10 CFR 871.2 - Public health and safety exemption.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Public health and safety exemption. 871.2 Section 871.2 Energy DEPARTMENT OF ENERGY AIR TRANSPORTATION OF PLUTONIUM § 871.2 Public health and safety exemption... property damage, or other significant threat to the public health and safety. [42 FR 48332, Sept. 23, 1977...

78 FR 65932 - Updating OSHA Standards Based on National Consensus Standards; Signage

Science.gov (United States)

2013-11-04

...; Signage AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor. ACTION... accompanied its direct final rule revising its signage standards for general industry and construction. DATES... proposed rule (NPRM) along with the direct final rule (DFR) (see 78 FR 35585) updating its signage...

75 FR 33696 - Safety Zone: July Firework Display in Captain of the Port, Puget Sound AOR

Science.gov (United States)

2010-06-15

...-AA00 Safety Zone: July Firework Display in Captain of the Port, Puget Sound AOR AGENCY: Coast Guard... Captain of the Port, Puget Sound AOR. (a) Safety Zone. The following area is a designated safety zone: all..., Captain of the Port, Puget Sound. [FR Doc. 2010-14294 Filed 6-14-10; 8:45 am] BILLING CODE 9110-04-P ...

Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors

International Nuclear Information System (INIS)

Motloch, C.G.; Modro, S.M.

1990-01-01

An assessment of the applicability of using RELAP5 for performing safety analyses of the AP600 and PIUS advanced reactor concepts is being performed. This ongoing work is part of a larger safety assessment of advanced reactors sponsored by the United States Nuclear Regulatory Commission. RELAP5 models and correlations are being reviewed from the perspective of the new AP600 and PIUS phenomena and features that could be important to reactor safety. The purpose is to identify those areas in which new mathematical models of physical phenomena would be required to be added to RELAP5. In most cases, the AP600 and PIUS designs and systems and the planned and off-normal operations are similar enough to current Pressurized Water Reactors (PWR) that RELAP5 safety analysis applicability is unchanged. However, for AP600 the single most important systemic and phenomenological difference between it and current PWRs is in the close coupling between the reactor system and the containment during postulated Loss of Coolant Accident (LOCA) events. This close coupling may require the addition of some thermal-hydraulic models to RELAP5. And for PIUS, the most important new feature is the thermal density locks. These and other important safety-related features are discussed. This document presents general descriptions of RELAP5, AP600, and PIUS, describes the new features and phenomena of the reactors, and discusses the code/reactors safety-related issues. 32 refs., 4 figs., 2 tabs

77 FR 66639 - Advisory Committee on Construction Safety and Health (ACCSH)

Science.gov (United States)

2012-11-06

... Contract Work Hours and Safety Standards Act (Construction Safety Act) (40 U.S.C. 3701 et seq.) and the.../Women in Construction: 2:15 to 4:15 p.m. The following ACCSH Work Groups will meet November 28, 2012... Occupational Safety and Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety...

45-Day safety screening report for grab samples from Tank 241-AP-107

International Nuclear Information System (INIS)

Miller, G.L.

1995-01-01

Three samples; 107-AP-1C, 107-AP-2c and 107-AP-3C; were received at 222-S Laboratory for analysis of DSC, TGA and visual appearance. Four additional samples; 107-AP-1D, 107-AP-2D, 107-AP-3D and 107-AP-6; were received for visual appearance only. No results exceeded the safety screen notification criteria. This report compiles the analytical results. Tank 241-AP-107 is a double-shell tank which is not on any of the four Watch Lists

Westinghouse AP1000 advanced passive plant: design features and benefits

International Nuclear Information System (INIS)

Walls, S.J.; Cummins, W.E.

2003-01-01

The Westinghouse AP1000 Program is aimed at implementing the AP1000 plant to provide a further major improvement in plant economics while maintaining the passive safety advantages established by the AP600. An objective is to retain to the maximum extent possible the plant design of the AP600 so as to retain the licensing basis, cost estimate, construction schedule, modularization scheme, and the detailed design from the AP600 program. Westinghouse and the US Nuclear Regulatory Commission staff have embarked on a program to complete Design Certification for the AP1000 by 2004. A pre-certification review phase was completed in March 2002 and was successful in establishing the applicability of the AP600 test program and AP600 safety analysis codes to the AP1000 Design Certification. On March 28, 2002, Westinghouse submitted to US NRC the AP1000 Design Control Document and Probabilistic Risk Assessment, thereby initiating the formal design certification review process. The results presented in these documents verify the safety performance of the API 000 and conformance with US NRC licensing requirements. Plans are being developed for implementation of a series of AP1000 plants in the US. Key factors in this planning are the economics of AP1000, and the associated business model for licensing, constructing and operating these new plants. Similarly plans are being developed to get the AP1000 design reviewed for use in the UK. Part of this planning has been to examine the AP1000 design relative to anticipated UK safety and licensing issues. (author)

Principles and standards of nuclear safety and their implementation

International Nuclear Information System (INIS)

Franzen, L.F.

1979-01-01

Nuclear safety starts with the design of a nuclear facility and is only completed with its decommissioning. In the various phases of a nuclear facility's lifetime, safety evaluations are required. The licensing prerequisites for construction, operation, modification, decommissioning are based on elements of the relevant national legislation and related ordinances as well as on international regulations. They should be expanded by a system of criteria and standards spelling out the proven practice as developed over the last decades in the industrialized countries and by international organizations such IAEA with its safety codes and guides. (NEA) [fr

76 FR 34890 - Track Safety Standards; Concrete Crossties

Science.gov (United States)

2011-06-15

...-0007, Notice No. 3] RIN 2130-AC01 Track Safety Standards; Concrete Crossties AGENCY: Federal Railroad... effective concrete crossties, for rail fastening systems connected to concrete crossties, and for automated inspections of track constructed with concrete crossties. The Track Safety Standards were amended via final...

77 FR 54836 - Federal Motor Vehicle Safety Standards

Science.gov (United States)

2012-09-06

... DEPARTMENT OF TRANSPORTATION National Highway Traffic Safety Administration 49 CFR Part 571 Federal Motor Vehicle Safety Standards CFR Correction 0 In Title 49 of the Code of Federal Regulations... read as follows: Sec. 571.119 Standard No. 119; New pneumatic tires for motor vehicles with a GVWR of...

Clinical manifestations of antiphospholipid syndrome (APS) with and without antiphospholipid antibodies (the so-called 'seronegative APS').

Science.gov (United States)

Rodriguez-Garcia, Jose Luis; Bertolaccini, Maria Laura; Cuadrado, Maria Jose; Sanna, Giovanni; Ateka-Barrutia, Oier; Khamashta, Munther A

2012-02-01

Although the medical literature currently provides a growing number of isolated case reports of patients with clinically well-defined antiphospholipid syndrome (APS) and persistently negative antiphospholipid antibodies (aPL), there are no studies including a series of patients addressing the clinical features of this condition. The authors assessed clinical manifestations of APS in 154 patients: 87 patients with seropositive APS and 67 patients with thrombosis and/or pregnancy morbidity persistently negative for aPL and presenting with at least two additional non-criteria manifestations of APS (the so-called 'seronegative APS', SN-APS). Patients were interviewed at the time of recruitment, and a retrospective file review was carried out. There were no significant differences in the frequency of thrombotic events or obstetric morbidity in patients with SN-APS versus patients with seropositive APS: deep vein thrombosis (31.4% vs 31.0%), pulmonary embolism (23.8% vs 28.7%), stroke (14.9% vs 17.2%), transient ischaemic attack (11.9% vs 10.3%), early spontaneous abortions (67.1% vs 52.1%), stillbirths (62.5% vs 59.4%), prematurity (28.1% vs 21.7%) or pre-eclampsia (28.1% vs 23.1%). Classic and SN-APS patients show similar clinical profiles. The results suggest that clinical management in patients with APS should not be based only on the presence of conventional aPL.

AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

Energy Technology Data Exchange (ETDEWEB)

Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01

The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all

78 FR 39533 - Power Sector Carbon Pollution Standards

Science.gov (United States)

2013-07-01

... Sector Carbon Pollution Standards Executive Order 13647--Establishing the White House Council on Native... speeding the transition to more sustainable sources of energy. The Environmental Protection Agency (EPA.... (Presidential Sig.) THE WHITE HOUSE, Washington, June 25, 2013. [FR Doc. 2013-15941 Filed 6-28-13; 11:15 am...

Enhancing the safety of elderly victims after the close of an APS investigation.

Science.gov (United States)

Jackson, Shelly L; Hafemeister, Thomas L

2013-04-01

The purpose of this study was to test whether particular actions on the part of adult protective services (APS), the elderly victim, and/or society's response to abusive individuals, are associated with the continuation of abuse after the close of an APS investigation and thereby compromise victim safety. Interviews were conducted with 71 APS caseworkers, 55 of the elderly victims of substantiated abuse, and 35 third-party persons. A small proportion of elderly victims continue to experience abuse after the close of an APS investigation. Elderly victims were more likely to experience continued abuse when they chose to have ongoing contact with their abusers, vis-à-vis cohabitation or otherwise, and when their abusers experienced no consequences. Although continuation of abuse did not differ by the type of maltreatment involved, reasons for the cessation of abuse, and other safety indicators, did. To enhance victim safety, greater monitoring may be warranted in cases wherein elderly victims continue to have contact with their abuser and when abusive individuals experience no consequences. To further enhance victim safety, abusive individuals must be incorporated into an overall strategic response to elder abuse. A potential avenue for facilitating victim safety while maintaining victim autonomy is to understand their motivations for desiring continued contact with their abuser and developing interventions based upon such knowledge.

76 FR 73687 - Advisory Committee on Construction Safety and Health (ACCSH)

Science.gov (United States)

2011-11-29

... arising in the administration of the safety and health provisions under the Contract Work Hours and Safety... 10:10 a.m. to 12:10 p.m. Multilingual Issues, Diversity, Women in Construction 1 to 3 p.m. ACCSH Work... Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety Standards Act...

Piping benchmark problems for the Westinghouse AP600 Standardized Plant

International Nuclear Information System (INIS)

Bezler, P.; DeGrassi, G.; Braverman, J.; Wang, Y.K.

1997-01-01

To satisfy the need for verification of the computer programs and modeling techniques that will be used to perform the final piping analyses for the Westinghouse AP600 Standardized Plant, three benchmark problems were developed. The problems are representative piping systems subjected to representative dynamic loads with solutions developed using the methods being proposed for analysis for the AP600 standard design. It will be required that the combined license licensees demonstrate that their solutions to these problems are in agreement with the benchmark problem set

Study on the operation mode for indigenization and standardization of AP1000 technology

International Nuclear Information System (INIS)

Gao Zhihu; Cheng Huiping

2014-01-01

This paper describes the importance and necessity of developing standardized AP1000 technology, and analyzes the problems faced and measures to be taken. The operation mode, known as the Committee of AP1000 Standardized Design and Innovation Management, was first put forward in China. And the paper also discusses how to arouse the enthusiasm of the owners, designers, manufactures, as well as construction, installation, regulation and other parties, how to exploit the advantage of whole industry to promote the localization and standardization of AP1000 technology. (authors)

AP1000. The PWR revisited

International Nuclear Information System (INIS)

Gaio, P.

2006-01-01

The distinguishing features of Westinghouse's AP1000 advanced passive pressurized water reactor are highlighted. In particular, the AP1000's passive safety features are described as well as their implications for simplifying the design, construction, and operation of this design compared to currently operating plants, and significantly increasing safety margins over current plants as well. The AP1000 design specifically incorporates the knowledge acquired from the substantial accumulation of power reactor operating experience and benefits from the application of the Probabilistic Risk Assessment in the design process itself. The AP1000 design has been certified by the US Nuclear Regulatory Commission under its new rules for licensing new nuclear plants, 10 CFR Part 52, and is the subject of six combined Construction and Operating License applications now being developed. Currently the AP1000 design is being assessed against the EUR Rev C requirements for new nuclear power plants in Europe. (author)

Achieving mask order processing automation, interoperability and standardization based on P10

Science.gov (United States)

Rodriguez, B.; Filies, O.; Sadran, D.; Tissier, Michel; Albin, D.; Stavroulakis, S.; Voyiatzis, E.

2007-02-01

Last year the MUSCLE (Masks through User's Supply Chain: Leadership by Excellence) project was presented. Here is the project advancement. A key process in mask supply chain management is the exchange of technical information for ordering masks. This process is large, complex, company specific and error prone, and leads to longer cycle times and higher costs due to missing or wrong inputs. Its automation and standardization could produce significant benefits. We need to agree on the standard for mandatory and optional parameters, and also a common way to describe parameters when ordering. A system was created to improve the performance in terms of Key Performance Indicators (KPIs) such as cycle time and cost of production. This tool allows us to evaluate and measure the effect of factors, as well as the effect of implementing the improvements of the complete project. Next, a benchmark study and a gap analysis were performed. These studies show the feasibility of standardization, as there is a large overlap in requirements. We see that the SEMI P10 standard needs enhancements. A format supporting the standard is required, and XML offers the ability to describe P10 in a flexible way. Beyond using XML for P10, the semantics of the mask order should also be addressed. A system design and requirements for a reference implementation for a P10 based management system are presented, covering a mechanism for the evolution and for version management and a design for P10 editing and data validation.

Basic safety standards for radiation protection and their application to internal exposures

International Nuclear Information System (INIS)

Dousset, M.

Following a summary of the basic concepts on radiation protection units, the safety standards now in effect in France and those recommended by the International Commission on Radiological Protection (ICRP Publication 9, 1965) to be used as a basis to the next Euratom regulations are developed [fr

Quantitative dynamic reliability evaluation of AP1000 passive safety systems by using FMEA and GO-FLOW methodology

International Nuclear Information System (INIS)

Hashim Muhammad; Yoshikawa, Hidekazu; Matsuoka, Takeshi; Yang Ming

2014-01-01

The passive safety systems utilized in advanced pressurized water reactor (PWR) design such as AP1000 should be more reliable than that of active safety systems of conventional PWR by less possible opportunities of hardware failures and human errors (less human intervention). The objectives of present study are to evaluate the dynamic reliability of AP1000 plant in order to check the effectiveness of passive safety systems by comparing the reliability-related issues with that of active safety systems in the event of the big accidents. How should the dynamic reliability of passive safety systems properly evaluated? And then what will be the comparison of reliability results of AP1000 passive safety systems with the active safety systems of conventional PWR. For this purpose, a single loop model of AP1000 passive core cooling system (PXS) and passive containment cooling system (PCCS) are assumed separately for quantitative reliability evaluation. The transient behaviors of these passive safety systems are taken under the large break loss-of-coolant accident in the cold leg. The analysis is made by utilizing the qualitative method failure mode and effect analysis in order to identify the potential failure mode and success-oriented reliability analysis tool called GO-FLOW for quantitative reliability evaluation. The GO-FLOW analysis has been conducted separately for PXS and PCCS systems under the same accident. The analysis results show that reliability of AP1000 passive safety systems (PXS and PCCS) is increased due to redundancies and diversity of passive safety subsystems and components, and four stages automatic depressurization system is the key subsystem for successful actuation of PXS and PCCS system. The reliability results of PCCS system of AP1000 are more reliable than that of the containment spray system of conventional PWR. And also GO-FLOW method can be utilized for reliability evaluation of passive safety systems. (author)

NRC confirmatory safety system testing in support of AP600 design review

International Nuclear Information System (INIS)

Rhee, G.S.; Bessette, D.E.; Shotkin, L.M.

1994-01-01

Westinghouse Electric Corporation has submitted the Advanced Passive 600 MWe (AP600) nuclear power plant design to the NRC for design certification. The Office of Nuclear Regulatory Research is proceeding to conduct confirmatory testing to help the NRC staff evaluate the AP600 safety system design. For confirmatory testing, it was determined that the cost-effective route was to modify an existing full-height, full-pressure test facility rather than build a new one. Thus, all the existing integral effects test facilities, both in the US and abroad, were screened to select the best candidate. As a result, the ROSA-V (Rig of Safety Assessment-V) test facility located in the Japan Atomic Energy Research Institute (JAERI) was chosen. However, because of some differences in design between the existing ROSA-V facility and the AP600, the ROSA-V is being modified to conform to the AP600 safety system design. The modification work will be completed by the end of this year. A series of facility characterization tests will then be performed in January 1994 for the modified part of the facility before the main test series is initiated in February 1994. A total of 12 tests will be performed in 1994 under Phase I of this cooperative program with JAERI. Phase II testing is being considered to be conducted in 1995 mainly for beyond-design-basis accident evaluation

Significant advantages of the safety-first concept in construction, operation, and maintenance of the Westinghosue AP1000 reactor

International Nuclear Information System (INIS)

Cummins, E.; Benitz, K.

2004-01-01

In June 2003, the U.S. Nuclear Regulatory Commission (USNRC) published a draft opinion about safety of the AP1000 Westinghouse pressurized water reactor with 'passive safety' features. The report constitutes an important milestone in the development of the next generation of safe and cost-efficient nuclear power plants. A new AP1000 can be absolutely competitive with fossil fired power plants and may be able to revive the construction of new nuclear power plants worldwide. The reason for designing the AP1000 were safety considerations. The use of passive safety systems at the same time entails a considerable reduction in the costs of design, maintenance, and operation of an AP1000 plant. Independent experts confirmed that an AP1000 can be erected within three years or even less. The estimated electricity generating costs of an AP1000 plant in the United States amount to US Cent 3.2 to 3.6 per kilowatthour. (orig.)

AP1000R licensing and deployment in the United States

International Nuclear Information System (INIS)

Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L.

2012-01-01

In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed

40 CFR 413.14 - Pretreatment standards for existing sources.

Science.gov (United States)

2010-07-01

... management plan approved by the control authority. (Secs. 301, 304, 306, 307, 308, and 501 of the Clean Water...) EFFLUENT GUIDELINES AND STANDARDS ELECTROPLATING POINT SOURCE CATEGORY Electroplating of Common Metals... by the Clean Water Act of 1977, Pub. L. 95-217)) [46 FR 9467, Jan. 28, 1981; 46 FR 30626, June 10...

APS beamline standard components handbook, Version 1.3

International Nuclear Information System (INIS)

Hahn, U.; Shu, D.; Kuzay, T.M.

1993-02-01

This Handbook in its current version (1.3) contains descriptions, specifications, and preliminary engineering design drawings for many of the standard components. The design status and schedules have been provided wherever possible. In the near future, the APS plans to update engineering drawings of identified standard beamline components and complete the Handbook. The completed version of this Handbook will become available to both the CATs and potential vendors. Use of standard components should result in major cost reductions for CATs in the areas of beamline design and construction

75 FR 57297 - Petitions for Modification of Existing Mandatory Safety Standards

Science.gov (United States)

2010-09-20

... safety standards published in Title 30 of the Code of Federal Regulations. DATES: All comments on the... DEPARTMENT OF LABOR Mine Safety and Health Administration Petitions for Modification of Existing Mandatory Safety Standards AGENCY: Mine Safety and Health Administration (MSHA), Labor. ACTION: Notice...

76 FR 16640 - Petitions for Modification of Existing Mandatory Safety Standards

Science.gov (United States)

2011-03-24

... safety standards published in Title 30 of the Code of Federal Regulations. DATES: All comments on the... DEPARTMENT OF LABOR Mine Safety and Health Administration Petitions for Modification of Existing Mandatory Safety Standards AGENCY: Mine Safety and Health Administration (MSHA), Labor. ACTION: Notice...

76 FR 31846 - Safety Zone; 28th Annual Humboldt Bay Festival, Fireworks Display, Eureka, CA

Science.gov (United States)

2011-06-02

...-AA00 Safety Zone; 28th Annual Humboldt Bay Festival, Fireworks Display, Eureka, CA AGENCY: Coast Guard... support of the 28th Annual Humboldt Bay Festival Fireworks Display on the specified waters off the South... Humboldt Bay Festival Fireworks Display. The fireworks display is for entertainment purposes. This safety...

76 FR 55825 - Federal Motor Vehicle Safety Standards, Child Restraint Systems

Science.gov (United States)

2011-09-09

... [Docket No. NHTSA-2011-0139] RIN 2127-AJ44 Federal Motor Vehicle Safety Standards, Child Restraint Systems..., amends a provision in Federal Motor Vehicle Safety Standard No. 213, ``Child restraint systems,'' that... provision: When a motor vehicle safety standard is in effect under this chapter, a State or a political...

78 FR 29384 - Petitions for Modification of Application of Existing Mandatory Safety Standards

Science.gov (United States)

2013-05-20

... modify the application of any mandatory safety standard to a coal or other mine if the Secretary of Labor... running conveyor belt when a water sprinkler is activated. 9. Each automatic sprinkler will be a standard... the gauge indicates 10 psi or more. f. Verify that the water flow switch is activated and the dispatch...

