (owned by Exelon Corporation) for EDGs. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for GSUs. GSUs are main transformers that are directly connected to generators, stepping up the voltage from the generator output voltage to the highest transmission voltages for supplying electricity to the transmission grid. Technical experts from Shearon Harris are assisting INL and EPRI in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the FW-PHM Software Suite and tested using data from Shearon-Harris. Parallel research on EDGs is being conducted, and will be reported in an interim report during the first quarter of fiscal year 2013.« less

Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. First interim technical report, Phase D, January 1-March 31, 1981

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

Bruno, M.J.

1981-04-01

Operation of the bench AF-reactor on burden with all reducing carbon exterior to the ore pellet resulted in low metal alloy product yields and prematurely terminated runs, indicating the need for intimate contact between alumina and carbon to produce oxycarbide liquid prior to reaction with solid silicon carbide. Carbon solubility tests made on 60Al-40Si alloys at 2200/sup 0/C in graphite crucibles indicated continued reaction to form SiC for one hour. Efficiency of reduction to SiC ranged from 68 to 100%. The A-C two-electrode submerged arc reactor pilot, SAR-II, was successfully operated on both alumina-clay-coke and alumina-silicon carbide-coke (from the VSRmore » prereduction) burdens. Metal alloy was produced and tapped in each of four runs. The pilot crystallizer was operated to evalute the two-stage (stop and go) crystallization technique on obtaining high yields of Al in Al-Si eutectic, with a limit of 1.0% Fe and 0.1% Ti in the alloy product. 18 figures, 19 tables. (DLC)« less

Production of aluminum-silicon alloy and ferrosilicon and commercial purity aluminum by the direct reduction process. First interim technical report, Phase C for the period 1980 January 1-1980 March 31

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

Bruno, M.J.

1980-10-01

Pilot reactor VSR-3 was operated with 75 to 120 SCFH O/sub 2/ to supply part of the process heat requirements by combustion of coke. No alloy was made and burden bridging persistently stopped operations. Burning larger coke particles, -3/8 in. +6 mesh, with O/sub 2/ injected through a larger diameter tuyere orifice resulted in oxygen attack on the reactor graphite liner. Updated thermochemical data for Al/sub 2/O/sub 3/ significantly changed the calculated reflux loading for a one-atm blast furnace, predicting almost total reflux and no alloy recovery. Based on these calculations and the experimental problems with combustion heated operation, VSR-3more » was modified to study an alternate reduction concept - the blast-arc - which utilizes combustion heat to reduce SiO/sub 2/ to SiC at 1600/sup 0/C, and electrical heat to complete the reduction of Al/sub 2/O/sub 3/ and the production of alloy. Design, fabrication, and installation of most of the pilot crystallizer sytem was completed.« less

Safety and efficacy of lithium in combination with riluzole for treatment of amyotrophic lateral sclerosis: a randomised, double-blind, placebo-controlled trial.

PubMed

Aggarwal, Swati P; Zinman, Lorne; Simpson, Elizabeth; McKinley, Jane; Jackson, Katherine E; Pinto, Hanika; Kaufman, Petra; Conwit, Robin A; Schoenfeld, David; Shefner, Jeremy; Cudkowicz, Merit

2010-05-01

In a pilot study, lithium treatment slowed progression of amyotrophic lateral sclerosis (ALS). We aimed to confirm or disprove these findings by assessing the safety and efficacy of lithium in combination with riluzole in patients with ALS. We did a double-blind, placebo-controlled trial with a time-to-event design. Between January and June, 2009, patients with ALS who were taking a stable dose of riluzole for at least 30 days were randomly assigned (1:1) by a centralised computer to receive either lithium or placebo. Patients, caregivers, investigators, and all site study staff with the exception of site pharmacists were masked to treatment assignment. The primary endpoint was the time to an event, defined as a decrease of at least six points on the revised ALS functional rating scale score or death. Interim analyses were planned for when 84 patients had been allocated treatment, 6 months later or after 55 events, and after 100 events. Analysis was by intention to treat. The stopping boundary for futility at the first interim analysis was a p value of at least 0.68. We used a log-rank test to compare the distributions of the time to an event between the lithium and placebo groups. This trial is registered with ClinicalTrials.gov, NCT00818389. At the first interim analysis, 22 of 40 patients in the lithium group had an event compared with 20 of 44 patients in the placebo group (log rank p=0.51). The hazard ratio of reaching the primary endpoint was 1.13 (95% CI 0.61-2.07). The study was stopped at the first interim analysis because criterion for futility was met (p=0.78). The difference in mean decline in the ALS functional rating scale score between the lithium group and the placebo group was 0.15 (95% CI -0.43 to 0.73, p=0.61). There were no major safety concerns. Falls (p=0.04) and back pain (p=0.05) were more common in the lithium group than in the placebo group. We found no evidence that lithium in combination with riluzole slows progression of ALS more than riluzole alone. The time-to-event endpoint and use of prespecified interim analyses enabled a clear result to be obtained rapidly. This design should be considered for future trials testing the therapeutic efficacy of drugs that are easily accessible to people with ALS. National Institute of Neurological Disorders and Stroke, ALS Association, and ALS Society of Canada. Copyright 2010 Elsevier Ltd. All rights reserved.

Improving the Quality of Radiographs in Neonatal Intensive Care Unit Utilizing Educational Interventions.

PubMed

Gupta, Ashish O; Rorke, Jeanne; Abubakar, Kabir

2015-08-01

We aimed to develop an educational tool to improve the radiograph quality, sustain this improvement overtime, and reduce the number of repeat radiographs. A three phase quality control study was conducted at a tertiary care NICU. A retrospective data collection (phase1) revealed suboptimal radiograph quality and led to an educational intervention and development of X-ray preparation checklist (primary intervention), followed by a prospective data collection for 4 months (phase 2). At the end of phase 2, interim analysis revealed a gradual decline in radiograph quality, which prompted a more comprehensive educational session with constructive feedback to the NICU staff (secondary intervention), followed by another data collection for 6 months (phase 3). There was a significant improvement in the quality of radiographs obtained after primary educational intervention (phase 2) compared with phase 1 (p < 0.001). During interim analysis after phase 2, radiograph quality declined but still remained significantly better than phase 1. Secondary intervention resulted in significant improvement in radiograph quality to > 95% in all domains of image quality. No radiographs were repeated in phase 3, compared with 5.8% (16/277) in phase 1. A structured, collaborated educational intervention successfully improves the radiograph quality and decreases the need for repeat radiographs and radiation exposure in the neonates. Thieme Medical Publishers 333 Seventh Avenue, New York, NY 10001, USA.

Activities and interim outcomes of a multi-site development project to promote cognitive support technology use and employment success among postsecondary students with traumatic brain injuries.

PubMed

Hendricks, Deborah J; Sampson, Elaine; Rumrill, Phillip; Leopold, Anne; Elias, Eileen; Jacobs, Karen; Nardone, Amanda; Scherer, Marcia; Stauffer, Callista

2015-01-01

This article describes the activities and interim outcomes of a multi-site development project called Project Career, designed to promote cognitive support technology (CST) use and employment success for college and university students with traumatic brain injuries (TBIs). To obtain early intervention results from participants in Project Career's first 18 months of operation. Fifty-six students with TBI have participated to date across three implementation sites in Massachusetts, Ohio, and West Virginia, with 25 of these participants being military veterans. Descriptive analyses provide information regarding the participants, the barriers they face due to their TBI in obtaining a post-secondary education, and the impact services provided by Project Career have had to date in ameliorating those difficulties. Inferential statistical analyses provide preliminary results regarding program effectiveness. Preliminary results indicate the program is encouraging students to use CST strategies in the form of iPads and cognitive enhancement applications (also known as 'apps'). Significant results indicate participants are more positive, independent, and social; participants have a more positive attitude toward technology after six months in the program; and participants reported significantly improved experiences with technology during their first six months in the program. Participating students are actively preparing for their careers after graduation through a wide range of intensive vocational supports provided by project staff members.

222-S Laboratory Quality Assurance Plan. Revision 1

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

Meznarich, H.K.

1995-07-31

This Quality Assurance Plan provides,quality assurance (QA) guidance, regulatory QA requirements (e.g., 10 CFR 830.120), and quality control (QC) specifications for analytical service. This document follows the U.S Department of Energy (DOE) issued Hanford Analytical Services Quality Assurance Plan (HASQAP). In addition, this document meets the objectives of the Quality Assurance Program provided in the WHC-CM-4-2, Section 2.1. Quality assurance elements required in the Guidelines and Specifications for Preparing Quality Assurance Program Plans (QAMS-004) and Interim Guidelines and Specifications for Preparing Quality Assurance Project Plans (QAMS-005) from the US Environmental Protection Agency (EPA) are covered throughout this document. A qualitymore » assurance index is provided in the Appendix A. This document also provides and/or identifies the procedural information that governs laboratory operations. The personnel of the 222-S Laboratory and the Standards Laboratory including managers, analysts, QA/QC staff, auditors, and support staff shall use this document as guidance and instructions for their operational and quality assurance activities. Other organizations that conduct activities described in this document for the 222-S Laboratory shall follow this QA/QC document.« less

Remaining Sites Verification Package for the 100-F-26:12, 1.8-m (72-in.) Main Process Sewer Pipeline, Waste Site Reclassification Form 2007-034

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

J. M. Capron

2008-04-29

The 100-F-26:12 waste site was an approximately 308-m-long, 1.8-m-diameter east-west-trending reinforced concrete pipe that joined the North Process Sewer Pipelines (100-F-26:1) and the South Process Pipelines (100-F-26:4) with the 1.8-m reactor cooling water effluent pipeline (100-F-19). In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

Radiation Characterization Summary: ACRR Cadmium-Polyethylene (CdPoly) Bucket Located in the Central Cavity on the 32-Inch Pedestal at the Core Centerline

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

Parma, Edward J.; Naranjo, Gerald E.; Kaiser, Krista Irene

This document presents the facility-recommended characterization of the neutron, prompt gamma-ray, and delayed gamma-ray radiation fields in the Annular Core Research Reactor (ACRR) for the cadmium-polyethylene (CdPoly) bucket in the central cavity on the 32-inch pedestal at the core centerline. The designation for this environment is ACRR-CdPoly-CC-32-cl. The neutron, prompt gamma-ray, and delayed gamma-ray energy spectra, uncertainties, and covariance matrices are presented as well as radial and axial neutron and gamma-ray fluence profiles within the experiment area of the bucket. Recommended constants are given to facilitate the conversion of various dosimetry readings into radiation metrics desired by experimenters. Representative pulsemore » operations are presented with conversion examples. Acknowledgements The authors wish to thank the Annular Core Research Reactor staff and the Radiation Metrology Laboratory staff for their support of this work. Also thanks to Drew Tonigan for helping field the activation experiments in ACRR, David Samuel for helping to finalize the drawings and get the parts fabricated, and Elliot Pelfrey for preparing the active dosimetry plots.« less

Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177

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

Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre

2012-07-01

The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (∼49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leavingmore » the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)« less

5 CFR 772.102 - Interim personnel actions.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 5 Administrative Personnel 2 2011-01-01 2011-01-01 false Interim personnel actions. 772.102 Section 772.102 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT (CONTINUED) CIVIL SERVICE REGULATIONS (CONTINUED) INTERIM RELIEF General § 772.102 Interim personnel actions. When an employee or...

5 CFR 772.102 - Interim personnel actions.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 5 Administrative Personnel 2 2010-01-01 2010-01-01 false Interim personnel actions. 772.102 Section 772.102 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT (CONTINUED) CIVIL SERVICE REGULATIONS (CONTINUED) INTERIM RELIEF General § 772.102 Interim personnel actions. When an employee or...

Bias estimates used in lieu of validation of fission products and minor actinides in MCNP K eff calculations for PWR burnup credit casks

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

Mueller, Don E.; Marshall, William J.; Wagner, John C.

The U.S. Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation recently issued Interim Staff Guidance (ISG) 8, Revision 3. This ISG provides guidance for burnup credit (BUC) analyses supporting transport and storage of PWR pressurized water reactor (PWR) fuel in casks. Revision 3 includes guidance for addressing validation of criticality (k eff) calculations crediting the presence of a limited set of fission products and minor actinides (FP&MA). Based on previous work documented in NUREG/CR-7109, recommendation 4 of ISG-8, Rev. 3, includes a recommendation to use 1.5 or 3% of the FP&MA worth to conservatively cover the biasmore » due to the specified FP&MAs. This bias is supplementary to the bias and bias uncertainty resulting from validation of k eff calculations for the major actinides in SNF and does not address extension to actinides and fission products beyond those identified herein. The work described in this report involves comparison of FP&MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII based nuclear data and supports use of the 1.5% FP&MA worth bias when either SCALE or MCNP codes are used for criticality calculations, provided the other conditions of the recommendation 4 are met. The method used in this report may also be applied to demonstrate the applicability of the 1.5% FP&MA worth bias to other codes using ENDF/B V, VI or VII based nuclear data. The method involves use of the applicant s computational method to generate FP&MA worths for a reference SNF cask model using specified spent fuel compositions. The applicant s FP&MA worths are then compared to reference values provided in this report. The applicants FP&MA worths should not exceed the reference results by more than 1.5% of the reference FP&MA worths.« less

Review of APR+ Level 2 PSA. Revision 2

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

Lehner, John R.; Mubayi, Vinod; Pratt, W. Trevor

2012-02-17

Brookhaven National Laboratory (BNL) assisted the Korea Institute of Nuclear Safety (KINS) in reviewing the Level 2 Probabilistic Safety Assessment (PSA) of the APR+ Advanced Pressurized Water Reactor (PWR) prepared by the Korea Hydro & Nuclear Power Co., Ltd (KHNP) and KEPCO Engineering & Construction Co., Inc. (KEPCO-E&C). The work described in this report involves a review of the APR+ Level 2 PSA submittal [Ref. 1]. The PSA and, therefore, the review is limited to consideration of accidents initiated by internal events. As part of the review process, the review team also developed three sets of Requests for Additional Informationmore » (RAIs). These RAIs were provided to KHNP and KEPCO-E&C for their evaluation and response. This final detailed report documents the review findings for each technical element of the PSA and includes consideration of all of the RAIs made by the reviewers as well as the associated responses. This final report was preceded by an interim report [Ref. 2] that focused on identifying important issues regarding the PSA. In addition, a final meeting on the project was held at BNL on November 21-22, 2011, where BNL and KINS reviewers discussed their preliminary review findings with KHNP and KEPCO-E&C staffs. Additional information obtained during this final meeting was also used to inform the review findings of this final report. The review focused not only on the robustness of the APR+ design to withstand severe accidents, but also on the capability and acceptability of the Level 2 PSA in terms of level of detail and completeness. The Korean nuclear regulatory authorities will decide whether the PSA is acceptable and the BNL review team is providing its comments for KINS consideration. Section 2.0 provides the basis for the BNL review. Section 3.0 presents the review of each technical element of the PSA. Conclusions and a summary are presented in Section 4.0. Section 5.0 contains the references.« less

Fukushima Media Involvement: Lessons Learned and Challenges - 13261

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

Harvey, Geoffrey L.; Johnson, Wayne L.; Koller, Greg L.

Only days after the Fukushima nuclear reactor disaster on March 11, 2011, the DOE's Pacific Northwest National Laboratory, or PNNL, found itself in a maelstrom of media attention following its announcement of the detection of minute levels of radioactive material originating from the damaged reactors 4,500 miles away. Because PNNL develops state-of-the-art ultra-sensitive radionuclide detection and monitoring systems for national security applications, and has some of the equipment operating on its Richland campus, there was little surprise when one of these sophisticated systems led PNNL to be the first to detect measurable radionuclides in the United States. On Wednesday, Marchmore » 16, 2011, that system detected minuscule levels of short-lived radioactive xenon, a telltale element derived from either weapons testing or a major reactor disruption. Immediately after the detection was announced, a flurry of inquiries nearly overwhelmed staff as governments, scientific organizations, the general public, and reporters struggled to understand and estimate what impacts this disaster might have on health and environment. Over the course of about three weeks, PNNL's News and Media Relations staff and its scientists and engineers responded to more than 100 requests for information, and engaged in dozens of personal interviews with international, national, regional, and local media. While many of the interviews and resulting stories were accurate and well done, not all communication went flawlessly. In the midst of chaos and confusion, which are part of any significant crisis, hiccoughs are sure to occur. Addressed here is 'the rest of the story'. (authors)« less

Interim Expertise

ERIC Educational Resources Information Center

Anyaso, Hilary Hurd

2009-01-01

The Registry for College and University Presidents places former executives in interim presidential and other senior-level posts and is familiar with the challenges interim executives and institutions encounter in times of leadership transitions. However, the one big advantage interims bring to institutions, says Registry Vice President Kevin J.…

40 CFR 155.56 - Interim registration review decision.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Interim registration review decision... PROGRAMS REGISTRATION STANDARDS AND REGISTRATION REVIEW Registration Review Procedures § 155.56 Interim registration review decision. The Agency may issue, when it determines it to be appropriate, an interim...

17 CFR 210.8-03 - Interim financial statements.

Code of Federal Regulations, 2010 CFR

2010-04-01

... (§ 249.308(a) of this chapter) must be reviewed by an independent public accountant using professional... interim financial statements have been reviewed by an independent public accountant, a report of the accountant on the review must be filed with the interim financial statements. Interim financial statements...

24 CFR 35.1330 - Interim controls.

Code of Federal Regulations, 2012 CFR

2012-04-01

... 24 Housing and Urban Development 1 2012-04-01 2012-04-01 false Interim controls. 35.1330 Section... Lead-Paint Hazard Evaluation and Hazard Reduction Activities § 35.1330 Interim controls. Interim controls of lead-based paint hazards identified in a risk assessment shall be conducted in accordance with...

7 CFR 1738.21 - Interim financing.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section 1738.21... Interim financing. (a) Upon notification by RUS that an applicant's application is considered complete, the applicant may enter into an interim financing agreement with a lender other than RUS or use its...

An Approach for Evaluating the Technical Quality of Interim Assessments

ERIC Educational Resources Information Center

Li, Ying; Marion, Scott; Perie, Marianne; Gong, Brian

2010-01-01

Increasing numbers of schools and districts have expressed interest in interim assessment systems to prepare for summative assessments and to improve teaching and learning. However, with so many commercial interim assessments available, schools and districts are struggling to determine which interim assessment is most appropriate to their needs.…

47 CFR 51.611 - Interim wholesale rates.

Code of Federal Regulations, 2010 CFR

2010-10-01

... selecting a particular discount rate. The same discount percentage rate shall be used to establish interim... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim wholesale rates. 51.611 Section 51.611... Resale § 51.611 Interim wholesale rates. (a) If a state commission cannot, based on the information...

7 CFR 15a.71 - Interim procedures.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 7 Agriculture 1 2010-01-01 2010-01-01 false Interim procedures. 15a.71 Section 15a.71 Agriculture Office of the Secretary of Agriculture EDUCATION PROGRAMS OR ACTIVITIES RECEIVING OR BENEFITTING FROM FEDERAL FINANCIAL ASSISTANCE Procedures (Interim) § 15a.71 Interim procedures. For the purposes of...

7 CFR 1735.75 - Interim financing.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1735.75 Section 1735.75... Involving Loan Funds § 1735.75 Interim financing. (a) A borrower may submit a written request for RUS approval of interim financing if it is necessary to close an acquisition before the loan to finance the...

13 CFR 120.890 - Source of interim financing.

Code of Federal Regulations, 2014 CFR

2014-01-01

....890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may... experience or qualifications, SBA may require the interim loan to be managed by a third party such as a bank...

13 CFR 120.890 - Source of interim financing.

Code of Federal Regulations, 2010 CFR

2010-01-01

....890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may... experience or qualifications, SBA may require the interim loan to be managed by a third party such as a bank...

13 CFR 120.890 - Source of interim financing.

Code of Federal Regulations, 2013 CFR

2013-01-01

....890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may... experience or qualifications, SBA may require the interim loan to be managed by a third party such as a bank...

13 CFR 120.890 - Source of interim financing.

Code of Federal Regulations, 2012 CFR

2012-01-01

....890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may... experience or qualifications, SBA may require the interim loan to be managed by a third party such as a bank...

13 CFR 120.890 - Source of interim financing.

Code of Federal Regulations, 2011 CFR

2011-01-01

....890 Section 120.890 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION BUSINESS LOANS Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may... experience or qualifications, SBA may require the interim loan to be managed by a third party such as a bank...

75 FR 16203 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on EPR; Notice...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-31

... hold a meeting on April 20-21, 2010, at 11545 Rockville Pike, T2- B1, Rockville, Maryland. The entire... review Chapters 4, 5 and 17 of the Safety Evaluation Report with Open Items associated with the staff's... a.m.-5 p.m. The Subcommittee will review Chapter 12 of the Safety Evaluation Report with Open Items...

Neutronics, steady-state, and transient analyses for the Poland MARIA reactor for irradiation testing of LEU lead test fuel assemblies from CERCA : ANL independent verification results.

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

Garner, P. L.; Hanan, N. A.

The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Republic of Poland is considering conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel assemblies (FA). The FA design in MARIA is rather unique; a suitable LEU FA has never been designed or tested. IAE has contracted with CERCA (the fuel supply portion of AREVA in France) to supply 2 lead test assemblies (LTA). The LTAs will be irradiated in MARIA to burnup level of at least 40% for both LTAs and to 60% for one LTA. IAE may decidemore » to purchase additional LEU FAs for a full core conversion after the test irradiation. The Reactor Safety Committee within IAE and the National Atomic Energy Agency in Poland (PAA) must approve the LTA irradiation process. The approval will be based, in part, on IAE submitting revisions to portions of the Safety Analysis Report (SAR) which are affected by the insertion of the LTAs. (A similar process will be required for the full core conversion to LEU fuel.) The analysis required was established during working meetings between Argonne National Laboratory (ANL) and IAE staff during August 2006, subsequent email correspondence, and subsequent staff visits. The analysis needs to consider the current high-enriched uranium (HEU) core and 4 core configurations containing 1 and 2 LEU LTAs in various core positions. Calculations have been performed at ANL in support of the LTA irradiation. These calculations are summarized in this report and include criticality, burn-up, neutronics parameters, steady-state thermal hydraulics, and postulated transients. These calculations have been performed at the request of the IAE staff, who are performing similar calculations to be used in their SAR amendment submittal to the PAA. The ANL analysis has been performed independently from that being performed by IAE and should only be used as one step in the verification process.« less

12 CFR 552.2-2 - Procedures for organization of interim Federal stock association.

Code of Federal Regulations, 2010 CFR

2010-01-01

... Procedures for organization of interim Federal stock association. (a) Applications for permission to organize... chapter or § 552.2-1(b)(3) of this part. (b) Approval of an application for permission to organize an... the interim was chartered to facilitate. Applications for permission to organize an interim Federal...