IAEA Safety Standards

International Nuclear Information System (INIS)

2016-09-01

The IAEA Safety Standards Series comprises publications of a regulatory nature covering nuclear safety, radiation protection, radioactive waste management, the transport of radioactive material, the safety of nuclear fuel cycle facilities and management systems. These publications are issued under the terms of Article III of the IAEA’s Statute, which authorizes the IAEA to establish “standards of safety for protection of health and minimization of danger to life and property”. Safety standards are categorized into: • Safety Fundamentals, stating the basic objective, concepts and principles of safety; • Safety Requirements, establishing the requirements that must be fulfilled to ensure safety; and • Safety Guides, recommending measures for complying with these requirements for safety. For numbering purposes, the IAEA Safety Standards Series is subdivided into General Safety Requirements and General Safety Guides (GSR and GSG), which are applicable to all types of facilities and activities, and Specific Safety Requirements and Specific Safety Guides (SSR and SSG), which are for application in particular thematic areas. This booklet lists all current IAEA Safety Standards, including those forthcoming

Westinghouse AP600 advanced nuclear plant design

International Nuclear Information System (INIS)

Gangloff, W.

1999-01-01

As part of the cooperative US Department of Energy (DOE) Advanced Light Water Reactor (ALWR) Program and the Electric Power Research Institute (EPRI), the Westinghouse AP600 team has developed a simplified, safe, and economic 600-megawatt plant to enter into a new era of nuclear power generation. Designed to satisfy the standards set by DOE and defined in the ALWR Utility Requirements Document (URD), the Westinghouse AP600 is an elegant combination of innovative safety systems that rely on dependable natural forces and proven technologies. The Westinghouse AP600 design simplifies plant systems and significant operation, inspections, maintenance, and quality assurance requirements by greatly reducing the amount of valves, pumps, piping, HVAC ducting, and other complex components. The AP600 safety systems are predominantly passive, depending on the reliable natural forces of gravity, circulation, convection, evaporation, and condensation, instead of AC power supplies and motor-driven components. The AP600 provides a high degree of public safety and licensing certainty. It draws upon 40 years of experience in light water reactor components and technology, so no demonstration plant is required. During the AP600 design program, a comprehensive test program was carried out to verify plant components, passive safety systems components, and containment behavior. When the test program was completed at the end of 1994, the AP600 became the most thoroughly tested advanced reactor design ever reviewed by the US Nuclear Regulatory Commission (NRC). The test results confirmed the exceptional behavior of the passive systems and have been instrumental in facilitating code validations. Westinghouse received Final Design Approval from the NRC in September 1998. (author)

Discussion of QA grading for AP1000 NP plant

International Nuclear Information System (INIS)

Luo Shuiyun; Zhang Qingchuan

2012-01-01

The grading method of quality assurance for the following AP1000 project is presented based on the Westinghouse classification principle, referring to the classification method of the AP1000 self-reliance supporting project and considering the factors of classification, which can meet the requirements of domestic nuclear safety regulation and standard of the QA classification. (authors)

77 FR 48105 - Federal Motor Vehicle Safety Standards; Motorcycle Helmets

Science.gov (United States)

2012-08-13

... [Docket No. NHTSA-2012-0112] Federal Motor Vehicle Safety Standards; Motorcycle Helmets AGENCY: National... Vehicle Safety Standard for motorcycle helmets. Specifically, the final rule amended the helmet labeling... compliance test procedures of FMVSS No. 218, Motorcycle helmets, in order to make it more difficult to...

Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features

International Nuclear Information System (INIS)

Winters, J.W.; Corletti, M.M.; Hayashi, Y.

2003-01-01

A report of DOE sponsored portions of AP1000 Design Certification effort. On December 16, 1999, The United States Nuclear Regulatory Commission issued Design Certification of the AP600 standard nuclear reactor design. This culminated an 8-year review of the AP600 design, safety analysis and probabilistic risk assessment. The AP600 is a 600 MWe reactor that utilizes passive safety features that, once actuated, depend only on natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and have also significantly simplified plant systems and equipment, resulting in simplified plant operation and maintenance. The AP600 meets NRC deterministic safety criteria and probabilistic risk criteria with large margins. A summary comparison of key passive safety system design features is provided in Table 1. These key features are discussed due to their importance in affecting the key thermal-hydraulic phenomenon exhibited by the passive safety systems in critical areas. The scope of some of the design changes to the AP600 is described. These changes are the ones that are important in evaluating the passive plant design features embodied in the certified AP600 standard plant design. These design changes are incorporated into the AP1000 standard plant design that Westinghouse is certifying under 10 CFR Part 52. In conclusion, this report describes the results of the representative design certification activities that were partially supported by the Nuclear Energy Research Initiative. These activities are unique to AP1000, but are representative of research activities that must be driven to conclusion to realize successful licensing of the next generation of nuclear power plants in the United States

Advanced Photon Source experimental beamline Safety Assessment Document: Addendum to the Advanced Photon Source Accelerator Systems Safety Assessment Document (APS-3.2.2.1.0)

International Nuclear Information System (INIS)

1995-01-01

This Safety Assessment Document (SAD) addresses commissioning and operation of the experimental beamlines at the Advanced Photon Source (APS). Purpose of this document is to identify and describe the hazards associated with commissioning and operation of these beamlines and to document the measures taken to minimize these hazards and mitigate the hazard consequences. The potential hazards associated with the commissioning and operation of the APS facility have been identified and analyzed. Physical and administrative controls mitigate identified hazards. No hazard exists in this facility that has not been previously encountered and successfully mitigated in other accelerator and synchrotron radiation research facilities. This document is an updated version of the APS Preliminary Safety Analysis Report (PSAR). During the review of the PSAR in February 1990, the APS was determined to be a Low Hazard Facility. On June 14, 1993, the Acting Director of the Office of Energy Research endorsed the designation of the APS as a Low Hazard Facility, and this Safety Assessment Document supports that designation

76 FR 10246 - Updating Fire Safety Standards

Science.gov (United States)

2011-02-24

... public noted the importance of requiring facilities to meet up-to-date safety standards. The third... Affairs (VA) regulations concerning community residential care facilities, contract facilities for certain outpatient and residential services, and State home facilities. The final rule will clarify current...

Baculovirus p35 gene is oppositely regulated by P53 and AP-1 like factors in Spodoptera frugiperda

International Nuclear Information System (INIS)

Mohareer, Krishnaveni; Sahdev, Sudhir; Hasnain, Seyed E.

2011-01-01

Highlights: ► Baculovirus p35 is regulated by both viral and host factors. ► Baculovirus p35 is negatively regulated by SfP53-like factor. ► Baculovirus p35 is positively regulated by SfAP-1-like factor. -- Abstract: Baculovirus p35 belongs to the early class of genes of AcMNPV and requires viral factors like Immediate Early protein-1 for its transcription. To investigate the role of host factors in regulating p35 gene expression, the putative transcription factor binding sites were examined in silico and the role of these factors in influencing the transcription of p35 gene was assessed. We focused our studies on AP-1 and P53-like factors, which are activated under oxidative stress conditions. The AP-1 motif is located at −1401 while P53 motif is at −1912 relative to p35 translation start site. The predicted AP-1 and P53 elements formed specific complexes with Spodoptera frugiperda nuclear extracts. Both AP-1 and P53 motif binding proteins were down regulated as a function of AcMNPV infection in Spodoptera cells. To address the question whether during an oxidative outburst, the p35 transcription is enhanced; we investigated the role of these oxidative stress induced host transcription factors in influencing p35 gene transcription. Reporter assays revealed that AP-1 element enhances the transcription of p35 by a factor of two. Interestingly, P53 element appears to repress the transcription of p35 gene.

Baculovirus p35 gene is oppositely regulated by P53 and AP-1 like factors in Spodoptera frugiperda

Energy Technology Data Exchange (ETDEWEB)

Mohareer, Krishnaveni [Laboratory of Molecular and Cell Biology, Center for DNA Fingerprinting and Diagnostics, Hyderabad 500001 (India); Institute of Life Sciences, University of Hyderabad Campus, Prof. C.R. Rao Road, Gachibowli, Hyderabad 500046 (India); Sahdev, Sudhir [Laboratory of Molecular and Cell Biology, Center for DNA Fingerprinting and Diagnostics, Hyderabad 500001 (India); Ranbaxy Pharmaceuticals, Gurgaon, New Delhi (India); Hasnain, Seyed E., E-mail: seh@bioschool.iitd.ac.in [Institute of Life Sciences, University of Hyderabad Campus, Prof. C.R. Rao Road, Gachibowli, Hyderabad 500046 (India); Kusuma School of Biological Sciences, IIT Delhi, New Delhi 110016 (India); ILBS, Vasant Kunj, New Delhi (India); King Saud University, Riyadh, KSA (Saudi Arabia)

2011-11-04

Highlights: Black-Right-Pointing-Pointer Baculovirus p35 is regulated by both viral and host factors. Black-Right-Pointing-Pointer Baculovirus p35 is negatively regulated by SfP53-like factor. Black-Right-Pointing-Pointer Baculovirus p35 is positively regulated by SfAP-1-like factor. -- Abstract: Baculovirus p35 belongs to the early class of genes of AcMNPV and requires viral factors like Immediate Early protein-1 for its transcription. To investigate the role of host factors in regulating p35 gene expression, the putative transcription factor binding sites were examined in silico and the role of these factors in influencing the transcription of p35 gene was assessed. We focused our studies on AP-1 and P53-like factors, which are activated under oxidative stress conditions. The AP-1 motif is located at -1401 while P53 motif is at -1912 relative to p35 translation start site. The predicted AP-1 and P53 elements formed specific complexes with Spodoptera frugiperda nuclear extracts. Both AP-1 and P53 motif binding proteins were down regulated as a function of AcMNPV infection in Spodoptera cells. To address the question whether during an oxidative outburst, the p35 transcription is enhanced; we investigated the role of these oxidative stress induced host transcription factors in influencing p35 gene transcription. Reporter assays revealed that AP-1 element enhances the transcription of p35 by a factor of two. Interestingly, P53 element appears to repress the transcription of p35 gene.

AP1000{sup R} licensing and deployment in the United States

Energy Technology Data Exchange (ETDEWEB)

Jordan, R. P.; Russ, P. A.; Filiak, P. P.; Castiglione, L. L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2012-07-01

In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two new nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing

Tank 241-AP-106, Grab samples, 6AP-98-1, 6AP-98-2 and 6AP-98-3 Analytical results for the final report

Energy Technology Data Exchange (ETDEWEB)

FULLER, R.K.

1999-02-23

This document is the final report for tank 241-AP-106 grab samples. Three grab samples 6AP-98-1, 6AP-98-2 and 6AP-98-3 were taken from riser 1 of tank 241-AP-106 on May 28, 1998 and received by the 222-S Laboratory on May 28, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) (Sasaki, 1998) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded. The request for sample analysis received for AP-106 indicated that the samples were polychlorinated biphenyl (PCB) suspects. The results of this analysis indicated that no PCBs were present at the Toxic Substance Control Act (TSCA) regulated limit of 50 ppm. The results and raw data for the PCB analysis are included in this document.

Tank 241-AP-106, Grab samples, 6AP-98-1, 6AP-98-2 and 6AP-98-3 Analytical results for the final report

International Nuclear Information System (INIS)

FULLER, R.K.

1999-01-01

This document is the final report for tank 241-AP-106 grab samples. Three grab samples 6AP-98-1, 6AP-98-2 and 6AP-98-3 were taken from riser 1 of tank 241-AP-106 on May 28, 1998 and received by the 222-S Laboratory on May 28, 1998. Analyses were performed in accordance with the ''Compatability Grab Sampling and Analysis Plan'' (TSAP) (Sasaki, 1998) and the ''Data Quality Objectives for Tank Farms Waste Compatability Program (DQO). The analytical results are presented in the data summary report. No notification limits were exceeded. The request for sample analysis received for AP-106 indicated that the samples were polychlorinated biphenyl (PCB) suspects. The results of this analysis indicated that no PCBs were present at the Toxic Substance Control Act (TSCA) regulated limit of 50 ppm. The results and raw data for the PCB analysis are included in this document

Loss-of-normal-feedwater sensitivity studies for AP600 behavior characterization

International Nuclear Information System (INIS)

Saiu, G.

1996-01-01

Activity concerning the development of a RELAP5/MOD3 model to simulate the Westinghouse Electric Corporation AP600 is summarized. The aim is to gain initial insight into the capability of RELAP5 to simulate the behavior of AP600 safety features. A-loss-of-normal-feedwater event is studied. Of the transients that must be investigated, this transient has been chosen to be one of the most relevant because the response of the AP600 to a loss-of-normal-feedwater event differs significantly from that of current pressurized water reactors in the extensive use of passive safety features peculiar to the AP600. Also, strong interactions among the AP600 safety systems, which should be further analyzed to permit full optimization of the system actuation logic and operation, are shown. Finally, a loss of normal feedwater without reactor scram, performed to investigate short-term plant behavior, shows that the pressure peak is affected by critical discharge flow coefficients applied to the pressurizer safety valves, while a relatively small reduction of the pressure peak is observed when both heat exchangers of the passive heat removal system are operating as opposed to the case in which only one is available. The data used for this study are derived from the Standard Safety Analysis Report configuration of the Westinghouse AP600 as of 1992

76 FR 65653 - New Source Performance Standards (NSPS) Review

Science.gov (United States)

2011-10-24

... current within their review cycle, there are also multiple standards in different phases of the review... Rock Plants NN 04/16/1982 (47FR16589) 10/17/2000 3 4 (65FR61760) Polymeric Coating of Supporting VVV 09... whether review of a particular NSPS is necessary during the review cycle. A listing of any NSPS for which...

75 FR 76928 - Safety Management System for Certificated Airports; Extension of Comment Period

Science.gov (United States)

2010-12-10

...-0997; Notice No. 10-14] RIN 2120-AJ38 Safety Management System for Certificated Airports; Extension of... holder to establish a safety management system (SMS) for its entire airfield environment (including... ``Safety Management System for Certificated Airports'' (75 FR 62008). Comments to that document were to be...

Aviation Safety Program: Weather Accident Prevention (WxAP) Project Overview and Status

Science.gov (United States)

Nadell, Shari-Beth

2003-01-01

This paper presents a project overview and status for the Weather Accident Prevention (WxAP) aviation safety program. The topics include: 1) Weather Accident Prevention Project Background/History; 2) Project Modifications; 3) Project Accomplishments; and 4) Project's Next Steps.

AP190L and PDP-KI10: a hardware/software measurement report

International Nuclear Information System (INIS)

Maron, N.; Sutherland, G.G.

1979-01-01

This report discusses an AP190L array processor (manufactured by Floating Point Systems of Beaverton, Oregon) interfaced to a PDP-10 (Digital Equipment Corporation, Maynard, Mass.). After AP software installation, an analysis of the overhead was performed. The results of these measurements and some conclusions are presented. An AP monitor and software interface were written to minimize the overhead from the PDP-10. A vector extension to the FORTRAN language called FIVE was developed to increase user access to the AP. Some of the problems associated with defining and implementing FIVE are discussed. Its successes and limitations are reviewed. 2 figures, 2 tables

76 FR 33639 - Safety Zone; New York Water Taxi 10th Anniversary Fireworks

Science.gov (United States)

2011-06-09

...-AA00 Safety Zone; New York Water Taxi 10th Anniversary Fireworks, Upper New York Bay, Red Hook, NY... New York Water Taxi. The fireworks will commence at 9 p.m. on June 21, 2011 and will last... CFR Part 165 Harbors, Marine safety, Navigation (water), Reporting and recordkeeping requirements...

76 FR 22342 - National Standard 10 Guidelines

Science.gov (United States)

2011-04-21

.... 110218147-1199-01] RIN 0648-BA74 National Standard 10 Guidelines AGENCY: National Marine Fisheries Service... comment on potential adjustments to the National Standard 10 Guidelines. DATES: Written comments regarding... advisory guidelines (which shall not have the force and effect of law), based on the national standards to...

75 FR 15620 - Federal Motor Vehicle Safety Standards; Air Brake Systems

Science.gov (United States)

2010-03-30

... fully develop improved brake systems and also to ensure vehicle control and stability while braking... [Docket No. NHTSA 2009-0175] RIN 2127-AK62 Federal Motor Vehicle Safety Standards; Air Brake Systems... Federal motor vehicle safety standard for air brake systems by requiring substantial improvements in...

78 FR 9623 - Federal Motor Vehicle Safety Standards; Air Brake Systems

Science.gov (United States)

2013-02-11

... initial speeds, vehicle manufacturers will need to develop unique or complicated braking systems to comply... [Docket No. NHTSA-2013-0011] RIN 2127-AL11 Federal Motor Vehicle Safety Standards; Air Brake Systems... rule that amended the Federal motor vehicle safety standard for air brake systems by requiring...

Research on quality assurance classification methodology for domestic AP1000 nuclear power projects

International Nuclear Information System (INIS)

Bai Jinhua; Jiang Huijie; Li Jingyan

2012-01-01

To meet the quality assurance classification requirements of domestic nuclear safety codes and standards, this paper analyzes the quality assurance classification methodology of domestic AP1000 nuclear power projects at present, and proposes the quality assurance classification methodology for subsequent AP1000 nuclear power projects. (authors)

76 FR 44829 - Federal Motor Vehicle Safety Standards; Air Brake Systems

Science.gov (United States)

2011-07-27

... [Docket No. NHTSA-2009-0175] RIN 2127-AK84 Federal Motor Vehicle Safety Standards; Air Brake Systems... final rule that amended the Federal motor vehicle safety standard for air brake systems by requiring... between Bendix Commercial Vehicle Systems and Dana Corporation; and ArvinMeritor. The agency received four...

Induction of activator protein (AP)-1 and nuclear factor-kappaB by CD28 stimulation involves both phosphatidylinositol 3-kinase and acidic sphingomyelinase signals.

Science.gov (United States)

Edmead, C E; Patel, Y I; Wilson, A; Boulougouris, G; Hall, N D; Ward, S G; Sansom, D M

1996-10-15

A major obstacle in understanding the signaling events that follow CD28 receptor ligation arises from the fact that CD28 acts as a costimulus to TCR engagement, making it difficult to assess the relative contribution of CD28 signals as distinct from those of the TCR. To overcome this problem, we have exploited the observation that activated human T cell blasts can be stimulated via the CD28 surface molecule in the absence of antigenic challenge; thus, we have been able to observe the response of normal T cells to CD28 activation in isolation. Using this system, we observed that CD28 stimulation by B7-transfected CHO cells induced a proliferative response in T cells that was not accompanied by measurable IL-2 production. However, subsequent analysis of transcription factor generation revealed that B7 stimulation induced both activator protein-1 (AP-1) and nuclear factor-kappaB (NF-kappaB) complexes, but not NF-AT. In contrast, engagement of the TCR by class II MHC/superantigen, either with or without CD28 ligation, resulted in the induction of NF-AT, AP-1, and NF-kappaB as well as IL-2 production. Using selective inhibitors, we investigated the signaling pathways involved in the CD28-mediated induction of AP-1 and NF-kappaB. This revealed that NF-kappaB generation was sensitive to chloroquine, an inhibitor of acidic sphingomyelinase, but not to the phosphatidylinositol 3-kinase inhibitor, wortmannin. In contrast, AP-1 generation was inhibited by wortmannin and was also variably sensitive to chloroquine. These data suggest that in activated normal T cells, CD28-derived signals can stimulate proliferation at least in part via NF-kappaB and AP-1 generation, and that this response uses both acidic sphingomyelinase and phosphatidylinositol 3-kinase-linked pathways.

Nuclear transparency in 90 deg.c.m. quasielastic A(p,2p) reactions

International Nuclear Information System (INIS)

Aclander, J.; Alster, J.; Kosonovsky, I.; Malki, A.; Mardor, I.; Mardor, Y.; Navon, I.; Piasetzky, E.; Asryan, G.; Barton, D.S.; Buktoyarova, N.; Bunce, G.; Carroll, A.S.; Gushue, S.; Makdisi, Y.I.; Roser, T.; Tanaka, M.; Averiche, Y.; Panebratsev, Y.; Shimanskiy, S.

2004-01-01

We summarize the results of two experimental programs at the Alternating Gradient Synchrotron of BNL to measure the nuclear transparency of nuclei measured in the A(p,2p) quasielastic scattering process near 90 deg. in the pp center of mass. The incident momenta varied from 5.9 to 14.4 GeV/c, corresponding to 4.8 2 2 . Taking into account the motion of the target proton in the nucleus, the effective incident momenta extended from 5.0 to 15.8 GeV/c. First, we describe the measurements with the newer experiment, E850, which had more complete kinematic definition of quasielastic events. E850 covered a larger range of incident momenta, and thus provided more information regarding the nature of the energy dependence of the nuclear transparency. In E850 the angular dependence of the nuclear transparency near 90 deg. and the nuclear transparency deuterons were studied. Second, we review the techniques used in an earlier experiment, E834, and show that the two experiments are consistent for the carbon data. E834 also determines the nuclear transparencies for lithium, aluminum, copper, and lead nuclei as well as for carbon. A determination of the (π + ,π + p) transparencies is also reported. We find for both E850 and E834 that the A(p,2p) nuclear transparency, unlike that for A(e,e ' p) nuclear transparency, is incompatible with a constant value versus energy as predicted by Glauber calculations. The A(p,2p) nuclear transparency for carbon and aluminum increases by a factor of two between 5.9 and 9.5 GeV/c incident proton momentum. At its peak the A(p,2p) nuclear transparency is ∼80% of the constant A(e,e ' p) nuclear transparency. Then the nuclear transparency falls back to a value at least as small as that at 5.9 GeV/c, and is compatible with the Glauber level again. This oscillating behavior is generally interpreted as an interplay between two components of the pN scattering amplitude; one short ranged and perturbative, and the other long ranged and strongly absorbed

75 FR 6123 - Federal Motor Vehicle Safety Standards; Occupant Crash Protection

Science.gov (United States)

2010-02-08

... motor vehicle safety standard is in effect under this chapter, a State or a political subdivision of a... [Docket No. NHTSA-2009-0156] RIN 2127-AK57 Federal Motor Vehicle Safety Standards; Occupant Crash...'s response to petitions for reconsideration of a November 12, 2008 final rule that amended the child...

75 FR 22317 - Federal Motor Vehicle Safety Standards; Small Business Impacts of Motor Vehicle Safety

Science.gov (United States)

2010-04-28

... 1300 [Docket No. NHTSA-2010-0054] Federal Motor Vehicle Safety Standards; Small Business Impacts of Motor Vehicle Safety AGENCY: National Highway Traffic Safety Administration (NHTSA), Department of..., multipurpose passenger vehicles, trucks, buses, trailers, incomplete vehicles, motorcycles, and motor vehicle...

Kepler observations of rapidly oscillating Ap, δ Scuti and γ Doradus pulsations in Ap stars

DEFF Research Database (Denmark)

Balona, Luis A.; Cunha, Margarida S.; Kurtz, Donald W.

2011-01-01

Observations of the A5p star KIC 8677585 obtained during the Kepler 10-d commissioning run with 1-min time resolution show that it is a rapidly oscillating Ap (roAp) star with several frequencies with periods near 10 min. In addition, a low frequency at 3.142 d−1 is also clearly present....... Multiperiodic γ Doradus (γ Dor) and δ Scuti (δ Sct) pulsations, never before seen in any Ap star, are present in Kepler observations of at least three other Ap stars. Since γ Dor pulsations are seen in Ap stars, it is likely that the low frequency in KIC 8677585 is also a γ Dor pulsation. The simultaneous...... presence of both γ Dor and roAp pulsations and the unexpected detection of δ Sct and γ Dor pulsations in Ap stars present new opportunities and challenges for the interpretation of these stars. Since it is easy to confuse Am and Ap stars at classification dispersions, the nature of these Ap stars...

Westinghouse AP1000 licensing maturity

International Nuclear Information System (INIS)

Schulz, T.; Vijuk, R.P.

2005-01-01

The Westinghouse AP1000 Program is aimed at making available a nuclear power plant that is economical in the U.S deregulated electrical power industry in the near-term. The AP1000 is two-loop 1000 MWe pressurizer water reactor (PWR). It is an up rated version of the AP600. The AP1000 uses passive safety systems to provide significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The AP1000 uses proven technology, which builds on over 35 years of operating PWR experience. The AP1000 received Final Design Approval by the United States Nuclear Regulatory Commission (U.S. NRC) in September 2004. The AP1000 meets the US utility requirements. The AP1000 and its sister plant the AP600 have gone through a very through and complete licensing review. This paper describes the U.S. NRC review efforts of both the AP600 and the AP1000. The detail of the review and the independent calculations, evaluations and testing is discussed. The AP600 licensing documentation was submitted in 1992. The U.S. NRC granted Final Design Approval in 1999. During the intervening 7 years, the U.S. NRC asked thousands of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. For the AP1000 Westinghouse first engaged the U.S. NRC in pre-certification discussions to define the extent of the review required, since the design is so similar to the AP600. The AP1000 licensing documentation was submitted in March 2002. The U.S. NRC granted Final Design Approval in September 2004. During the intervening 2 1/2 years, the U.S. NRC asked hundreds of questions, performed independent safety analysis, audited Westinghouse calculations and analysis, and performed independent testing. The more significant areas of discussion will be described. The implications of this review and approval on AP1000 applications in

28 CFR 32.0 - Scope of part.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Scope of part. 32.0 Section 32.0 Judicial Administration DEPARTMENT OF JUSTICE PUBLIC SAFETY OFFICERS' DEATH, DISABILITY, AND EDUCATIONAL ASSISTANCE...) Educational assistance benefits. [73 FR 76528, Dec. 17, 2008] ...

75 FR 76692 - Federal Motor Vehicle Safety Standards; Small Business Impacts of Motor Vehicle Safety

Science.gov (United States)

2010-12-09

..., 510, 511, 512, 520, 523, 525, 526, and 571 [Docket No. NHTSA-2010-0159] Federal Motor Vehicle Safety Standards; Small Business Impacts of Motor Vehicle Safety AGENCY: National Highway Traffic Safety... that specifically relate to passenger cars, multipurpose passenger vehicles, trucks, buses, trailers...

75 FR 62739 - 2017 and Later Model Year Light Duty Vehicle GHG Emissions and CAFE Standards; Notice of Intent

Science.gov (United States)

2010-10-13

... Model Year Light Duty Vehicle GHG Emissions and CAFE Standards; Notice of Intent AGENCIES: Environmental... fuel economy (CAFE) standards in accordance with the Energy Policy and Conservation Act (EPCA), as... FR 49454, 49460 (September 28, 2009). The NHTSA CAFE standards are only based on technologies that...

[Traditional risk factors for cardiovascular disease in primary antiphospholipid syndrome (APS) when compared with secondary APS: a study with 96 patients].

Science.gov (United States)

Ribeiro, A R; Carvalho, J F

2010-01-01

To evaluate the prevalence of traditional risk factors in patients with primary antiphospholipid syndrome (APS) in comparison to those with systemic lupus erythematosus-secondary APS. Transversal study of 96 APS patients (Sapporo's criteria). Demographic and clinical data, cardiovascular risk factors and drug use were investigated. Thirty-nine Primary APS and 57 secondary APS were included. The groups did not differ regarding age (38.5 +/- 9.9 vs. 39.4 +/- 10.5 years, p=0.84) and female gender (84.6 vs. 96.5%, p=0.06), respectively. Arterial events were more observed in primary than secondary APS (59 vs. 36.8%, p=0.04) patients. No difference was seen concerning venous and obstetric events. In regard to traditional risk factors for cardiovascular disease, both groups were comparable related to current or previous smoking, sedentarism, family history for coronary disease, systemic hypertension, diabetes mellitus, overweight and obesity. The frequencies of altered lipid profiles were alike in the two groups, except for a higher prevalence of low HDL-c levels in primary APS group (84.6 vs. 45.5%, p=0.0001). Concerning drug use, no significant differences were observed related to chloroquine and statin use, however the secondary APS patients had a higher rate of prednisone use (10.2 vs. 57.9%, pAPS, except for a high frequency of low HDL-c in primary APS patients.

77 FR 73345 - Safety Standard for Bedside Sleepers

Science.gov (United States)

2012-12-10

... durable infant or toddler products, in consultation with representatives of consumer groups, juvenile... Commission (Commission or CPSC) to promulgate consumer product safety standards for durable infant or toddler... marking, labeling, and instructional literature of the proposed rule should be directed to the Office of...

Expression, purification, crystallization and structure of human adipocyte lipid-binding protein (aP2)

International Nuclear Information System (INIS)

Marr, Eric; Tardie, Mark; Carty, Maynard; Brown Phillips, Tracy; Wang, Ing-Kae; Soeller, Walt; Qiu, Xiayang; Karam, George

2006-01-01

The crystal structure of human adipocyte lipid-binding protein (aP2) with a bound palmitate is reported at 1.5 Å resolution. Human adipocyte lipid-binding protein (aP2) belongs to a family of intracellular lipid-binding proteins involved in the transport and storage of lipids. Here, the crystal structure of human aP2 with a bound palmitate is described at 1.5 Å resolution. Unlike the known crystal structure of murine aP2 in complex with palmitate, this structure shows that the fatty acid is in a folded conformation and that the loop containing Phe57 acts as a lid to regulate ligand binding by excluding solvent exposure to the central binding cavity

Westinghouse AP1000® PWR: Meeting Customer Commitments and Market Needs

International Nuclear Information System (INIS)

Shulyak, Nick

2014-01-01

Westinghouse Electric Company once again sets a new industry standard with the AP1000 reactor. Historically, Westinghouse plant designs and technology have forged the cutting edge of worldwide nuclear technology. Today, about 50 percent of the world's 440 nuclear plants are based on Westinghouse technology. The AP1000 is the safest and most economical nuclear power plant available in the worldwide commercial marketplace, and is the only Generation III+ reactor to receive Design Certification from the U.S. Nuclear Regulatory Commission (NRC). The AP1000 features proven technology, innovative passive safety systems and offers: Unequalled safety, Economic competitiveness, Improved and more efficient operations. The AP1000 builds and improves upon the established technology of major components used in current Westinghouse-designed plants with proven, reliable operating experience over the past 50 years. These components include: Steam generators, Digital instrumentation and controls, Fuel, Pressurizers, Reactor vessels. Simplification was a major design objective for the AP1000. The simplified plant design includes overall safely systems, normal operating systems, the control room, construction techniques, and instrumentation and control systems. The result is a plant that is easier and less expensive to build, operate and maintain. The AP1000 design saves money and time with an accelerated construction time period of approximately 36 months, from the pouring of first concrete to the loading of fuel. Also, the innovative AP1000 features: 50% fewer safety-related valves, 80% less safety-related piping, 85% less control cable, 35% fewer pumps , 45% less seismic building volume. Eight AP1000 units under construction worldwide-Four units in China-Four units in the United States. (author)

The dyad palindromic glutathione transferase P enhancer binds multiple factors including AP1.

Science.gov (United States)

Diccianni, M B; Imagawa, M; Muramatsu, M

1992-10-11

Glutathione Transferase P (GST-P) gene expression is dominantly regulated by an upstream enhancer (GPEI) consisting of a dyad of palindromically oriented imperfect TPA (12-O-tetradecanoyl-phorbol-13-acetate)-responsive elements (TRE). GPEI is active in AP1-lacking F9 cells as well in AP1-containing HeLa cells. Despite GPEI's similarity to a TRE, c-jun co-transfection has only a minimal effect on transactivation. Antisense c-jun and c-fos co-transfection experiments further demonstrate the lack of a role for AP1 in GPEI mediated trans-activation in F9 cells, although endogenously present AP1 can influence GPEI in HeLa cells. Co-transfection of delta fosB with c-jun, which forms an inactive c-Jun/delta FosB heterodimer that binds TRE sequences, inhibits GPEI-mediated transcription in AP1-lacking F9 cells as well as AP1-containing HeLa cells. These data suggest novel factor(s) other than AP1 are influencing GPEI. Binding studies reveal multiple nucleoproteins bind to GPEI. These factors are likely responsible for the high level of GPEI-mediated transcription observed in the absence of AP1 and during hepatocarcinogenesis.

Recommendation for an European wind turbine safety standard

Energy Technology Data Exchange (ETDEWEB)

Hjuler Jensen, P.; Hauge Madsen, P.; Winther-Jensen, M.; Machielse, L.; Stam, W.; Einsfeld, V.; Woelfel, E.; Elliot, G.; Wilde, L. de

1988-09-15

The objective is to establish an European standard for wind safety which should apply for all member countries of the European Communities. The document contains a list of recommended safety requirements in relation to the system, structure, electrical installations, operation and maintenance of wind turbines. The recommended safety standards cover electricity producing wind turbines connected to electricity grids in both single and cluster applications and with a swept area in excess of 25 square meters and/or a rated power of 10kW. The document should be used in combination with The European Standards for Wind Turbine Loads and other relevant European Standards. Environmental condition, with the emphasis of wind conditions and more extreme climatic conditions, are also considered in relation to safety requirements. (AB).

Order of 10 october 1977 on the special safety measures applicable to certain large nuclear installations

International Nuclear Information System (INIS)

1978-01-01

This Order by the Minister of Industry, Commerce and Crafts and the Minister of Labour was made in implementation of Section 40 of Decree No. 75-306 of 28 April 1975 on the protection of workers against the hazards of ionizing radiation in large nuclear installations. It lays down the safety measures applicable to nuclear reactors and ancillary facilities, particle accelerators, irradiated fuel reprocessing plants and facilities for the storage of radioactive waste. (NEA) [fr

46 CFR 28.10 - Authority.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Authority. 28.10 Section 28.10 Shipping COAST GUARD... General Provisions § 28.10 Authority. The regulations in this part are prescribed by the Commandant of the Coast Guard, pursuant to a delegation of authority by the Secretary of Homeland Security set forth in...

AP1000 Design for Security

International Nuclear Information System (INIS)

Long, L.B.; Cummins, W.E.; Winters, J.W.

2006-01-01

Nuclear power plants are protected from potential security threats through a combination of robust structures around the primary system and other vital equipment, security systems and equipment, and defensive strategy. The overall objective for nuclear power plant security is to protect public health and safety by ensuring that attacks or sabotage do not challenge the ability to safely shutdown the plant or protect from radiological releases. In addition, plants have systems, features and operational strategies to cope with external conditions, such as loss of offsite power, which could be created as part of an attack. Westinghouse considered potential security threats during design of the AP1000 PWR. The differences in plant configuration, safety system design, and safe shutdown equipment between existing plants and AP1000 affect potential vulnerabilities. This paper provides an evaluation of AP1000 with respect to vulnerabilities to security threats. The AP1000 design differs from the design of operating PWRs in the US in the configuration and the functional requirements for safety systems. These differences are intentional departures from conventional PWR designs which simplify plant design and enhance overall safety. The differences between the AP1000 PWR and conventional PWRs can impact vulnerabilities to security threats. The NRC addressed security concerns as part of their reviews for AP1000 Design Certification, and did not identify any security issues of concern. However, much of the detailed security design information for the AP1000 was deferred to the combined Construction and Operating License (COL) phase as many of the security issues are site-specific. Therefore, NRC review of security issues related to the AP1000 is not necessarily complete. Further, since the AP1000 plant design differs from existing PWRs, it is not obvious that the analyses and assessments prepared for existing plants also apply to the AP1000. We conclude that, overall, the AP1000

Food Safety & Standards

Institute of Scientific and Technical Information of China (English)

无

2005-01-01

@@ An increasing number of people have realized that food safety is an important issue for public health. It not only concerns public health and safety, but also has direct influence on national economic progress and social development. The development and implementation of food safety standards play a vital role in protecting public health, as well as in standardizing and facilitating the sound development of food production and business.

Radiological and nuclear safety- evolution, standards and similarity

International Nuclear Information System (INIS)

Soman, S.D.

1996-01-01

With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

28 CFR 345.83 - Job safety training.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Job safety training. 345.83 Section 345... INDUSTRIES (FPI) INMATE WORK PROGRAMS FPI Inmate Training and Scholarship Programs § 345.83 Job safety training. FPI provides inmates with regular job safety training which is developed and scheduled in...

78 FR 15920 - Federal Motor Vehicle Safety Standards; Tire Selection and Rims

Science.gov (United States)

2013-03-13

... [Docket No. NHTSA-2013-0030] RIN 2127-AL24 Federal Motor Vehicle Safety Standards; Tire Selection and Rims... Safety Standard (FMVSS) No. 110 to make it clear that special trailer (ST) tires are permitted to be... also proposes to exclude these trailers from a vehicle testing requirement that a tire must be retained...

Synthesis of diadenosine 5', 5'''-P1, P4-tetraphosphate (AP4A) in sea urchin embryos

International Nuclear Information System (INIS)

Morioka, Mizue; Shimada, Hiraku

1984-01-01

Sea urchin embryos were labeled with ( 3 H)adenosine at two developmental stages (morula and prism) and the labeled acid-soluble nucleotides were fractionated successively by column chromatography with DEAE-Sephadex and DEAE-cellulose, and by thin-layer chromatography on a PEI-cellulose plate. Significant radioactivity was detected on the PEI-cellulose plate at the region of diadenosine 5', 5'''-P 1 , P 4 -tetraphosphate (AP 4 A). After treatment of this fraction with phosphodiesterase, the radioactivity was all recovered in the AMP region, while alkaline phosphatase had no effect on the AP 4 A fraction. The present result suggests that AP 4 A is actively synthesized in the sea urchin embryos. (author)

Safety first. Status reports on the IAEA's safety standards

International Nuclear Information System (INIS)

Webb, G.; Karbassioun, A.; Linsley, G.; Rawl, R.

1998-01-01

Documents in the IAEA's Safety Standards Series known as RASS (Radiation Safety Standards) are produced to develop an internally consistent set of regulatory-style publications that reflects an international consensus on the principles of radiation protection and safety and their application through regulation. In this article are briefly presented the Agency's programmes on Nuclear Safety Standards (NUSS), Radioactive Waste Safety Standards (RADWASS), and Safe Transport of Radioactive Materials

10CFR50.59 safety evaluations

International Nuclear Information System (INIS)

Grime, L.; Page, E.

1987-01-01

As a plant changes from the design phase to the operational phase, new regulations and standards apply. One such regulation is 10CFR50.59 on safety evaluations. Once an operating license is issued, it is mandatory to submit all applicable changes, tests, and experiments to the safety evaluation process. As preparation for this transition, Detroit Edison had procedures in place and conducted personnel training. Reviews of the safety engineering were conducted by the on-site review board. The off-site board delegated detailed reviews of most safety evaluations to the independent safety evaluation group (ISEG). The on-site group review included presentation of complete design packages by engineers. The ISEG and off-site review group's activity focused on safety evaluation. This paper addresses industry trends that were studied, Detroit Edison's recent actions, and industry issues related to 10CFR50.59 safety evaluations

Gamma spectroscopy of 33Cl and 29P fed in 32S(p,γ)33Cl and 28Si(p,γ)29P reactions

International Nuclear Information System (INIS)

Aleonard, M.-M.

1975-01-01

The properties of the levels of the A=4N+1 33 Cl and 29 P nuclei were studied via the 32 S(p,γ) 33 Cl and 28 Si(p,γ) 29 P reactions. Absolute and relative resonance strength measurements were performed in chlorine and phosphorus isotopes with 80cm 3 Ge(Li) detector and natural targets of sulfur or silicon compounds. Three new resonances were observed in the 32 S(p,γ) 33 Cl reaction at E(p)=1588, 1748 and 1880keV and a doublet clearly shown at E(p) approximately equal to 1900keV. The Q-value of the reaction, as well as the energies, γ-branching, and mean lifetimes of the levels below E(x)=4.78MeV were measured. The spins of the E(x)=2.35, 3.82, 3.97 and 4.78MeV levels were determined. A comparison of the γ-ray transition strengths is made against mirror transitions and shell-model or weak coupling model predictions, for positive and negative parity states. Resonance strengths and decays of 29 P levels populated via the 28 Si(p,γ) 29 P reaction were measured for E(p)=0.4 to 2.28MeV. Pecular attention was paid to the E(x)=3447 and 4642keV levels. Resonance strengths as well as γ-branching, mean lifetimes and angular distributions lead to the following characteristics: E(x)=3447keV, J(π)=7/2 - , tau=13+-(9)7fs; E(x)=4642keV, J(π)=3/2 + , 5/2-9/2, tau=52+-20fs. Comparison of the mirror levels characteristics in 29 Si and 29 P favours a J(π)=9/2 + assignment for the E(x)=4642keV level [fr

45 CFR 2543.84 - Contract Work Hours and Safety Standards Act.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Contract Work Hours and Safety Standards Act. 2543... OTHER NON-PROFIT ORGANIZATIONS Statutory Compliance § 2543.84 Contract Work Hours and Safety Standards Act. Where applicable, all contracts awarded by recipients in excess of $2000 for construction...

76 FR 30308 - National Standard 10 Guidelines; Public Meetings

Science.gov (United States)

2011-05-25

... Standard 10 Guidelines; Public Meetings AGENCY: National Marine Fisheries Service (NMFS), National Oceanic... to the National Standard 10 (NS10) Guidelines and announced a public meeting to be held on May 19... presentations will be given on the National Standard 10 ANPR. The public will be allowed to comment at the...

76 FR 52231 - Restrictions on Operators Employing Former Flight Standards Service Aviation Safety Inspectors

Science.gov (United States)

2011-08-22

... its implementation of safety management systems, issued its report titled, ``Managing Risks in Civil... Standards Service Aviation Safety Inspectors AGENCY: Federal Aviation Administration (FAA), DOT. ACTION... responsible for the oversight of, a Flight Standards Service Aviation Safety Inspector, and had direct...