Operational Philosophy for the Advanced Test Reactor National Scientific User Facility

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

J. Benson; J. Cole; J. Jackson

2013-02-01

In 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF). At its core, the ATR NSUF Program combines access to a portion of the available ATR radiation capability, the associated required examination and analysis facilities at the Idaho National Laboratory (INL), and INL staff expertise with novel ideas provided by external contributors (universities, laboratories, and industry). These collaborations define the cutting edge of nuclear technology research in high-temperature and radiation environments, contribute to improved industry performance of current and future light-water reactors (LWRs), and stimulate cooperative research between user groupsmore » conducting basic and applied research. To make possible the broadest access to key national capability, the ATR NSUF formed a partnership program that also makes available access to critical facilities outside of the INL. Finally, the ATR NSUF has established a sample library that allows access to pre-irradiated samples as needed by national research teams.« less

Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies

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

Mckerley, Bill; Bustamante, Jacqueline M; Costa, David A

2010-01-01

We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is inmore » support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.« less

History of 232-F, tritium extraction processing

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

Blackburn, G.W.

1994-08-01

In 1950 the Atomic Energy Commission authorized the Savannah River Project principally for the production of tritium and plutonium-239 for use in thermonuclear weapons. 232-F was built as an interim facility in 1953--1954, at a cost of $3.9M. Tritium extraction operations began in October, 1955, after the reactor and separations startups. In July, 1957 a larger tritium facility began operation in 232-H. In 1958 the capacity of 232-H was doubled. Also, in 1957 a new task was assigned to Savannah River, the loading of tritium into reservoirs that would be actual components of thermonuclear weapons. This report describes the historymore » of 232-F, the process for tritium extraction, and the lessons learned over the years that were eventually incorporated into the new Replacement Tritium Facility.« less

Remaining Sites Verification Package for the 116-C-3, 105-C Chemical Waste Tanks, Waste Site Reclassification Form 2008-002

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

L. M. Dittmer

2008-01-31

The 116-C-3 waste site consisted of two underground storage tanks designed to receive mixed waste from the 105-C Reactor Metals Examination Facility chemical dejacketing process. Confirmatory evaluation and subsequent characterization of the site determined that the southern tank contained approximately 34,000 L (9,000 gal) of dejacketing wastes, and that the northern tank was unused. In accordance with this evaluation, the verification sampling and modeling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrate that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils.more » The results also show that residual contaminant concentrations are protective of groundwater and the Columbia River.« less

Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators - Interim Report for FY 2013

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

Binh T. Pham; Nancy J. Lybeck; Vivek Agarwal

The Light Water Reactor Sustainability program at Idaho National Laboratory is actively conducting research to develop and demonstrate online monitoring capabilities for active components in existing nuclear power plants. Idaho National Laboratory and the Electric Power Research Institute are working jointly to implement a pilot project to apply these capabilities to emergency diesel generators and generator step-up transformers. The Electric Power Research Institute Fleet-Wide Prognostic and Health Management Software Suite will be used to implement monitoring in conjunction with utility partners: Braidwood Generating Station (owned by Exelon Corporation) for emergency diesel generators, and Shearon Harris Nuclear Generating Station (owned bymore » Duke Energy Progress) for generator step-up transformers. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for emergency diesel generators. Emergency diesel generators provide backup power to the nuclear power plant, allowing operation of essential equipment such as pumps in the emergency core coolant system during catastrophic events, including loss of offsite power. Technical experts from Braidwood are assisting Idaho National Laboratory and Electric Power Research Institute in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the Fleet-Wide Prognostic and Health Management Software Suite and tested using data from Braidwood. Parallel research on generator step-up transformers was summarized in an interim report during the fourth quarter of fiscal year 2012.« less

Radiological characterization of skyshine from a retired, low-level, radioactive liquid effluent disposal facility at Hanford

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

Brown, R.C.; Perkins, C.J.

1991-02-01

The 1301-N Liquid Waste Disposal Facility, located on the Hanford Site received N Reactor low-level radioactive liquid process effluent from 1962 to 1985. Radiation emanating from the top of the trench sections was not significant because of the sediments were normally under several meters of water, which provided the necessary shielding. Following retirement of the facility, the liquid in the trench sections percolated into the ground leaving the residual radioactively contaminated sediments unshielded along the bottom and sides of the trench sections. The radioactive constituents of the contaminated sediments include the gamma-emitting isotopes Co-60 and Cs-137. Because of the lackmore » of water covering, some of the gamma photons that were emitted upward were scattered downward due to Compton interaction with atmospheric constituents. This phenomenon is known as skyshine.'' A radiological characterization was required to provide guidance for determining the effectiveness of interim stabilization alternatives that would not adversely affect future Resource Conservation and Recovery Act site closure activities, (e.g., filling in trench sections with spoils from excavation activities). A noninvasive radiological characterization of this disposal facility and the affected area of the Columbia River shoreline was conducted. This characterization confirmed that skyshine is the cause of the elevated shoreline exposure rates and provided a model that could be used to rate the effectiveness of alternative interim stabilization measures. 4 refs., 5 figs.« less

The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

NASA Astrophysics Data System (ADS)

Butler, Thomas S.

Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

76 FR 14559 - Federal Acquisition Regulation; Justification and Approval of Sole-Source 8(a) Contracts

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-16

... Space Administration (NASA). ACTION: Interim rule. SUMMARY: DoD, GSA, and NASA are issuing an interim..., and NASA are issuing an interim rule amending the FAR, to implement section 811 of the National... meetings, DoD, GSA, and NASA weighed the costs and benefits of publishing this rule as proposed or interim...

Interim Administrators in Higher Education: A National Study

ERIC Educational Resources Information Center

Huff, Marie Thielke; Neubrander, Judy

2015-01-01

The focus of this paper is on the roles and experiences of interim administrators in higher education. A survey was given to current and recent interim administrators in four-year public universities and colleges across the United States. The goals were to identify the advantages and disadvantages of using and serving as interims, and to solicit…

76 FR 76815 - Business Opportunity Rule

Federal Register 2010, 2011, 2012, 2013, 2014

2011-12-08

...The Commission is adopting final amendments to its Trade Regulation Rule entitled ``Disclosure Requirements and Prohibitions Concerning Business Opportunities'' (``Business Opportunity Rule'' or ``Rule''). Among other things, the Business Opportunity Rule has been amended to broaden its scope to cover business opportunity sellers not covered by the interim Business Opportunity Rule, such as sellers of work-at-home opportunities, and to streamline and simplify the disclosures that sellers must provide to prospective purchasers. The final Rule is based upon the comments received in response to an Advance Notice of Proposed Rulemaking (``ANPR''), an Initial Notice of Proposed Rulemaking (``INPR''), a Revised Notice of Proposed Rulemaking (``RNPR''), a public workshop, a Staff Report, and other information discussed herein. This document also contains the text of the final Rule and the Rule's Statement of Basis and Purpose (``SBP''), including a Regulatory Analysis.

Overview of Chromium Remediation Technology Evaluations At The Hanford Site, Richland Washington

NASA Astrophysics Data System (ADS)

Morse, J. G.; Hanson, J. P.

2009-12-01

This paper will present an overview of the different technologies and the results to date for optimizing and improving the remediation of Cr+6 in the soil and groundwater at the Hanford Site. The Hanford Site, par of the U.S. Department of Energy's (DOE)nuclear weapons complex, encompasses approximately 586 square miles in southeast Washington State. The Columbia River flows through the site (Hanford Reach.) Reactors were located along the Hanford Reach as part of the production process. Sodium dichromate was used as a corrosion inhibitor in the cooling water for the reactors. As a result chromium (Cr+6) is present in the soil and groundwater. Since the mid 90's interim groundwater pump and treat systems have been in place to try and contain or mitigate the migration of contaminated groundwater into the Columbia River. The primary concern being the protection of aquatic spawning habitat for salmon and other species. In order to improve the effectiveness of the remedial actions a number of different technologies have been evaluated and/or deployed. These include, permeable reactive barriers, in-situ bio-stimulation, in-situ chemical reduction, zero-valent iron injection and evaluation of improved above ground treatment technologies. An overview of the technologies and results to date are presented.

Operating experience feedback report: New plants, Commercial power reactors

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

Dennig, R.L.; O'Reilly, P.D.

1987-07-01

This report documents a detailed review of the cause of unplanned events during the early months of licensed operation for plants licensed between March 1983 and April 1986. The major lessons and corrective actions that appear to have the greatest potential for improving the effectiveness of plant startups are provided for consideration through the operating experience feedback programs and activities of the industry and the NRC staff.

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

Not Available

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE`s Systemmore » 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report.« less

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

Not Available

This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE`s Systemmore » 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E.« less

Assessment of surgical discharge summaries and evaluation of a new quality improvement model.

PubMed

Stein, Ran; Neufeld, David; Shwartz, Ivan; Erez, Ilan; Haas, Ilana; Magen, Ada; Glassberg, Elon; Shmulevsky, Pavel; Paran, Haim

2014-11-01

Discharge summaries after hospitalization provide the most reliable description and implications of the hospitalization. A concise discharge summary is crucial for maintaining continuity of care through the transition from inpatient to ambulatory care. Discharge summaries often lack information and are imprecise. Errors and insufficient recommendations regarding changes in the medical regimen may harm the patient's health and may result in readmission. To evaluate a quality improvement model and training program for writing postoperative discharge summaries for three surgical procedures. Medical records and surgical discharge summaries were reviewed and scored. Essential points for communication between surgeons and family physicians were included in automated forms. Staff was briefed twice regarding required summary contents with an interim evaluation. Changes in quality were evaluated. Summaries from 61 cholecystectomies, 42 hernioplasties and 45 colectomies were reviewed. The average quality score of all discharge summaries increased from 72.1 to 78.3 after the first intervention (P < 0.0005) to 81.0 following the second intervention. As the discharge summary's quality improved, its length decreased significantly. Discharge summaries lack important information and are too long. Developing a model for discharge summaries and instructing surgical staff regarding their contents resulted in measurable improvement. Frequent interventions and supervision are needed to maintain the quality of the surgical discharge summary.

42 CFR 418.307 - Periodic interim payments.

Code of Federal Regulations, 2010 CFR

2010-10-01

... (CONTINUED) MEDICARE PROGRAM HOSPICE CARE Payment for Hospice Care § 418.307 Periodic interim payments... payments. The biweekly interim payment amount is based on the total estimated Medicare payments for the...

Replacement of a hopeless maxillary central incisor: a technique for the fabrication of an immediate implant-supported interim restoration.

PubMed

Graiff, Lorenzo; Vigolo, Paolo

2012-04-01

Placement of a dental implant and an interim restoration in the esthetic zone immediately following tooth extraction is now a common procedure. However, in such clinical situations, the fabrication of an appropriate interim restoration may be challenging. The aim of this article is to present a technique for modifying the extracted tooth so it can be used as an implant-supported interim restoration.

International validation study for interim PET in ABVD-treated, advanced-stage hodgkin lymphoma: interpretation criteria and concordance rate among reviewers.

PubMed

Biggi, Alberto; Gallamini, Andrea; Chauvie, Stephane; Hutchings, Martin; Kostakoglu, Lale; Gregianin, Michele; Meignan, Michel; Malkowski, Bogdan; Hofman, Michael S; Barrington, Sally F

2013-05-01

At present, there are no standard criteria that have been validated for interim PET reporting in lymphoma. In 2009, an international workshop attended by hematologists and nuclear medicine experts in Deauville, France, proposed to develop simple and reproducible rules for interim PET reporting in lymphoma. Accordingly, an international validation study was undertaken with the primary aim of validating the prognostic role of interim PET using the Deauville 5-point score to evaluate images and with the secondary aim of measuring concordance rates among reviewers using the same 5-point score. This paper focuses on the criteria for interpretation of interim PET and on concordance rates. A cohort of advanced-stage Hodgkin lymphoma patients treated with doxorubicin, bleomycin, vinblastine, and dacarbazine (ABVD) were enrolled retrospectively from centers worldwide. Baseline and interim scans were reviewed by an international panel of 6 nuclear medicine experts using the 5-point score. Complete scan datasets of acceptable diagnostic quality were available for 260 of 440 (59%) enrolled patients. Independent agreement among reviewers was reached on 252 of 260 patients (97%), for whom at least 4 reviewers agreed the findings were negative (score of 1-3) or positive (score of 4-5). After discussion, consensus was reached in all cases. There were 45 of 260 patients (17%) with positive interim PET findings and 215 of 260 patients (83%) with negative interim PET findings. Thirty-three interim PET-positive scans were true-positive, and 12 were false-positive. Two hundred three interim PET-negative scans were true-negative, and 12 were false-negative. Sensitivity, specificity, and accuracy were 0.73, 0.94, and 0.91, respectively. Negative predictive value and positive predictive value were 0.94 and 0.73, respectively. The 3-y failure-free survival was 83%, 28%, and 95% for the entire population and for interim PET-positive and -negative patients, respectively (P < 0.0001). The agreement between pairs of reviewers was good or very good, ranging from 0.69 to 0.84 as measured with the Cohen kappa. Overall agreement was good at 0.76 as measured with the Krippendorf α. The 5-point score proposed at Deauville for reviewing interim PET scans in advanced Hodgkin lymphoma is accurate and reproducible enough to be accepted as a standard reporting criterion in clinical practice and for clinical trials.

Publishing interim results of randomised clinical trials in peer-reviewed journals.

PubMed

Counsell, Nicholas; Biri, Despina; Fraczek, Joanna; Hackshaw, Allan

2017-02-01

Interim analyses of randomised controlled trials are sometimes published before the final results are available. In several cases, the treatment effects were noticeably different after patient recruitment and follow-up completed. We therefore conducted a literature review of peer-reviewed journals to compare the reported treatment effects between interim and final publications and to examine the magnitude of the difference. We performed an electronic search of MEDLINE from 1990 to 2014 (keywords: 'clinical trial' OR 'clinical study' AND 'random*' AND 'interim' OR 'preliminary'), and we manually identified the corresponding final publication. Where the electronic search produced a final report in which the abstract cited interim results, we found the interim publication. We also manually searched every randomised controlled trial in eight journals, covering a range of impact factors and general medical and specialist publications (1996-2014). All paired articles were checked to ensure that the same comparison between interventions was available in both. In all, 63 studies are included in our review, and the same quantitative comparison was available in 58 of these. The final treatment effects were smaller than the interim ones in 39 (67%) trials and the same size or larger in 19 (33%). There was a marked reduction, defined as a ≥20% decrease in the size of the treatment effect from interim to final analysis, in 11 (19%) trials compared to a marked increase in 3 (5%), p = 0.057. The magnitude of percentage change was larger in trials where commercial support was reported, and increased as the proportion of final events at the interim report decreased in trials where commercial support was reported (interaction p = 0.023). There was no evidence of a difference between trials that stopped recruitment at the interim analysis where this was reported as being pre-specified versus those that were not pre-specified (interaction p = 0.87). Published interim trial results were more likely to be associated with larger treatment effects than those based on the final report. Publishing interim results should be discouraged, in order to have reliable estimates of treatment effects for clinical decision-making, regulatory authority reviews and health economic analyses. Our work should be expanded to include conference publications and manual searches of additional journal publications.

Different predictive values of interim 18F-FDG PET/CT in germinal center like and non-germinal center like diffuse large B-cell lymphoma.

PubMed

Kim, Jihyun; Lee, Jeong-Ok; Paik, Jin Ho; Lee, Won Woo; Kim, Sang Eun; Song, Yoo Sung

2017-01-01

Diffuse large B-cell lymphoma (DLBCL) is a pathologically heterogeneous disease with different prognoses according to its molecular profiles. Despite the broad usage of 18 F-fluoro-2-dexoxy-D-glucose (FDG) positron emission tomography/computed tomography (PET/CT), previous studies that have investigated the value of interim 18 F-FDG PET/CT in DLBCL have given the controversial results. The purpose of this study was to evaluate the prognostic value of interim 18 F-FDG PET/CT in DLBCL according to germinal center B cell-like (GCB) and non-GCB molecular profiling. We enrolled 118 newly diagnosed DLBCL patients treated with rituximab, cyclophosphamide, doxorubicin, vincristine, and prednisolone (R-CHOP). Interim 18 F-FDG PET/CT scans performed after 2 or 3 cycles of R-CHOP treatment were evaluated based on the Lugano response criteria. Patients were grouped as GCB or non-GCB molecular subtypes according to immunohistochemistry results of CD10, BCL6, and MUM1, based on Hans' algorithm. In total 118 DLBCL patients, 35 % were classified as GCB, and 65 % were classified as non-GCB. Interim PET/CT was negative in 70 %, and positive in 30 %. During the median follow-up period of 23 months, the positive interim 18 F-FDG PET/CT group showed significantly inferior progression free survival (PFS) compared to the negative interim 18 F-FDG PET/CT group (P = 0.0004) in entire patients. A subgroup analysis according to molecular profiling demonstrated significant difference of PFS between the positive and negative interim 18 F-FDG PET groups in GCB subtype of DLBCL (P = 0.0001), but there was no significant difference of PFS between the positive and negative interim 18 F-FDG PET groups in non-GCB subtype of DLBCL. Interim 18 F-FDG PET/CT scanning had a significant predictive value for disease progression in patients with the GCB subtype of DLBCL treated with R-CHOP, but not in those with the non-GCB subtype. Therefore, molecular profiles of DLBCL should be considered for interim 18 F-FDG PET/CT practice.

Implementation of ALARA at the design stage of Nuclear Power Plants

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

Brissaud, A.; Ridoux, P.

1995-03-01

In the 1970s, Electricite de France (EdF) had limited knowledge and experience of pressurized water reactors (PWRs). Electricity generation by nuclear units was oriented towards gas-graphite reactors, even though EdF had a share in the PWR unit of CHOOZ A-1 (250 MWe, later upgraded to 320 MWe). Some facts about the origin of doses in that king of reactor were known to the research and development (R&D) support staff of EdF, which mainly comprises the French Atomic Commission (CEA), but only a few of EdF`s engineers were aware of these facts. One has to bear in mind that CHOOZ A-1more » only went critical in April 1967 and was officially connected to the grid in May 1970 after some important problems had been solved. Meanwhile, the nuclear program was launched at full speed, beginning with the order for FESSENHEIM 1 in 1970, FESSENHEIM 2 and BUGEY 2 and 3 in 1971. TIHANGE 1, in which EdF had a share, went on-line in September 1975. Also, supposing that EdF had had such knowledge and experience, it is quite evident that it would have been very difficult to modify the lay-out inside the reactor building.« less

Guidance: Interim Municipal Settlement Policy

EPA Pesticide Factsheets

Interim guidance and fact sheets regarding settlements involving municipalities or municipal waste under Section 122 CERCLA as amended by SARA. Interim policy sets forth the criteria by which EPA generally determines whether to exercise enforcement discretion to pursue MSW generators and transporters as PRPs.

Neutronics Analyses of the Minimum Original HEU TREAT Core

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

Kontogeorgakos, D.; Connaway, H.; Yesilyurt, G.

2014-04-01

This work was performed to support the feasibility study on the potential conversion of the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory from the use of high-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by the GTRI Reactor Conversion staff at the Argonne National Laboratory (ANL). The objective of this study was to validate the MCNP model of the TREAT reactor with the well-documented measurements which were taken during the start-up and early operation of TREAT. Furthermore, the effect of carbon graphitization was also addressed. The graphitization level was assumedmore » to be 100% (ANL/GTRI/TM-13/4). For this purpose, a set of experiments was chosen to validate the TREAT MCNP model, involving the approach to criticality procedure, in-core neutron flux measurements with foils, and isothermal temperature coefficient and temperature distribution measurements. The results of this study extended the knowledge base for the TREAT MCNP calculations and established the credibility of the MCNP model to be used in the core conversion feasibility analysis.« less

Accounting for interim safety monitoring of an adverse event upon termination of a clinical trial.

PubMed

Dallas, Michael J

2008-01-01

Upon termination of a clinical trial that uses interim evaluations to determine whether the trial can be stopped, a proper statistical analysis must account for the interim evaluations. For example, in a group-sequential design where the efficacy of a treatment regimen is evaluated at interim stages, and the opportunity to stop the trial based on positive efficacy findings exists, the terminal p-value, point estimate, and confidence limits of the outcome of interest must be adjusted to eliminate bias. While it is standard practice to adjust terminal statistical analyses due to opportunities to stop for "positive" findings, adjusting due to opportunities to stop for "negative" findings is also important. Stopping rules for negative findings are particularly useful when monitoring a specific rare serious adverse event in trials designed to show safety with respect to the event. In these settings, establishing conservative stopping rules are appropriate, and therefore accounting for the interim monitoring can have a substantial effect on the final results. Here I present a method to account for interim safety monitoring and illustrate its usefulness. The method is demonstrated to have advantages over methodology that does not account for interim monitoring.

28 CFR 94.41 - Interim emergency payment.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 28 Judicial Administration 2 2012-07-01 2012-07-01 false Interim emergency payment. 94.41 Section 94.41 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIME VICTIM SERVICES International Terrorism Victim Expense Reimbursement Program Payment of Claims § 94.41 Interim emergency payment...

28 CFR 94.41 - Interim emergency payment.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 28 Judicial Administration 2 2011-07-01 2011-07-01 false Interim emergency payment. 94.41 Section 94.41 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIME VICTIM SERVICES International Terrorism Victim Expense Reimbursement Program Payment of Claims § 94.41 Interim emergency payment...

28 CFR 94.41 - Interim emergency payment.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Interim emergency payment. 94.41 Section 94.41 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIME VICTIM SERVICES International Terrorism Victim Expense Reimbursement Program Payment of Claims § 94.41 Interim emergency payment...

28 CFR 94.41 - Interim emergency payment.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 28 Judicial Administration 2 2014-07-01 2014-07-01 false Interim emergency payment. 94.41 Section 94.41 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIME VICTIM SERVICES International Terrorism Victim Expense Reimbursement Program Payment of Claims § 94.41 Interim emergency payment...

28 CFR 94.41 - Interim emergency payment.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 28 Judicial Administration 2 2013-07-01 2013-07-01 false Interim emergency payment. 94.41 Section 94.41 Judicial Administration DEPARTMENT OF JUSTICE (CONTINUED) CRIME VICTIM SERVICES International Terrorism Victim Expense Reimbursement Program Payment of Claims § 94.41 Interim emergency payment...

76 FR 4369 - Special Law Enforcement Commissions

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-25

... DEPARTMENT OF THE INTERIOR Bureau of Indian Affairs Special Law Enforcement Commissions AGENCY... of the Interim Special Law Enforcement Commission Policy, Rules and Procedures, the Interim Special Law Enforcement Commission Protocols and the Interim Domestic Violence Waiver that will be used by the...

47 CFR 51.715 - Interim transport and termination pricing.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51... SERVICES (CONTINUED) INTERCONNECTION Reciprocal Compensation for Transport and Termination of Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

47 CFR 51.715 - Interim transport and termination pricing.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 47 Telecommunication 3 2011-10-01 2011-10-01 false Interim transport and termination pricing. 51... SERVICES (CONTINUED) INTERCONNECTION Reciprocal Compensation for Transport and Termination of Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

33 CFR 385.9 - Implementation principles.

Code of Federal Regulations, 2013 CFR

2013-07-01

... of the Plan at specific time intervals during implementation. Interim targets to evaluate progress on... accordance with § 385.39. Interim goals and interim targets shall be consistent with each other. (c... ensure that new information resulting from changed or unforeseen circumstances, new scientific and...