Regulatory practices and safety standards for nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The International Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants was jointly organized by the International Atomic Energy Agency (IAEA), for Nuclear Energy Agency of the OECD and the Government of the Federal Republic of Germany with the objective of providing an international forum for the exchange of information on regulatory practices and safety standards for nuclear power plants. The Symposium was held in Munich, Federal Republic of Germany, from 7 to 10 November 1988. It was attended by 201 experts from some 32 Member States and 4 international organizations. Fifty-one papers from 19 Member States and 2 international organizations were presented and discussed in 5 technical sessions covering the following subjects: National Regulatory Practices and Safety Standards (14 papers); Implementation of Regulatory Practices - Technical Issues (8 papers); Implementation of Regulatory Practices - Operational Aspects (8 papers); Developments and Trends in Safety Standards and Practices (11 papers); International Aspects (10 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

76 FR 29333 - Pipeline Safety: Meetings of the Technical Pipeline Safety Standards Committee and the Technical...

Science.gov (United States)

2011-05-20

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Technical Hazardous Liquid Pipeline Safety Standards Committee AGENCY: Pipeline and Hazardous Materials... for natural gas pipelines and for hazardous liquid pipelines. Both committees were established under...

75 FR 38432 - Railroad Safety Appliance Standards, Miscellaneous Revisions

Science.gov (United States)

2010-07-02

...: Stephen J. Carullo, Railroad Safety Specialist, Office of Safety, FRA, 1200 New Jersey Avenue, SE..., Office of Chief Counsel, FRA, 1200 New Jersey Avenue, SE., Mail Stop 10, Washington, DC 20590 (telephone... government (FRA and Transport Canada participate as non-voting members), as well as ergonomics experts. The...

77 FR 15351 - Federal Motor Vehicle Safety Standards; Theft Protection and Rollaway Prevention

Science.gov (United States)

2012-03-15

... [Docket No. NHTSA-2011-0174] RIN 2127-AK88 Federal Motor Vehicle Safety Standards; Theft Protection and... (NPRM) to amend Federal Motor Vehicle Safety Standard (FMVSS) No. 114, Theft Protection and Rollaway... requesting that certain information, including vehicle owner questionnaires (VOQs) referenced in the NPRM, be...

The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000

International Nuclear Information System (INIS)

Schene, R.

2009-01-01

Featuring proven technology and innovative passive safety systems, the Westinghouse AP1000 pressurized water reactor can achieve competitive generation costs in the current electricity market without emitting harmful greenhouse gases and further harming the environment. Westinghouse Electric Company, the pioneer in nuclear energy once again sets a new industry standard with the AP1000. The AP1000 is a two-loop pressurized water reactor that uses simplified, innovative and effective approach to safety. With a gross power rating of 3415 megawatt thermal and a nominal net electrical output of 1117 megawatt electric, the AP1000 is ideal for new base load generation. The AP1000 is the safest and most economical nuclear power plant available in the worldwide commercial marketplace, and is the only Generation III+ reactor to receive a design certification from the U.S. Nuclear Regulatory Commission (NRC). Based on nearly 20 years of research and development, the AP1000 builds and improves upon the established technology of major components used in current Westinghouse designed plants. These components, including steam generators, digital instrumentation and controls, fuel, pressurizers, and reactor vessels, are currently in use around the world and have years of proven, reliable operating experience. Historically, Westinghouse plant designs and technology have forged the cutting edge technology of nuclear plant around the world. Today, nearly 50 percent of the world's 440 nuclear plants are based on Westinghouse technology. Westinghouse continues to be the nuclear industry's global leader. (author)

76 FR 55056 - Toy Safety Standard: Strategic Outreach and Education Plan

Science.gov (United States)

2011-09-06

... to test and certify to the toy safety standard. We plan to use traditional and social media to... testing and certification requirements for children's toys and toy chests and their compliance with ASTM... manufacturers of children's toys must ensure that covered toys are tested for compliance with the toy safety...

Contribution of the C.E.A. to standardization of nuclear plant equipments

International Nuclear Information System (INIS)

Dumax, P.; Seran, R.

1980-01-01

In research and production laboratories working in the nuclear field standardization of equipments greatly improves the profits of the installation and the protection of individuals and goods. The standardization effort on technical equipments of shielding, handling, detection and safety (so called P.M.D.S.) initiated by the C.E.A. in 1967 is being carried out now within the Institute of Protection and Nuclear Safety (I.P.S.N.) by a technical Service specialized in protection and dosimetry (S.T.E.P.D.). Its purpose is to establish standardization documents for internal use and to take part in the work of official standardization organizations. The benefits of standardization are reviewed. The achievements of the various working groups common to C.E.A. centers are stated and the documents published or to be published are listed [fr

75 FR 51521 - Federal Motor Vehicle Safety Standards; Air Brake Systems; Technical Report on the Effectiveness...

Science.gov (United States)

2010-08-20

....121) mandates antilock braking systems (ABS) on all new air-braked vehicles with a GVWR of 10,000...-0116] Federal Motor Vehicle Safety Standards; Air Brake Systems; Technical Report on the Effectiveness of Antilock Braking Systems in Heavy Truck Tractors and Trailers AGENCY: National Highway Traffic...

Final characterization and safety screen report of double shell tank 241-AP-105 for evaporator campaign 97-1

International Nuclear Information System (INIS)

Miller, G.L.

1997-01-01

Evaporator candidate feed from tank 241-AP-105 (hereafter referred to as AP-105) was characterized for physical, inorganic, organic and radiochemical parameters by the 222-S Laboratory as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4, and Engineering Change Notice, number 635332, Reference 5. This data package satisfies the requirement for a format IV, final report as described in Reference 1. This data package is also a follow-up to the 45-Day safety screen results for tank AP-105, Reference 8, which was issued on November 5, 1996, and is attached as Section II to this report. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory's Quality Assurance P1an, References 6 and 7. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation

Testing of Software Routine to Determine Deviate and Cumulative Probability: ModStandardNormal Version 1.0

International Nuclear Information System (INIS)

A.H. Monib

1999-01-01

The purpose of this calculation is to document that the software routine ModStandardNomal Version 1.0 which is a Visual Fortran 5.0 module, provides correct results for a normal distribution up to five significant figures (three significant figures at the function tails) for a specified range of input parameters. The software routine may be used for quality affecting work. Two types of output are generated in ModStandardNomal: a deviate, x, given a cumulative probability, p, between 0 and 1; and a cumulative probability, p, given a deviate, x, between -8 and 8. This calculation supports Performance Assessment, under Technical Product Development Plan, TDP-EBS-MD-000006 (Attachment I, DIRS 3) and is written in accordance with the AP-3.12Q Calculations procedure (Attachment I, DIRS 4)

75 FR 57274 - Financial Management and Assurance; Government Auditing Standards

Science.gov (United States)

2010-09-20

... GOVERNMENT ACCOUNTABILITY OFFICE Financial Management and Assurance; Government Auditing Standards.... Dalkin, Director, Financial Management and Assurance. [FR Doc. 2010-23374 Filed 9-17-10; 8:45 am] BILLING... financial and performance auditing drawn from all levels of government, private enterprise, public...

The IAEA safety standards

International Nuclear Information System (INIS)

Karbassioun, Ahmad

1995-01-01

During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

77 FR 22637 - Federal Motor Vehicle Safety Standards; Accelerator Control Systems

Science.gov (United States)

2012-04-16

... revise the Federal Motor Vehicle Safety Standard for accelerator control systems (ACS) in two ways. First... Standard (FMVSS) No. 124, Accelerator Control Systems,\\2\\ in two ways. First, we are proposing to update... February 2011 final report ``Technical Assessment of Toyota Electronic Throttle Control Systems,'' the...

Safety standards and safety record of nuclear power plants

International Nuclear Information System (INIS)

Davis, A.B.

1984-01-01

This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

Performance standards of road safety management

Directory of Open Access Journals (Sweden)

Čabarkapa Milenko R.

2016-01-01

Full Text Available Road safety management controlling means the process of finding out the information whether the road safety is improving in a measure to achieve the objectives. The process of control consists of three basic elements: definition of performances and standards, measurement of current performances and comparison with the set standards, and improvement of current performances, if they deviate from the set standards. The performance standards of road safety management system are focused on a performances measurement, in terms of their design and characteristics, in order to support the performances improvement of road safety system and thus, ultimately, improve the road safety. Defining the performance standards of road safety management system, except that determines the design of the system for performances measurement, directly sets requirements whose fulfillment will produce a road safety improvement. The road safety management system, based on the performance standards of road safety, with a focus on results, will produce the continuous improvement of road safety, achieving the long-term 'vision zero', the philosophy of road safety, that human life and health take priority over mobility and other traffic objectives of the road traffic.

77 FR 76003 - Submission for OMB Review; Comment Request-Safety Standard for Omnidirectional Citizens Band Base...

Science.gov (United States)

2012-12-26

... Request--Safety Standard for Omnidirectional Citizens Band Base Station Antennas AGENCY: Consumer Product... information associated with the Commission's safety standard for omnidirectional citizens band base station... information required in the Safety Standard for Omnidirectional Citizens Band Base Station (16 CFR Part 1204...

The dyad palindromic glutathione transferase P enhancer binds multiple factors including AP1.

OpenAIRE

Diccianni, M B; Imagawa, M; Muramatsu, M

1992-01-01

Glutathione Transferase P (GST-P) gene expression is dominantly regulated by an upstream enhancer (GPEI) consisting of a dyad of palindromically oriented imperfect TPA (12-O-tetradecanoyl-phorbol-13-acetate)-responsive elements (TRE). GPEI is active in AP1-lacking F9 cells as well in AP1-containing HeLa cells. Despite GPEI's similarity to a TRE, c-jun co-transfection has only a minimal effect on transactivation. Antisense c-jun and c-fos co-transfection experiments further demonstrate the lac...

Status of the IAEA safety standards programme

International Nuclear Information System (INIS)

2002-01-01

This presentation describes the status of the IAEA safety standards program to May 2002. The safety standards program overcome whole main nuclear implementations as General safety, Nuclear safety, Radiation safety, Radioactive waste safety, and Transport safety. Throughout this report the first column provides the list of published IAEA Safety Standards. The second gives the working identification number (DS) of standards being developed or revised. The bold type indicates standard issued under the authority the Board of Governors, others are issued under authority of the Director General. The last column provides the list of Committees, the first Committee listed has the lead in the preparation and review of the particular standard

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

NASA relies more and more on software to control, monitor, and verify its safety critical systems, facilities and operations. Since the 1960's there has hardly been a spacecraft launched that does not have a computer on board that will provide command and control services. There have been recent incidents where software has played a role in high-profile mission failures and hazardous incidents. For example, the Mars Orbiter, Mars Polar Lander, the DART (Demonstration of Autonomous Rendezvous Technology), and MER (Mars Exploration Rover) Spirit anomalies were all caused or contributed to by software. The Mission Control Centers for the Shuttle, ISS, and unmanned programs are highly dependant on software for data displays, analysis, and mission planning. Despite this growing dependence on software control and monitoring, there has been little to no consistent application of software safety practices and methodology to NASA's projects with safety critical software. Meanwhile, academia and private industry have been stepping forward with procedures and standards for safety critical systems and software, for example Dr. Nancy Leveson's book Safeware: System Safety and Computers. The NASA Software Safety Standard, originally published in 1997, was widely ignored due to its complexity and poor organization. It also focused on concepts rather than definite procedural requirements organized around a software project lifecycle. Led by NASA Headquarters Office of Safety and Mission Assurance, the NASA Software Safety Standard has recently undergone a significant update. This new standard provides the procedures and guidelines for evaluating a project for safety criticality and then lays out the minimum project lifecycle requirements to assure the software is created, operated, and maintained in the safest possible manner. This update of the standard clearly delineates the minimum set of software safety requirements for a project without detailing the implementation for those

New quantitative safety standards: different techniques, different results?

International Nuclear Information System (INIS)

Rouvroye, J.L.; Brombacher, A.C.

1999-01-01

Safety Instrumented Systems (SIS) are used in the process industry to perform safety functions. Many factors can influence the safety of a SIS like system layout, diagnostics, testing and repair. In standards like the German DIN no quantitative analysis is demanded (DIN V 19250 Grundlegende Sicherheitsbetrachtungen fuer MSR-Schutzeinrichtungen, Berlin, 1994; DIN/VDE 0801 Grundsaetze fuer Rechner in Systemen mit Sicherheitsaufgaben, Berlin, 1990). The analysis according to these standards is based on expert opinion and qualitative analysis techniques. New standards like the IEC 61508 (IEC 61508 Functional safety of electrical/electronic/programmable electronic safety-related systems, IEC, Geneve, 1997) and the ISA-S84.01 (ISA-S84.01.1996 Application of Safety Instrumented Systems for the Process Industries, Instrument Society of America, Research Triangle Park, 1996) require quantitative risk analysis but do not prescribe how to perform the analysis. Earlier publications of the authors (Rouvroye et al., Uncertainty in safety, new techniques for the assessment and optimisation of safety in process industry, D W. Pyatt (ed), SERA-Vol. 4, Safety engineering and risk analysis, ASME, New York 1995; Rouvroye et al., A comparison study of qualitative and quantitative analysis techniques for the assessment of safety in industry, P.C. Cacciabue, I.A. Papazoglou (eds), Proceedings PSAM III conference, Crete, Greece, June 1996) have shown that different analysis techniques cover different aspects of system behaviour. This paper shows by means of a case study, that different (quantitative) analysis techniques may lead to different results. The consequence is that the application of the standards to practical systems will not always lead to unambiguous results. The authors therefore propose a technique to overcome this major disadvantage

AP1000, a nuclear central of advanced design; AP1000, una central nuclear de diseno avanzado

Energy Technology Data Exchange (ETDEWEB)

Hernandez M, N.; Viais J, J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: nhm@nuclear.inin.mx

2005-07-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

77 FR 73354 - Safety Standard for Hand-Held Infant Carriers

Science.gov (United States)

2012-12-10

.... Edwards, Project Manager, Directorate for Engineering Sciences, U.S. Consumer Product Safety Commission, 5..., allergic reactions and near- choking episodes are the most common injuries reported in the remaining 58... modification of the ASTM standard to address the requirements for flammability, surface chemicals, cords...

The development of beam current monitors in the APS

International Nuclear Information System (INIS)

Wang, X.; Lenkszus, F.; Rotela, E.

1995-01-01

The Advanced Photon Source (APS) is a third-generation 7-GeV synchrotron radiation source. The precision measurement of beam current is a challenging task in high energy accelerators, such as the APS, with a wide range of beam parameters and complicated noise, radiation, and thermal environments. The beam pulses in the APS injector and storage ring have charge ranging from 50pC to 25nC with pulse durations varying from 30ps to 30ns. A total of nine non- intercepting beam current monitors have been installed in the APS facility (excluding those in the linac) for general current measurement. In addition, several independent current monitors with specially designed redundant interlock electronics are installed for personnel safety and machine protection. This paper documents the design and development of current monitors in the APS,. discusses the commissioning experience in the past year, and presents the results of recent operations

Survey of familial glioma and role of germline p16INK4A/p14ARF and p53 mutation

DEFF Research Database (Denmark)

Robertson, Lindsay B; Armstrong, Georgina N; Olver, Bianca D

2010-01-01

There is increasing recognition of familial propensity to glioma as a distinct clinical entity beyond a few rare syndromes; however its genetic basis is poorly understood. The role of p16(INK4A)/p14(ARF) and p53 mutations in sporadic glioma provides a strong rationale for investigating germline m...

Setting the standard: The IAEA safety standards set the global reference

International Nuclear Information System (INIS)

Williams, L.

2003-01-01

For the IAEA, setting and promoting standards for nuclear radiation, waste, and transport safety have been priorities from the start, rooted in the Agency's 1957 Statute. Today, a corpus of international standards are in place that national regulators and industries in many countries are applying, and more are being encouraged and assisted to follow them. Considerable work is done to keep safety standards updated and authoritative. They cover five main areas: the safety of nuclear facilities; radiation protection and safety of radiation sources; safe management of radioactive waste; safe transport of radioactive material; and thematic safety areas, such as emergency preparedness or legal infrastructures. Overall, the safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. All IAEA Member States can nominate experts for the Agency standards committees and provide comments on draft standards. Through this ongoing cycle of review and feedback, the standards are refined, updated, and extended where needed

The Optimation of Crude Fiber Content of Diet for Fattening Madura Beef Cattle to Achieve Good A:P Ratio and Low Methane Production

Science.gov (United States)

Luthfi, N.; Restitrisnani, V.; Umar, M.

2018-02-01

Abtract. Methane (CH4) is one of the major greenhouse gases being reducted. This study was carried out to determine the optimum of crude fiber needed for fattening Madura beef cattle to achieve low methane production. Twenty-four male madura beef cattles with an average body weight of 206.89 ± 7.82 kg were used in this study. Cattle were fed contained 47.65 - 70.23 % Total Digestible Nutrients (TDN), 9.22 - 13.20% Crude Protein (CP), and 10.25 - 28.53% Crude Fiber (CF). Correlation analysis was used to describe the correlations among crude fiber,Methane, and Acetate:Propionate acid ratio. The result showed that crude fiber (%) had medium possitive correlation with methane and the equation was y = 0.0936x + 5.4853 with determination as much as 33.98%. The Acetate: propionate acid had positive correlation withmethane and the equation was y = 1.1121x + 3.581 with determination as much as 61.64%. Crude fiber (%) had low possitive correlation with A/P ratio and the equation was y = 0.039x + 2.4437 with determination as much as 9.56%. According to the results, it can be concluded that the optimum ofcrude fiberof diet for Madura beef cattle should be 15.38% to obtain A:P ratio of 3 or less and methane production of 6.91 MJ/d.

IAEA safety standards for research reactors

International Nuclear Information System (INIS)

Abou Yehia, H.

2007-01-01

The general structure of the IAEA Safety Standards and the process for their development and revision are briefly presented and discussed together with the progress achieved in the development of Safety Standards for research reactor. These documents provide the safety requirements and the key technical recommendations to achieve enhanced safety. They are intended for use by all organizations involved in safety of research reactors and developed in a way that allows them to be incorporated into national laws and regulations. The author reviews the safety standards for research reactors and details their specificities. There are 4 published safety standards: 1) Safety assessment of research reactors and preparation of the safety analysis report (35-G1), 2) Safety in the utilization and modification of research reactors (35-G2), 3) Commissioning of research reactors (NS-G-4.1), and 4) Maintenance, periodic testing and inspection of research reactors (NS-G-4.2). There 5 draft safety standards: 1) Operational limits and conditions and operating procedures for research reactors (DS261), 2) The operating organization and the recruitment, training and qualification of personnel for research reactors (DS325), 3) Radiation protection and radioactive waste management in the design and operation of research reactors (DS340), 4) Core management and fuel handling at research reactors (DS350), and 5) Grading the application of safety requirements for research reactors (DS351). There are 2 planned safety standards, one concerning the ageing management for research reactor and the second deals with the control and instrumentation of research reactors

Safety standards for near surface disposal and the safety case and supporting safety assessment for demonstrating compliance with the standards

International Nuclear Information System (INIS)

Metcalf, P.

2003-01-01

The report presents the safety standards for near surface disposal (ICRP guidance and IAEA standards) and the safety case and supporting safety assessment for demonstrating compliance with the standards. Special attention is paid to the recommendations for disposal of long-lived solid radioactive waste. The requirements are based on the principle for the same level of protection of future individuals as for the current generation. Two types of exposure are considered: human intrusion and natural processes and protection measures are discussed. Safety requirements for near surface disposal are discussed including requirements for protection of human health and environment, requirements or safety assessments, waste acceptance and requirements etc

77 FR 10358 - Acceptance of ASTM F963-11 as a Mandatory Consumer Product Safety Standard

Science.gov (United States)

2012-02-22

... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Chapter II Acceptance of ASTM F963-11 as a Mandatory... have accepted the revised ASTM F963-11 standard titled, Standard Consumer Safety Specifications for Toy Safety. Pursuant to section 106 of the Consumer Product Safety Improvement Act of 2008, ASTM F963-11 will...

76 FR 2199 - Locomotive Safety Standards

Science.gov (United States)

2011-01-12

..., alcohol and drug testing, locomotive engineer certification, and workplace safety. In 1980, FRA issued the...) Association of State Rail Safety Managers (ASRSM) Brotherhood of Locomotive Engineers and Trainmen (BLET... desirable to minimize the health and safety effects of temperature extremes. Depending upon the workplace...

78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

Science.gov (United States)

2013-03-20

... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

78 FR 21850 - Federal Motor Vehicle Safety Standards; Matters Incorporated by Reference

Science.gov (United States)

2013-04-12

... to the 1985 Annual Book of ASTM Standards, Vol. 05.04, ``Test Methods for Rating Motor, Diesel... for Rating Motor, Diesel, Aviation Fuels, A2. Reference Materials and Blending Accessories, (``ASTM... [Docket No. NHTSA-2011-0185] RIN 2127-AL25 Federal Motor Vehicle Safety Standards; Matters Incorporated by...

77 FR 66638 - The Standard on Process Safety Management of Highly Hazardous Chemicals; Extension of the Office...

Science.gov (United States)

2012-11-06

... Standard on Process Safety Management of Highly Hazardous Chemicals; Extension of the Office of Management...) approval of the information collection requirements specified in the Standard on Process Safety Management...: The Standard on Process Safety Management of Highly Hazardous Chemicals (29 CFR 1910.119). OMB Number...

Development and validation of the Affect in Play Scale-brief rating version (APS-BR).

Science.gov (United States)

Cordiano, Tori J Sacha; Russ, Sandra W; Short, Elizabeth J

2008-01-01

The Affect in Play Scale (APS; Russ, 1987, 2004) is one of few reliable, standardized measures of pretend play, yet the fact that it requires videotaping and extensive training to score compromises its clinical utility. In this study, we developed and validated a brief rating version (APS-BR) that does not require videotaping. Construct validity was established by comparing scores from the original APS and the APS-BR using an existing data set of videotaped play (n = 46). We examined associations between scores on the APS-BR and theoretically relevant measures of divergent thinking and emotional memories. Scores on the APS-BR related strongly to those on the APS, and the pattern of correlations for each scale and relevant criterion measures was similar in strength and direction, supporting the APS-BR as an alternate form of the APS. In addition, we completed a pilot study to examine the efficacy of using the APS-BR in its intended in vivo format (n = 28). Results from both studies suggest that the APS-BR is a promising brief measure of children's pretend play that can be substituted for the APS in clinical and research settings.

7 CFR 28.107 - Original cotton standards and reserve sets.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Original cotton standards and reserve sets. 28.107... Standards Act Practical Forms of Cotton Standards § 28.107 Original cotton standards and reserve sets. (a) The containers of the original Universal Standards and other official cotton standards of the United...

Finite element modeling of AP1000 nuclear island

International Nuclear Information System (INIS)

Tinic, S.; Orr, R.

2003-01-01

The AP1000 is a standard design developed by Westinghouse and its partners for an advanced nuclear power plant utilizing passive safety features. It is based on the certified design of the AP600 and has been uprated to 1000 MWe. The plant has five principal building structures; the nuclear island, the turbine building; the annex building; the diesel generator building and the radwaste building. The nuclear island consists of the containment building (the steel containment vessel and the containment internal structures), the shield building, and the auxiliary building. These structures are founded on a common basemat and are collectively known as the nuclear island. This paper describes use of the general purpose finite element program ANSYS [2] in structural analyses and qualification of the AP1000 nuclear island buildings. It describes the modeling of the shield building and the auxiliary building and the series of analyses and the flow of information from the global analyses to the detailed analyses and building qualification. (author)

75 FR 66828 - Eleventh Meeting: RTCA Special Committee 214: Working Group 78: Standards for Air Traffic Data...

Science.gov (United States)

2010-10-29

.... Now TORS(OCL/DSC, update ED 154/Doxxx, * * *). Outcome FRAC/consultation DO306/ED 122 and Publication... TORs and Work Plan. Review of Position Papers and Contributions. 13:30-17:00: Plenary Session.... Robert L. Bostiga, RTCA Advisory Committee. [FR Doc. 2010-27260 Filed 10-28-10; 8:45 am] BILLING CODE...

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

A new gap separation mechanism for APS insertion devices

International Nuclear Information System (INIS)

Trakhtenberg, E. M.; Tcheskidov, V.; Den Hartog, P. K.; Deriy, B.; Erdmann, M.; Makarov, O.; Moog, E. R.

1999-01-01

A new gap separation mechanism for use with the standard Advanced Photon Source (APS) 3.3-cm-period undulator magnetic structures has been designed and built and the first system has been installed in the APS storage ring. The system allows a minimum magnetic gap of 10 mm for use with the APS 8-mm insertion device vacuum chambers. The mechanism is a bolted steel frame structure with a simple 4-motor mechanical drive train. The control system uses servomotors with incremental rotary encoders and virtual absolute linear encoders

Increasing the reliability, availability, and maintainability of the AP600 by design

International Nuclear Information System (INIS)

Trombola, D.; Meyer, C.

1993-01-01

The AP600 design is based on providing a safe, simple, standardized, and economically competitive design with a high degree of operability and ease of maintenance. Design features such as component selection, layout, and standardization increase the probability that targeted repair times are achieved. Design requirements from the utility industry and industry design practices have established criteria for: layout, changeout and replacement of parts and components; access for major pieces of equipment; and vehicle passage. These features coupled with a solid reliability assurance and maintenance program will help the AP600 meet its objectives for operation and maintenance. The AP600 draws on the operating experience and lessons learned from the utility community through design workshops and design review interaction, as well as operating plant data from sources several sources. Internally, the AP600 program incorporates the resources of Westinghouse NSD (Nuclear Service Division), which for decades has provided refueling, steam generator, reactor coolant pump, and other operating plant services. Since the early phases of the design process, the AP600 Program has executed a comprehensive reliability, availability, and maintainability program (RAM) which dealt primarily with assessing and improving plant availability. In conjunction with this program a Probabilistic Risk Assessment (PRA) was performed and submitted to the NRC with the Standard Safety Analysis Report (SSAR) in June 1992. This paper describes how AP600 ensures that the plant has design features to enhance reliability, availability, and maintainability. The RAM program that brings the plant through the design certification phase is described

The radiation safety standards programme

International Nuclear Information System (INIS)

Bilbao, A.A.

2000-01-01

In this lecture the development of radiation safety standards by the IAEA which is a statutory function of the IAEA is presented. The latest editions of the basic safety standards published by the IAEA in cooperation with ICRP, FAO, ILO, NEA/OECD, PAHO and WHO are reviewed

Ectopic AP4 expression induces cellular senescence via activation of p53 in long-term confluent retinal pigment epithelial cells.

Science.gov (United States)

Wang, Yiping; Wong, Matthew Man-Kin; Zhang, Xiaojian; Chiu, Sung-Kay

2015-11-15

When cells are grown to confluence, cell-cell contact inhibition occurs and drives the cells to enter reversible quiescence rather than senescence. Confluent retinal pigment epithelial (RPE) cells exhibiting contact inhibition was used as a model in this study to examine the role of overexpression of transcription factor AP4, a highly expressed transcription factor in many types of cancer, in these cells during long-term culture. We generated stable inducible RPE cell clones expressing AP4 or AP4 without the DNA binding domain (DN-AP4) and observed that, when cultured for 24 days, RPE cells with a high level of AP4 exhibit a large, flattened morphology and even cease proliferating; these changes were not observed in DN-AP4-expressing cells or non-induced cells. In addition, AP4-expressing cells exhibited senescence-associated β-galactosidase activity and the senescence-associated secretory phenotype. We demonstrated that the induced cellular senescence was mediated by enhanced p53 expression and that AP4 regulates the p53 gene by binding directly to two of the three E-boxes present on the promoter of the p53 gene. Moreover, we showed that serum is essential for AP4 in inducing p53-associated cellular senescence. Collectively, we showed that overexpression of AP4 mediates cellular senescence involving in activation of p53 in long-term post-confluent RPE cells. Copyright © 2015 Elsevier Inc. All rights reserved.

Status and trends in IAEA safety standards

International Nuclear Information System (INIS)

Lipar, M.

2004-01-01

While safety is a national responsibility, international standards and approaches to safety promote consistency and facilitate international technical co-operation and trade, and help to provide assurance that nuclear and radiation related technologies are used safely. The standards also provide support for States in meeting their international obligations. One general international obligation is that a State must not pursue activities that cause damage in another State. More specific obligations on Contracting States are set out in international safety related conventions. The internationally agreed IAEA safety standards provide the basis for States to demonstrate that they are meeting these obligations. These standards are founded in the IAEA's Statute, which authorizes the Agency to establish standards of safety for nuclear and radiation related facilities and activities and to provide for their application. The safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. (orig.) [de

AP600 - an ALWR conceptual design

International Nuclear Information System (INIS)

Bruce, R.A.; Vijuk, R.P.

1988-01-01

The Electric Power Research Institute is spearheading an effort to develop utility requirements for the Advanced Light Water Reactor (ALWR) plants which will become the next generation nuclear power plants for the U.S. This EPRI ALWR Program involves utilities, the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and various industry suppliers. The ALWR Program is aimed at ALWR plants which incorporate step improvements in safety, reliability, operability and power generation costs. As part of the ALWR efforts, a Westinghouse team is conducting conceptual design development of a PWR plant design called the AP600, reflecting advanced passive safety features and the chosen 600 MWe plant output. The AP600 conceptual design provides significant improvements while employing proven component technology. This paper describes the basic reactor and primary coolant system features, the passive safety system features, and plant arrangement/construction features of AP600

Westinghouse Advances in Passive Plant Safety

International Nuclear Information System (INIS)

Bruschi, H. J.; Manager, General; Gerstenhaber, E.

1993-01-01

On June 26, 1992, Westinghouse submitted the Ap600 Standard Safety Analysis Report and comprehensive PIRA results to the U. S. NRC for review as part of the Ap600 design certification program. This major milestone was met on time on a schedule set more than 3 years before submittal and is the result of the cooperative efforts of the U. S. Department of Energy (DOE), the Electric Power Requirements Program, and the Westinghouse Ap600 design team. These efforts were initiated in 1985 to develop a 600 MW advanced light water reactor plant design based on specific technical requirements established to provide the safety, simplicity, reliability, and economics necessary for the next generation of nuclear power plants. The Ap600 design achieves the ALRR safety requirements through ample design margins, simplified safety systems based on natural driving forces, and on a human-engineered man-machine interface system. Extensive Probabilistic Risk evolution, have recently shown that even if none of the active defense-in-depth safety systems are available, the passive systems alone meet safety goals. Furthermore, many tests in an extensive test program have begun or have been completed. Early tests show that passive safety perform well and meet design expectations

BRC/IoP standard importance in packaging quality assurance

Directory of Open Access Journals (Sweden)

Agnieszka Kawecka

2014-10-01

Full Text Available BRC/IoP (British Retail Consortium / Institute of Packaging is the only industry standard dedicated entrepreneurs operating in the packaging industry, primarily intended for contact with food. The requirements of the BRC / IoP guarantee the safety of packaging and fulfillment of all legal and hygienic requirements. The article presents the main features of the standard, the basic requirements contained in the document and the results of research on the implementation of quality management systems, including standard BRC / IoP and the actions that are required checklists. It is noticeable that there is little interest in certification BRC / IoP, due to low awareness of the standard, despite the fulfillment of some of the basic requirements of the surveyed companies.

Development of fusion safety standards

International Nuclear Information System (INIS)

Longhurst, G.R.; Petti, D.A.; Dinneen, G.A.; Herring, J.S.; DeLooper, J.; Levine, J.D.; Gouge, M.J.

1996-01-01

Two new U.S. Department of Energy (DOE) standards have been prepared to assist in the design and regulation of magnetic fusion facilities. They are DOE-STD-6002-96, 'Safety of Magnetic Fusion Facilities - Requirements,' and DOE-STD-6003-96 'Safety of Magnetic Fusion Facilities - Guidance.' The first standard sets forth requirements, mostly based on the Code of Federal Regulations, deemed necessary for the safe design and operation of fusion facilities and a set of safety principles to use in the design. The second standard provides guidance on how to meet the requirements identified in DOE-STD-6002-96. It is written specifically for a facility such as the International Thermonuclear Experimental Reactor (ITER) in the DOE regulatory environment. As technical standards, they are applicable only to the extent that compliance with these standards is included in the contracts of the developers. 7 refs., 1 fig

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

International Nuclear Information System (INIS)

1998-05-01

This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

An analysis of AP600 design features

International Nuclear Information System (INIS)

Park, Jong Kyoon; Jang, Moon Heui; Hwang, Yung Dong

1994-01-01

In the aspect of engineering, passive safety system concept has improved the safety degree of nuclear power plant. Therefore, the objective of this study is to check on the possibility of the capacity upgrade of nuclear power plant in the case of adopting the passive safety system concept of AP 600. The characteristics of AP 600 are the advanced functions in ECCS, heat removal of containment building and residual heat removal under the passive safety system concept. The result of this study will become the basic data of capacity upgrade of nuclear power plant and will be widely used in second year project. (Author)

An analysis of AP600 design features

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Kyoon; Jang, Moon Heui; Hwang, Yung Dong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); and others

1994-01-01

In the aspect of engineering, passive safety system concept has improved the safety degree of nuclear power plant. Therefore, the objective of this study is to check on the possibility of the capacity upgrade of nuclear power plant in the case of adopting the passive safety system concept of AP 600. The characteristics of AP 600 are the advanced functions in ECCS, heat removal of containment building and residual heat removal under the passive safety system concept. The result of this study will become the basic data of capacity upgrade of nuclear power plant and will be widely used in second year project. (Author).

The international dimensions of nuclear safety standards

International Nuclear Information System (INIS)

Reed, J.M.

1992-01-01

The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

Notch1/3 and p53/p21 are a potential therapeutic target for APS-induced apoptosis in non-small cell lung carcinoma cell lines.

Science.gov (United States)

Zhang, Jing-Xi; Han, Yi-Ping; Bai, Chong; Li, Qiang

2015-01-01

Previous studies have shown that Astragalus polysaccharide (APS) can be applied to anti-cancer. However, the mechanism by which APS mediate this effect is unclear. In the present study, APS-mediated NSCLC cell apoptosis was investigated through the regulation of the notch signaling pathway. The cell viability was detected by the CCK8 assay. The mRNA and protein expression of notch1/3 and tumor suppressors were analyzed by RT-PCR and western blotting, respectively. The mRNA and protein of notch1 and notch3 were significantly up-regulated in tumor tissues as compared to non-tumor adjacent tissues. Treatment of human NSCLC cells with APS induced cell death in a dose-and time-dependent manner by using CCK8 assay. The mRNA and protein expression of notch1 and notch3 were significantly lower in NSCLC cells with APS treatment than that in control group. Moreover, western blotting analysis showed that treatment of H460 cells with APS significantly increased the pro-apoptotic Bax and caspase 8 levels, decreased the anti-apoptotic Bcl-2 level. Furthermore, p53, p21 and p16 were obviously up-regulated by APS treatment in H460 cell. This study demonstrated that APS-treated could inhibit proliferation and promote cell apoptosis, at least partially, through suppressing the expression of notch1 and notch3 and up-regulating the expression of tumor suppressors in H460 NSCLC cell lines.

78 FR 73692 - Revisions to Safety Standards for Infant Bath Seats, Toddler Beds, and Full-Size Baby Cribs

Science.gov (United States)

2013-12-09

... standard issued under the Danny Keysar Child Product Safety Notification Act was based, the revision... standard. Section 26(c) of the CPSA also provides that states or political subdivisions of states may apply... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Parts 1215, 1217 and 1219 Revisions to Safety Standards...

Learning through delivery, Westinghouse AP1000 plant construction

International Nuclear Information System (INIS)

Gorgemans, J.; Hinman, R.D.; Steuck, C.M.; Greco, P.L.

2014-01-01

The AP1000 plant, which is a 1100 MWe class pressurized water reactor with passive safety features, is designed around a conventional 2 loop, 2 steam generator primary system configuration with 2 hot legs, 4 reactor coolant pumps directly mounted in the steam generator lower head and 4 cold legs. A particular feature of AP1000 is its modular construction to minimize the time and cost of construction. Modular construction allows activities to be run in parallel, it allows more activities to be performed in a controlled factory instead of in the field, and it provides a better level of quality. The AP1000 plant design includes 106 structural modules and 52 mechanical modules. Structural modules include all penetrations for piping, cable trays, HVAC duct runs, and all reinforcement for pipe, equipment hangers, and supports. Structural modules are shipped in sub-modules to support transportation by rail or truck or barge. Mechanical modules contain equipment such as pumps, tanks, heat exchangers, air-handling units, and filters along with interconnecting pipes, valves, instruments, wiring and support services. Modular construction requires strong coordination between engineering, supply chain and construction. A total of 8 AP1000 units are currently under construction in China and in the United States. The lessons learned and best practices of each new AP1000 construction are systematically incorporated into the standard design. (A.C.)

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

Consensus standards utilized and implemented for nuclear criticality safety in Japan

International Nuclear Information System (INIS)

Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

1996-01-01

The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

77 FR 72998 - Policy Statement on Occupational Safety and Health Standards for Aircraft Cabin Crewmembers

Science.gov (United States)

2012-12-07

... [Docket No.: FAA-2012-0953] Policy Statement on Occupational Safety and Health Standards for Aircraft... regarding the regulation of some occupational safety and health conditions affecting cabin crewmembers on aircraft by the Occupational Safety and Health Administration (OSHA). This policy statement will enhance...

40 CFR 413.24 - Pretreatment standards for existing sources.

Science.gov (United States)

2010-07-01

... management plan approved by the control authority. (Secs. 301, 304, 306, 307, 308, and 501 of the Clean Water...) EFFLUENT GUIDELINES AND STANDARDS ELECTROPLATING POINT SOURCE CATEGORY Electroplating of Precious Metals... by the Clean Water Act of 1977, Pub. L. 95-217)) [46 FR 9467, Jan. 28, 1981, as amended at 48 FR...

GRIM-19 disrupts E6/E6AP complex to rescue p53 and induce apoptosis in cervical cancers.

Directory of Open Access Journals (Sweden)

Ying Zhou

Full Text Available BACKGROUND: Our previous studies showed a down-regulation of GRIM-19 in primary human cervical cancers, and restoration of GRIM-19 induced tumor regression. The induction of tumor suppressor protein p53 ubiquitination and degradation by E6 oncoportein of high risk-HPV through forming a stable complex with E6AP is considered as a critical mechanism for cervical tumor development. The aims of this study were to determine the potential role of GRIM-19 in rescuing p53 protein and inducing cervical cancer cell apoptosis. METHODOLOGY/PRINCIPAL FINDINGS: The protein levels of GRIM-19 and p53 were detected in normal cervical tissues from 45 patients who underwent hysterectomy for reasons other than neoplasias of either the cervix or endometrium, and cervical cancer tissues from 60 patients with non-metastatic squamous epithelial carcinomas. Coimmunoprecipitation and GST pull-down assay were performed to examine the interaction of GRIM-19 with 18E6 and E6AP in vivo and in vitro respectively. The competition of 18E6 with E6AP in binding GRIM-19 by performing competition pull-down assays was designed to examine the disruption of E6/E6AP complex by GRIM-19. The augment of E6AP ubiquitination by GRIM-19 was detected in vivo and in vitro ubiquitination assay. The effects of GRIM-19-dependent p53 accumulation on cell proliferation, cell cycle, apoptosis were explored by MTT, flow cytometry and transmission electron microscopy respectively. The tumor suppression was detected by xenograft mouse model. CONCLUSION/SIGNIFICANCE: The levels of GRIM-19 and p53 were concurrently down regulated in cervical cancers. The restoration of GRIM-19 can induce ubiquitination and degradation of E6AP, and disrupt the E6/E6AP complex through the interaction of N-terminus of GRIM-19 with both E6 and E6AP, which protected p53 from degradation and promoted cell apoptosis. Tumor xenograft studies also revealed the suppression of p53 degradation in presence of GRIM-19. These data

Dynamic Response of AP1000 Nuclear Island Due to Safe Shutdown Earthquake Loading

Directory of Open Access Journals (Sweden)

Gan Buntara S.

2017-01-01

Full Text Available AP1000 is a standard nuclear power plant developed by Westinghouse and its partners by using an advanced passive safety feature. Among the five principle building structures, namely the nuclear island, turbine building, annex building, diesel generator building and radwaste building, the safety of the nuclear island building is the most concerned. This paper investigates the dynamic response of the nuclear island building of the AP1000 plant subjected to safe shutdown earthquake loadings. A finite element model for the building, which is assumed to be built in a hard-rock base, is developed and its dynamic response is computed with the aid of the commercial finite element package ANSYS. The dynamic characteristics, including the natural frequencies, the vibration modes, and the time histories for displacements, velocities, and accelerations of the building are obtained for two typical safe shutdown earthquakes, El Centro and Kobe earthquakes. The dynamic behavior of the building due to the earthquakes and its safety is examined and highlighted.

76 FR 38018 - Safety Zone, Newport River; Morehead City, NC

Science.gov (United States)

2011-06-29

...-AA00 Safety Zone, Newport River; Morehead City, NC AGENCY: Coast Guard, DHS. ACTION: Temporary final... the main span US 70/Morehead City-Newport River high rise bridge in Carteret County, NC. This safety...) entitled Safety Zone, Newport River; Morehead City, North Carolina in the Federal Register (33 FR 165). We...

40 CFR 420.07 - Effluent limitations guidelines and standards for pH.

Science.gov (United States)

2010-07-01

...) EFFLUENT GUIDELINES AND STANDARDS IRON AND STEEL MANUFACTURING POINT SOURCE CATEGORY General Provisions § 420.07 Effluent limitations guidelines and standards for pH. (a) The pH level in process wastewaters... 40 Protection of Environment 28 2010-07-01 2010-07-01 true Effluent limitations guidelines and...