33 CFR 385.9 - Implementation principles.

Code of Federal Regulations, 2014 CFR

2014-07-01

... of the Plan at specific time intervals during implementation. Interim targets to evaluate progress on... accordance with § 385.39. Interim goals and interim targets shall be consistent with each other. (c... ensure that new information resulting from changed or unforeseen circumstances, new scientific and...

33 CFR 385.9 - Implementation principles.

Code of Federal Regulations, 2011 CFR

2011-07-01

... of the Plan at specific time intervals during implementation. Interim targets to evaluate progress on... accordance with § 385.39. Interim goals and interim targets shall be consistent with each other. (c... ensure that new information resulting from changed or unforeseen circumstances, new scientific and...

33 CFR 385.9 - Implementation principles.

Code of Federal Regulations, 2012 CFR

2012-07-01

... of the Plan at specific time intervals during implementation. Interim targets to evaluate progress on... accordance with § 385.39. Interim goals and interim targets shall be consistent with each other. (c... ensure that new information resulting from changed or unforeseen circumstances, new scientific and...

A systematic review of the reporting of Data Monitoring Committees' roles, interim analysis and early termination in pediatric clinical trials

PubMed Central

2009-01-01

Background Decisions about interim analysis and early stopping of clinical trials, as based on recommendations of Data Monitoring Committees (DMCs), have far reaching consequences for the scientific validity and clinical impact of a trial. Our aim was to evaluate the frequency and quality of the reporting on DMC composition and roles, interim analysis and early termination in pediatric trials. Methods We conducted a systematic review of randomized controlled clinical trials published from 2005 to 2007 in a sample of four general and four pediatric journals. We used full-text databases to identify trials which reported on DMCs, interim analysis or early termination, and included children or adolescents. Information was extracted on general trial characteristics, risk of bias, and a set of parameters regarding DMC composition and roles, interim analysis and early termination. Results 110 of the 648 pediatric trials in this sample (17%) reported on DMC or interim analysis or early stopping, and were included; 68 from general and 42 from pediatric journals. The presence of DMCs was reported in 89 of the 110 included trials (81%); 62 papers, including 46 of the 89 that reported on DMCs (52%), also presented information about interim analysis. No paper adequately reported all DMC parameters, and nine (15%) reported all interim analysis details. Of 32 trials which terminated early, 22 (69%) did not report predefined stopping guidelines and 15 (47%) did not provide information on statistical monitoring methods. Conclusions Reporting on DMC composition and roles, on interim analysis results and on early termination of pediatric trials is incomplete and heterogeneous. We propose a minimal set of reporting parameters that will allow the reader to assess the validity of trial results. PMID:20003383

78 FR 55339 - Regulatory Capital Rules: Regulatory Capital, Implementation of Basel III, Capital Adequacy...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-09-10

...The Federal Deposit Insurance Corporation (FDIC) is adopting an interim final rule that revises its risk-based and leverage capital requirements for FDIC-supervised institutions. This interim final rule is substantially identical to a joint final rule issued by the Office of the Comptroller of the Currency (OCC) and the Board of Governors of the Federal Reserve System (Federal Reserve) (together, with the FDIC, the agencies). The interim final rule consolidates three separate notices of proposed rulemaking that the agencies jointly published in the Federal Register on August 30, 2012, with selected changes. The interim final rule implements a revised definition of regulatory capital, a new common equity tier 1 minimum capital requirement, a higher minimum tier 1 capital requirement, and, for FDIC-supervised institutions subject to the advanced approaches risk-based capital rules, a supplementary leverage ratio that incorporates a broader set of exposures in the denominator. The interim final rule incorporates these new requirements into the FDIC's prompt corrective action (PCA) framework. In addition, the interim final rule establishes limits on FDIC-supervised institutions' capital distributions and certain discretionary bonus payments if the FDIC-supervised institution does not hold a specified amount of common equity tier 1 capital in addition to the amount necessary to meet its minimum risk-based capital requirements. The interim final rule amends the methodologies for determining risk-weighted assets for all FDIC-supervised institutions. The interim final rule also adopts changes to the FDIC's regulatory capital requirements that meet the requirements of section 171 and section 939A of the Dodd-Frank Wall Street Reform and Consumer Protection Act. The interim final rule also codifies the FDIC's regulatory capital rules, which have previously resided in various appendices to their respective regulations, into a harmonized integrated regulatory framework. In addition, the FDIC is amending the market risk capital rule (market risk rule) to apply to state savings associations. The FDIC is issuing these revisions to its capital regulations as an interim final rule. The FDIC invites comments on the interaction of this rule with other proposed leverage ratio requirements applicable to large, systemically important banking organizations. This interim final rule otherwise contains regulatory text that is identical to the common rule text adopted as a final rule by the Federal Reserve and the OCC. This interim final rule enables the FDIC to proceed on a unified, expedited basis with the other federal banking agencies pending consideration of other issues. Specifically, the FDIC intends to evaluate this interim final rule in the context of the proposed well- capitalized and buffer levels of the supplementary leverage ratio applicable to large, systemically important banking organizations, as described in a separate Notice of Proposed Rulemaking (NPR) published in the Federal Register August 20, 2013. The FDIC is seeking commenters' views on the interaction of this interim final rule with the proposed rule regarding the supplementary leverage ratio for large, systemically important banking organizations.

NGNP High Temperature Materials White Paper

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

Lew Lommers; George Honma

2012-08-01

This white paper is one in a series of white papers that address key generic issues of the combined construction and operating license (COL) pre-application program key generic issues for the Next Generation Nuclear Plant reactor using the prismatic block fuel technology. The purpose of the pre-application program interactions with the NRC staff is to reduce the time required for COL application review by identifying and addressing key regulatory issues and, if possible, obtaining agreements for their resolution

42 CFR 417.574 - Interim settlement.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Interim settlement. 417.574 Section 417.574 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED... PLANS Medicare Payment: Cost Basis § 417.574 Interim settlement. (a) Determination. Within 30 days...

14 CFR 136.41 - Interim operating authority.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 14 Aeronautics and Space 3 2012-01-01 2012-01-01 false Interim operating authority. 136.41 Section 136.41 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED... technology, as appropriate, and (9) Shall allow for modifications of the interim operating authority based on...

14 CFR 136.41 - Interim operating authority.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 14 Aeronautics and Space 3 2014-01-01 2014-01-01 false Interim operating authority. 136.41 Section 136.41 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED... technology, as appropriate, and (9) Shall allow for modifications of the interim operating authority based on...

47 CFR 73.404 - Interim hybrid IBOC DAB operation.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 47 Telecommunication 4 2012-10-01 2012-10-01 false Interim hybrid IBOC DAB operation. 73.404 Section 73.404 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The...

47 CFR 73.404 - Interim hybrid IBOC DAB operation.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 47 Telecommunication 4 2011-10-01 2011-10-01 false Interim hybrid IBOC DAB operation. 73.404 Section 73.404 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The...

47 CFR 73.404 - Interim hybrid IBOC DAB operation.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 47 Telecommunication 4 2013-10-01 2013-10-01 false Interim hybrid IBOC DAB operation. 73.404 Section 73.404 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The...

47 CFR 73.404 - Interim hybrid IBOC DAB operation.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 47 Telecommunication 4 2014-10-01 2014-10-01 false Interim hybrid IBOC DAB operation. 73.404 Section 73.404 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The...

10 CFR 590.403 - Emergency interim orders.

Code of Federal Regulations, 2010 CFR

2010-01-01

... DEPARTMENT OF ENERGY (CONTINUED) NATURAL GAS (ECONOMIC REGULATORY ADMINISTRATION) ADMINISTRATIVE PROCEDURES WITH RESPECT TO THE IMPORT AND EXPORT OF NATURAL GAS Opinions and Orders § 590.403 Emergency interim... and issue an emergency interim order authorizing the import or export of natural gas. After issuance...

EPA Interim Evaluation of 2016-2017 Milestone Progress in the Chesapeake Bay Watershed

EPA Pesticide Factsheets

This page provides the EPA interim evaluations of the 2016-2017 milestones for the Chesapeake Bay TMDL. These interim assessments provide a mid-point check on the progress made on the 2016-2017 milestones, recognizing the achievements made in 2016.

EPA Interim Evaluation of 2012-2013 Milestone Progress in the Chesapeake Bay Watershed

EPA Pesticide Factsheets

This page provides the EPA interim evaluations of the 2012-2013 milestones for the Chesapeake Bay TMDL. These interim assessments provide a mid-point check on the progress made on the 2012-2013 milestones, recognizing the achievements made in 2012.

49 CFR 37.193 - Interim service requirements.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Interim service requirements. 37.193 Section 37.193 Transportation Office of the Secretary of Transportation TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Over-the-Road Buses (OTRBs) § 37.193 Interim service requirements. (a) Until...

76 FR 57657 - Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-16

...] Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances AGENCY: Environmental Protection Agency (EPA). ACTION: Final rule. SUMMARY: This regulation establishes an extension of time-limited interim..., and Cosmetic Act (FFDCA). The time-limited tolerances expire on March 18, 2013. DATES: This regulation...

EPA Interim Evaluation of 2014-2015 Milestone Progress in the Chesapeake Bay Watershed

EPA Pesticide Factsheets

This page provides the EPA interim evaluations of the 2014-2015 milestones for the Chesapeake Bay TMDL. These interim assessments provide a mid-point check on the progress made on the 2014-2015 milestones, recognizing the achievements made in 2014.

45 CFR 1623.6 - Interim funding.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 45 Public Welfare 4 2013-10-01 2013-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this part...

45 CFR 1623.6 - Interim funding.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 45 Public Welfare 4 2012-10-01 2012-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this part...

45 CFR 1623.6 - Interim funding.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 45 Public Welfare 4 2011-10-01 2011-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this part...

45 CFR 1623.6 - Interim funding.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 45 Public Welfare 4 2014-10-01 2014-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this part...

45 CFR 1623.6 - Interim funding.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Interim funding. 1623.6 Section 1623.6 Public Welfare Regulations Relating to Public Welfare (Continued) LEGAL SERVICES CORPORATION SUSPENSION PROCEDURES § 1623.6 Interim funding. (a) Pending the completion of suspension proceedings under this part...

Measurement station for interim inspections of Lightbridge metallic fuel rods at the Halden Boiling Water Reactor

NASA Astrophysics Data System (ADS)

Hartmann, C.; Totemeier, A.; Holcombe, S.; Liverud, J.; Limi, M.; Hansen, J. E.; Navestad, E. AB(; )

2018-01-01

Lightbridge Corporation has developed a new Uranium-Zirconium based metallic fuel. The fuel rods aremanufactured via a co-extrusion process, and are characterized by their multi-lobed (cruciform-shaped) cross section. The fuel rods are also helically-twisted in the axial direction. Two experimental fuel assemblies, each containing four Lightbridge fuel rods, are scheduled to be irradiated in the Halden Boiling Water Reactor (HBWR) starting in 2018. In addition to on-line monitoring of fuel rod elongation and critical assembly conditions (e.g. power, flow rates, coolant temperatures, etc.) during the irradiation, several key parameters of the fuel will be measured out-of-core during interim inspections. An inspection measurement station for use in the irradiated fuel handling compartment at the HBWR has therefore been developed for this purpose. The multi-lobed cladding cross section combined with the spiral shape of the Lightbridge metallic fuel rods requires a high-precision guiding system to ensure good position repeatability combined with low-friction guiding. The measurement station is equipped with a combination of instruments and equipment supplied from third-party vendors and instruments and equipment developed at Institute for Energy Technology (IFE). Two sets of floating linear voltage differential transformer (LVDT) pairs are used to measure swelling and diameter changes between the lobes and the valleys over the length of the fuel rods. Eddy current probes are used to measure the thickness of oxide layers in the valleys and on the lobe tips and also to detect possible surface cracks/pores. The measurement station also accommodates gamma scans. Additionally, an eddy-current probe has been developed at IFE specifically to detect potential gaps or discontinuities in the bonding layer between the metallic fuel and the Zirconium alloy cladding. Potential gaps in the bonding layer will be hidden behind a 0.5-1.0 mm thick cladding wall. It has therefore been necessary to perform a careful design study of the probe geometry. For this, finite element analysis (FEA) has been performed in combination with practical validation tests on representative fuel dummies with machined flaws to find the probe geometry that best detects a hidden flaw. Tests performed thus far show that gaps down to 25 μm thickness can be detected with good repeatability and good discrimination from lift-off signals.

An interim prosthesis program for lower limb amputees: comparison of public and private models of service.

PubMed

Gordon, Robert; Magee, Christopher; Frazer, Anna; Evans, Craig; McCosker, Kathryn

2010-06-01

This study compared the outcomes of an interim mechanical prosthesis program for lower limb amputees operated under a public and private model of service. Over a two-year period, 60 transtibial amputees were fitted with an interim prosthesis as part of their early amputee care. Thirty-four patients received early amputee care under a public model of service, whereby a prosthetist was employed to provide the interim mechanical prosthesis service. The remaining 26 patients received early amputee care under a private model of service, where an external company was contracted to provide the interim mechanical prosthesis service. The results suggested comparable clinical outcomes between the two patient groups. However, the public model appeared to be less expensive with the average labour cost per patient being 29.0% lower compared with the private model. The results suggest that a public model of service may provide a more comprehensive and less expensive interim prosthesis program for lower limb amputees.

78 FR 14487 - Tetrachlorvinphos; Proposed Extension of Time-Limited Interim Pesticide Tolerances

Federal Register 2010, 2011, 2012, 2013, 2014

2013-03-06

...] Tetrachlorvinphos; Proposed Extension of Time-Limited Interim Pesticide Tolerances AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: This regulation proposes the extension of the time-limited... related to EPA's extension of the time-limited interim tolerances for the combined residues of the...

78 FR 15880 - Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances

Federal Register 2010, 2011, 2012, 2013, 2014

2013-03-13

... Tetrachlorvinphos; Extension of Time-Limited Interim Pesticide Tolerances AGENCY: Environmental Protection Agency (EPA). ACTION: Final rule. SUMMARY: This regulation extends the time-limited interim tolerances for the... . II. Background A detailed summary of the background related to EPA's extension of the time-limited...

24 CFR 115.207 - Consequences of interim certification and certification.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Consequences of interim certification and certification. 115.207 Section 115.207 Housing and Urban Development Regulations Relating to... ENFORCEMENT AGENCIES Certification of Substantially Equivalent Agencies § 115.207 Consequences of interim...

46 CFR 308.203 - Amount insured under interim binder.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 46 Shipping 8 2014-10-01 2014-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

46 CFR 308.203 - Amount insured under interim binder.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 46 Shipping 8 2013-10-01 2013-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

46 CFR 308.203 - Amount insured under interim binder.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 46 Shipping 8 2011-10-01 2011-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

46 CFR 308.203 - Amount insured under interim binder.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 46 Shipping 8 2010-10-01 2010-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

46 CFR 308.203 - Amount insured under interim binder.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 46 Shipping 8 2012-10-01 2012-10-01 false Amount insured under interim binder. 308.203 Section 308.203 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE War Risk Protection and Indemnity Insurance § 308.203 Amount insured under interim binder. The...

78 FR 20503 - Energy Conservation Program: Availability of the Interim Technical Support Document for High...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-04-05

... Conservation Program: Availability of the Interim Technical Support Document for High-Intensity Discharge Lamps... high-intensity discharge (HID) lamps energy conservation standards in the Federal Register. This... interim analysis for high- intensity discharge lamps energy conservation standards. The notice provided...

Treatment of G1 Baskets at the CEA Marcoule Site - 12027

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

Fourquet, Line; Boya, Didier

2012-07-01

In the dismantling program for the first-generation French reactors in accordance with the nonproliferation treaty, the CEA is in charge of cleanup and dismantling operations for the facilities at Marcoule, including the decladding units. The G1 decladding was built between 1955 and 1957 in order to de-clad spent fuel elements from the G1 plutonium-producing reactor and prepare them for dissolution. The facility was also used for interim storage of G1, G2 and G3 fuel dissolution baskets, which had been used during plant operation for transfer (from the decladding facility to the UP1 plant) and/or dissolution of spent fuel elements. Onemore » of the cleanup projects involves recovery of the baskets, which will be cut up, sorted, and conditioned in metal bins. The bins will be immobilized with cement grout, then transferred to the onsite solid waste conditioning facility (CDS) and to the repository operated by the French National Radioactive Waste Management Agency (ANDRA). The project is now in progress, after special safety permits were issued and measurement stations and dedicated tools were developed to handle all types of baskets (which differed according to their origin and use). The disposal of all the baskets is scheduled to last 2 years and will produce 55 metal waste bins. (authors)« less

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 30 Mineral Resources 3 2012-07-01 2012-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 30 Mineral Resources 3 2014-07-01 2014-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 30 Mineral Resources 3 2013-07-01 2013-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-22

... DEPARTMENT OF COMMERCE [Docket T-1-2010] Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA, Inc. (Cell Phones); Notice of.../ interim manufacturing (T/IM) authority, on behalf of LG Electronics Mobilecomm USA, Inc. (LGEMU), to...

76 FR 37781 - Foreign-Trade Zone 26; Atlanta, GA; Application for Temporary/Interim Manufacturing Authority...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-06-28

..., GA; Application for Temporary/ Interim Manufacturing Authority; Makita Corporation of America; (Hand- Held Power Tool and Gasoline/Electric-Powered Garden Product Manufacturing); Buford, GA An application... Georgia Foreign-Trade Zone, Inc., grantee of FTZ 26, requesting temporary/interim manufacturing (T/IM...

Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit

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

Bradley, J.

2002-06-18

The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process.

The Intentional Interim

ERIC Educational Resources Information Center

Nugent, Patricia A.

2011-01-01

The author spent years in central-office administration, most recently in an interim position. Some interim administrators simply see themselves as placeholders until the real deal is hired, giving the organization the opportunity to coast. There are others who see themselves as change agents and cannot wait to undo or redo what their predecessor…

Presidential Transition: The Experience of Two Community College Interim Presidents

ERIC Educational Resources Information Center

Thompson, Matthew D.

2010-01-01

The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

47 CFR 73.404 - Interim hybrid IBOC DAB operation.

Code of Federal Regulations, 2010 CFR

2010-10-01

... RADIO BROADCAST SERVICES Digital Audio Broadcasting § 73.404 Interim hybrid IBOC DAB operation. (a) The... test operation pursuant to § 73.1620, may commence interim hybrid IBOC DAB operation with digital... No. 99-325. FM stations are permitted to operate with hybrid digital effective radiated power equal...

17 CFR 210.10-01 - Interim financial statements.

Code of Federal Regulations, 2010 CFR

2010-04-01

... accountant on the review must be filed with the interim financial statements. (e) Filing of other interim... sheets shall include only major captions (i.e., numbered captions) prescribed by the applicable sections... the date of any material accounting change and the reasons for making it. In addition, for filings on...

75 FR 66553 - Truth in Lending

Federal Register 2010, 2011, 2012, 2013, 2014

2010-10-28

... AGENCY: Board of Governors of the Federal Reserve System. ACTION: Interim final rule; request for public comment. SUMMARY: The Board is publishing for public comment an interim final rule amending Regulation Z (Truth in Lending). The interim rule implements Section 129E of the Truth in Lending Act (TILA), which...

Faculty and Student Views of the Interim Term

ERIC Educational Resources Information Center

Centra, John A.; Sobol, Marion G.

1974-01-01

Evaluations of the interim term or 4-1-4 program at various colleges have been generally favorable. A detailed evaluation of the Rider College interim study program based on faculty and student reports indicated that the more nontraditionally oriented courses were rated higher than the more traditional offerings. (Editor/PG)

12 CFR 541.18 - Interim Federal savings association.

Code of Federal Regulations, 2010 CFR

2010-01-01

... an existing savings and loan holding company or to facilitate any other transaction the Office may... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Interim Federal savings association. 541.18... REGULATIONS AFFECTING FEDERAL SAVINGS ASSOCIATIONS § 541.18 Interim Federal savings association. The term...

15 CFR 904.322 - Interim action.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Interim action. 904.322 Section 904... Sanctions and Denials Permit Sanction for Violations § 904.322 Interim action. (a) To protect marine resources during the pendency of an action under this subpart, in cases of willfulness, or as otherwise...

15 CFR 904.322 - Interim action.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 15 Commerce and Foreign Trade 3 2011-01-01 2011-01-01 false Interim action. 904.322 Section 904... Sanctions and Denials Permit Sanction for Violations § 904.322 Interim action. (a) To protect marine resources during the pendency of an action under this subpart, in cases of willfulness, or as otherwise...

Into the Sunset: Reflections of an Interim Administrator.

ERIC Educational Resources Information Center

Marlowe, John

2000-01-01

One advantage to an interim administrative position is that the public cuts short-timers a little slack. Temporary administrators can learn on the job and become experts on specialized subjects. Personnel issues demand more time than interims possess. Such positions usually do not turn into long-term contracts. (MLH)

PCoD Lite - Using an Interim PCoD Protocol to Assess the Effects of Disturbance Associated with US Navy Exercises on Marine Mammal Populations

DTIC Science & Technology

2015-09-30

1 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. PCoD Lite - Using an Interim PCoD Protocol to Assess...US National Research Council (NRC 2005). Here, we provide an insight into how the Interim PCoD approach (Harwood et al. 2014, King et al. 2015...illustrate how the interim PCoD protocol can be used to inform the process of determining whether or not Navy activities are likely to have an impact on

Health justice partnerships: initial insights into the delivery of an integrated health and legal service for youth in regional Victoria.

PubMed

Ollerenshaw, Alison; Camilleri, Margaret

2017-01-01

This article presents interim findings from research examining the implementation of a health justice partnership (HJP) focusing on the legal and health needs of regional young people. HJPs provide an innovative service model offering an integrated health and legal service for the community. HJPs are a relatively new service model for Australia, yet the program is well suited to meet the needs of particular population cohorts, including young people and those in regional locations experiencing complex legal issues. Funded by the Victorian Legal Services Board and Commissioner, an HJP in partnership with three organisations was established in a large regional area in Victoria, Australia. Research is being conducted alongside the program to examine its impact on young people, and the implications on practice for staff in the partner organisations. Findings provide preliminary support for the HJP model with a number of young people - from predominantly disadvantaged backgrounds and with varying legal issues - having been referred to the program in the first 6 months. Referrals were received from both partner agencies and external agencies. Initial client and staff survey responses indicate that the legal problem of the young people was affecting how they feel. While these findings provide preliminary support for the HJP further research will offer longer term insights about HJPs within the Australian context, particularly rural and regional settings.

Calibration of ITER Instant Power Neutron Monitors: Recommended Scenario of Experiments at the Reactor

NASA Astrophysics Data System (ADS)

Borisov, A. A.; Deryabina, N. A.; Markovskij, D. V.