77 FR 75600 - Policy Statement on Occupational Safety and Health Standards for Aircraft Cabin Crewmembers...

Science.gov (United States)

2012-12-21

... [Docket No. FAA-2012-0953] Policy Statement on Occupational Safety and Health Standards for Aircraft Cabin... announced a proposed policy statement regarding the regulation of some occupational safety and health conditions affecting cabin crewmembers on aircraft by the Occupational Safety and Health Administration. The...

7 CFR 28.123 - Costs of practical forms of cotton standards.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Costs of practical forms of cotton standards. 28.123 Section 28.123 Agriculture Regulations of the Department of Agriculture AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE COMMODITY STANDARDS AND STANDARD...

76 FR 40648 - Safety Enhancements Part 139, Certification of Airports; Reopening of Comment Period

Science.gov (United States)

2011-07-11

... that was published on February 1, 2011. In that document, the FAA proposed several safety enhancements...-0247; Notice No. 11-01] RIN 2120-AJ70 Safety Enhancements Part 139, Certification of Airports... comment period for the NPRM published on February 1, 2011 (76 FR 5510) and reopened (76 FR 20570) April 13...

77 FR 20558 - Federal Motor Vehicle Safety Standards; Platform Lifts for Motor Vehicles; Platform Lift...

Science.gov (United States)

2012-04-05

... unrelated to the barrier's safety. Lift-U also questioned the agency's statement that it could be difficult... DEPARTMENT OF TRANSPORTATION National Highway Traffic Safety Administration 49 CFR Part 571 [Docket No. NHTSA-2012-0039] RIN 2127-AJ93 Federal Motor Vehicle Safety Standards; Platform Lifts for...

Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

Energy Technology Data Exchange (ETDEWEB)

RIECK, C.A.

1999-02-25

The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be used during qualification testing and acceptance testing to verify operability.

Project W-211, initial tank retrieval systems, description of operations for 241-AP-102 and 241-AP-104

International Nuclear Information System (INIS)

RIECK, C.A.

1999-01-01

The primary purpose of the Initial Tank Retrieval Systems (ITRS) is to provide systems for retrieval of radioactive wastes stored in underground double-shell tanks (DSTS) for transfer to alternate storage, evaporation, pretreatment or treatment, while concurrently reducing risks associated with safety watch list and other DSTs. This Description of Operations (DOO) defines the control philosophy for the waste retrieval system for tanks 241-AP-102 (AP-102) and 241-AP-104 (AP-104). This DOO will provide a basis for the detailed design of the Retrieval Control System (RCS) for AP-102 and AP-104 and establishes test criteria for the RCS. The test criteria will be used during qualification testing and acceptance testing to verify operability

76 FR 16277 - System Restoration Reliability Standards

Science.gov (United States)

2011-03-23

... electric system. Blackstart units are essential to restart generation and restore power to the grid in the... Standard EOP-007-0. \\2\\ Mandatory Reliability Standards for the Bulk-Power System, Order No. 693, 72 FR... = $5,894,624. Title: Mandatory Reliability Standards for the Bulk-Power System. Action: FERC 725A...

IAEA Safety Standards on Management Systems and Safety Culture

International Nuclear Information System (INIS)

Persson, Kerstin Dahlgren

2007-01-01

The IAEA has developed a new set of Safety Standard for applying an integrated Management System for facilities and activities. The objective of the new Safety Standards is to define requirements and provide guidance for establishing, implementing, assessing and continually improving a Management System that integrates safety, health, environmental, security, quality and economic related elements to ensure that safety is properly taken into account in all the activities of an organization. With an integrated approach to management system it is also necessary to include the aspect of culture, where the organizational culture and safety culture is seen as crucial elements of the successful implementation of this management system and the attainment of all the goals and particularly the safety goals of the organization. The IAEA has developed a set of service aimed at assisting it's Member States in establishing. Implementing, assessing and continually improving an integrated management system. (author)

78 FR 3843 - Federal Motor Vehicle Safety Standards; New Pneumatic and Certain Specialty Tires

Science.gov (United States)

2013-01-17

... Approval Handbook for Japanese Certification, Safety Regulations for Road Vehicles, Technical Standards For... Technology Transfer and Advancement Act Section 12(d) of the National Technology Transfer and Advancement Act... vehicle safety, Motor vehicles, Rubber and rubber products, and Tires. In consideration of the foregoing...

Decree No. 85-140 of 28 January 1985 on the Higher Council for Nuclear Safety

International Nuclear Information System (INIS)

1985-01-01

The Council set up in 1973 under the supervision of the Minister responsible for energy matters, is charged with all questions dialing with nuclear safety. This Decree expands membership in the Council. (NEA) [fr

AP1000, a nuclear central of advanced design

International Nuclear Information System (INIS)

Hernandez M, N.; Viais J, J.

2005-01-01

The AP1000 is a design of a nuclear reactor of pressurized water (PWR) of 1000 M We with characteristic of safety in a passive way; besides presenting simplifications in the systems of the plant, the construction, the maintenance and the safety, the AP1000 is a design that uses technology endorsed by those but of 30 years of operational experience of the PWR reactors. The program AP1000 of Westinghouse is focused to the implementation of the plant to provide improvements in the economy of the same one and it is a design that is derived directly of the AP600 designs. On September 13, 2004 the US-NRC (for their initials in United States- Nuclear Regulatory Commission) approved the final design of the AP1000, now Westinghouse and the US-NRC are working on the whole in a complete program for the certification. (Author)

Safety research colloquium 2013-2014. Vol. 10

International Nuclear Information System (INIS)

Pieper, Ralf

2015-01-01

Volume 10 of the safety research colloquium 2013-2014 covers the following issues: Design, ergonomics and safety in product development; Germany is searching a final repository site: concepts and status of the final disposal of nuclear waste; collaborating robots - status of research, standardization and validation; psychological workloads - empirical indications; psychological workloads - actual challenges; expert security by occupational health management - challenges to operational practice; expert security by occupational health management - example of a demographic program in the practical realization; challenges in employment legislation - reduction of the key staff; consideration of human factors in hazard assessment a a challenge for every safety engineer, innovative technologies for work equipment and working systems in the context of ambient intelligence and industry 4.0; challenges of functional safety in the automotive sector; nanotechnology - an example for successful technology assessment.

Preliminary analyses of AP600 using RELAP5

International Nuclear Information System (INIS)

Modro, S.M.; Beelman, R.J.; Fisher, J.E.

1991-01-01

This paper presents results of preliminary analyses of the proposed Westinghouse Electric Corporation AP600 design. AP600 is a two loop, 600 MW (e) pressurized water reactor (PWR) arranged in a two hot leg, four cold leg nuclear steam supply system (NSSS) configuration. In contrast to the present generation of PWRs it is equipped with passive emergency core coolant (ECC) systems. Also, the containment and the safety systems of the AP600 interact with the reactor coolant system and each other in a more integral fashion than present day PWRs. The containment in this design is the ultimate heat sink for removal of decay heat to the environment. Idaho National Engineering Laboratory (INEL) has studied applicability of the RELAP5 code to AP600 safety analysis and has developed a model of the AP600 for the Nuclear Regulatory Commission. The model incorporates integral modeling of the containment, NSSS and passive safety systems. Best available preliminary design data were used. Nodalization sensitivity studies were conducted to gain experience in modeling of systems and conditions which are beyond the applicability of previously established RELAP5 modeling guidelines or experience. Exploratory analyses were then undertaken to investigate AP600 system response during postulated accident conditions. Four small break LOCA calculations and two large break LOCA calculations were conducted

Performance Analysis of AP1000 Passive Systems during Direct Vessel Injection (DVI Line Break

Directory of Open Access Journals (Sweden)

A.S. Ekariansyah

2016-08-01

Full Text Available Generation II Nuclear Power Plants (NPPs have a design weakness as shown by the Fukushima accident. Therefore, Generation III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, and the use of passive safety system. One type of Generation III+ NPP is the AP1000 that is a pressurized water reactor (PWR type that has received the final design acceptance from US-NRC and is already under construction at several sites in China as of 2015. The aim of this study is to investigate the behavior and performance of the passive safety system in the AP1000 and to verify the safety margin during the direct vessel injection (DVI line break as selected event. This event was simulated using RELAP5/SCDAP/Mod3.4 as a best-estimate code developed for transient simulation of light water reactors during postulated accidents. This event is also described in the AP1000 design control document as one of several postulated accidents simulated using the NOTRUMP code. The results obtained from RELAP5 calculation was then compared with the results of simulations using the NOTRUMP code. The results show relatively good agreements in terms of time sequences and characteristics of some injected flow from the passive safety system. The simulation results show that the break of one of the two available DVI lines can be mitigated by the injected coolant flowing, which is operated effectively by gravity and density difference in the cooling system and does not lead to core uncovery. Despite the substantial effort to obtain an apropriate AP1000 model due to lack of detailed geometrical data, the present model can be used as a platform model for other initiating event considered in the AP1000 accident analysis.

Safety standards for wind turbines; Sicherheitsnormen fuer Windenergieanlagen

Energy Technology Data Exchange (ETDEWEB)

Boyce, K. [Underwriters Laboratories Inc., Northbrook, IL (United States)

2012-08-15

As the global wind infrastructure sustains rapid growth, compliance with relevant standards provide validation of design principles and establish due diligence in addressing critical attributes such as safety. The IEC 61400 series of standards provides important information for addressing safety and performance of wind turbine systems. Efforts to address unique issues within the United States market has led to development of two safety standards, UL 6141 for large wind turbines and UL 6142 for small wind turbines. These standards, which are being published as American National Standards, contain key safety requirements for the electrical system, electrical safety and controls system, grid connection, and related safety issues. In the future, collaborative efforts will lead to continued exchange of best practices and opportunities for broader harmonization. Development of these standards, and their use by the manufacturing community in design and development of wind turbine products, supports maximal safety and performance of the burgeoning wind infrastructure. (orig.)

Implementation of the INEEL safety analyst training standard

International Nuclear Information System (INIS)

Hochhalter, E. E.

2000-01-01

The Idaho Nuclear Technology and Engineering Center (INTEC) safety analysis units at the Idaho National Engineering and Environmental Laboratory (INEEL) are in the process of implementing the recently issued INEEL Safety Analyst Training Standard (STD-1107). Safety analyst training and qualifications are integral to the development and maintenance of core safety analysis capabilities. The INEEL Safety Analyst Training Standard (STD-1107) was developed directly from EFCOG Training Subgroup draft safety analyst training plan template, but has been adapted to the needs and requirements of the INEEL safety analysis community. The implementation of this Safety Analyst Training Standard is part of the Integrated Safety Management System (ISMS) Phase II Implementation currently underway at the INEEL. The objective of this paper is to discuss (1) the INEEL Safety Analyst Training Standard, (2) the development of the safety analyst individual training plans, (3) the implementation issues encountered during this initial phase of implementation, (4) the solutions developed, and (5) the implementation activities remaining to be completed

Basic safety standards for radiation protection. 1982 ed

International Nuclear Information System (INIS)

1982-01-01

The International Atomic Energy Agency, the World Health Organization, the International Labour Organisation and the Nuclear Energy Agency of the OECD have undertaken to provide jointly a world-wide basis for harmonized and up-to-date radiation protection standards. The new Basic Safety Standards for Radiation Protection are based upon the latest recommendations by the International Commission on Radiological Protection (ICRP) which are essentially contained in its Publication No.26. These new Basic Safety Standards have been elaborated by an Advisory Group of Experts which met in Vienna from 10-14 October 1977, from 23-27 October 1978 and from 1-12 December 1980 under the joint auspices of the IAEA, ILO, WHO and the Nuclear Energy Agency of the OECD. Comments on the draft Basic Safety Standards received from Member States and relevant organizations were taken into account by the Advisory Group in the process of preparation of the revised Basic Safety Standards for Radiation Protection, which are published by the IAEA on behalf of the four sponsoring organizations. One of the main features of this revision is an increased emphasis on the recommendation to keep all exposures to ionizing radiation as low as reasonably achievable, economic and social factors being taken into account; consequently, radiation protection should not only apply the basic dose limits but also comply with this recommendation. Detailed guidance is given to assist those who have to decide on the implementation of this recommendation in particular cases. Another important feature is the recommendation of a more coherent method for achieving consistency in limiting risks to health, irrespective of whether the risk is of uniform or non-uniform exposure of the body.

Study on modular construction management in AP1000 nuclear plant project

International Nuclear Information System (INIS)

Fang Xiaopeng; Shen Wenrong; Sun Kebin; Wei Zhong

2010-01-01

The construction of AP1000 Nuclear Power Plant (NPP) has commenced in China. The AP1000 NPP features a passive design concept and modular construction technology. Based on the management of the construction of current AP1000 NNP, this paper describes the effects on Nuclear Island (NI) construction project management resulting from modular construction technology, as well as new construction techniques and methods. This paper puts forward new requirements for construction schedule management of the nuclear island construction at different levels. The AP1000 NI construction logic features the parallel construction of civil and structural erection as the main approach, with the integrated schedule of module fabrication, assembly and installation as support. The structural modules of AP1000 project are prefabricated in shop, delivered to site as sub-modules and assembled to integrated structural module. The assembled module is transported to the construction site, hoisted and finally set in NI. This paper illustrates how to ensure the construction quality of structural modules by analyzing the interface process and key links in the quality control program, and introduces how to ensure the safety of heavy structural components during various construction phases by evaluating and analyzing the construction safety process. This paper also makes an analysis of the safe environment for the assembly and installation of Containment Vessel, the management of product protection and personnel safety inside the Containment Building during 'Open Top' construction, raises to implement effective protection for the numerous pre-set mechanical modules and equipments, as well as personnel safety protection programs and measures. The modular construction feature of AP1000 NPP design requires technique improvement and management innovation during the NI construction. This paper makes a study and research on the control management of schedule, quality and safety of AP1000 NPP NI

AP1000{sup TM} plant modularization

Energy Technology Data Exchange (ETDEWEB)

Cantarero L, C.; Demetri, K. J. [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States); Quintero C, F. P., E-mail: cantarc@westinghouse.com [Westinghouse Electric Spain, Padilla 17, 28006 Madrid (Spain)

2016-09-15

The AP1000{sup TM} plant is an 1100 M We pressurized water reactor (PWR) with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance and safety. Modules are used extensively in the design of the AP1000 plant nuclear island. The AP1000 plant uses modern, modular-construction techniques for plant construction. The design incorporates vendor-designed skids and equipment packages, as well as large, multi-ton structural modules and special equipment modules. Modularization allows traditionally sequential construction tasks to be completed simultaneously. Factory-built modules can be installed at the site in a planned construction schedule. The modularized AP1000 plant allows many more construction activities to proceed in parallel. This reduces plant construction calendar time, thus lowering the costs of plant financing. Furthermore, performing less work onsite significantly reduces the amount of skilled field-craft labor, which costs more than shop labor. In addition to labor cost savings, doing more welding and fabrication in a factory environment raises the quality of work, allowing more scheduling flexibility and reducing the amount of specialized tools required onsite. The site layout for the AP1000 plant has been established to support modular construction and efficient operations during construction. The plant layout is compact, using less space than previous conventional plant layouts. This paper provides and overview of the AP1000 plant modules with an emphasis on structural modules. Currently the Westinghouse AP1000 plant has four units under construction in China and four units under construction in the United States. All have shown successful fabrication and installation of various AP1000 plant modules. (Author)

AP1000"T"M plant modularization

International Nuclear Information System (INIS)

Cantarero L, C.; Demetri, K. J.; Quintero C, F. P.

2016-09-01

The AP1000"T"M plant is an 1100 M We pressurized water reactor (PWR) with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance and safety. Modules are used extensively in the design of the AP1000 plant nuclear island. The AP1000 plant uses modern, modular-construction techniques for plant construction. The design incorporates vendor-designed skids and equipment packages, as well as large, multi-ton structural modules and special equipment modules. Modularization allows traditionally sequential construction tasks to be completed simultaneously. Factory-built modules can be installed at the site in a planned construction schedule. The modularized AP1000 plant allows many more construction activities to proceed in parallel. This reduces plant construction calendar time, thus lowering the costs of plant financing. Furthermore, performing less work onsite significantly reduces the amount of skilled field-craft labor, which costs more than shop labor. In addition to labor cost savings, doing more welding and fabrication in a factory environment raises the quality of work, allowing more scheduling flexibility and reducing the amount of specialized tools required onsite. The site layout for the AP1000 plant has been established to support modular construction and efficient operations during construction. The plant layout is compact, using less space than previous conventional plant layouts. This paper provides and overview of the AP1000 plant modules with an emphasis on structural modules. Currently the Westinghouse AP1000 plant has four units under construction in China and four units under construction in the United States. All have shown successful fabrication and installation of various AP1000 plant modules. (Author)

76 FR 35130 - Pipeline Safety: Control Room Management/Human Factors

Science.gov (United States)

2011-06-16

...: Control Room Management/Human Factors AGENCY: Pipeline and Hazardous Materials Safety Administration... the Control Room Management/Human Factors regulations in order to realize the safety benefits sooner... FR 5536). By this amendment to the Control Room Management/Human Factors (CRM) rule, an operator must...

75 FR 74151 - Greenhouse Gas Emissions Standards and Fuel Efficiency Standards for Medium- and Heavy-Duty...

Science.gov (United States)

2010-11-30

..., 2010 in Chicago, IL; and November 18, 2010 in Cambridge, MA, as announced at 75 FR 67059, November 1... everyone has had a chance to speak. The hearing in Cambridge will begin at 10 a.m. and continue until 5 p.m... be reproduced. Provide specific examples to illustrate your concerns, and suggest alternatives...

Implante coclear em crianças pós-linguais: resultados funcionais após 10 anos da cirurgia Cochlear implant in postlingual children: functional results 10 years after the surgery

Directory of Open Access Journals (Sweden)

Liege Franzini Tanamati

2012-04-01

Full Text Available Os benefícios do implante coclear (IC às habilidades comunicativas são obtidos ao longo de anos de uso. Há poucos estudos sobre os resultados a longo prazo em crianças pós-linguais que cresceram usando o dispositivo. OBJETIVO: Reportar os resultados funcionais em crianças pós-linguais, após 10 anos de uso do dispositivo. MATERIAL E MÉTODO: Dez crianças pós-linguais, implantadas antes dos 18 anos, participaram deste estudo. Foram avaliadas: a percepção da fala para sentenças e a inteligibilidade de fala. Informações sobre o uso/funcionamento do dispositivo e nível acadêmico/ocupacional foram documentadas. Desenho científico: Estudo de série. RESULTADOS: O reconhecimento para sentenças no silêncio foi igual a 73% e, no ruído, 40%. Para o método de transcrição, a média de acertos foi igual a 92% e, na escala de inteligibilidade, 4.15. Não houve falhas no dispositivo interno. Três participantes haviam concluído o ensino superior e, outros cinco, o ensino médio. Oito participantes estavam empregados. CONCLUSÃO: Este estudo mostrou que o IC é um procedimento seguro e confiável. As crianças pós-linguais após 10 anos de uso do IC alcançaram resultados funcionais em relação à percepção e a inteligibilidade da fala, concluíram ao menos o ensino superior e estavam inseridas no mercado de trabalho.The benefits of cochlear implants (CI for communication skills are obtained over the years. There are but a few studies regarding the long-term outcomes in postlingual deaf children who grew up using the electronic device. AIM: To assess the functional results in a group of postlingual children, 10 years after using a CI. METHODS: Ten postlingual deaf children, implanted before 18 years of age, participated in this study. We assessed: sentence recognition and speech intelligibility. We documented: device use and function and the patient's academic/occupational status. Study design: series. RESULTS: The mean scores were

Basic Safety Standards for Radiation Protection

International Nuclear Information System (INIS)

1962-01-01

Pursuant to the provisions of its Statute relevant to the adoption and application of safety standards for protection against radiation, the Agency convened a panel of experts which formulated the Basic Safety Standards set forth in this publication. The panel met under the chairmanship of Professor L. Bugnard, Director of the French Institut National d'Hygiene, and representatives of the United Nations and of several of its specialized agencies participated in its work. The Basic Safety Standards thus represent the result of a most careful assessment of the variety of complex scientific and administrative problems involved. Nevertheless, of course, they will need to be revised from time to time in the light of advances in scientific knowledge, of comments received from Member States and of the work of other competent international organizations. The Agency's Board of Governors in June 1962 approved the Standards as a first edition, subject to later revision as mentioned above, and authorized Director General Sigvard Eklund to apply the Standards in Agency and Agency-assisted operations and to invite Governments of Member States to take them as a basis in formulating national regulations or recommendations on protection against the dangers arising from ionizing radiations. It is mainly for this last purpose that the Basic Safety Standards are now being published in the Safety Series; but it is hoped that this publication will also interest a much wider circle of readers.

Standardization and validation of a novel and simple method to assess lumbar dural sac size

International Nuclear Information System (INIS)

Daniels, M.L.A.; Lowe, J.R.; Roy, P.; Patrone, M.V.; Conyers, J.M.; Fine, J.P.; Knowles, M.R.; Birchard, K.R.

2015-01-01

Aim: To develop and validate a simple, reproducible method to assess dural sac size using standard imaging technology. Materials and methods: This study was institutional review board-approved. Two readers, blinded to the diagnoses, measured anterior–posterior (AP) and transverse (TR) dural sac diameter (DSD), and AP vertebral body diameter (VBD) of the lumbar vertebrae using MRI images from 53 control patients with pre-existing MRI examinations, 19 prospectively MRI-imaged healthy controls, and 24 patients with Marfan syndrome with prior MRI or CT lumbar spine imaging. Statistical analysis utilized linear and logistic regression, Pearson correlation, and receiver operating characteristic (ROC) curves. Results: AP-DSD and TR-DSD measurements were reproducible between two readers (r = 0.91 and 0.87, respectively). DSD (L1–L5) was not different between male and female controls in the AP or TR plane (p = 0.43; p = 0.40, respectively), and did not vary by age (p = 0.62; p = 0.25) or height (p = 0.64; p = 0.32). AP-VBD was greater in males versus females (p = 1.5 × 10 −8 ), resulting in a smaller dural sac ratio (DSR) (DSD/VBD) in males (p = 5.8 × 10 −6 ). Marfan patients had larger AP-DSDs and TR-DSDs than controls (p = 5.9 × 10 −9 ; p = 6.5 × 10 −9 , respectively). Compared to DSR, AP-DSD and TR-DSD better discriminate Marfan from control subjects based on area under the curve (AUC) values from unadjusted ROCs (AP-DSD p < 0.01; TR-DSD p = 0.04). Conclusion: Individual vertebrae and L1–L5 (average) AP-DSD and TR-DSD measurements are simple, reliable, and reproducible for quantitating dural sac size without needing to control for gender, age, or height. - Highlights: • DSD (L1-L5) does not differ in the AP or TR plane by gender, height, or age. • AP- and TR-DSD measures correlate well between readers with different experience. • Height is positively correlated to AP-VBD in both males and females. • Varying

Uncoupling of Obesity from Insulin Resistance Through a Targeted Mutation in aP2, the Adipocyte Fatty Acid Binding Protein

Science.gov (United States)

Hotamisligil, Gokhan S.; Johnson, Randall S.; Distel, Robert J.; Ellis, Ramsey; Papaioannou, Virginia E.; Spiegelman, Bruce M.

1996-11-01

Fatty acid binding proteins (FABPs) are small cytoplasmic proteins that are expressed in a highly tissue-specific manner and bind to fatty acids such as oleic and retinoic acid. Mice with a null mutation in aP2, the gene encoding the adipocyte FABP, were developmentally and metabolically normal. The aP2-deficient mice developed dietary obesity but, unlike control mice, they did not develop insulin resistance or diabetes. Also unlike their obese wild-type counterparts, obese aP2-/- animals failed to express in adipose tissue tumor necrosis factor-α (TNF-α), a molecule implicated in obesity-related insulin resistance. These results indicate that aP2 is central to the pathway that links obesity to insulin resistance, possibly by linking fatty acid metabolism to expression of TNF-α.

French PWR Safety Philosophy

International Nuclear Information System (INIS)

Conte, M. M.

1986-01-01

The first 900 MWe units, built under the American Westinghouse licence and with reference to the U. S. regulation, were followed by 28 standardized units, C P1 and C P2 series. Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. As early as 1976, this experience was taken into account by French Safety organisms to discuss, with Electricite de France, the safety options for the planned 1300 MWe units, P4 and P4 series. In 1983, the new reactor scheduled, Ni4 series 1400 MWe, is a totally French design which satisfies the French regulations and other French standards and codes. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach each of them having possibilities and limits. Increasing knowledge and lessons learned from operating experience have contributed to the French safety philosophy improvement. The methodology now applied to safety evaluation develops a new facet of the in depth defense concept by taking highly unlikely events into consideration, by developing the search of safety consistency of the design, and by completing the deterministic approach by the probabilistic one

77 FR 22564 - Proposed Collection; Comment Request; Safety Standards for Full-Size Baby Cribs and Non-Full-Size...

Science.gov (United States)

2012-04-16

... CONSUMER PRODUCT SAFETY COMMISSION [Docket No. CPSC-2012-0019] Proposed Collection; Comment Request; Safety Standards for Full- Size Baby Cribs and Non-Full-Size Baby Cribs; Compliance Form AGENCY... safety standards for full-size and non-full-size baby cribs in response to the direction under section...

15 CFR 10.3 - Development of a proposed standard.

Science.gov (United States)

2010-01-01

... rational statements pertaining to the requirements and test methods contained in the standard, if deemed... be submitted to the Department for further processing. [51 FR 22497, June 20, 1986, as amended at 55...

28 CFR 524.10 - Purpose.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Purpose. 524.10 Section 524.10 Judicial Administration BUREAU OF PRISONS, DEPARTMENT OF JUSTICE INMATE ADMISSION, CLASSIFICATION, AND TRANSFER... subpart is to explain the Bureau of Prisons (Bureau) process for classifying newly committed inmates and...

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution using a 28-cm-thickness slab core

International Nuclear Information System (INIS)

Yamamoto, Toshihiro; Miyoshi, Yoshinori; Kikuchi, Tsukasa; Watanabe, Shouichi

2002-01-01

The second series of critical experiments with 10% enriched uranyl nitrate solution using 28-cm-thick slab core have been performed with the Static Experiment Critical Facility of the Japan Atomic Energy Research Institute. Systematic critical data were obtained by changing the uranium concentration of the fuel solution from 464 to 300 gU/l under various reflector conditions. In this paper, the thirteen critical configurations for water-reflected cores and unreflected cores are identified and evaluated. The effects of uncertainties in the experimental data on k eff are quantified by sensitivity studies. Benchmark model specifications that are necessary to construct a calculational model are given. The uncertainties of k eff 's included in the benchmark model specifications are approximately 0.1%Δk eff . The thirteen critical configurations are judged to be acceptable benchmark data. Using the benchmark model specifications, sample calculation results are provided with several sets of standard codes and cross section data. (author)

Certification of boiler safety equipment with ALSPA P320 system, to IEC 61508 standard; Certification des equipements de securite chaudiere avec le systeme ALSPA P320 selon la norme IEC 61508

Energy Technology Data Exchange (ETDEWEB)

Dalzon, J.P. [Alstom Power (France)

2002-02-01

Safety and environmental protection are major priorities governing Alstom work on control systems (Alspa P320) for power plant applications, especially when potentially dangerous processes like high-power flame boilers (typically rated at 100 to 600 MW) are involved. Here, automatic protection chains are implemented to guard against the risk of serious incident such as explosion and equipment destruction. In this kind of situation, the IEC 61508 standard provides baseline specifications for certification of safety systems. (authors)

76 FR 49532 - Federal Motor Vehicle Safety Standards; Electronic Stability Control; Technical Report on the...

Science.gov (United States)

2011-08-10

...-0112] Federal Motor Vehicle Safety Standards; Electronic Stability Control; Technical Report on the Effectiveness of Electronic Stability Control Systems for Cars and LTVs AGENCY: National Highway Traffic Safety..., Electronic Stability Control Systems. The report's title is: Crash Prevention Effectiveness in Light-Vehicle...

Periodic safety review of the HTR-10 safety analysis

International Nuclear Information System (INIS)

Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

2015-01-01

Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

10 CFR 850.28 - Respiratory protection.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Respiratory protection. 850.28 Section 850.28 Energy... Respiratory protection. (a) The responsible employer must establish a respiratory protection program that complies with the respiratory protection program requirements of 29 CFR 1910.134, Respiratory Protection...

10 CFR 10.28 - Conduct of hearing.

Science.gov (United States)

2010-01-01

... regular or routine procedure by the business or agency from which obtained, or other physical evidence... of business, or other physical evidence other than investigative reports, relating to a controverted... NATIONAL SECURITY INFORMATION OR AN EMPLOYMENT CLEARANCE Procedures § 10.28 Conduct of hearing. (a) The...

US Department of Energy DOE Nevada Operations Office, Nevada Test Site: Underground safety and health standards

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

The Nevada Test Site Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada Test Site Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all.

US Department of Energy DOE Nevada Operations Office, Nevada Test Site: Underground safety and health standards

International Nuclear Information System (INIS)

1993-05-01

The Nevada Test Site Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada Test Site Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all

76 FR 56242 - Energy Northwest; Establishment of Atomic Safety and Licensing Board

Science.gov (United States)

2011-09-12

... Northwest's Columbia Generating Station,'' was received via E-Filing on August 22, 2011.\\1\\ \\1\\ On August 22... with the NRC E-Filing rule, which the NRC promulgated in August 2007 (72 FR 49,139). Issued at..., 1972, published in the Federal Register, 37 FR 28,710 (1972), and the Commission's regulations, see, e...

76 FR 29645 - Safety Zone, Newport River; Morehead City, NC

Science.gov (United States)

2011-05-23

...-AA00 Safety Zone, Newport River; Morehead City, NC AGENCY: Coast Guard, DHS. ACTION: Temporary final... the main span US 70/Morehead City--Newport River high rise bridge in Carteret County, NC. This safety... Zone, Newport River; Morehead City, North Carolina in the Federal Register (33 FR 165). We received no...

Standards of conduct for NASA employees

Science.gov (United States)

1987-01-01

'Standards of Conduct' for employees (14 CFR Part 1207) is set forth in this handbook and is hereby incorporated in the NASA Directives System. This handbook incorporates, for the convenience of NASA employees, the regulations now in effect prescribing standards of conduct for NASA employees. These regulations set forth the high ethical standards of conduct required of NASA employees in carrying out their duties and responsibilities. These regulations have been approved by the Office of Government Ethics, Office of Personnel Management. The regulations incorporated in this handbook were first published in the Federal Register on October 21, 1967 (32 FR 14648-14659); Part B concerning the acceptance of gifts, gratuities, or entertainment was extensively revised on January 19, 1976 (41 FR 2631-2633) to clarify and generally to restrict the exceptions to the general rule against the acceptance by a NASA employee from persons or firms doing or seeking business with NASA. Those regulations were updated on January 29, 1985 (50 FR 3887) to ensure conformity to the Ethics in Government Act of 1978 regarding the public financial disclosure statement. These regulations were published in the Federal Register on June 16, 1987 (52 FR 22755-764) and a correction was printed on Sept. 28, 1987 (52 FR 36234).

Vehicular Networks and Road Safety: an Application for Emergency/Danger Situations Management Using the WAVE/802.11p Standard

Directory of Open Access Journals (Sweden)

Peppino Fazio

2013-01-01

Full Text Available Car-to-car communication makes possible offering many services for vehicular environment, mainly to improve the safety. The decentralized kind of these networks requires new protocols to distribute information. The advantages that it offers depend on the penetration rate, that will be enough only after years since the introduction, due to the longevity of the current cars. The V2X communication requires On-Board Units (OBUs in the vehicles, and Road-Side Units (RSUs on the roads. The proposed application uses the peculiarities of the VANETs to advise danger or emergency situations with V2V and V2I message exchange. IEEE 802.11p is standard on which the communication is based, that provides the physical and the MAC layers. The WAVE protocol uses this standard, implementing other protocols defined by the family of standards IEEE P1609 in the upper layers. They define security services, resource management, multichannel operations and the message exchange protocol in WAVE. The performance of the application will be evaluated through many simulations executed in different scenarios, to provide general data independent from them.

49 CFR 393.28 - Wiring systems.

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Wiring systems. 393.28 Section 393.28 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY... NECESSARY FOR SAFE OPERATION Lamps, Reflective Devices, and Electrical Wiring § 393.28 Wiring systems...

New requirements on safety of nuclear power plants according to the IAEA safety standards

International Nuclear Information System (INIS)

Misak, J.

2005-01-01

In this presentation author presents new requirements on safety of nuclear power plants according to the IAEA safety standards. It is concluded that: - New set of IAEA Safety Standards is close to completion: around 40 standards for NPPs; - Different interpretation of IAEA Safety Standards at present: best world practices instead of previous 'minimum common denominator'; - A number of safety improvements required for NPPs; - Requirements related to BDBAs and severe accidents are the most demanding due to degradation of barriers: hardware modifications and accident management; - Large variety between countries in implementation of accident management programmes: from minimum to major hardware modifications; -Distinction between existing and new NPPs is essential from the point of view of the requirements; WWER 440 reactors have potential to reflect IAEA Safety Standards for existing NPPs; relatively low reactor power offers broader possibilities

MDEP AP1000WG Design-Specific Common Position CP-AP1000WG-02. Common position addressing Fukushima Daiichi NPP accident-related issues

International Nuclear Information System (INIS)

2016-09-01

A severe accident involving several units took place in Japan at Fukushima Daiichi nuclear power plant (NPP) in March 2011. The immediate cause of the accident was an earthquake followed by a tsunami coupled with inadequate provisions against the consequences of such events in the design. Opportunities to improve protection against a realistic design basis tsunami had not been taken. As a consequence of the tsunami, safety equipment and the related safety functions were lost at the plant, leading to core damage in three units and subsequently to large radioactive release. Several studies have already been performed to better understand the accident progression and detailed technical studies are still in progress in Japan and elsewhere. In the meantime, on-going studies on the behaviour of nuclear power plants in very severe situations, similar to Fukushima Daiichi, seek to identify potential vulnerabilities in plant design and operation; to suggest reasonably practicable upgrades; or to recommend enhanced regulatory requirements and guidance to address such situations. Likewise, agencies around the world that are responsible for regulating the design, construction and operation of AP1000 R plants are engaged in similar activities. The MDEP AP1000 R Working Group (AP1000 WG) members consist of members from Canada, China, the United Kingdom and the United States. Since the regulatory review of their AP1000 R applications have not been completed by all of these Countries yet, this paper identifies common preliminary approaches to address potential safety improvements for AP1000 R plants as related to lessons learned from the Fukushima Daiichi accident or Fukushima Daiichi-related issues. In seeking common position, regulators will provide input to this paper to reflect their safety conclusions regarding the AP1000 R design and how the design could be enhanced to address Fukushima Daiichi issues. The common preliminary approaches are organized into five sections

NUSS safety standards: A critical assessment

International Nuclear Information System (INIS)

Minogue, R.B.

1985-01-01

The NUSS safety standards are based on systematic review of safety criteria of many countries in a process carefully defined to assure completeness of coverage. They represent an international consensus of accepted safety principles and practices for regulation and for the design, construction, and operation of nuclear power plants. They are a codification of principles and practices already in use by some Member States. Thus, they are not standards which describe methodologies at their present state of evolution as a result of more recent experience and improvements in technological understanding. The NUSS standards assume an underlying body of national standards and a defined technological base. Detailed design and industrial practices vary between countries and the implementation of basic safety standards within countries has taken approaches that conform with national industrial practices. Thus, application of the NUSS standards requires reconciliation with the standards of the country where the reactor will be built as well as with the country from which procurement takes place. Experience in making that reconciliation will undoubtedly suggest areas of needed improvement. After the TMI accident a reassessment of the NUSS programme was made and it was concluded that, given the information at that time and the then level of technology, the basic approach was sound; the NUSS programme should be continued to completion, and the standards should be brought into use. It was also recognized, however, that in areas such as probabilistic risk assessment, human factors methodology, and consideration of detailed accident sequences, more advanced technology was emerging. As these technologies develop, and become more amenable to practical application, it is anticipated that the NUSS standards will need revision. Ideally those future revisions will also flow from experience in their use

Enhancing AP1000 reactor accident management capabilities for long term accidents

International Nuclear Information System (INIS)

Jiang Pingting; Liu Mengying; Duan Chengjie; Liao Yehong

2015-01-01

Passive safety actions are considered as main measures under severe accident in AP1000 power plant. However, risk is still existed. According to PSA, several probable scenarios for AP1000 nuclear power plant are analyzed in this paper with MAAP the severe accident analysis code. According to the analysis results, several deficiencies of AP1000 severe accident management are found. The long term cooling and containment depressurization capability for AP1000 power plant appear to be most important factors under such accidents. Then, several temporary strategies for AP1000 power plant are suggested, including PCCWST temporary water supply strategy after 72h, temporary injection strategy for IRWST, hydrogen relief action in fuel building, which would improve the safety of AP1000 power plant. At last, assessments of effectiveness for these strategies are performed, and the results are compared with analysis without these strategies. The comparisons showed that correct actions of these strategies would effectively prevent the accident process of AP1000 power plant. (author)

Prognostic value of Angiographic Perfusion Score (APS) following percutaneous interventions in acute coronary syndromes.

Science.gov (United States)

Narain, V S; Fischer, L; Puri, A; Sethi, R; Dwivedi, S K

2013-01-01

Identifying reperfusion and predicting post procedure risk is important following Percutaneous Coronary Interventions (PCI). An Angiographic Perfusion Score (APS) combining TIMI flow (TFG) and myocardial perfusion (TMPG) grades before and after PCI can accurately measure both epicardial and myocardial perfusion and predict Major Adverse Cardiac Events (MACE). APS was calculated in 226 (88 ST elevation Myocardial Infarction (STEMI) and 138 Non STEMI) patients. Maximum score being 12, reperfusion was defined as failed: 0-3, partial: 4-9, and full APS: 10-12. Thirty day MACE were observed. APS identified reperfusion significantly more than TMPG alone (STEMI: 50.6% vs 11.8% (p APS group (1.8% vs 22.5%) (p APS detects more low risk reperfused patients, post PCI. Copyright © 2012. Published by Elsevier B.V.

Safety Criteria and Standards for Bearing Capacity of Foundation

Directory of Open Access Journals (Sweden)

Yanlong Li

2017-01-01

Full Text Available This paper focuses on the evaluation standards of factor of safety for foundation stability analysis. The problem of foundation stability is analyzed via the methods of risk analysis of engineering structures and reliability-based design, and the factor of safety for foundation stability is determined by using bearing capacity safety-factor method (BSFM and strength safety-factor method (SSFM. Based on a typical example, the admissible factors of safety were calibrated with a target reliability index specified in relevant standards. Two safety criteria and their standards of bearing capacity of foundation for these two methods (BSFM and SSFM were established. The universality of the safety criteria and their standards for foundation reliability was verified based on the concept of the ratio of safety margin (RSM.

Safety features of the MAPLE-X10 reactor design

International Nuclear Information System (INIS)

Lee, A.G.; Bishop, W.E.; Heeds, W.

1990-09-01

The MAPLE-X10 reactor is a D 2 0-reflected, H 2 0-cooled and -moderated pool-type reactor under construction at the Chalk River Nuclear Laboratories. This 10-MW reactor will produce key medical and industrial radio-isotopes such as 99 Mo, 125 I, and 192 Ir. As the prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor since standards for the licensing of new research reactors have not been developed yet by the licensing authority in Canada

Safety features of the MAPLE-X10 reactor design

International Nuclear Information System (INIS)

Lee, A.G.; Bishop, W.E.; Heeds, W.

1990-01-01

This paper reports on the MAPLE-X10 reactor D 2 O-reflected, H 2 O-cooled and -moderated pool- type reactor, under construction at the Chalk River Nuclear Laboratories. This 10-MW will produce key medical and industrial radioisotopes such as 99 Mo, 125 I, and 192 Ir. The prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor as standards for the licensing of new research reactors have not been developed by the licensing authority in Canada

Prevention of Breast Cancer Cell Transformation by Blockade of the AP-1 Transcription Factor

Science.gov (United States)

2001-10-01

to transfection. pLPCX-TAM67 and control plasmids were transfected with Fugene 6 Regent (Roche) according to manufacture’s protocol. Chloroquine was...breast tu- mor growth with nonisomerizable analogues of similar to those in other reports (27,28). whether increasing or inhibiting AP-1 ac- tamoxifen

77 FR 43811 - Submission for OMB Review; Comment Request-Safety Standards for Full-Size Baby Cribs and Non-Full...

Science.gov (United States)

2012-07-26

... CONSUMER PRODUCT SAFETY COMMISSION Submission for OMB Review; Comment Request--Safety Standards for Full-Size Baby Cribs and Non-Full-Size Baby Cribs; Compliance Form AGENCY: Consumer Product Safety... standards for full-size and non-full-size baby cribs in response to the direction under section 104(b) of...

Safety standards of IAEA for management systems

International Nuclear Information System (INIS)

Vincze, P.