2017-12-01

Instant power is a key parameter of the ITER. Its monitoring with an accuracy of a few percent is an urgent and challenging aspect of neutron diagnostics. In a series of works published in Problems of Atomic Science and Technology, Series: Thermonuclear Fusion under a common title, the step-by-step neutronics analysis was given to substantiate a calibration technique for the DT and DD modes of the ITER. A Gauss quadrature scheme, optimal for processing "expensive" experiments, is used for numerical integration of 235U and 238U detector responses to the point sources of 14-MeV neutrons. This approach allows controlling the integration accuracy in relation to the number of coordinate mesh points and thus minimizing the number of irradiations at the given uncertainty of the full monitor response. In the previous works, responses of the divertor and blanket monitors to the isotropic point sources of DT and DD neutrons in the plasma profile and to the models of real sources were calculated within the ITER model using the MCNP code. The neutronics analyses have allowed formulating the basic principles of calibration that are optimal for having the maximum accuracy at the minimum duration of in situ experiments at the reactor. In this work, scenarios of the preliminary and basic experimental ITER runs are suggested on the basis of those principles. It is proposed to calibrate the monitors only with DT neutrons and use correction factors to the DT mode calibration for the DD mode. It is reasonable to perform full calibration only with 235U chambers and calibrate 238U chambers by responses of the 235U chambers during reactor operation (cross-calibration). The divertor monitor can be calibrated using both direct measurement of responses at the Gauss positions of a point source and simplified techniques based on the concepts of equivalent ring sources and inverse response distributions, which will considerably reduce the amount of measurements. It is shown that the monitor based on the average responses of the horizontal and vertical neutron chambers remains spatially stable as the source moves and can be used in addition to the staff monitor at neutron fluxes in the detectors four orders of magnitude lower than on the first wall, where staff detectors are located. Owing to low background, detectors of neutron chambers do not need calibration in the reactor because it is actually determination of the absolute detector efficiency for 14-MeV neutrons, which is a routine out-of-reactor procedure.

75 FR 7591 - Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-02-22

... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-SFUND-2009-0907; FRL-9114-6] RIN 2050-ZA05 Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites; Extension of... Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response...

Do Interim Assessments Reduce the Race and SES Achievement Gaps?

ERIC Educational Resources Information Center

Konstantopoulos, Spyros; Li, Wei; Miller, Shazia R.; van der Ploeg, Arie

2017-01-01

The authors examined differential effects of interim assessments on minority and low socioeconomic status students' achievement in Grades K-6. They conducted a large-scale cluster randomized experiment in 2009-2010 to evaluate the impact of Indiana's policy initiative introducing interim assessments statewide. The authors used 2-level models to…

31 CFR 50.7 - Special Rules for Interim Guidance Safe Harbors.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 31 Money and Finance: Treasury 1 2013-07-01 2013-07-01 false Special Rules for Interim Guidance Safe Harbors. 50.7 Section 50.7 Money and Finance: Treasury Office of the Secretary of the Treasury TERRORISM RISK INSURANCE PROGRAM General Provisions § 50.7 Special Rules for Interim Guidance Safe Harbors...

31 CFR 50.7 - Special Rules for Interim Guidance Safe Harbors.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 31 Money and Finance: Treasury 1 2014-07-01 2014-07-01 false Special Rules for Interim Guidance Safe Harbors. 50.7 Section 50.7 Money and Finance: Treasury Office of the Secretary of the Treasury TERRORISM RISK INSURANCE PROGRAM General Provisions § 50.7 Special Rules for Interim Guidance Safe Harbors...

31 CFR 50.7 - Special Rules for Interim Guidance Safe Harbors.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 31 Money and Finance: Treasury 1 2012-07-01 2012-07-01 false Special Rules for Interim Guidance Safe Harbors. 50.7 Section 50.7 Money and Finance: Treasury Office of the Secretary of the Treasury TERRORISM RISK INSURANCE PROGRAM General Provisions § 50.7 Special Rules for Interim Guidance Safe Harbors...

31 CFR 50.7 - Special Rules for Interim Guidance Safe Harbors.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 31 Money and Finance: Treasury 1 2011-07-01 2011-07-01 false Special Rules for Interim Guidance Safe Harbors. 50.7 Section 50.7 Money and Finance: Treasury Office of the Secretary of the Treasury TERRORISM RISK INSURANCE PROGRAM General Provisions § 50.7 Special Rules for Interim Guidance Safe Harbors...

75 FR 54526 - Defense Federal Acquisition Regulation Supplement; Payment of Costs Prior to Definitization...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-08

... in 48 CFR Part 217 Government procurement. Ynette R. Shelkin, Editor, Defense Acquisition Regulations...). ACTION: Final rule. SUMMARY: DoD is adopting as final, without change, an interim rule amending the... interim rule. Therefore, DoD is finalizing the interim rule without change. This rule was not subject to...

76 FR 43260 - Foreign-Trade Zone 72-Indianapolis, IN; Application for Temporary/Interim Manufacturing Authority...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-07-20

...--Indianapolis, IN; Application for Temporary/Interim Manufacturing Authority; Brevini Wind USA, Inc. (Wind... temporary/interim manufacturing (T/IM) authority within FTZ 72 at the Brevini Wind USA, Inc. (Brevini... requested authority to produce wind turbine gear boxes (HTSUS 8483.40, duty rate: 2.5%). Foreign components...

75 FR 60436 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2010-09-30

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it is releasing an interim...

75 FR 24667 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2010-05-05

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it released an interim change...

75 FR 10476 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-08

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it released an interim change...

76 FR 776 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) NO. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2011-01-06

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) NO. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it is releasing an interim...

75 FR 15420 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) NO. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-29

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) NO. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it will release an interim...

76 FR 59119 - Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-23

... DEPARTMENT OF DEFENSE Department of the Army Interim Change to the Military Freight Traffic Unified Rules Publication (MFTURP) No. 1 AGENCY: Department of the Army, DoD. SUMMARY: The Military Surface Deployment and Distribution Command (SDDC) is providing notice that it has released an interim...

Can Interim Assessments Be Used for Instructional Change? Policy Brief. RB-51

ERIC Educational Resources Information Center

Goertz, Margaret E.; Olah, Leslie Nabors; Riggan, Matthew

2009-01-01

The purpose of this exploratory study was to examine the use of interim assessments and the policy supports that promote their use to change instruction, focusing on elementary school mathematics. The authors use the term "interim assessments" to refer to assessments that: a) evaluate student knowledge and skills, typically within a…

40 CFR Appendix III to Part 265 - EPA Interim Primary Drinking Water Standards

Code of Federal Regulations, 2011 CFR

2011-07-01

...) SOLID WASTES (CONTINUED) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT... 40 Protection of Environment 26 2011-07-01 2011-07-01 false EPA Interim Primary Drinking Water... Water Standards Parameter Maximum level (mg/l) Arsenic 0.05 Barium 1.0 Cadmium 0.01 Chromium 0.05...

40 CFR Appendix III to Part 265 - EPA Interim Primary Drinking Water Standards

Code of Federal Regulations, 2010 CFR

2010-07-01

...) SOLID WASTES (CONTINUED) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT... 40 Protection of Environment 25 2010-07-01 2010-07-01 false EPA Interim Primary Drinking Water... Water Standards Parameter Maximum level (mg/l) Arsenic 0.05 Barium 1.0 Cadmium 0.01 Chromium 0.05...

33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

Code of Federal Regulations, 2010 CFR

2010-07-01

... section, when— (1) The company's valid Document of Compliance certificate or Interim Document of Compliance certificate applies to that vessel type; (2) The company's safety management system for the vessel... to the responsible person or their company. (b) An Interim Safety Management Certificate is valid for...

76 FR 15028 - Airport Improvement Program (AIP): Interim Policy Regarding Access to Airports From Residential...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-18

... resolution. The goal of the interim policy is to strike a careful balance by accommodating residential... will allow the agency to complete a separate, ongoing general aviation airport study that is analyzing the federally assisted general aviation airport system. The interim policy adopts the changes proposed...

18 CFR 300.20 - Interim acceptance and review of Bonneville Power Administration rates.

Code of Federal Regulations, 2010 CFR

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Interim acceptance and review of Bonneville Power Administration rates. 300.20 Section 300.20 Conservation of Power and Water... Director of the Office of Energy Market Regulation; or (ii) Deny the Administrator's interim rate request...

42 CFR 417.572 - Budget and enrollment forecast and interim reports.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... PLANS, AND HEALTH CARE PREPAYMENT PLANS Medicare Payment: Cost Basis § 417.572 Budget and enrollment forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget...

78 FR 5830 - Draft Environmental Assessment and Proposed Habitat Conservation Plan for the Interim Operations...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-01-28

... Operations of PacifiCorp's Klamath Hydroelectric Project on the Klamath River, Klamath County, OR, and... Environmental Policy Act (NEPA) for the interim operations of the Klamath Hydroelectric Project in [[Page 5831... habitats upon which they depend, resulting from the interim operations of the Klamath Hydroelectric Project...

40 CFR Appendix III to Part 265 - EPA Interim Primary Drinking Water Standards

Code of Federal Regulations, 2014 CFR

2014-07-01

... 40 Protection of Environment 26 2014-07-01 2014-07-01 false EPA Interim Primary Drinking Water Standards III Appendix III to Part 265 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) INTERIM STATUS STANDARDS FOR OWNERS AND OPERATORS OF HAZARDOUS WASTE TREATMENT, STORAGE, AND DISPOSAL FACILITIES Pt....

75 FR 65528 - Membership of the National Science Board's Senior Executive Service Performance Review Board

Federal Register 2010, 2011, 2012, 2013, 2014

2010-10-25

...: Comments should be addressed to Interim Director, Division of Human Resource Management and Chief Human.... Judith S. Sunley, Interim Director, Division of Human Resource Management and Chief Human Capital Officer..., Interim Director, Division of Human Resource Management and Chief Human Capital Officer. [FR Doc. 2010...

46 CFR 308.6 - Period of interim binders, updating application information and new applications.

Code of Federal Regulations, 2013 CFR

2013-10-01

... information and new applications. 308.6 Section 308.6 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE General § 308.6 Period of interim binders, updating... interim binders are required to notify the American War Risk Agency annually, by June 30th, of any change...

46 CFR 308.6 - Period of interim binders, updating application information and new applications.

Code of Federal Regulations, 2011 CFR

2011-10-01

... information and new applications. 308.6 Section 308.6 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE General § 308.6 Period of interim binders, updating... interim binders are required to notify the American War Risk Agency annually, by June 30th, of any change...

46 CFR 308.6 - Period of interim binders, updating application information and new applications.

Code of Federal Regulations, 2012 CFR

2012-10-01

... information and new applications. 308.6 Section 308.6 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE General § 308.6 Period of interim binders, updating... interim binders are required to notify the American War Risk Agency annually, by June 30th, of any change...

46 CFR 308.6 - Period of interim binders, updating application information and new applications.

Code of Federal Regulations, 2010 CFR

2010-10-01

... information and new applications. 308.6 Section 308.6 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE General § 308.6 Period of interim binders, updating... interim binders are required to notify the American War Risk Agency annually, by June 30th, of any change...

31 CFR 50.7 - Special Rules for Interim Guidance Safe Harbors.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Special Rules for Interim Guidance Safe Harbors. 50.7 Section 50.7 Money and Finance: Treasury Office of the Secretary of the Treasury TERRORISM RISK INSURANCE PROGRAM General Provisions § 50.7 Special Rules for Interim Guidance Safe Harbors...

A Conservative Method of Retaining an Interim Obturator for a Total Maxillectomy Patient

PubMed Central

Bettie, Nirmal Famila

2017-01-01

Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report. PMID:29284985

A Conservative Method of Retaining an Interim Obturator for a Total Maxillectomy Patient.

PubMed

Bettie, Nirmal Famila

2017-11-01

Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

The Australian Replacement Research Reactor

NASA Astrophysics Data System (ADS)

Kennedy, Shane; Robinson, Robert

2004-03-01

The 20-MW Australian Replacement Research Reactor represents possibly the greatest single research infrastructure investment in Australia's history. Construction of the facility has commenced, following award of the construction contract in July 2000, and the construction licence in April 2002. The project includes a large state-of-the-art liquid deuterium cold-neutron source and supermirror guides feeding a large modern guide hall, in which most of the instruments are placed. Alongside the guide hall, there is good provision of laboratory, office and space for support activities. While the facility has "space" for up to 18 instruments, the project has funding for an initial set of 8 instruments, which will be ready when the reactor is fully operational in July 2006. Instrument performance will be competitive with the best research-reactor facilities anywhere, and our goal is to be in the top 3 such facilities worldwide. Staff to lead the design effort and man these instruments have been hired on the international market from leading overseas facilities, and from within Australia, and 7 out of 8 instruments have been specified and costed. At present the instrumentation project carries 10contingency. An extensive dialogue has taken place with the domestic user community and our international peers, via various means including a series of workshops over the last 2 years covering all 8 instruments, emerging areas of application like biology and the earth sciences, and computing infrastructure for the instruments.

Gap Analysis of Material Properties Data for Ferritic/Martensitic HT-9 Steel

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

Brown, Neil R.; Serrano De Caro, Magdalena; Rodriguez, Edward A.

2012-08-28

The US Department of Energy (DOE), Office of Nuclear Energy (NE), is supporting the development of an ASME Code Case for adoption of 12Cr-1Mo-VW ferritic/martensitic (F/M) steel, commonly known as HT-9, primarily for use in elevated temperature design of liquid-metal fast reactors (LMFR) and components. In 2011, Los Alamos National Laboratory (LANL) nuclear engineering staff began assisting in the development of a small modular reactor (SMR) design concept, previously known as the Hyperion Module, now called the Gen4 Module. LANL staff immediately proposed HT-9 for the reactor vessel and components, as well as fuel clad and ducting, due to itsmore » superior thermal qualities. Although the ASME material Code Case, for adoption of HT-9 as an approved elevated temperature material for LMFR service, is the ultimate goal of this project, there are several key deliverables that must first be successfully accomplished. The most important key deliverable is the research, accumulation, and documentation of specific material parameters; physical, mechanical, and environmental, which becomes the basis for an ASME Code Case. Time-independent tensile and ductility data and time-dependent creep and creep-rupture behavior are some of the material properties required for a successful ASME Code case. Although this report provides a cursory review of the available data, a much more comprehensive study of open-source data would be necessary. This report serves three purposes: (a) provides a list of already existing material data information that could ultimately be made available to the ASME Code, (b) determines the HT-9 material properties data missing from available sources that would be required and (c) estimates the necessary material testing required to close the gap. Ultimately, the gap analysis demonstrates that certain material properties testing will be required to fulfill the necessary information package for an ASME Code Case.« less

Dual benefit robotics programs at Sandia National Laboratories

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

Jones, A.T.

Sandia National Laboratories has one of the largest integrated robotics laboratories in the United States. Projects include research, development, and application of one-of-a-kind systems, primarily for the Department of Energy (DOE) complex. This work has been underway for more than 10 years. It began with on-site activities that required remote operation, such as reactor and nuclear waste handling. Special purpose robot systems were developed using existing commercial manipulators and fixtures and programs designed in-house. These systems were used in applications such as servicing the Sandia pulsed reactor and inspecting remote roof bolts in an underground radioactive waste disposal facility. Inmore » the beginning, robotics was a small effort, but with increasing attention to the use of robots for hazardous operations, efforts now involve a staff of more than 100 people working in a broad robotics research, development, and applications program that has access to more than 30 robotics systems.« less

The simulation of decontamination works in premises of the research reactor in NRC 'Kurchatov institute'

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

Danilovich, Alexey; Ivanov, Oleg; Potapov, Victor

2013-07-01

Application of remote sensing methods using a spectrometric collimated system allows obtaining information about features of a formation of radiation fields in contaminated premises. This information helps in a preparation of a phased plan for dismantling of contaminated equipment. When the survey of technological premises of the research reactor at the Russian Research Centre 'Kurchatov institute' was conducted the remote controlled collimated spectrometric system was used. With its help the scanning of surveyed premises were carried out. As a result of this work, the distribution pattern of radionuclides activity was restored. The simulation of decontamination works was carried out andmore » maps of the distribution of activity and dose rate for surveyed premises were plotted and superimposed on its photo for situations before and after decontamination. The use of obtained results will allow significantly reduce radiation dose for staff at work on dismantling. (authors)« less

50 CFR 660.720 - Interim protection for sea turtles.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 50 Wildlife and Fisheries 13 2012-10-01 2012-10-01 false Interim protection for sea turtles. 660... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707... harvest of swordfish (Xiphias gladius) using longline gear deployed on the high seas of the Pacific Ocean...

50 CFR 660.720 - Interim protection for sea turtles.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 50 Wildlife and Fisheries 13 2013-10-01 2013-10-01 false Interim protection for sea turtles. 660... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707... harvest of swordfish (Xiphias gladius) using longline gear deployed on the high seas of the Pacific Ocean...

50 CFR 660.720 - Interim protection for sea turtles.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 50 Wildlife and Fisheries 11 2011-10-01 2011-10-01 false Interim protection for sea turtles. 660... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707... harvest of swordfish (Xiphias gladius) using longline gear deployed on the high seas of the Pacific Ocean...

50 CFR 660.720 - Interim protection for sea turtles.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 50 Wildlife and Fisheries 13 2014-10-01 2014-10-01 false Interim protection for sea turtles. 660... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707... harvest of swordfish (Xiphias gladius) using longline gear deployed on the high seas of the Pacific Ocean...

49 CFR 37.169 - Interim requirements for over-the-road bus service operated by private entities.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Interim requirements for over-the-road bus service... Interim requirements for over-the-road bus service operated by private entities. (a) Private entities operating over-the-road buses, in addition to compliance with other applicable provisions of this part...

76 FR 48197 - Self-Regulatory Organizations; Municipal Securities Rulemaking Board; Notice of Filing of...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-08-08

... assessable professional reported or required to be reported by a municipal advisor to the MSRB on Form A-11... Assessment and Form A-11- Interim. For purposes of the interim assessment, an assessable professional of a...-Interim as an assessable professional any associated person (i) Who otherwise qualifies as an assessable...

75 FR 12217 - Notice of Availability for Comments Regarding the Planned Environmental Assessment Interim Report...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-03-15

... public comments for a planned Environmental Assessment. The Corps is directed to conduct a study of.... The study is structured as a series of interim reports. Interim Report IIIa, limited to the impacts of.... Comments are requested to assist in determining the level of analysis and impacts to be considered for...

78 FR 53038 - Interim Final Determination to Stay and Defer Sanctions; California; San Joaquin Valley

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-28

... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2013-0534; FRL-9900-36-Region 9.... Environmental Protection Agency (EPA). ACTION: Interim final rule. SUMMARY: EPA is making an interim [email protected] . Mail or deliver: Frances Wicher (AIR-2), U.S. Environmental Protection Agency Region 9...

Chooz A, First Pressurized Water Reactor to be Dismantled in France - 13445

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

Boucau, Joseph; Mirabella, C.; Nilsson, Lennart

2013-07-01

Nine commercial nuclear power plants have been permanently shut down in France to date, of which the Chooz A plant underwent an extensive decommissioning and dismantling program. Chooz Nuclear Power Station is located in the municipality of Chooz, Ardennes region, in the northeast part of France. Chooz B1 and B2 are 1,500 megawatt electric (MWe) pressurized water reactors (PWRs) currently in operation. Chooz A, a 305 MWe PWR implanted in two caves within a hill, began operations in 1967 and closed in 1991, and will now become the first PWR in France to be fully dismantled. EDF CIDEN (Engineering Centermore » for Dismantling and Environment) has awarded Westinghouse a contract for the dismantling of its Chooz A reactor vessel (RV). The project began in January 2010. Westinghouse is leading the project in a consortium with Nuvia France. The project scope includes overall project management, conditioning of the reactor vessel (RV) head, RV and RV internals segmentation, reactor nozzle cutting for lifting the RV out of the pit and seal it afterwards, dismantling of the RV thermal insulation, ALARA (As Low As Reasonably Achievable) forecast to ensure acceptable doses for the personnel, complementary vacuum cleaner to catch the chips during the segmentation work, needs and facilities, waste characterization and packaging, civil work modifications, licensing documentation. The RV and RV internals will be segmented based on the mechanical cutting technology that Westinghouse applied successfully for more than 13 years. The segmentation activities cover the cutting and packaging plan, tooling design and qualification, personnel training and site implementation. Since Chooz A is located inside two caves, the project will involve waste transportation from the reactor cave through long galleries to the waste buffer area. The project will end after the entire dismantling work is completed, and the waste storage is outside the caves and ready to be shipped either to the ANDRA (French National Radioactive Waste Management Agency) waste disposal facilities - (for low-level waste [LLW] and very low-level waste [VLLW], which are considered short lived) - or to the EDF Interim Storage Facility planned to be built on another site - (for low- and intermediate-level waste [LILW], which is considered long lived). The project has started with a detailed conceptual study that determines the step-by-step approach for dismantling the reactor and eventually supplying the packed containers ready for final disposal. All technical reports must be verified and approved by EDF and the French Nuclear Safety Authority before receiving the authorization to start the site work. The detailed conceptual study has been completed to date and equipment design and manufacturing is ongoing. This paper will present the conceptual design of the reactor internals segmentation and packaging process that will be implemented at Chooz A, including the planning, methodology, equipment, waste management, and packaging strategy. (authors)« less

Evaluation of ERA-Interim precipitation data in complex terrain

NASA Astrophysics Data System (ADS)

Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

2013-04-01

Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced overestimate in the southern flank of Alps. The poor topographical and flow related characteristic representation of ERA-Interim model is possibly responsible for the bias. Particularly, the mountain block effect of moisture is weak captured. The comparison demonstrates that ERA-Interim precipitation intensity needs bias correction for further alpine climate studies, although it reasonably captures precipitation frequency. This critical evaluation not only diagnosed the data quality of ERA-Interim, but also provided the evidence for reanalysis products downscaling and bias correction in complex terrain.

In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

PubMed

Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

2016-05-01

The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (P<.001). At the facial margin, the mean horizontal component of the Telio crowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (P<.001). However, the mean percentage dye penetration was significantly correlated with the vertical and horizontal marginal discrepancies of the Jet interim crowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (P<.01 in each instance). A significantly smaller vertical marginal discrepancy was found with the interim crowns fabricated by CAD/CAM as compared with PMMA crowns; however, this difference was not observed for the horizontal component. The percentage dye penetration was correlated with vertical and horizontal discrepancies at the facial surface for the Jet interim crowns and with horizontal discrepancies at the lingual surface for the Caulk interim crowns. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

Prognostic value of interim FDG-PET in R-CHOP-treated diffuse large B-cell lymphoma: Systematic review and meta-analysis.

PubMed

Adams, Hugo J A; Kwee, Thomas C

2016-10-01

This study aimed to systematically review and meta-analyze the prognostic value of interim (18)F-fluoro-2-deoxy-d-glucose positron emission tomography (FDG-PET) in diffuse large B-cell lymphoma (DLBCL) patients treated with rituximab, cyclophosphamide, doxorubicin, vincristine, and prednisolone (R-CHOP). MEDLINE and EMBASE were systematically searched for suitable studies. Included studies were methodologically appraised, and results were summarized both descriptively and meta-analytically. Nine studies, comprising a total of 996 R-CHOP-treated DLBCL patients, were included. Overall, studies were of moderate methodological quality. The area under the summary receiver operating curve (AUC) of interim FDG-PET in predicting treatment failure and death were 0.651 and 0.817, respectively. There was no heterogeneity in diagnostic odds ratios across available studies (I(2)=0.0%). At multivariable analysis, 2 studies reported interim FDG-PET to have independent prognostic value in addition to the International Prognostic Index (IPI) in predicting treatment failure, whereas 3 studies reported that this was not the case. One study reported interim FDG-PET to have independent prognostic value in addition to the IPI in predicting death, whereas 2 studies reported that this was not the case. In conclusion, interim FDG-PET in R-CHOP-treated DLBCL has some correlation with outcome, but its prognostic value is homogeneously suboptimal across studies and it has not consistently proven to surpass the prognostic potential of the IPI. Moreover, there is a lack of studies that compared interim FDG-PET to the recently developed and superior National Comprehensive Cancer Network-IPI. Therefore, at present there is no scientific base to support the clinical use of interim FDG-PET in R-CHOP-treated DLBCL. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Quantifying the bias in the estimated treatment effect in randomized trials having interim analyses and a rule for early stopping for futility.

PubMed

Walter, S D; Han, H; Briel, M; Guyatt, G H

2017-04-30

In this paper, we consider the potential bias in the estimated treatment effect obtained from clinical trials, the protocols of which include the possibility of interim analyses and an early termination of the study for reasons of futility. In particular, by considering the conditional power at an interim analysis, we derive analytic expressions for various parameters of interest: (i) the underestimation or overestimation of the treatment effect in studies that stop for futility; (ii) the impact of the interim analyses on the estimation of treatment effect in studies that are completed, i.e. that do not stop for futility; (iii) the overall estimation bias in the estimated treatment effect in a single study with such a stopping rule; and (iv) the probability of stopping at an interim analysis. We evaluate these general expressions numerically for typical trial scenarios. Results show that the parameters of interest depend on a number of factors, including the true underlying treatment effect, the difference that the trial is designed to detect, the study power, the number of planned interim analyses and what assumption is made about future data to be observed after an interim analysis. Because the probability of stopping early is small for many practical situations, the overall bias is often small, but a more serious issue is the potential for substantial underestimation of the treatment effect in studies that actually stop for futility. We also consider these ideas using data from an illustrative trial that did stop for futility at an interim analysis. Copyright © 2017 John Wiley & Sons, Ltd. Copyright © 2017 John Wiley & Sons, Ltd.

A global validation of ERA-Interim integrated water vapor estimates using ground-based GNSS observations

NASA Astrophysics Data System (ADS)

Ahmed, F.; Dousa, J.; Hunegnaw, A.; Teferle, F. N.; Bingley, R.

2017-12-01

Integrated water vapor (IWV) derived from climate reanalysis models, such as the European Centre for Medium-range Weather Forecasts (ECMWF) ReAnalysis-Interim (ERA-Interim), is widely used in many atmospheric applications. Therefore, it is of interest to assess the quality of this reanalysis product using available observations. Observations from Global Navigation Satellite Systems (GNSS) are, as of now, available for a period of over 2 decades and their global availability makes it possible to validate the IWV obtained from climate reanalysis models in different geographical and climatic regions. In this study, primarily, three 5-year long homogeneously reprocessed GNSS-derived IWV datasets containing over 400 globally distributed ground-based GNSS stations have been used to validate the IWV estimates obtained from the ERA-Interim climate reanalysis model in 25 different climate zones. The IWV from ERA-Interim has been obtained by vertically integrating the specific humidity at all model levels above the locations of GNSS stations. It has been studied how the difference between the ERA-Interim IWV and the GNSS-derived IWV varies with respect to the different climate zones as well as with respect to the difference in the model orography and latitude. The results show a dependence of the ability of ERA-Interim to model the IWV on difference in climate types and latitude. This dependence, however, is dictated by the concentration of water vapor in different climate zones and at different latitudes. Furthermore, as a secondary focus of this study, the weighted mean atmospheric temperature (Tm) obtained from ERA-Interim has been compared to its equivalent obtained using two widely used approximations globally.

Elimination of exemptions for chemical mixtures containing the list I chemicals ephedrine and/or pseudoephedrine. Final rule.

PubMed

2008-07-10

The Drug Enforcement Administration (DEA) is finalizing, without change, the Interim Rule with Request for Comment published in the Federal Register on July 25, 2007 (72 FR 40738). The Interim Rule removed the Controlled Substances Act (CSA) exemptions for chemical mixtures containing ephedrine and/or pseudoephedrine with concentration limits at or below five percent. Upon the effective date of the Interim Rule, all ephedrine and pseudoephedrine chemical mixtures, regardless of concentration and form, became subject to the regulatory provisions of the CSA. DEA regulated the importation, exportation, manufacture, and distribution of these chemical mixtures by requiring persons who handle these chemical mixtures to register with DEA, maintain certain records common to business practice, and file certain reports, regarding these chemical mixtures. No comments to the Interim Rule were received. This Final Rule finalizes the Interim Rule without change.

Small Reactor Designs Suitable for Direct Nuclear Thermal Propulsion: Interim Report

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

Bruce G. Schnitzler

Advancement of U.S. scientific, security, and economic interests requires high performance propulsion systems to support missions beyond low Earth orbit. A robust space exploration program will include robotic outer planet and crewed missions to a variety of destinations including the moon, near Earth objects, and eventually Mars. Past studies, in particular those in support of both the Strategic Defense Initiative (SDI) and the Space Exploration Initiative (SEI), have shown nuclear thermal propulsion systems provide superior performance for high mass high propulsive delta-V missions. In NASA's recent Mars Design Reference Architecture (DRA) 5.0 study, nuclear thermal propulsion (NTP) was again selectedmore » over chemical propulsion as the preferred in-space transportation system option for the human exploration of Mars because of its high thrust and high specific impulse ({approx}900 s) capability, increased tolerance to payload mass growth and architecture changes, and lower total initial mass in low Earth orbit. The recently announced national space policy2 supports the development and use of space nuclear power systems where such systems safely enable or significantly enhance space exploration or operational capabilities. An extensive nuclear thermal rocket technology development effort was conducted under the Rover/NERVA, GE-710 and ANL nuclear rocket programs (1955-1973). Both graphite and refractory metal alloy fuel types were pursued. The primary and significantly larger Rover/NERVA program focused on graphite type fuels. Research, development, and testing of high temperature graphite fuels was conducted. Reactors and engines employing these fuels were designed, built, and ground tested. The GE-710 and ANL programs focused on an alternative ceramic-metallic 'cermet' fuel type consisting of UO2 (or UN) fuel embedded in a refractory metal matrix such as tungsten. The General Electric program examined closed loop concepts for space or terrestrial applications as well as open loop systems for direct nuclear thermal propulsion. Although a number of fast spectrum reactor and engine designs suitable for direct nuclear thermal propulsion were proposed and designed, none were built. This report summarizes status results of evaluations of small nuclear reactor designs suitable for direct nuclear thermal propulsion.« less

40 CFR 52.243 - Interim approval of the Carbon Monoxide plan for the South Coast.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 40 Protection of Environment 3 2010-07-01 2010-07-01 false Interim approval of the Carbon Monoxide plan for the South Coast. 52.243 Section 52.243 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.243 Interim approval of the Carbon...

49 CFR 1152.29 - Prospective use of rights-of-way for interim trail use and rail banking.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 49 Transportation 8 2010-10-01 2010-10-01 false Prospective use of rights-of-way for interim trail... Governing Notice, Applications, Financial Assistance, Acquisition for Public Use, and Trail Use § 1152.29 Prospective use of rights-of-way for interim trail use and rail banking. (a) If any state, political...

Temps at the Top: Factors Related to the Appointment of Interim Community College Presidents

ERIC Educational Resources Information Center

Goff, Susan L.

2012-01-01

The appointment of interim community college presidents, the topic of this study, is a little understood phenomenon. A growing shortage of community college presidents coupled with a lack of replacements suggests the appointment of interims will continue well into the future. This study, with a purpose of looking at the factors related to the…

Office of Inspector General; Medicare and state health care programs: fraud and abuse; issuance of advisory opinions by the OIG. Final rule.

PubMed

2008-07-17

OIG is adopting in final form, without change, an interim final rule published on March 26, 2008 (73 FR 15937). We received no comments to the interim final rule. The interim final rule revised the process for advisory opinion requestors to submit payments for advisory opinion costs.

From Testing to Teaching: The Use of Interim Assessments in Classroom Instruction. CPRE Research Report # RR-65

ERIC Educational Resources Information Center

Goertz, Margaret E.; Olah, Leslie Nabors; Riggan, Matthew

2009-01-01

The purpose of this exploratory study is to examine the use of interim assessments and the policy supports that promote use to improve instruction, focusing on elementary school mathematics. The authors use the term "interim assessments" to refer to assessments that a) evaluate student knowledge and skills, typically within a limited…

40 CFR 52.243 - Interim approval of the Carbon Monoxide plan for the South Coast.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 40 Protection of Environment 3 2014-07-01 2014-07-01 false Interim approval of the Carbon Monoxide plan for the South Coast. 52.243 Section 52.243 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.243 Interim approval of the Carbon...

40 CFR 52.243 - Interim approval of the Carbon Monoxide plan for the South Coast.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 40 Protection of Environment 3 2013-07-01 2013-07-01 false Interim approval of the Carbon Monoxide plan for the South Coast. 52.243 Section 52.243 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.243 Interim approval of the Carbon...

40 CFR 52.243 - Interim approval of the Carbon Monoxide plan for the South Coast.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 40 Protection of Environment 3 2012-07-01 2012-07-01 false Interim approval of the Carbon Monoxide plan for the South Coast. 52.243 Section 52.243 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.243 Interim approval of the Carbon...

76 FR 5564 - Grant of Interim Extension of the Term of U.S. Patent No. 4,971,802; MIFAMURTIDE

Federal Register 2010, 2011, 2012, 2013, 2014

2011-02-01

... DEPARTMENT OF COMMERCE Patent and Trademark Office [Docket No. PTO-P-2011-0001] Grant of Interim... Office, Commerce. ACTION: Notice of interim patent term extension. SUMMARY: The United States Patent and... States Patent and Trademark Office. [FR Doc. 2011-2088 Filed 1-31-11; 8:45 am] BILLING CODE 3510-16-P ...

Interim Testing, Socio-Economic Status, and the Odds of Passing Grade 8 State Tests in New Jersey

ERIC Educational Resources Information Center

Babo, Gerard; Tienken, Christopher H.; Gencarelli, Maria A.

2014-01-01

A review of the literature pertaining to the effect and influence of commercially-prepared interim assessments in mathematics and language arts literacy reveals a lack of quantitative data to determine the value of these products for school reform. This study examined the ability of commercially-prepared interim pretest and posttest assessments in…

47 CFR 51.715 - Interim transport and termination pricing.

Code of Federal Regulations, 2013 CFR

2013-10-01

... shall set interim transport and termination rates either at the default ceilings specified in § 51.705(c) or in accordance with a bill-and-keep methodology as defined in § 51.713. (3) In a state in which the... minute of use), and transport (as described in § 51.707(b)(2)). (c) An interim arrangement shall cease to...

47 CFR 51.715 - Interim transport and termination pricing.

Code of Federal Regulations, 2014 CFR

2014-10-01

... shall set interim transport and termination rates either at the default ceilings specified in § 51.705(c) or in accordance with a bill-and-keep methodology as defined in § 51.713. (3) In a state in which the... minute of use), and transport (as described in § 51.707(b)(2)). (c) An interim arrangement shall cease to...

47 CFR 51.715 - Interim transport and termination pricing.

Code of Federal Regulations, 2012 CFR

2012-10-01

... shall set interim transport and termination rates either at the default ceilings specified in § 51.705(c) or in accordance with a bill-and-keep methodology as defined in § 51.713. (3) In a state in which the... minute of use), and transport (as described in § 51.707(b)(2)). (c) An interim arrangement shall cease to...

77 FR 34399 - Public Housing Assessment System (PHAS): Capital Fund Interim Scoring Notice; Request for Comment

Federal Register 2010, 2011, 2012, 2013, 2014

2012-06-11

...-indicator of the Capital Fund indicator to all PHAs for the Capital Fund Indicator under the PHAS interim... transition to the scoring system implemented by the PHAS interim rule, especially as relates to the indicator that assesses occupancy rate. The 5 points for the occupancy sub-indicator will be awarded for fiscal...

ORNL Neutron Sciences Annual Report for 2007

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

Anderson, Ian S; Horak, Charlie M; Counce, Deborah Melinda

2008-07-01

This is the first annual report of the Oak Ridge National Laboratory Neutron Sciences Directorate for calendar year 2007. It describes the neutron science facilities, current developments, and future plans; highlights of the year's activities and scientific research; and information on the user program. It also contains information about education and outreach activities and about the organization and staff. The Neutron Sciences Directorate is responsible for operation of the High Flux Isotope Reactor and the Spallation Neutron Source. The main highlights of 2007 were highly successful operation and instrument commissioning at both facilities. At HFIR, the year began with themore » reactor in shutdown mode and work on the new cold source progressing as planned. The restart on May 16, with the cold source operating, was a significant achievement. Furthermore, measurements of the cold source showed that the performance exceeded expectations, making it one of the world's most brilliant sources of cold neutrons. HFIR finished the year having completed five run cycles and 5,880 MWd of operation. At SNS, the year began with 20 kW of beam power on target; and thanks to a highly motivated staff, we reached a record-breaking power level of 183 kW by the end of the year. Integrated beam power delivered to the target was 160 MWh. Although this is a substantial accomplishment, the next year will bring the challenge of increasing the integrated beam power delivered to 887 MWh as we chart our path toward 5,350 MWh by 2011.« less

Fabrication of an interim complete removable dental prosthesis with an in-office digital light processing three-dimensional printer: A proof-of-concept technique.

PubMed

Lin, Wei-Shao; Harris, Bryan T; Pellerito, John; Morton, Dean

2018-04-30

This report describes a proof of concept for fabricating an interim complete removable dental prosthesis with a digital light processing 3-dimensional (3D) printer. Although an in-office 3D printer can reduce the overall production cost for an interim complete removable dental prosthesis, the process has not been validated with clinical studies. This report provided a preliminary proof of concept in developing a digital workflow for the in-office additively manufactured interim complete removable dental prosthesis. Copyright © 2018 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

National School Lunch Program and School Breakfast Program: Nutrition Standards for All Foods Sold in School as Required by the Healthy, Hunger-Free Kids Act of 2010. Final rule and interim final rule.

PubMed

2016-07-29

This rule adopts as final, with some modifications, the National School Lunch Program and School Breakfast Program regulations set forth in the interim final rule published in the Federal Register on June 28, 2013. The requirements addressed in this rule conform to the provisions in the Healthy, Hunger-Free Kids Act of 2010 regarding nutrition standards for all foods sold in schools, other than food sold under the lunch and breakfast programs. Most provisions of this final rule were implemented on July 1, 2014, a full year subsequent to publication of the interim final rule. This was in compliance with section 208 of the Healthy, Hunger-Free Kids Act of 2010, which required that State and local educational agencies have at least one full school year from the date of publication of the interim final rule to implement the competitive food provisions. Based on comments received on the interim final rule and implementation experience, this final rule makes a few modifications to the nutrition standards for all foods sold in schools implemented on July 1, 2014. In addition, this final rule codifies specific policy guidance issued after publication of the interim rule. Finally, this rule retains the provision related to the standard for total fat as interim and requests further comment on this single standard.

Resource Use and Real-World Outcomes for Ranibizumab Treat and Extend for Neovascular Age-Related Macular Degeneration in the UK: Interim Results from TERRA.

PubMed

Yang, Yit; Downey, Louise; Mehta, Hemal; Mushtaq, Bushra; Narendran, Niro; Patel, Nishal; Patel, Praveen J; Ayan, Filis; Gibson, Kara; Igwe, Franklin; Jeffery, Pete

2017-06-01

Ranibizumab is an inhibitor of vascular endothelial growth factor-A (anti-VEGF) approved for the treatment of neovascular age-related macular degeneration (nAMD). The treat and extend (T&E) regimen can potentially reduce the burden of clinic visits compared with a pro re nata (PRN) regimen. Retrospective, interim analyses of clinical effectiveness, treatment and resource use patterns were conducted using real-world data in England and Wales from the TERRA study. Two cohorts, those switching from a PRN to a T&E regimen ('prior PRN') and those initiating ranibizumab on the T&E regimen as their first anti-VEGF therapy ('anti-VEGF-naïve') were enrolled in TERRA. Retrospective clinical assessments were gathered from medical records, while resource use patterns were collected via an operating cost questionnaire completed by each study site. At the interim analysis cut-off date (15 November 2016), 11 sites had enrolled 145 patients (prior PRN: n = 110; anti-VEGF-naïve: n = 35). Mean change from baseline (date of first injection) in visual acuity and central subfield retinal thickness to 12 months was +7.6 Early Treatment Diabetic Retinopathy Study letters [95% confidence interval (CI) 2.8, 12.4; p = 0.003; n = 27] and -67.7 μm (95% CI -106.5, -28.9; p = 0.001, n = 29), respectively, in the anti-VEGF-naïve cohort. Most T&E clinics were run as one-stop services (same-day monitoring and injection), whereas 4/10 PRN clinics were run as two-stop services (monitoring and injection on different days). In general, one-stop clinics used less staff resources and were likely to be shorter in duration for healthcare providers than the cumulative time spent for two-stop clinics. This is the first real-world observational study conducted in England and Wales demonstrating the effectiveness of the ranibizumab T&E regimen in anti-VEGF-naïve patients. T&E is compatible with one-stop clinic services, which these real-world data suggest to be less resource intensive than two-stop clinic services, possibly providing a dosing regimen beneficial to both patients and resource burden in UK clinical practice. Novartis Pharmaceuticals UK Limited.

WWC Review of the Report "The Impact of Indiana's System of Interim Assessments on Mathematics and Reading." What Works Clearinghouse Single Study Review

ERIC Educational Resources Information Center

What Works Clearinghouse, 2015

2015-01-01

The study, "The Impact of Indiana's System of Interim Assessments on Mathematics and Reading," examined the effects of using Diagnostic Assessment Tools (DAT) on mathematics and reading outcomes for students in 59 Indiana schools during the 2009-10 academic year. DAT consists of interim assessment tools--Wireless Generation's mCLASS for…

The Predictive Validity of Interim Assessment Scores Based on the Full-Information Bifactor Model for the Prediction of End-of-Grade Test Performance

ERIC Educational Resources Information Center

Immekus, Jason C.; Atitya, Ben

2016-01-01

Interim tests are a central component of district-wide assessment systems, yet their technical quality to guide decisions (e.g., instructional) has been repeatedly questioned. In response, the study purpose was to investigate the validity of a series of English Language Arts (ELA) interim assessments in terms of dimensionality and prediction of…

25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

Code of Federal Regulations, 2014 CFR

2014-04-01

... 25 Indians 1 2014-04-01 2014-04-01 false Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Pre-kindergarten Programs § 39.1100 Interim fiscal year...

25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

Code of Federal Regulations, 2012 CFR

2012-04-01

... 25 Indians 1 2012-04-01 2011-04-01 true Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Pre-kindergarten Programs § 39.1100 Interim fiscal year...

25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

Code of Federal Regulations, 2010 CFR

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Pre-kindergarten Programs § 39.1100 Interim fiscal year...

25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

Code of Federal Regulations, 2013 CFR

2013-04-01

... 25 Indians 1 2013-04-01 2013-04-01 false Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Pre-kindergarten Programs § 39.1100 Interim fiscal year...

25 CFR 39.1100 - Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously...

Code of Federal Regulations, 2011 CFR

2011-04-01

... 25 Indians 1 2011-04-01 2011-04-01 false Interim fiscal year 1980 and fiscal year 1981 funding for pre-kindergarten programs previously funded by the Bureau. 39.1100 Section 39.1100 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION THE INDIAN SCHOOL EQUALIZATION PROGRAM Pre-kindergarten Programs § 39.1100 Interim fiscal year...

Chemicals from coal. Interim report for USBM Synthoil

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

Peters, B.C.

1977-10-01

This document contains the results of an investigation to determine the suitability of the USBM Synthoil Product as a petrochemical feedstock. A sample of the whole crude was distilled into two straight run fractions; 350 to 650/sup 0/F mid-distillate and 650/sup 0/F+ residue. Laboratory studies in metal reactors and computer and mathematical simulations were performed to provide overall material balance data for a conceptual plant. The mid-distillate was hydrocracked to produce naphtha which was further processed by hydrotreating and reforming. The reformate from the mid-distillate was then mathematically hydrodealkylated to convert it to a product slate consisting of methane, LPG's,more » benzene, and fuel, along with the total hydrogen consumed. The value of the products obtained per 100 pounds of mid-distillate was $6.89. The high aromatic yield obtained from the hydrocrackate naphtha makes this fraction very attractive as a petrochemical feedstock. Because the gas oil would be extremely difficult to process, it was not investigated.« less

PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

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

MAY TH

The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revisionmore » includes information on additional feed tanks.« less

The utility of Bayesian predictive probabilities for interim monitoring of clinical trials

PubMed Central

Connor, Jason T.; Ayers, Gregory D; Alvarez, JoAnn

2014-01-01

Background Bayesian predictive probabilities can be used for interim monitoring of clinical trials to estimate the probability of observing a statistically significant treatment effect if the trial were to continue to its predefined maximum sample size. Purpose We explore settings in which Bayesian predictive probabilities are advantageous for interim monitoring compared to Bayesian posterior probabilities, p-values, conditional power, or group sequential methods. Results For interim analyses that address prediction hypotheses, such as futility monitoring and efficacy monitoring with lagged outcomes, only predictive probabilities properly account for the amount of data remaining to be observed in a clinical trial and have the flexibility to incorporate additional information via auxiliary variables. Limitations Computational burdens limit the feasibility of predictive probabilities in many clinical trial settings. The specification of prior distributions brings additional challenges for regulatory approval. Conclusions The use of Bayesian predictive probabilities enables the choice of logical interim stopping rules that closely align with the clinical decision making process. PMID:24872363

INTERIM -- Starlink Software Environment

NASA Astrophysics Data System (ADS)

Pearce, Dave; Pavelin, Cliff; Lawden, M. D.

Early versions of this paper were based on a number of other papers produced at a very early stage of the Starlink project. They contained a description of a specific implementation of a subroutine library, speculations on the desirable attributes of a software environment, and future development plans. They reflected the experimental nature of the Starlink software environment at that time. Since then, the situation has changed. The implemented subroutine library, INTERIM_DIR:INTERIM.OLB, is now a well established and widely used piece of software. A completely new Starlink software environment (ADAM) has been developed and distributed. Thus the library released in 1980 as `STARLINK' and now called `INTERIM' has reached the end of its development cycle and is now frozen in its current state, apart from bug corrections. This paper has, therefore, been completely rewritten and restructured to reflect the new situation. Its aim is to describe the facilities of the INTERIM subroutine library as clearly and concisely as possible. It avoids speculation, discussion of design decisions, and announcements of future plans.

Prohibited Contaminants in Dietary Supplements.

PubMed

Mathews, Neilson M

With the increasing use of unregulated dietary supplements, athletes are at continued risk from adverse medical events and inadvertent doping. A review of Clinical Key, MEDLINE, and PubMed databases from 2012 to 2017 was performed using search terms, including dietary supplement, contamination, doping in athletes, inadvertent doping, and prohibited substances. The references of pertinent articles were reviewed for other relevant sources. Clinical review. Level 3. Poor manufacturing processes and intentional contamination with many banned substances continue to occur in dietary supplements sold in the United States. Certain sectors, such as weight loss and muscle-building supplements, pose a greater threat because they are more likely to be contaminated. Athletes will continue to be at risk for adverse events and failed doping tests due to contaminated dietary supplements until legislation changes how they are regulated. In the interim, there are several steps that can be taken to mitigate this risk, including improved education of medical staff and athletes and use of third party-certified products.

TTI CM/AQ evaluation model user`s guide and workshop training materials. Interim research report, September 1993-August 1996

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

NONE

1995-08-01

The TTI CM/AQ Evaluation Model evaluates potential projects based on the following criteria: eligibility, travel impacts, emission impacts, and cost-effectiveness. To compare independent projects within a region during the decision process for CM/AQ funding, each project evaluated with this model is given an overall score based on the project`s effects for the criteria listed above. Training workshops were held by TTI in the first quarter of 1995 to teach metropolitan planning organization, state department of transportation, and regional air quality organization staff how to use this model. Basics of sketch-planning applications were also taught. The DRCOG and TTI CM/AQ Evaluationmore » Models represent significant steps toward the development of analytical methodologies for selecting projects for CM/AQ funding. Because the needs of nonattainment and attainment areas change over time, this model is particularly useful as key evaluation criteria can be modified to reflect the changing needs of a metropolitan area.« less

17 CFR 402.2a - Appendix A-Calculation of market risk haircut for purposes of § 402.2(g)(2).

Code of Federal Regulations, 2014 CFR

2014-04-01

... larger in absolute value of the two residual position interim haircuts being netted, and (ii) zero, in... category of the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in... the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in the...

17 CFR 402.2a - Appendix A-Calculation of market risk haircut for purposes of § 402.2(g)(2).

Code of Federal Regulations, 2011 CFR

2011-04-01

... larger in absolute value of the two residual position interim haircuts being netted, and (ii) zero, in... category of the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in... the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in the...

17 CFR 402.2a - Appendix A-Calculation of market risk haircut for purposes of § 402.2(g)(2).

Code of Federal Regulations, 2012 CFR

2012-04-01

... larger in absolute value of the two residual position interim haircuts being netted, and (ii) zero, in... category of the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in... the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in the...

17 CFR 402.2a - Appendix A-Calculation of market risk haircut for purposes of § 402.2(g)(2).

Code of Federal Regulations, 2010 CFR

2010-04-01

... larger in absolute value of the two residual position interim haircuts being netted, and (ii) zero, in... category of the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in... the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in the...

17 CFR 402.2a - Appendix A-Calculation of market risk haircut for purposes of § 402.2(g)(2).

Code of Federal Regulations, 2013 CFR

2013-04-01

... larger in absolute value of the two residual position interim haircuts being netted, and (ii) zero, in... category of the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in... the larger (in absolute value) of the two interim haircuts that were netted, and (2) a zero in the...

Interim Report by Asia International Grid Connection Study Group

NASA Astrophysics Data System (ADS)

Omatsu, Ryo

2018-01-01

The Asia International Grid Connection Study Group Interim Report examines the feasibility of developing an international grid connection in Japan. The Group has investigated different cases of grid connections in Europe and conducted research on electricity markets in Northeast Asia, and identifies the barriers and challenges for developing an international grid network including Japan. This presentation introduces basic contents of the interim report by the Study Group.

Commentary: Interim leadership of academic departments at U.S. medical schools.

PubMed

Grigsby, R Kevin; Aber, Robert C; Quillen, David A

2009-10-01

Medical schools and teaching hospitals are experiencing more frequent turnover of department chairs. Loss of a department chair creates instability in the department and may have a negative effect on the organization at large. Interim leadership of academic departments is common, and interim chairs are expected to immediately demonstrate skills and leadership abilities. However, little is known about how persons are prepared to assume the interim chair role. Newer competencies for effective leadership include an understanding of the business of medicine, interpersonal and communication skills, the ability to deal with conflict and solve adaptive challenges, and the ability to build and work on teams. Medical schools and teaching hospitals need assistance to meet the unique training and support needs of persons serving as interim leaders. For example, the Association of American Medical Colleges and individual chair societies can develop programs to allow current chairs to reflect on their present positions and plan for the future. Formal leadership training, mentorship opportunities, and conscientious succession planning are good first steps in preparing to meet the needs of academic departments during transitions in leadership. Also, interim leadership experience may be useful as a means for "opening the door" to underrepresented persons, including women, and increasing the diversity of the leadership team.

Use of artificial intelligence in severe accident diagnosis for PWRs

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

Wu, Zheng; Okrent, D.; Kastenberg, W.E.

1995-12-31

A combination approach of an expert system and neural networks is used to implement a prototype severe accident diagnostic system which would monitor the progression of the severe accident and provide necessary plant status information to assist the plant staff in accident management during the accident. The station blackout accident in a pressurized water reactor (PWR) is used as the study case. The current phase of research focus is on distinguishing different primary system failure modes and following the accident transient before and up to vessel breach.

Hazardous waste management programs; Florida: authorization for interim authorization phase I--Environmental Protection Agency. Notice of final determination.

PubMed

1982-05-07

The State of Florida has applied for interim Authorization Phase I. EPA has reviewed Florida's application for Phase I and has determined that Florida's hazardous waste program is substantially equivalent to the Federal program covered by Phase I. The State of Florida is, hereby, granted Interim Authorization for Phase I to operate the State 's hazardous waste program, in lieu of the Federal program.

The Archaeology of Coralville Lake, Iowa. Volume 4. Recreation Area Survey. (Interim Report 2).

DTIC Science & Technology

1985-09-01

THE ARCHAEOLOGY OF CORALVILLE LAKE, IOWA VOLUME IV: RECREATION AREA SURVEY (INTERIM REPORT II) p - [ JAN 1 4 1986 WAUWATOSA. WISCONSIN 86 1.13 117...THE ARCHAEOLOGY OF CORALVILLE LAKE, IOWA ; VOLUME IV: RECREATION AREA SURVEY (INTERIM REPORT II) Submitted To: Rock Island District Corps of Engineers...presents the results of intensive archaeological and geomorphic investigations at 14 special use or recreation areas at Coralville Lake, Iowa . The

Medicare and Medicaid programs; fire safety requirements for certain health care facilities; amendment. Interim final rule with comment period.

PubMed

2005-03-25

This interim final rule with comment period adopts the substance of the April 15, 2004 temporary interim amendment (TIA) 00-1 (101), Alcohol Based Hand Rub Solutions, an amendment to the 2000 edition of the Life Safety Code, published by the National Fire Protection Association (NFPA). This amendment will allow certain health care facilities to place alcohol-based hand rub dispensers in egress corridors under specified conditions. This interim final rule with comment period also requires that nursing facilities install smoke detectors in resident rooms and public areas if they do not have a sprinkler system installed throughout the facility or a hard-wired smoke detection system in those areas.

Used Nuclear Fuel: From Liability to Benefit

NASA Astrophysics Data System (ADS)

Orbach, Raymond L.

2011-03-01

Nuclear power has proven safe and reliable, with operating efficiencies in the U.S. exceeding 90%. It provides a carbon-free source of electricity (with about a 10% penalty arising from CO2 released from construction and the fuel cycle). However, used fuel from nuclear reactors is highly toxic and presents a challenge for permanent disposal -- both from technical and policy perspectives. The half-life of the ``bad actors'' is relatively short (of the order of decades) while the very long lived isotopes are relatively benign. At present, spent fuel is stored on-site in cooling ponds. Once the used fuel pools are full, the fuel is moved to dry cask storage on-site. Though the local storage is capable of handling used fuel safely and securely for many decades, the law requires DOE to assume responsibility for the used fuel and remove it from reactor sites. The nuclear industry pays a tithe to support sequestration of used fuel (but not research). However, there is currently no national policy in place to deal with the permanent disposal of nuclear fuel. This administration is opposed to underground storage at Yucca Mountain. There is no national policy for interim storage---removal of spent fuel from reactor sites and storage at a central location. And there is no national policy for liberating the energy contained in used fuel through recycling (separating out the fissionable components for subsequent use as nuclear fuel). A ``Blue Ribbon Commission'' has been formed to consider alternatives, but will not report until 2012. This paper will examine alternatives for used fuel disposition, their drawbacks (e.g. proliferation issues arising from recycling), and their benefits. For recycle options to emerge as a viable technology, research is required to develop cost effective methods for treating used nuclear fuel, with attention to policy as well as technical issues.

Capitation funding of primary health organisations in New Zealand: are enrolled populations being funded according to need?

PubMed

Langton, Jennifer; Crampton, Peter

2008-04-18

To determine whether the three main funding formulas for Primary Health Organisations achieved a stated aim of the Primary Health Care Strategy to fund enrolled populations according to need. National data were obtained from the Ministry of Health for a 12-month period beginning in April 2004: these included demographic characteristics of the enrolled Primary Health Organisation population, plus rates tables for: First-Contact Services, Services to Improve Access, and Health Promotion. Funding for Access and Interim practices for four-quarters was calculated for each of these three funding streams. Analysis of the demographic characteristics of Access and Interim practices was undertaken. Maori and Pacific peoples made up a greater proportion of the Access population than the Interim, had higher rates of deprivation than the non-Maori/non-Pacific population, and demonstrated a younger age distribution. The first quarter (April 2004-June 2004) showed there was preferential funding for Access PHOs and in particular high-needs groups. In quarter two, this level of preferential funding had diminished, coinciding with the introduction of increased government funding for all Interim enrolees aged 65 and over. The greater funding for Access enrolees was notably eroded with the introduction of Access-level funding for those aged 65+ in Interim PHOs. Since these data were analysed all remaining Interim age groups have shifted to Access-level funding, benefiting non-Maori /non-Pacific in Interim PHOs. The rapid shift to Access-level funding for First Contact Services has seen a continued erosion of the redistributive effect of the original needs-based formulas. A system cannot be considered equitable if some members of society are not realising their health potential, and financing of primary care should remain redistributive until such a time as this objective is attained.

FY2017 Defense Spending Under an Interim Continuing Resolution (CR): In Brief

DTIC Science & Technology

2016-09-16

rated based on the fraction of a year for which the interim CR is in effect . In recent fiscal years, the referenced funding level on which interim or...of the Federal Government: Causes, Processes, and Effects , coordinated by Clinton T. Brass. 8 Typically, such funding is specified as an annualized...congressional consideration of a CR to fund the federal government through the opening months of the fiscal year is widely anticipated. This report

Interim overdentures.

PubMed

Fenton, A H

1976-07-01

The construction of an interim overdenture using existing removable partial dentures with natural tooth crowns and artificial teeth can be a simple and economical method of providing patients with dentures while tissues heal and teeth are prepared and restored. A more definite prognosis for both the patient and his remaining dentition can be established before the final overdenture is completed. The procedures necessary to provide three types of interim overdentures have been outlined. Patients tolerate this method of changing their dentitions extremely well.

Predictive probability methods for interim monitoring in clinical trials with longitudinal outcomes.

PubMed

Zhou, Ming; Tang, Qi; Lang, Lixin; Xing, Jun; Tatsuoka, Kay

2018-04-17

In clinical research and development, interim monitoring is critical for better decision-making and minimizing the risk of exposing patients to possible ineffective therapies. For interim futility or efficacy monitoring, predictive probability methods are widely adopted in practice. Those methods have been well studied for univariate variables. However, for longitudinal studies, predictive probability methods using univariate information from only completers may not be most efficient, and data from on-going subjects can be utilized to improve efficiency. On the other hand, leveraging information from on-going subjects could allow an interim analysis to be potentially conducted once a sufficient number of subjects reach an earlier time point. For longitudinal outcomes, we derive closed-form formulas for predictive probabilities, including Bayesian predictive probability, predictive power, and conditional power and also give closed-form solutions for predictive probability of success in a future trial and the predictive probability of success of the best dose. When predictive probabilities are used for interim monitoring, we study their distributions and discuss their analytical cutoff values or stopping boundaries that have desired operating characteristics. We show that predictive probabilities utilizing all longitudinal information are more efficient for interim monitoring than that using information from completers only. To illustrate their practical application for longitudinal data, we analyze 2 real data examples from clinical trials. Copyright © 2018 John Wiley & Sons, Ltd.

Exploring the contribution of the Clinical Librarian to facilitating evidence-based nursing.

PubMed

Tod, Angela M; Bond, Beverly; Leonard, Niamh; Gilsenan, Irene J; Palfreyman, Simon

2007-04-01

To examine the potential role of the Clinical Librarian in facilitating evidence-based practice of nurses in acute hospital settings and develop a model for the role. There is a growing policy and professional expectation that nurses will seek out and apply evidence in their clinical practice. Studies have demonstrated that nurses experience barriers in working with an evidence-based approach. The role of Clinical Librarian has been used in other countries and within medicine to overcome some of the barriers to evidence-based practice. There are limitations in the previous work in terms of rigour of evaluation, scope of the Clinical Librarian role and application to nursing in a UK setting. A qualitative consultation of 72 nurses in acute care settings. Six consultation group interviews of between 4-19 participants. Written records were recorded by the scribe. Content analysis was undertaken to identify the range and frequency of comments. Clinical questions currently go unanswered because of barriers of time, skills deficits and access to resources. Literature searching, skills training and evidence dissemination were the main areas of work the staff requested that a Clinical Librarian should undertake. It was anticipated that the Clinical Librarian could interact and work productively with nursing staff with a limited but regular presence on the ward. Interim communication could be via e-mail, phone and written suggestions and requests for work. It was seen to be vital that the Clinical Librarian worked in partnership with staff to build evidence-based practice capacity and ensure clinical relevance of the work. This study has generated the first model for the Clinical Librarian role with an emphasis on nursing. It is derived from the views of clinical nurses. Recommendations are made for the implementation and evaluation of such a role. The Clinical Librarian could be an invaluable support to promoting evidence-based nursing.

Inter-Disciplinary Collaboration in Support of the Post-Standby TREAT Mission

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

DeHart, Mark; Baker, Benjamin; Ortensi, Javier

Although analysis methods have advanced significantly in the last two decades, high fidelity multi- physics methods for reactors systems have been under development for only a few years and are not presently mature nor deployed. Furthermore, very few methods provide the ability to simulate rapid transients in three dimensions. Data for validation of advanced time-dependent multi- physics is sparse; at TREAT, historical data were not collected for the purpose of validating three-dimensional methods, let alone multi-physics simulations. Existing data continues to be collected to attempt to simulate the behavior of experiments and calibration transients, but it will be insufficient formore » the complete validation of analysis methods used for TREAT transient simulations. Hence, a 2018 restart will most likely occur without the direct application of advanced modeling and simulation methods. At present, the current INL modeling and simulation team plans to work with TREAT operations staff in performing reactor simulations with MAMMOTH, in parallel with the software packages currently being used in preparation for core restart (e.g., MCNP5, RELAP5, ABAQUS). The TREAT team has also requested specific measurements to be performed during startup testing, currently scheduled to run from February to August of 2018. These startup measurements will be crucial in validating the new analysis methods in preparation for ultimate application for TREAT operations and experiment design. This document describes the collaboration between modeling and simulation staff and restart, operations, instrumentation and experiment development teams to be able to effectively interact and achieve successful validation work during restart testing.« less

How the University of Texas system responded to the need for interim storage of low-level radioactive waste materials.

PubMed

Emery, Robert J

2012-11-01

Faced with the prospect of being unable to permanently dispose of low-level radioactive wastes (LLRW) generated from teaching, research, and patient care activities, component institutions of the University of Texas System worked collaboratively to create a dedicated interim storage facility to be used until a permanent disposal facility became available. Located in a remote section of West Texas, the University of Texas System Interim Storage Facility (UTSISF) was licensed and put into operation in 1993, and since then has provided safe and secure interim storage for up to 350 drums of dry solid LLRW at any given time. Interim storage capability provided needed relief to component institutions, whose on-site waste facilities could have possibly become overburdened. Experiences gained from the licensing and operation of the site are described, and as a new permanent LLRW disposal facility emerges in Texas, a potential new role for the storage facility as a surge capacity storage site in times of natural disasters and emergencies is also discussed.

CMM Interim Check Design of Experiments (U)

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

Montano, Joshua Daniel

2015-07-29

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factorsmore » (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.« less

Industry Application ECCS / LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model

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

Zhang, Hongbin; Szilard, Ronaldo; Epiney, Aaron

Under the auspices of the DOE LWRS Program RISMC Industry Application ECCS/LOCA, INL has engaged staff from both South Texas Project (STP) and the Texas A&M University (TAMU) to produce a generic pressurized water reactor (PWR) model including reactor core, clad/fuel design and systems thermal hydraulics based on the South Texas Project (STP) nuclear power plant, a 4-Loop Westinghouse PWR. A RISMC toolkit, named LOCA Toolkit for the U.S. (LOTUS), has been developed for use in this generic PWR plant model to assess safety margins for the proposed NRC 10 CFR 50.46c rule, Emergency Core Cooling System (ECCS) performance duringmore » LOCA. This demonstration includes coupled analysis of core design, fuel design, thermalhydraulics and systems analysis, using advanced risk analysis tools and methods to investigate a wide range of results. Within this context, a multi-physics best estimate plus uncertainty (MPBEPU) methodology framework is proposed.« less

Current training initiatives at Nuclear Electric plc

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

Fowler, C.D.

1993-01-01

Nuclear Electric, one of the three generating companies to emerge from the demise of the U.K.'s Central Electricity Generating Board (CEGB), owns and operates the commercial nuclear power stations in England and Wales. The U.K. government proscribed further construction beyond Sizewell B, the United Kingdom's first pressurized water reactor (PWR) station, pending the outcome of a review of the future of nuclear power to be held in 1994. The major challenges facing Nuclear Electric at its formation in 1990 were therefore to demonstrate that nuclear power is safe, economical, and environmentally acceptable and to complete the PWR station under constructionmore » on time and within budget. A significant number of activities were started that were designed to increase output, reduce costs, and ensure that the previous excellent safety standards were maintained. A major activity was to reduce the numbers of staff employed, with a recognition from the outset that this reduction could only be achieved with a significant human resource development program. Future company staff would have to be competent in more areas and more productive. This paper summarizes some of the initiatives currently being pursued throughout the company and the progress toward ensuring that staff with the required competences are available to commission and operate the Sizewell B program in 1994.« less

Implementation of EPA criminal enforcement strategy for RCRA interim status facilities

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

Not Available

1985-11-15

The directive discusses criminal enforcement priorities and procedures related to the RCRA section 3007(e)(2) Loss of Interim Status (LOIS) provision, including: (1) identifying/targeting facilities with violations, (2) verifying receipt of RCRA 3007 letters, and (3) inspections of facilities. The directive supplements directive no. 9930.0-1 RCRA LOIS Enforcement Strategy, dated October 15, 1985. The directive is supplemented by directive no. 9930.0-2a, Accepting Nonhazardous Waste After Losing Interim Status, dated December 20, 1986.

Implementation of the Ryan Haight Online Pharmacy Consumer Protection Act of 2008. Interim final rule with request for comments.

PubMed

2009-04-06

The Ryan Haight Online Pharmacy Consumer Protection Act, which was enacted on October 15, 2008, amended the Controlled Substances Act and Controlled Substances Import and Export Act by adding several new provisions to prevent the illegal distribution and dispensing of controlled substances by means of the Internet. DEA is hereby issuing an interim rule to amend its regulations to implement the legislation and is requesting comments on the interim rule.

Evaluation and analysis of Seasat-A scanning multichannel Microwave Radiometer (SMMR) Antenna Pattern Correction (APC) algorithm

NASA Technical Reports Server (NTRS)

Kitzis, J. L.; Kitzis, S. N.

1979-01-01

The brightness temperature data produced by the SMMR final Antenna Pattern Correction (APC) algorithm is discussed. The algorithm consisted of: (1) a direct comparison of the outputs of the final and interim APC algorithms; and (2) an analysis of a possible relationship between observed cross track gradients in the interim brightness temperatures and the asymmetry in the antenna temperature data. Results indicate a bias between the brightness temperature produced by the final and interim APC algorithm.

Conceptual design statement of work for the immobilized low-activity waste interim storage facility project

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

Carlson, T.A., Fluor Daniel Hanford

1997-02-06

The Immobilized Low-Activity Waste Interim Storage subproject will provide storage capacity for immobilized low-activity waste product sold to the U.S. Department of Energy by the privatization contractor. This statement of work describes the work scope (encompassing definition of new installations and retrofit modifications to four existing grout vaults), to be performed by the Architect-Engineer, in preparation of a conceptual design for the Immobilized Low-Activity Waste Interim Storage Facility.

22 CFR 127.8 - Interim suspension.

Code of Federal Regulations, 2010 CFR

2010-04-01

... world peace or the security or foreign policy of the United States. The interim suspension orders... Trade Controls will issue an appropriate order disposing of the motion or petition and will promptly...

How well do Reanalysis represent polar lows?

NASA Astrophysics Data System (ADS)

Zappa, G.; Shaffrey, L.; Hodges, K.

2013-12-01

Polar lows are intense maritime mesocyclones forming at high latitudes during polar air outbreaks. The associated high surface winds can be an important cause of coastal damage.They also seem to play a relevant role in the climate system by modulating the oceanic surface heat fluxes. This creates strong interest in understanding whether modern reanalysis datasets are able to represent polar lows, as well as how their representation may be sensitive to the model resolution. In this talk we investigate how ERA-Interim reanalysis represents the polar lows identified by the Norwegian meteorological services and listed in the STARS (Combination of Sea Surface Temperature and AltimeteR Synergy) dataset for the period 2002-2011. The sensitivity to resolution is explored by comparing ERA-Interim to the ECMWF operational analyses (2008-2011), which have three times higher horizontal resolution compared to ERA-Interim. We show that ERAI-Interim has excellent ability to capture the observed polar lows events with up to 90% of the observed events being found in the reanalysis. However, ERA-Interim tends to have polar lows of weaker dynamical intensity, in terms of both winds and vorticity, and with less spatial structure than in the ECMWF operational analyses (See Fig 1). Furthermore, we apply an objective feature tracking algorithm to the 3 hourly vorticity at 850 hPa with constraints on vorticity intensity and atmospheric static stability to objectively identify polar lows in the ERA-Interim reanalysis. We show that for the stronger polar lows the objective climatology shows good agreement with the STARS dataset over the 2002-2011 period. This allows us to extend the polar lows climatology over the whole ERA Interim period. Differences with another reanalysis product (NCEP-CFSR) will be also discussed. Fig 1: Composite of the tangential wind speed at 925 hPa for 34 polar lows observed in the Norwegian sea between 2008-2010 as represented by the ERA-Interim reanalysis (left) and by the ECMWF Operational analysis (right). Positive values indicate cyclonic circulation. The composite is centered on the polar low vorticity maxima and it is presented for a radial cap of 5 degrees of radius on the sphere (~550Km).

Registration Review Schedules

EPA Pesticide Factsheets

This schedule indicates plans for completion of risk assessments, proposed interim decisions and interim decisions for pesticides in the Registration Review program, EPA reviews all registered pesticides at least every 15 years as required by FIFRA.

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

Soldaini, Michel

The first heading of your manuscript must be 'Introduction'. Phenix is the only remaining French fast breeder reactor after the shutdown of Superphenix (1999) and Rapsodie (1983). Phenix is located inside the Marcoule nuclear site along the Rhone river near Bagnols-sur-Ceze in southeastern France. Phenix is one of the facilities belonging the French Atomic Energy Commission (CEA) on the Marcoule site. It is a fast breeder reactor (FBR) developed at the end of the 1960's. that has been in operation since 1973 and was connected to the power grid in 1974. It is a second generation prototype developed while themore » first generation FBR, Rapsodie, was still in operation. Phenix is a 250 electrical MW power plant. During the first 20 years of operation, its main aim was to demonstrate the viability of sodium-cooled FBRs. Since the 1991 radioactive waste management act, Phenix has become an irradiation tool for the actinide transmutation program. To extend its operating life for 6 additional cycles, it was necessary to refurbish the plant; this involved major work performed from 1999 to 2003 at a total cost of about 250 M??. Today, with a realistic expectation, the final shutdown is planned for the beginning of 2009. The main objective of the Phenix dismantling project is to eliminate all the process equipment and clean all the building to remove all the radioactive zones. To reach this objective, three main hazards must be eliminated: Fuel (criticality hazard), Sodium, Radioactive equipment. The complexity of decommissioning a facility such as Phenix is increased by: - the lack of storage facility for high radioactive material, - the decision to treat all the radioactive sodium and sodium waste inside the plant, - the very high irradiation of the core structures due to the presence of cobalt alloys. On the other hand, Phenix plant is still under operating with a qualified staff and the radioactivity coming from structural activation is well known. After the final shutdown, the first operations will be conducted by the same staff under the same safety report. Another interesting fact is that the decommissioning funds project exist and are available. The CEA decided to begin the dismantling phase without waiting because after a period of decay it is not really cheaper or easier to work. This approach needs interim storage facilities not long after the final shutdown. For the low- and intermediate-level radioactive waste there are national storage centers but for the high-level wastes, each operator must manage its waste until a suitable disposal site is available. At Marcoule a new storage facility is now being designed and scheduled to begin operating after 2013-2014. After removal of the fuel and core elements, the primary sodium will be drained and eliminated by a carbonation process. To ensure biological shielding, the reference scenario calls for filling the primary vessel with water. The most radioactive structures (dia-grid and core support) will be cut up with remote tools, after which the rest of the structure will be cut up manually. Phenix contains about 1450 metric tons of sodium. The CEA initially planned to build ATENA, a new facility for all radioactive sodium waste from R and D and FBR facilities. For various reasons, but mainly to save money, the CEA decided to treat all radioactive sodium and sodium waste in the framework of the Phenix dismantling project. There are no real difficulties in the dismantling schedule because of the advanced state of development of the processes selected for the ATENA project. Because of the knowledge already obtained, the issues concern project management, waste management and human resources reduction more than technical 0014challe.« less

45 CFR 689.8 - Interim administrative actions.

Code of Federal Regulations, 2011 CFR

2011-10-01

... RESEARCH MISCONDUCT § 689.8 Interim administrative actions. (a) After an inquiry or during an external or... misconduct. Such an order will normally be issued on recommendation from OIG and in consultation with the...

45 CFR 689.8 - Interim administrative actions.

Code of Federal Regulations, 2012 CFR

2012-10-01

... RESEARCH MISCONDUCT § 689.8 Interim administrative actions. (a) After an inquiry or during an external or... misconduct. Such an order will normally be issued on recommendation from OIG and in consultation with the...

45 CFR 689.8 - Interim administrative actions.

Code of Federal Regulations, 2010 CFR

2010-10-01

... RESEARCH MISCONDUCT § 689.8 Interim administrative actions. (a) After an inquiry or during an external or... misconduct. Such an order will normally be issued on recommendation from OIG and in consultation with the...

45 CFR 689.8 - Interim administrative actions.

Code of Federal Regulations, 2013 CFR

2013-10-01

... RESEARCH MISCONDUCT § 689.8 Interim administrative actions. (a) After an inquiry or during an external or... misconduct. Such an order will normally be issued on recommendation from OIG and in consultation with the...

45 CFR 689.8 - Interim administrative actions.

Code of Federal Regulations, 2014 CFR

2014-10-01

... RESEARCH MISCONDUCT § 689.8 Interim administrative actions. (a) After an inquiry or during an external or... misconduct. Such an order will normally be issued on recommendation from OIG and in consultation with the...

7 CFR 1710.109 - Reimbursement of general funds and interim financing.

Code of Federal Regulations, 2010 CFR

2010-01-01

... be limited, except in cases of extreme financial hardship as determined by the Administrator, to the...) Policies for reimbursement of general funds and interim financing following certain mergers, consolidations...

Preventive maintenance study : interim report.

DOT National Transportation Integrated Search

2017-09-01

This interim report details the performance of 69 test sites treated with various preventive maintenance treatments. The maintenance treatments applied included crack sealing, full lane chip sealing, wheel path chip sealing, dig outs (mill and fill),...

Interim Open Source Software (OSS) Policy

EPA Pesticide Factsheets

This interim Policy establishes a framework to implement the requirements of the Office of Management and Budget's (OMB) Federal Source Code Policy to achieve efficiency, transparency and innovation through reusable and open source software.

75 FR 47444 - Amendments to the Informal and Other Procedures, Rules of Organization and Program Management...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-08-06

... Practice; Interim Commission Review of Public Company Accounting Oversight Board Inspection Reports and... facilitate interim Commission review of Public Company Accounting Oversight Board [[Page 47445

Interim Policy for Evaluation of Stereoisomeric Pesticides

EPA Pesticide Factsheets

An interim approach for determining data requirements for non-racemic mixtures of stereoisomeric pesticides. These data are needed in order to assess the risk posed to ecosystems and drinking water sources by these mixtures.

EPA's Revised Interim Financial Assistance Conflict of Interest Policy

EPA Pesticide Factsheets

EPA has established the following revised interim policy governing disclosure of actual and potential conflicts of interest (COI Policy) by applicants for, and recipients of, federal financial assistance awards from EPA.

An allowable cladding peak temperature for spent nuclear fuels in interim dry storage

NASA Astrophysics Data System (ADS)

Cha, Hyun-Jin; Jang, Ki-Nam; Kim, Kyu-Tae

2018-01-01

Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens were heated up to various temperatures and then cooled down under tensile hoop stresses. Cool-down specimens indicate that higher heat-up temperature and larger tensile hoop stress generated larger radial hydride precipitation and smaller tensile strength and plastic hoop strain. Unirradiated specimens generated relatively larger radial hydride precipitation and plastic strain than did neutron irradiated specimens. Assuming a minimum plastic strain requirement of 5% for cladding integrity maintenance in interim dry storage, it is proposed that a cladding peak temperature during the interim dry storage is to keep below 250 °C if cladding tubes are cooled down to room temperature.

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

The role and meaning of interim housing in housing first programs for people experiencing homelessness and mental illness.

PubMed

Zerger, Suzanne; Francombe Pridham, Katherine; Jeyaratnam, Jeyagobi; Connelly, Jolynn; Hwang, Stephen; O'Campo, Patricia; Stergiopoulos, Vicky

2014-07-01

The housing first (HF) model for individuals experiencing homelessness and mental illness differs by design from traditional models that require consumers to achieve "housing readiness" by meeting program or treatment prerequisites in transitional housing settings prior to permanent housing placement. Given a growing body of evidence for its favorable outcomes and cost effectiveness, HF is increasingly seen as an alternative to and argument against these traditional programs. As such, it is important that the elements and implementation challenges of the HF model be clearly understood and articulated. This qualitative study explored a largely unexamined aspect of the HF model-the need for and meaning of temporary residential settings (interim housing), a place to stay while waiting to secure permanent housing-using interviews and focus groups with service providers and consumers who experienced interim housing during implementation of HF in a large urban center. Although interim housing may not be necessary for all programs implementing the model, our study revealed numerous reasons and demands for safe, flexible interim housing options, and illustrated how they influence the effectiveness of consumer recovery, continuous service engagement, and housing stability.

What a Difference a Day Makes: Change in Memory for Newly Learned Word Forms Over 24 Hours

PubMed Central

McGregor, Karla K.

2014-01-01

Purpose This study explored the role of time and retrieval experience in the consolidation of word forms. Method Participants were 106 adults trained on 16 novel word-referent pairs, then tested immediately and 24 hr later for recognition and recall of word forms. In the interim, tests were repeated 2 hr or 12 hr after training, or not at all, thus varying the amount and timing of retrieval experience. Results Recognition accuracy was stable and speed improved over the 24-hr period. But these manifestations of consolidation did not depend on interim retrieval experience; in fact, the 2-hr interim test interfered with improvements in speed. In contrast, the number of word forms recalled increased only with interim retrieval experiences, and the 12-hr interim test was more advantageous to recall than the 2-hr test. Conclusions After a word form is encoded, it can become stronger with time. Retrieval experience can also strengthen the trace, but, if retrieval occurs when the memory is still labile, it can be disruptive. This complex interplay between retrieval experience and time holds implications for measuring learning outcomes and for scheduling practice in classrooms and clinics. PMID:24845578

Interim report : a non-overlay cathodic protection system.

DOT National Transportation Integrated Search

1983-01-01

This interim report describes Virginia's experience in installing its first cathodic protection system for a bridge deck. The installation was completed with practically no problems. Very minor problems have been encountered with the rectifier/contro...

Amendment to the interim final rules for group health plans and health insurance coverage relating to status as a grandfathered health plan under the Patient Protection and Affordable Care Act. Amendment to interim final rules with request for comments.

PubMed

2010-11-17

This document contains an amendment to interim final regulations implementing the rules for group health plans and health insurance coverage in the group and individual markets under provisions of the Patient Protection and Affordable Care Act regarding status as a grandfathered health plan; the amendment permits certain changes in policies, certificates, or contracts of insurance without loss of grandfathered status.

PCoD Lite - Using an Interim PCoD Protocol to Assess the Effects of Disturbance Associated with US Navy Exercises on Marine Mammal Populations

DTIC Science & Technology

2014-09-30

1 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. PCoD Lite - Using an Interim PCoD Protocol to Assess...Skookum Tom Road Friday Harbor, WA, USA phone: 1-360-370-5493 email: jw@smrullc.com Award Number: N000141410406 http://www.smrumarine.com/ pcod ...DATE 30 SEP 2014 2. REPORT TYPE 3. DATES COVERED 00-00-2014 to 00-00-2014 4. TITLE AND SUBTITLE PCoD Lite - Using an Interim PCoD Protocol to

Interim Radiological Scoping and Characterization Survey Report, 1963 Igloo 572 Accident (Former Medina Base), Lackland Training Annex, Lackland AFB, Texas

DTIC Science & Technology

2002-03-01

9045 4 8985 4 9001 5 8804 5 8893 Mean: 8788.8 Mean: 8925.4 Expected S.D.: 93.7 Expected S.D.: 94.5 Standard Dev.: 136.9 Standard Dev.: 107.4 Variance...subject to lit]) severe criminal penalties. Dissemination in 200204 5 042accordance with DoD Directive 5230.25" Air Force Institute for Environment...COVERED March 2002 INTERIM (2001 - 2002) 4. TITLE AND SUBTITLE 5 . FUNDING NUMBERS Interim Radiological Scoping and Characterization Survey Report, 1963

Interim Land Use Control Implementation Plan

NASA Technical Reports Server (NTRS)

Applegate, Joseph L.

2014-01-01

This Interim Land Use Control Implementation Plan (LUCIP) has been prepared to inform current and potential future users of the Kennedy Space Center (KSC) Contractors Road Heavy Equipment (CRHE) Area (SWMU 055; "the Site") of institutional controls that have been implemented at the Site1. Although there are no current unacceptable risks to human health or the environment associated with the CRHE Area, an interim institutional land use control (LUC) is necessary to prevent human health exposure to volatile organic compound (VOC)-affected groundwater at the Site. Controls will include periodic inspection, condition certification, and agency notification.

Integrated waste management system costs in a MPC system

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

Supko, E.M.

1995-12-01

The impact on system costs of including a centralized interim storage facility as part of an integrated waste management system based on multi-purpose canister (MPC) technology was assessed in analyses by Energy Resources International, Inc. A system cost savings of $1 to $2 billion occurs if the Department of Energy begins spent fuel acceptance in 1998 at a centralized interim storage facility. That is, the savings associated with decreased utility spent fuel management costs will be greater than the cost of constructing and operating a centralized interim storage facility.

A randomized controlled trial of interim methadone maintenance.

PubMed

Schwartz, Robert P; Highfield, David A; Jaffe, Jerome H; Brady, Joseph V; Butler, Carol B; Rouse, Charles O; Callaman, Jason M; O'Grady, Kevin E; Battjes, Robert J

2006-01-01

Effective alternatives to long waiting lists for entry into methadone hydrochloride maintenance treatment are needed to reduce the complications of continuing heroin dependence and to increase methadone treatment entry. To compare the effectiveness of interim methadone maintenance with that of the usual waiting list condition in facilitating methadone treatment entry and reducing heroin and cocaine use and criminal behavior. Randomized, controlled, clinical trial using 2 conditions, with treatment assignment on a 3:2 basis to interim maintenance-waiting list control. A methadone treatment program in Baltimore. A total of 319 individuals meeting the criteria for current heroin dependence and methadone maintenance treatment. Participants were randomly assigned to either interim methadone maintenance, consisting of an individually determined methadone dose and emergency counseling only for up to 120 days, or referral to community-based methadone treatment programs. Entry into comprehensive methadone maintenance therapy at 4 months from baseline; self-reported days of heroin use, cocaine use, and criminal behavior; and number of urine drug test results positive for heroin and cocaine at the follow-up interview conducted at time of entry into comprehensive methadone treatment (or at 4 months from baseline for participants who did not enter regular treatment). Significantly more participants assigned to the interim methadone maintenance condition entered comprehensive methadone maintenance treatment by the 120th day from baseline (75.9%) than those assigned to the waiting list control condition (20.8%) (P<.001). Overall, in the past 30 days at follow-up, interim participants reported significantly fewer days of heroin use (P<.001), had a significant reduction in heroin-positive drug test results (P<.001), reported spending less money on drugs (P<.001), and received less illegal income (P<.02) than the waiting list participants. Interim methadone maintenance results in a substantial increase in the likelihood of entry into comprehensive treatment, and is an effective means of reducing heroin use and criminal behavior among opioid-dependent individuals awaiting entry into a comprehensive methadone treatment program.

5th ESA Workshop on Joint Interim Approaches to NAS Recommendations

EPA Pesticide Factsheets

EPA and its federal partners, Fish and Wildlife Service and National Marine Fisheries Service, held a two-day meeting that provided a forum for stakeholder suggestions for refining some of the interim scientific methods

77 FR 31374 - Notice of Submission of Proposed Information Collection to OMB; Rural Housing Stability Program...

Federal Register 2010, 2011, 2012, 2013, 2014

2012-05-25

... through the HEARTH Act. The statutory provisions and the implementing interim regulations that govern RHSP... HEARTH Act. The statutory provisions and the implementing interim regulations that govern RHSP require...

Intelligent cruise control field operational test : interim report

DOT National Transportation Integrated Search

1997-03-01

This interim document reports on a cooperative agreement between NHTSA and UMTRI entitled Intelligent Cruise Control (ICC) Field Operational Test (FOT). The overarching goal of the work is to characterize safety and comfort issues that are fundamenta...

Computerization of material test data reporting system : interim report.

DOT National Transportation Integrated Search

1973-09-01

This study was initiated to provide an integrated system of reporting, storing, and retrieving of construction and material test data using computerized (storage-retrieval) and quality control techniques. The findings reported in this interim report ...

A quality assurance audit: phase III trial of maximal androgen deprivation in prostate cancer (TROG 96.01).

PubMed

Steigler, A; Mameghan, H; Lamb, D; Joseph, D; Matthews, J; Franklin, I; Turner, S; Spry, N; Poulsen, M; North, J; Kovacev, O; Denham, J

2000-02-01

In 1997 the Trans-Tasman Radiation Oncology Group (TROG) performed a quality assurance (QA) audit of its phase III randomized clinical trial investigating the effectiveness of different durations of maximal androgen deprivation prior to and during definitive radiation therapy for locally advanced carcinoma of the prostate (TROG 96.01). The audit reviewed a total of 60 cases from 15 centres across Australia and New Zealand. In addition to verification of technical adherence to the protocol, the audit also incorporated a survey of centre planning techniques and a QA time/cost analysis. The present report builds on TROG's first technical audit conducted in 1996 for the phase III accelerated head and neck trial (TROG 91.01) and highlights the significant progress TROG has made in the interim period. The audit provides a strong validation of the results of the 96.01 trial, as well as valuable budgeting and treatment planning information for future trials. Overall improvements were detected in data quality and quantity, and in protocol compliance, with a reduction in the rate of unacceptable protocol violations from 10 to 4%. Audit design, staff education and increased data management resources were identified as the main contributing factors to these improvements. In addition, a budget estimate of $100 per patient has been proposed for conducting similar technical audits. The next major QA project to be undertaken by TROG during the period 1998-1999 is an intercentre dosimetry study. Trial funding and staff education have been targeted as the key major issues essential to the continued success and expansion of TROG's QA programme.

Cleaning products and work-related asthma.

PubMed

Rosenman, Kenneth D; Reilly, Mary Jo; Schill, Donald P; Valiante, David; Flattery, Jennifer; Harrison, Robert; Reinisch, Florence; Pechter, Elise; Davis, Letitia; Tumpowsky, Catharine M; Filios, Margaret

2003-05-01

To describe the characteristics of individuals with work-related asthma associated with exposure to cleaning products, data from the California-, Massachusetts-, Michigan-, and New Jersey state-based surveillance systems of work-related asthma were used to identify cases of asthma associated with exposure to cleaning products at work. From 1993 to 1997, 236 (12%) of the 1915 confirmed cases of work-related asthma identified by the four states were associated with exposure to cleaning products. Eighty percent of the reports were of new-onset asthma and 20% were work-aggravated asthma. Among the new-onset cases, 22% were consistent with reactive airways dysfunction syndrome. Individuals identified were generally women (75%), white non-Hispanic (68%), and 45 years or older (64%). Their most likely exposure had been in medical settings (39%), schools (13%), or hotels (6%), and they were most likely to work as janitor/cleaners (22%), nurse/nurses' aides (20%), or clerical staff (13%). However, cases were reported with exposure to cleaning products across a wide range of job titles. Cleaning products contain a diverse group of chemicals that are used in a wide range of industries and occupations as well as in the home. Their potential to cause or aggravate asthma has recently been recognized. Further work to characterize the specific agents and the circumstances of their use associated with asthma is needed. Additional research to investigate the frequency of adverse respiratory effects among regular users, such as housekeeping staff, is also needed. In the interim, we recommend attention to adequate ventilation, improved warning labels and Material Safety Data Sheets, and workplace training and education.

2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

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

D. Shanklin

2006-07-19

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities fro the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13,more » Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003.« less

2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

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

D. E. Shanklin

2007-02-14

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action ismore » functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772).« less

Using ERA-Interim reanalysis for creating datasets of energy-relevant climate variables

NASA Astrophysics Data System (ADS)

Jones, Philip D.; Harpham, Colin; Troccoli, Alberto; Gschwind, Benoit; Ranchin, Thierry; Wald, Lucien; Goodess, Clare M.; Dorling, Stephen

2017-07-01

The construction of a bias-adjusted dataset of climate variables at the near surface using ERA-Interim reanalysis is presented. A number of different, variable-dependent, bias-adjustment approaches have been proposed. Here we modify the parameters of different distributions (depending on the variable), adjusting ERA-Interim based on gridded station or direct station observations. The variables are air temperature, dewpoint temperature, precipitation (daily only), solar radiation, wind speed, and relative humidity. These are available on either 3 or 6 h timescales over the period 1979-2016. The resulting bias-adjusted dataset is available through the Climate Data Store (CDS) of the Copernicus Climate Change Data Store (C3S) and can be accessed at present from ftp://ecem.climate.copernicus.eu. The benefit of performing bias adjustment is demonstrated by comparing initial and bias-adjusted ERA-Interim data against gridded observational fields.

The WFIRST Interim Design Reference Mission: Capabilities, Constraints, and Open Questions

NASA Technical Reports Server (NTRS)

Kruk, Jeffrey W.

2012-01-01

The Project Office and Science Definition Team for the Wide-Field Infrared Survey Telescope (WFIRST) are in the midst of a pre-Phase A study to establish a Design Reference Mission (DRM). An Interim report was released in June 2011, with a final report due later in 2012. The predicted performance of the Interim DRM Observatory will be described, including optical quality, observing efficiency, and sensitivity for representative observing scenarios. Observing constraints and other limitations on performance will also be presented, with an emphasis on potential Guest Observer programs. Finally, a brief status update will be provided on open trade studies of interest to the scientific community. The final DRM may differ from the Interim DRM presented here. However, the underlying requirements of the scientific programs are not expected to change, hence the capabilities of the IDRM are likely to be maintained even if the implementation changes in significant ways.

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

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

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi

2013-07-01

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these includemore » the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)« less

Long-term high-level waste technology. Composite report

NASA Astrophysics Data System (ADS)

Cornman, W. R.

1981-12-01

Research and development studies on the immobilization of high-level wastes from the chemical reprocessing of nuclear reactor fuels are summarized. The reports are grouped under the following tasks: (1) program management and support; (2) waste preparation; (3) waste fixation; and (4) final handling. Some of the highlights are: leaching properties were obtained for titanate and tailored ceramic materials being developed at ICPP to immobilize zirconia calcine; comparative leach tests, hot-cell tests, and process evaluations were conducted of waste form alternatives to borosilicate glass for the immobilization of SRP high-level wastes, experiments were run at ANL to qualify neutron activation analysis and radioactive tracers for measuring leach rates from simulated waste glasses; comparative leach test samples of SYNROC D were prepared, characterized, and tested at LLNL; encapsulation of glass marbles with lead or lead alloys was demonstrated on an engineering scale at PNL; a canister for reference Commercial HLW was designed at PNL; a study of the optimization of salt-crete was completed at SRL; a risk assessment showed that an investment for tornado dampers in the interim storage building of the DWPF is unjustified.

Latex and microsilica modified concrete bridge deck overlays in Oregon : interim report.

DOT National Transportation Integrated Search

1994-08-01

This interim report presented information collected from 24 bridge deck overlays constructed in Oregon between 1989 and 1993. Decks were placed on a variety of existing structures using hydroblasting, milling and diamond grinding surface preparation....

Autonomy Level Specification for Intelligent Autonomous Vehicles

DTIC Science & Technology

2003-09-01

Autonomy Level Specification for Intelligent Autonomous Vehicles : Interim Progress Report Hui-Min Huang, Elena Messina, James Albus...Level Specification for Intelligent Autonomous Vehicles : Interim Progress Report 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6

Evaluation of experimental rumble strip areas in Louisiana : interim report No. 1.

DOT National Transportation Integrated Search

1985-03-01

This interim report was prepared to provide a review of nineteen rumble strip areas installed experimentally in Louisiana between August 1982 and September 1983. Situated randomly throughout central and southern Louisiana, construction of these coars...

78 FR 53183 - Request for Public Comments Regarding the Interim Environmental Review of the Trans-Pacific...

Federal Register 2010, 2011, 2012, 2013, 2014

2013-08-28

... Agreement (TPP). The interim environmental review will be available at: http://www.ustr.gov/trade-topics... available at: http://www.ustr.gov/trade-topics/environment/environmental-reviews . The purpose of...

Interim Assessment of the VAL Automated Guideway Transit System.

DOT National Transportation Integrated Search

1981-11-01

This report describes an interim assessment of the VAL (Vehicules Automatiques Legers or Light Automated Vehicle) AGT system which is currently under construction in Lille, France, and which is to become fully operational in December 1983. This repor...

Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit

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

Wagner, J.C.

2001-09-28

The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory Commission's (U.S. NRC) Spent Fuel Project Office recommends restricting the use of burnup credit to assemblies that have not used burnable absorbers. This recommended restriction eliminates a large portion of the currently discharged spent fuel assemblies from cask loading, and thus severely limits the practical usefulness of burnup credit. In the absence of readily available information on burnable poison rod (BPR) design specifications and usage in U.S. pressurized-water-reactors (PWRs), and the subsequent reactivity effect of BPR exposure on discharged spent nuclear fuel (SNF), NRC staffmore » has indicated a need for additional information in these areas. In response, this report presents a parametric study of the effect of BPR exposure on the reactivity of SNF for various BPR designs, fuel enrichments, and exposure conditions, and documents BPR design specifications. Trends in the reactivity effects of BPRs are established with infinite pin-cell and assembly array calculations with the SCALE and HELIOS code packages, respectively. Subsequently, the reactivity effects of BPRs for typical initial enrichment and burnup combinations are quantified based on three-dimensional (3-D) KENO V.a Monte Carlo calculations with a realistic rail-type cask designed for burnup credit. The calculations demonstrate that the positive reactivity effect due to BPR exposure increases nearly linearly with burnup and is dependent on the number, poison loading, and design of the BPRs and the initial fuel enrichment. Expected typical reactivity increases, based on one-cycle BPR exposure, were found to be less than 1% {Delta}k. Based on the presented analysis, guidance is offered on an appropriate approach for calculating bounding SNF isotopic data for assemblies exposed to BPRs. Although the analyses do not address the issue of validation of depletion methods for assembly designs with BPRs, they do demonstrate that the effect of BPRs is generally well behaved and that independent codes and cross-section libraries predict similar results. The report concludes with a discussion of the issues for consideration and recommendations for inclusion of SNF assemblies exposed to BPRs in criticality safety analyses using burnup credit for dry cask storage and transport.« less

Results of a nuclear power plant application of A New Technique for Human Error Analysis (ATHEANA)

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

Whitehead, D.W.; Forester, J.A.; Bley, D.C.

1998-03-01

A new method to analyze human errors has been demonstrated at a pressurized water reactor (PWR) nuclear power plant. This was the first application of the new method referred to as A Technique for Human Error Analysis (ATHEANA). The main goals of the demonstration were to test the ATHEANA process as described in the frame-of-reference manual and the implementation guideline, test a training package developed for the method, test the hypothesis that plant operators and trainers have significant insight into the error-forcing-contexts (EFCs) that can make unsafe actions (UAs) more likely, and to identify ways to improve the method andmore » its documentation. A set of criteria to evaluate the success of the ATHEANA method as used in the demonstration was identified. A human reliability analysis (HRA) team was formed that consisted of an expert in probabilistic risk assessment (PRA) with some background in HRA (not ATHEANA) and four personnel from the nuclear power plant. Personnel from the plant included two individuals from their PRA staff and two individuals from their training staff. Both individuals from training are currently licensed operators and one of them was a senior reactor operator on shift until a few months before the demonstration. The demonstration was conducted over a 5-month period and was observed by members of the Nuclear Regulatory Commission`s ATHEANA development team, who also served as consultants to the HRA team when necessary. Example results of the demonstration to date, including identified human failure events (HFEs), UAs, and EFCs are discussed. Also addressed is how simulator exercises are used in the ATHEANA demonstration project.« less

Fluor Hanford ALARA Center is a D and D Resource

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

Waggoner, L.O.

2008-01-15

The mission at the Hanford Nuclear Reservation changed when the last reactor plant was shut down in 1989 and work was started to place all the facilities in a safe condition and begin decontamination, deactivation, decommissioning, and demolition (D and D). These facilities consisted of old shutdown reactor plants, spent fuel pools, processing facilities, and 177 underground tanks containing 53 million gallons of highly radioactive and toxic liquids and sludge. New skills were needed by the workforce to accomplish this mission. By 1995, workers were in the process of getting the facilities in a safe condition and it became obviousmore » improvements were needed in their tools, equipment and work practices. The Hanford ALARA Program looked good on paper, but did little to help contractors that were working in the field. The Radiological Control Director decided that the ALARA program needed to be upgraded and a significant improvement could be made if workers had a place they could visit that had samples of the latest technology and could talk to experienced personnel who have had success doing D and D work. Two senior health physics personnel who had many years experience in doing radiological work were chosen to obtain tools and equipment from vendors and find a location centrally located on the Hanford site. Vendors were asked to loan their latest tools and equipment for display. Most vendors responded and the Hanford ALARA Center of Technology opened on October 1, 1996. Today, the ALARA Center includes a classroom for conducting training and a mockup area with gloveboxes. Two large rooms have a containment tent, several glove bags, samples of fixatives/expandable foam, coating displays, protective clothing, heat stress technology, cutting tools, HEPA filtered vacuums, ventilation units, pumps, hydraulic wrenches, communications equipment, shears, nibblers, shrouded tooling, and several examples of innovative tools developed by the Hanford facilities. See Figures I and II. The ALARA Center staff routinely researches and tests new technology, sponsor vendor demonstrations, and redistribute tools, equipment and temporary shielding that may not be needed at one facility to another facility that needs it. The ALARA Center staff learns about new technology in several ways. This includes past radiological work experience, interaction with vendors, lessons learned, networking with other DOE sites, visits to the Hanford Technical Library, attendance at off-site conferences and ALARA Workshops. Personnel that contact the ALARA Center for assistance report positive results when they implement the tools, equipment and work practices recommended by the ALARA Center staff. This has translated to reduced exposure for workers and reduced the risk of contamination spread. For example: using a hydraulic shear on one job saved 16 Rem of exposure that would have been received if workers had used saws-all tools to cut piping in twenty-nine locations. Currently, the ALARA Center staff is emphasizing D and D techniques on size-reducing materials, decontamination techniques, use of remote tools/video equipment, capture ventilation, fixatives, using containments and how to find lessons learned. The ALARA Center staff issues a weekly report that discusses their interaction with the workforce and any new work practices, tools and equipment being used by the Hanford contractors. Distribution of this weekly report is to about 130 personnel on site and 90 personnel off site. This effectively spreads the word about ALARA throughout the DOE Complex. DOE EM-23, in conjunction with the D and D and Environmental Restoration work group of the Energy Facility Contractors Organization (EFCOG) established the Hanford ALARA Center as the D and D Hotline for companies who have questions about how D and D work is accomplished. The ALARA Center has become a resource to the nuclear industry and routinely helps contractors at other DOE Sites, power reactors, DOD sites, and sites in England, Europe and Indonesia. Other ALARA Centers are located at the Savannah River Site and Los Alamos National Lab.« less

Acoustic emission monitoring of steel bridge members : interim report.

DOT National Transportation Integrated Search

1995-01-01

This interim report describes the current status of acoustic emission (AE) monitoring of steel bridge members. The report includes a brief introduction to the theory of acoustic emission and a comprehensive summary of previous efforts to apply AE mon...

33 CFR 385.38 - Interim goals.

Code of Federal Regulations, 2010 CFR

2010-07-01

.... (ii) Improvement in water quality; including: (A) Total phosphorus concentrations in the Everglades...) Increases in total spatial extent of restored wetlands; (B) Improvement in habitat quality; and (C... implementation process. In addition, interim goals will facilitate adaptive management and allow the Corps of...

16 CFR 1209.1 - Scope and application.

Code of Federal Regulations, 2014 CFR

2014-01-01

... Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS INTERIM... part 1209, an interim consumer product safety standard, prescribes flame resistance and corrosiveness requirements for cellulose insulation that is a consumer product. These requirements are intended to reduce or...

16 CFR 1209.1 - Scope and application.

Code of Federal Regulations, 2011 CFR

2011-01-01

... Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS INTERIM... part 1209, an interim consumer product safety standard, prescribes flame resistance and corrosiveness requirements for cellulose insulation that is a consumer product. These requirements are intended to reduce or...

16 CFR 1209.1 - Scope and application.

Code of Federal Regulations, 2012 CFR

2012-01-01

... Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS INTERIM... part 1209, an interim consumer product safety standard, prescribes flame resistance and corrosiveness requirements for cellulose insulation that is a consumer product. These requirements are intended to reduce or...

Determination of rainfall losses in Virginia, phase II : interim report.

DOT National Transportation Integrated Search

1981-01-01

This interim report summarizes results obtained for the project through May 1981. The objective of the study is to develop rainfall loss parameters for localities in Virginia. For this purpose, the state has been divided into eleven hydrologic region...

75 FR 77733 - Federal Acquisition Regulation; Preventing Abuse of Interagency Contracts

Federal Register 2010, 2011, 2012, 2013, 2014

2010-12-13

... DEPARTMENT OF DEFENSE GENERAL SERVICES ADMINISTRATION NATIONAL AERONAUTICS AND SPACE... Aeronautics and Space Administration (NASA). ACTION: Interim rule with request for comments. SUMMARY: The..., including economies and efficiencies and the ability to leverage resources. This interim rule, which...

76 FR 12550 - Lavatory Oxygen Systems

Federal Register 2010, 2011, 2012, 2013, 2014

2011-03-08

... Lavatory Oxygen Systems AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Interim final rule... related to the provisioning of supplemental oxygen inside lavatories. This action is necessitated by other mandatory actions that temporarily render such oxygen systems inoperative. DATES: This interim rule is...

75 FR 7955 - Changes in Flood Elevation Determinations

Federal Register 2010, 2011, 2012, 2013, 2014

2010-02-23

... DEPARTMENT OF HOMELAND SECURITY Federal Emergency Management Agency 44 CFR Part 65 [Docket ID FEMA...: Federal Emergency Management Agency, DHS. ACTION: Interim rule. SUMMARY: This interim rule lists..., Engineering Management Branch, Mitigation Directorate, Federal Emergency Management Agency, 500 C Street SW...

76 FR 49674 - Changes in Flood Elevation Determinations

Federal Register 2010, 2011, 2012, 2013, 2014

2011-08-11

... in their floodplain management requirements. The community may at any time enact stricter... DEPARTMENT OF HOMELAND SECURITY Federal Emergency Management Agency 44 CFR Part 65 [Docket ID FEMA...: Federal Emergency Management Agency, DHS. ACTION: Interim rule. SUMMARY: This interim rule lists...

Lessons for outsourcing and interim management relationships.

PubMed

Macko, W; Kostyack, P T

1999-01-01

Few decisions can affect an organization more than the selection of an outsourcing or interim management partner. More and more health care organizations face such decisions in today's competitive market in order to face new business needs. Making these relationships successful can be important for health care organizations seeking competitive advantages or seeking immediately accessible management support. These relationships, however, require careful partner selection and development. Success in outsourcing and interim management relationships is contingent upon a thorough selection process, a strong contract that has clearly and explicitly detailed responsibilities and a culture-sensitive business rapport between the client and selected partner.

Atmospheric Effects of Subsonic Aircraft: Interim Assessment Report of the Advanced Subsonic Technology Program

NASA Technical Reports Server (NTRS)

Friedl, Randall R. (Editor)

1997-01-01

This first interim assessment of the subsonic assessment (SASS) project attempts to summarize concisely the status of our knowledge concerning the impacts of present and future subsonic aircraft fleets. It also highlights the major areas of scientific uncertainty, through review of existing data bases and model-based sensitivity studies. In view of the need for substantial improvements in both model formulations and experimental databases, this interim assessment cannot provide confident numerical predictions of aviation impacts. However, a number of quantitative estimates are presented, which provide some guidance to policy makers.

Civilian Health and Medical Program of the Uniformed Services (CHAMPUS); TRICARE Reserve Select for certain members of the selected reserve; Transitional Assistance Management Program; early eligibility for TRICARE for certain reserve component members. Interim final rule with comment period.

PubMed

2005-03-16

This interim final rule establishes requirements and procedures for implementation of TRICARE Reserve Select. It also revises requirements and procedures for the Transitional Assistance Management Program. In addition, it establishes requirements and procedures for implementation of the earlier TRICARE eligibility for certain reserve component members. The rule is being published as an interim final rule with comment period in order to comply with statutory effective dates.

Use of materials derived from cattle in human food and cosmetics; reopening of the comment period. Interim final rule; reopening of the comment period.

PubMed

2013-03-04

The Food and Drug Administration (FDA or ``we'') is reopening the comment period for the interim final rule entitled "Use of Materials Derived From Cattle in Human Food and Cosmetics'' that published in the Federal Register of July 14, 2004 (69 FR 42256). The interim final rule prohibited the use of certain cattle material to address the potential risk of bovine spongiform encephalopathy (BSE) in human food, including dietary supplements, and cosmetics. In the Federal Register of September 7, 2005 (70 FR 53063), we amended the interim final rule to make changes, including providing that the small intestine of cattle, formerly prohibited cattle material, could be used in human food and cosmetics if the distal ileum was removed by a specified procedure or one that the establishment could demonstrate is equally effective in ensuring complete removal of the distal ileum. Since 2005, peer-reviewed studies have been published showing the presence of infectivity in the proximal ileum, jejunum, ileocecal junction, and colon of cattle with BSE. Therefore, we are reopening the comment period for the interim final rule to give interested parties an opportunity to comment on the new studies concerning infectivity in parts of the small intestine other than the distal ileum.

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

Partial defect verification of spent fuel assemblies by PDET: Principle and field testing in Interim Spent fuel Storage Facility (CLAB) in Sweden

DOE PAGES

Ham, Y.; Kerr, P.; Sitaraman, S.; ...

2016-05-05

Here, the need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called "difficult-to-access" areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into "difficult-to-access" areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reportedmore » the successful development of a new, credible partial defect verification method for pressurized water reactor (PWR) spent fuel assemblies without use of operator data, and further reported the validation experiments using commercial spent fuel assemblies with some missing fuel pins. The method was found to be robust as the method is relatively invariant to the characteristic variations of spent fuel assemblies such as initial fuel enrichment, cooling time, and burn-up. Since then, the PDET system has been designed and prototyped for 17×17 PWR spent fuel assemblies, complete with data acquisition software and acquisition electronics. In this paper, a summary description of the PDET development followed by results of the first successful field testing using the integrated PDET system and actual spent fuel assemblies performed in a commercial spent fuel storage site, known as Central Interim Spent fuel Storage Facility (CLAB) in Sweden will be presented. In addition to partial defect detection initial studies have determined that the tool can be used to verify the operator declared average burnup of the assembly as well as intra-assembly bunrup levels.« less

Partial Defect Verification of Spent Fuel Assemblies by PDET: Principle and Field Testing in Interim Spent Fuel Storage Facility (CLAB) in Sweden

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

Ham, Y.S.; Kerr, P.; Sitaraman, S.

The need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called 'difficult-to-access' areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into 'difficult-to-access' areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reported themore » successful development of a new, credible partial defect verification method for pressurized water reactor (PWR) spent fuel assemblies without use of operator data, and further reported the validation experiments using commercial spent fuel assemblies with some missing fuel pins. The method was found to be robust as the method is relatively invariant to the characteristic variations of spent fuel assemblies such as initial fuel enrichment, cooling time, and burn-up. Since then, the PDET system has been designed and prototyped for 17x17 PWR spent fuel assemblies, complete with data acquisition software and acquisition electronics. In this paper, a summary description of the PDET development followed by results of the first successful field testing using the integrated PDET system and actual spent fuel assemblies performed in a commercial spent fuel storage site, known as Central Interim Spent fuel Storage Facility (CLAB) in Sweden will be presented. In addition to partial defect detection initial studies have determined that the tool can be used to verify the operator declared average burnup of the assembly as well as intra-assembly burnup levels. (authors)« less

Partial defect verification of spent fuel assemblies by PDET: Principle and field testing in Interim Spent fuel Storage Facility (CLAB) in Sweden

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

Ham, Y.; Kerr, P.; Sitaraman, S.

Here, the need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called "difficult-to-access" areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into "difficult-to-access" areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reportedmore » the successful development of a new, credible partial defect verification method for pressurized water reactor (PWR) spent fuel assemblies without use of operator data, and further reported the validation experiments using commercial spent fuel assemblies with some missing fuel pins. The method was found to be robust as the method is relatively invariant to the characteristic variations of spent fuel assemblies such as initial fuel enrichment, cooling time, and burn-up. Since then, the PDET system has been designed and prototyped for 17×17 PWR spent fuel assemblies, complete with data acquisition software and acquisition electronics. In this paper, a summary description of the PDET development followed by results of the first successful field testing using the integrated PDET system and actual spent fuel assemblies performed in a commercial spent fuel storage site, known as Central Interim Spent fuel Storage Facility (CLAB) in Sweden will be presented. In addition to partial defect detection initial studies have determined that the tool can be used to verify the operator declared average burnup of the assembly as well as intra-assembly bunrup levels.« less

Women and the Hanford Site

NASA Astrophysics Data System (ADS)

Gerber, Michele

2014-03-01

When we study the technical and scientific history of the Manhattan Project, women's history is sometimes left out. At Hanford, a Site whose past is rich with hard science and heavy construction, it is doubly easy to leave out women's history. After all, at the World War II Hanford Engineer Works - the earliest name for the Hanford Site - only nine percent of the employees were women. None of them were involved in construction, and only one woman was actually involved in the physics and operations of a major facility - Dr. Leona Woods Marshall. She was a physicist present at the startup of B-Reactor, the world's first full-scale nuclear reactor - now a National Historic Landmark. Because her presence was so unique, a special bathroom had to be built for her in B-Reactor. At World War II Hanford, only two women were listed among the nearly 200 members of the top supervisory staff of the prime contractor, and only one regularly attended the staff meetings of the Site commander, Colonel Franklin Matthias. Overall, women comprised less than one percent of the managerial and supervisory staff of the Hanford Engineer Works, most of them were in nursing or on the Recreation Office staff. Almost all of the professional women at Hanford were nurses, and most of the other women of the Hanford Engineer Works were secretaries, clerks, food-service workers, laboratory technicians, messengers, barracks workers, and other support service employees. The one World War II recruiting film made to attract women workers to the Site, that has survived in Site archives, is entitled ``A Day in the Life of a Typical Hanford Girl.'' These historical facts are not mentioned to criticize the past - for it is never wise to apply the standards of one era to another. The Hanford Engineer Works was a 1940s organization, and it functioned by the standards of the 1940s. Just as we cannot criticize the use of asbestos in constructing Hanford (although we may wish they hadn't used so much of it), we cannot criticize the employment realities or the social practices of those days. If we can simply understand the past, then maybe we can learn from it. This presentation will highlight the success stories of many of Hanford's women. About 4,000 women came to the gargantuan, remote desert location, most of them young and away from home for the first time. Almost all of them were coming to a place they had never heard of and undertaking a mission that could not be explained to them because it was Top Secret. Faced with decidedly unequal opportunity, they came and took the jobs that were available, because they felt a personal dedication to the war effort. They had fun at Hanford, despite living in dusty barracks and eating mess hall food, and they left their mark on Hanford and its memories in many ways. Without them, the Site could not have functioned, and the war might not have been won as soon as it was. They then became the grandmothers of Richland, Washington, who told their stories to me in the 1990s. This presentation will show the lives of these women at Hanford during the Manhattan Project, as they worked to make the best of the situation, contribute and do their jobs. Their feelings about the work 50 years later will also be discussed.

Text processing for technical reports (direct computer-assisted origination, editing, and output of text)

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

De Volpi, A.; Fenrick, M. R.; Stanford, G. S.

1980-10-01

Documentation often is a primary residual of research and development. Because of this important role and because of the large amount of time consumed in generating technical reports, particularly those containing formulas and graphics, an existing data-processing computer system has been adapted so as to provide text-processing of technical documents. Emphasis has been on accuracy, turnaround time, and time savings for staff and secretaries, for the types of reports normally produced in the reactor development program. The computer-assisted text-processing system, called TXT, has been implemented to benefit primarily the originator of technical reports. The system is of particular value tomore » professional staff, such as scientists and engineers, who have responsibility for generating much correspondence or lengthy, complex reports or manuscripts - especially if prompt turnaround and high accuracy are required. It can produce text that contains special Greek or mathematical symbols. Written in FORTRAN and MACRO, the program TXT operates on a PDP-11 minicomputer under the RSX-11M multitask multiuser monitor. Peripheral hardware includes videoterminals, electrostatic printers, and magnetic disks. Either data- or word-processing tasks may be performed at the terminals. The repertoire of operations has been restricted so as to minimize user training and memory burden. Spectarial staff may be readily trained to make corrections from annotated copy. Some examples of camera-ready copy are provided.« less

76 FR 19909 - International Terrorism Victim Expense Reimbursement Program

Federal Register 2010, 2011, 2012, 2013, 2014

2011-04-11

... 1121-AA78 International Terrorism Victim Expense Reimbursement Program AGENCY: Office of Justice... promulgating this interim-final rule for its International Terrorism Victim Expense Reimbursement Program... international terrorism. DATES: Effective date: This interim-final rule is effective April 11, 2011. Comment...

LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

EPA Science Inventory

A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

75 FR 41381 - Private Land Mobile Radio Services

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-16

...] Private Land Mobile Radio Services AGENCY: Federal Communications Commission. ACTION: Final rule. SUMMARY... to the January 1, 2011 interim deadlines associated with the narrowbanding of private land mobile... to the January 1, 2011 interim deadlines associated with the narrowbanding of private land mobile...

Evaluation of US 119 Pine Mountain safety improvements : interim report.

DOT National Transportation Integrated Search

2003-10-01

The safety improvement project for a section of US 119 across Pine Mountain in Letcher County was initiated as an interim effort to address safety issues related t o roadway geometrics and specific problems related to truck traffic. : Specific object...

Evaluation of experimental railroad-highway grade crossings in Louisiana : interim report No. 5.

DOT National Transportation Integrated Search

1980-04-01

This interim report is prepared to provide a review of the performance evaluation exhibited on twenty-three (23) experimental railroad-highway grade-crossing projects in the state of Louisiana. The railroad crossings were installed during a ten-year ...

76 FR 54456 - Petition for Waiver and Notice of Granting the Application for Interim Waiver of Samsung from the...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-09-01

... anti-sweat heaters. Therefore, it is ordered that: The application for interim waiver filed by Samsung... control anti-sweat heaters according to the alternate test procedure as set forth in section IV...

40 CFR 94.12 - Interim provisions.

Code of Federal Regulations, 2014 CFR

2014-07-01

... differences in testing will not affect NOX emission rates. (g) Flexibility for engines over 560kW... EMISSIONS FROM MARINE COMPRESSION-IGNITION ENGINES General Provisions for Emission Regulations for Compression-Ignition Marine Engines § 94.12 Interim provisions. This section contains provisions that apply...