2005-01-01

IAEA has developed a new series of safety standards which are assigned for constitution of the conditions and which give the instruction for setting up the management systems that integrate the aims of safety, health, life environment and quality. The new standard shall replace IAEA 50-C-Q - Requirements for security of the quality for safety in nuclear power plants and other nuclear facilities as well as 14 related safety instructions mentioned in the Safety series No. 50-C/SG-Q (1996). When developing of this complex, integrated set of requirements for management systems, the IAEA requirements 50-C-Q (1996) were taken into consideration as well as the publications developed within the International organisation for standardization (ISO) ISO 9001:2000 and ISO14001: 1996. The experience of European Union member states during the development, implementation and improvement of the management systems were also taken into consideration

Comparison and analysis for item classifications between AP1000 and traditional PWR

International Nuclear Information System (INIS)

Luo Shuiyun; Liu Xiaoyan

2012-01-01

The comparison and analysis for the safety classification, seismic category, code classification and QA classification between AP1000 and traditional PWR were presented. The safety could be guaranteed and the construction and manufacture costs could be cut down since all sorts of AP1000 classifications. It is suggested that the QA classification and the QA requirements correspond to the national conditions should be drafted in the process of AP1000 domestication. (authors)

29 CFR 1925.2 - Safety and health standards.

Science.gov (United States)

2010-07-01

.... Every contractor and subcontractor shall comply with the safety and health standards published in 41 CFR... 29 Labor 7 2010-07-01 2010-07-01 false Safety and health standards. 1925.2 Section 1925.2 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR...

A phase 2 consortium (P2C) trial of 3-aminopyridine-2-carboxaldehyde thiosemicarbazone (3-AP) for advanced adenocarcinoma of the pancreas

Science.gov (United States)

Attia, Steven; Kolesar, Jill; Mahoney, Michelle R.; Pitot, Henry C.; Laheru, Daniel; Heun, James; Huang, Wei; Eickhoff, Jens; Erlichman, Charles

2015-01-01

Summary 3-Aminopyridine-2-carboxaldehyde thiosemicarbazone (3-AP, Triapine®) is a novel small molecule inhibitor of ribonucleotide reductase (RR) with clinical signs of activity in pancreatic cancer. Therefore, the Phase 2 Consortium (P2C) initiated a trial (two single stage studies with planned interim analysis) of 3-AP at 96 mg/m2 intravenously days 1–4 and 15–18 of a 28-day cycle in both chemotherapy-naive and gemcitabine-refractory (GR) patients with advanced pancreatic cancer. The primary endpoint was survival at six months (chemotherapy-naive) and four months (GR). Secondary endpoints were toxicity, response, overall survival, time to progression and mechanistic studies. Fifteen patients were enrolled including one chemotherapy-naïve and 14 GR. The chemotherapy-naïve patient progressed during cycle 1 with grade 3 and 4 toxicities. Of 14 GR patients, seven received two cycles, six received one cycle and one received eight cycles. Progression precluded further treatment in 11 GR patients. Additionally, one died of an ileus in cycle 1 considered related to treatment and two stopped treatment due to toxicity. Five GR patients had grade 4 toxicities possibly related to 3-AP and six GR patients had grade 3 fatigue. Toxicities and lack of meaningful clinical benefit prompted early study closure. Four-month survival in GR patients was 21% (95% CI: 8–58%). Correlative studies confirmed that 3-AP increased the percentage of S-phase buccal mucosal cells, the presence of multidrug resistance gene polymorphisms appeared to predict leukopenia, and baseline pancreatic tumor RR M2 expression was low relative to other tumors treated with 3-AP. In conclusion, this regimen appears inactive against predominantly GR pancreatic cancer. RR M2 protein may not have a critical role in the malignant potential of pancreatic cancer. PMID:18278438

Update on the development of cotton gin PM10 emission factors for EPA's AP-42

Science.gov (United States)

A cotton ginning industry-supported project was initiated in 2008 to update the U.S. Environmental Protection Agency’s (EPA) Compilation of Air Pollution Emission Factors (AP-42) to include PM10 emission factors. This study develops emission factors from the PM10 emission factor data collected from ...

Malignant transformation of neurofibromas in neurofibromatosis 1 is associated with CDKN2A/p16 inactivation

DEFF Research Database (Denmark)

Nielsen, G P; Stemmer-Rachamimov, A O; Ino, Y

1999-01-01

examined the CDKN2A/p16 gene and p16 protein in NFs and MPNSTs from patients with NF1. On immunohistochemical analysis, all NFs expressed p16 protein. The MPNSTs, however, were essentially immunonegative for p16, with striking transitions in cases that contained both benign and malignant elements. None...

75 FR 35286 - Agency Information Collection Activities; Proposed Collection; Comment Request; Safety Standard...

Science.gov (United States)

2010-06-21

... the retail package. There are seven known firms supplying walkers to the United States market. Four of... instructional literature requirements in the Safety Standard for Infant walkers. DATES: Submit written or... for marking and instructional literature. We estimate the burden of this collection of information as...

75 FR 30783 - Agency Information Collection Activities; Proposed Collection; Comment Request; Safety Standard...

Science.gov (United States)

2010-06-02

... product and the retail package. There are three known firms supplying bath seats to the United States... marking and instructional literature requirements in the Safety Standard for Infant Bath Seats. DATES... for marking and instructional literature. We estimate the burden of this collection of information as...

ANALISIS SKENARIO KEGAGALAN SISTEM UNTUK MENENTUKAN PROBABILITAS KECELAKAAN PARAH AP1000

Directory of Open Access Journals (Sweden)

D.T. Sony Tjahyani

2014-03-01

Full Text Available Kejadian Fukushima telah menunjukkan bahwa kecelakaan parah dapat terjadi, maka dari itu sangatlah penting untuk menganalisis tingkat keselamatan pada reaktor daya. Berdasarkan rekomendasi expert mission IAEA setelah kejadian Fukushima, perlu dilakukan upaya untuk meminimalisasi terjadinya kecelakaan parah yaitu dengan melakukan proses pendinginan yang maksimal. Dalam konsep keselamatan fasilitas nuklir, khususnya reaktor daya telah diterapkan konsep keselamatan berlapis (Defence in Depth, DiD. Konsep keselamatan tersebut terdiri atas 5 level pertahanan yang bertujuan mencegah dan mengurangi lepasan produk fisi ke masyarakat dan lingkungan pada saat reaktor daya mengalami kecelakaan. Dalam reaktor telah didesain sistem atau tindakan yang mempunyai fungsi untuk mengatasi setiap level tersebut. Tujuan dari analisis ini adalah menentukan probabilitas kecelakaan parah dengan melakukan skenario kegagalan sistem dalam proses pendinginan di reaktor. Sebagai obyek analisis adalah reaktor daya AP1000, karena jenis reaktor ini sedang banyak dibangun saat ini. Skenario dilakukan dengan mengasumsikan beberapa kombinasi kegagalan sistem yang termasuk dalam DiD level 2 dan 3. Kegagalan sistem kemudian dianalisis dengan menggunakan analisis pohon kegagalan berdasarkan perangkat lunak SAPHIRE ver. 6.76. Dari analisis didapatkan probabilitas gagal dari kelompok sistem DiD level 2 dan 3 pada AP1000 masih di bawah batas kriteria dari IAEA yaitu lebih kecil dari 10-2, serta probabilitas kecelakaan parah didapatkan sebesar 6,17 x 10-10. Berdasarkan analisis ini disimpulkan bahwa AP1000 mempunyai tingkat keselamatan yang cukup tinggi, karena melalui skenario kegagalan sistem didapatkan probabilitas kecelakaan parah yang sangat kecil.   ABSTRACT Fukushima accident has shown that severe accident could be occurred, therefore it is important to analyze safety level of nuclear power plants. Based on the recommendations of IAEA expert mission after the Fukushima accident

The System 80+ Standard Plant design control document. Volume 10

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

The IAEA radioactive waste safety standards programme

International Nuclear Information System (INIS)

Tourtellotte, James R.

1995-01-01

The IAEA is currently reviewing more than thirty publications in its Safety Series with a view toward consolidating and organizing information pertaining to radioactive waste. the effort is entitled Radioactive Waste Safety Standards programme (RADWASS). RADWASS is a significant undertaking and may have far reaching effects on radioactive waste management both in the international nuclear community and in individual nuclear States. This is because IAEA envisions the development of a consensus on the final document. In this circumstance, the product of RADWASS may ultimately be regarded as an international norm against which future actions of Member States may be measured. This program is organized in five subjects: planning, pre-disposal, disposal, uranium and thorium waste management and decommissioning, which has four levels: safety fundamentals, safety standards, safety guides and safety practices. (author)

General philosophy of safety standards

International Nuclear Information System (INIS)

Dunster, H.J.

1987-01-01

Safety standards should be related to the form and magnitude of the risk they aim to limit. Because of the lack of direct information at the exposure levels experienced, radiation protection standards have to be based on risk assumptions that, while plausible, are not proven. The pressure for standards has come as much from public perceptions and fears as from the reality of the risk. (author)

Development of cotton gin PM10 emission factors for EPA’s AP-42

Science.gov (United States)

The Compilation of Air Pollution Emission Factors (AP-42) emission factors are assigned ratings, from A (Excellent) to E (Poor), based on the quality of data used to develop them. All current PM10 cotton gin emission factors received quality ratings of D or lower. In an effort to improve these ratin...

Tank characterization report for double-shell Tank 241-AP-107

International Nuclear Information System (INIS)

DeLorenzo, D.S.; Simpson, B.C.

1994-01-01

The purpose of this tank characterization report is to describe and characterize the waste in Double-Shell Tank 241-AP-107 based on information gathered from various sources. This report summarizes the available information regarding the waste in Tank 241-AP-107, and arranges it in a useful format for making management and technical decisions concerning this particular waste tank. In addition, conclusion and recommendations based on safety and further characterization needs are given. Specific objectives reached by the sampling and characterization of the waste in Tank 241-AP-107 are: Contribute toward the fulfillment of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05 concerning the characterization of Hanford Site high-level radioactive waste tanks; Complete safety screening of the contents of Tank 241-AP-107 to meet the characterization requirements of the Defense Nuclear Facilities Safety board (DNFSB) Recommendation 93-5; and Provide tank waste characterization to the Tank Waste Remediation System (TWRS) Program Elements in accordance with the TWRS Tank Waste Analysis Plan

28 CFR 70.21 - Standards for financial management systems.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Standards for financial management..., HOSPITALS AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 70.21 Standards for financial management systems. (a) Recipients must relate financial data to...

Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA

International Nuclear Information System (INIS)

Ferreira Guimaraes, Antonio Cesar; Franklin Lapa, Celso Marcelo; Lamego Simoes Filho, Francisco Fernando; Cabral, Denise Cunha

2011-01-01

Research highlights: → This article presents an uncertainty modelling study using a fuzzy approach. → The AP1000 Westinghouse NPP was used and it is provided of passive safety systems. → The use of advanced passive safety systems in NPP has limited operational experience. → Failure rates and basic events probabilities used on the fault tree analysis. → Fuzzy uncertainty approach was employed to reliability of the AP1000 large LOCA. - Abstract: This article presents an uncertainty modeling study using a fuzzy approach applied to the Westinghouse advanced nuclear reactor. The AP1000 Westinghouse Nuclear Power Plant (NPP) is provided of passive safety systems, based on thermo physics phenomenon, that require no operating actions, soon after an incident has been detected. The use of advanced passive safety systems in NPP has limited operational experience. As it occurs in any reliability study, statistically non-significant events report introduces a significant uncertainty level about the failure rates and basic events probabilities used on the fault tree analysis (FTA). In order to model this uncertainty, a fuzzy approach was employed to reliability analysis of the AP1000 large break Loss of Coolant Accident (LOCA). The final results have revealed that the proposed approach may be successfully applied to modeling of uncertainties in safety studies.

IAEA safety standards and approach to safety of advanced reactors

International Nuclear Information System (INIS)

Gasparini, M.

2004-01-01

The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

76 FR 11415 - Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems

Science.gov (United States)

2011-03-02

... [Docket No. NHTSA-2011-0027] RIN 2127-AK52 Federal Motor Vehicle Safety Standards; Power-Operated Window, Partition, and Roof Panel Systems AGENCY: National Highway Traffic Safety Administration (NHTSA), Department... automatic reversal systems (ARS) for power windows and to make a final decision. The agency has decided not...

Oswer integrated health and safety standard operating practices. Directive

International Nuclear Information System (INIS)

1993-02-01

The directive implements the OSWER (Office of Solid Waste and Emergency Response) Integrated Health and Safety Standards Operating Practices in conjunction with the OSHA (Occupational Safety and Health Act) Worker Protection Standards, replacing the OSWER Integrated Health and Safety Policy

Penta-acetyl geniposide-induced apoptosis involving transcription of NGF/p75 via MAPK-mediated AP-1 activation in C6 glioma cells

International Nuclear Information System (INIS)

Peng, C.-H.; Huang, C.-N.; Hsu, S.-P.; Wang, C.-J.

2007-01-01

We have demonstrated the herbal derivative penta-acetyl geniposide ((Ac) 5 GP) induces C6 glioma cell apoptosis through the critical sphingomyelinase (SMase)/nerve growth factor (NGF)/p75 and its downstream signals. It has been reported mitogen-activated protein kinase (MAPK) mediates NGF synthesis induced by SMase activation. In this study, ERK, p38 and JNK are shown to mediate (Ac) 5 GP-induced glioma cell apoptosis and elevation of NGF and p75. Treatment of PD98059 (ERK-specific inhibitor), SB203580 (p38 MAPK inhibitor) and SP600125 (JNK inhibitor) decreases the elevation of NGF and p75 mRNA induced by (Ac) 5 GP, indicating possible transcription regulation via MAPKs. The results of nuclear extract blotting and EMSA further confirm (Ac) 5 GP maximally increases AP-1 and NF-κB DNA binding at 6 h. Inhibition of ERK, p38 and JNK block the activation of AP-1 and NF-κB, suggesting these MAPKs are involved in (Ac) 5 GP-induced transcription regulation. We thereby used RT-PCR to analyze cells treated with (Ac) 5 GP, with or without AP-1 or NF-κB inhibitors. AP-1 inhibitor NDGA decreases NGF/p75 and expression of FasL and caspase 3 induced by (Ac) 5 GP, suggesting the importance of AP-1 in mediating NGF/p75 and their downstream apoptotic signals. However, FasL and caspase 3 do not change with the NF-κB inhibitor PDTC; NF-κB might be linked to other cellular events. Overall, we demonstrate that MAPK mediates (Ac) 5 GP-induced activation of AP-1, promoting the transcription of NGF/p75 and downstream apoptotic signals. These results further highlight the potential therapeutic effects of (Ac) 5 GP in chemoprevention or as an anti-tumor agent

76 FR 57105 - Greenhouse Gas Emissions Standards and Fuel Efficiency Standards for Medium- and Heavy-Duty...

Science.gov (United States)

2011-09-15

... CFR Parts 523, 534, and 535 Greenhouse Gas Emissions Standards and Fuel Efficiency Standards for...-2010-0079; FRL-9455-1] RIN 2060-AP61; 2127-AK74 Greenhouse Gas Emissions Standards and Fuel Efficiency... Heavy-Duty National Program that will reduce greenhouse gas emissions and fuel consumption for on-road...

76 FR 41304 - Advisory Committee on Construction Safety and Health (ACCSH)

Science.gov (United States)

2011-07-13

... arising in the administration of the safety and health provisions under the Contract Work Hours and Safety....; Multilingual Issues, Diversity, Women in Construction-- 3:45 to 5 p.m. For additional information on ACCSH Work... and Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety Standards...

Selecting safety standards for nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

31 CFR 10.28 - Return of client's records.

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Return of client's records. 10.28... § 10.28 Return of client's records. (a) In general, a practitioner must, at the request of a client, promptly return any and all records of the client that are necessary for the client to comply with his or...

Best Estimate plus Uncertainty (BEPU) Analyses in the IAEA Safety Standards

International Nuclear Information System (INIS)

Dusic, Milorad; )

2013-01-01

The Safety Standards Series establishes an essential basis for safety and represents the broadest international consensus. Safety Standards Series publications are categorized into: Safety Fundamental (Present the overall objectives, concepts and principles of protection and safety, they are the policy documents of the safety standards), Safety Requirements (Establish requirements that must be met to ensure the protection and safety of people and the environment, both now and in the future), and Safety Guides (Provide guidance, in the form of more detailed actions, conditions or procedures that can be used to comply with the Requirements). The incorporation of more detailed requirements, in accordance with national practice, may still be necessary. There should be only one set of international safety standards. Each safety standard will be reviewed by the relevant committee or by the commission every five years. Best Estimate plus Uncertainty (BEPU) Analyses are approached in the following IAEA Safety Standards: - Safety Requirements SSR 2/1 - Safety of NPPs, Design (Revision of NS-R-1); - General Safety Requirement GSR Part 4: Safety Assessment for Facilities and Activities; - Safety Guide SSG-2 Deterministic Safety Analysis for Nuclear Power Plants. NUSSC suggested that new safety guides should be accompanied by documents like TECDOCs or Safety Reports describing in detail their recommendations where appropriate. Special review is currently underway to identify needs for revision in the light of the Fukushima accident. Revision will concern, first, the Safety Requirements, and then, the Selected Safety Guides

78 FR 55225 - Determination of Attainment for the Chico Nonattainment Area for the 2006 Fine Particle Standard...

Science.gov (United States)

2013-09-10

...); and 75 FR 27944 (May 19, 2010) (Coso Junction, California area). Thus EPA has established that, under... Office of Management and Budget under Executive Order 12866 (58 FR 51735, October 4, 1993); Does not... based on health or safety risks subject to Executive Order 13045 (62 FR 19885, April 23, 1997); Is not a...

Mutation of CD2AP and SH3KBP1 Binding Motif in Alphavirus nsP3 Hypervariable Domain Results in Attenuated Virus.

Science.gov (United States)

Mutso, Margit; Morro, Ainhoa Moliner; Smedberg, Cecilia; Kasvandik, Sergo; Aquilimeba, Muriel; Teppor, Mona; Tarve, Liisi; Lulla, Aleksei; Lulla, Valeria; Saul, Sirle; Thaa, Bastian; McInerney, Gerald M; Merits, Andres; Varjak, Margus

2018-04-27

Infection by Chikungunya virus (CHIKV) of the Old World alphaviruses (family Togaviridae) in humans can cause arthritis and arthralgia. The virus encodes four non-structural proteins (nsP) (nsP1, nsp2, nsP3 and nsP4) that act as subunits of the virus replicase. These proteins also interact with numerous host proteins and some crucial interactions are mediated by the unstructured C-terminal hypervariable domain (HVD) of nsP3. In this study, a human cell line expressing EGFP tagged with CHIKV nsP3 HVD was established. Using quantitative proteomics, it was found that CHIKV nsP3 HVD can bind cytoskeletal proteins, including CD2AP, SH3KBP1, CAPZA1, CAPZA2 and CAPZB. The interaction with CD2AP was found to be most evident; its binding site was mapped to the second SH3 ligand-like element in nsP3 HVD. Further assessment indicated that CD2AP can bind to nsP3 HVDs of many different New and Old World alphaviruses. Mutation of the short binding element hampered the ability of the virus to establish infection. The mutation also abolished ability of CD2AP to co-localise with nsP3 and replication complexes of CHIKV; the same was observed for Semliki Forest virus (SFV) harbouring a similar mutation. Similar to CD2AP, its homolog SH3KBP1 also bound the identified motif in CHIKV and SFV nsP3.

Charges collection induced in APS by heavy particles: influence of design parameters

International Nuclear Information System (INIS)

Belredon, Xavier

2003-01-01

We have studied the design parameters influence on heavy ions-induced charge collection physics in APS. The goal is to determine the key parameters for an optimised space environment 'particle detector' APS design. It appears that diffusion is the dominant charge collection mechanism in all the studied technology types, with a smaller magnitude in case of epitaxial technologies. Following proton irradiation, a delayed charge collection and loss of collected charges have been observed. These phenomena are explained by the combination of carriers diffusion and action of the traps generated in the device. Even if they cannot be avoid in space applications, these effects are reduced in case of epitaxial technologies. This work led to the design parameters definition of an optimized APS 'particle detector' and to its fabrication. The results obtained on this APS confirm the previous conclusions and let us define the detection range of such detectors from 0.03 to 50 MeV.cm 2 .mg -1 . (author) [fr

Radiation safety: New international standards

International Nuclear Information System (INIS)

Gonzalez, A.J.

1994-01-01

This article highlights an important result of this work for the international harmonization of radiation safety: specifically, it present an overview of the forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources - the so-called BSS. They have been jointly developed by six organizations - the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (NEA/OECD), the Pan American Health Organization (PAHO), and the World Health Organization (WHO)

Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

International Nuclear Information System (INIS)

Wang, Zujun; Huang, Shaoyan; Liu, Minbo; Xiao, Zhigang; He, Baoping; Yao, Zhibin; Sheng, Jiangkun

2014-01-01

The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 10 8 n/cm 2 s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 10 11 , 5 × 10 11 , and 1 × 10 12 n/cm 2 , respectively. The mean dark signal (K D ), dark signal spike, dark signal non-uniformity (DSNU), noise (V N ), saturation output signal voltage (V S ), and dynamic range (DR) versus neutron fluence are investigated. The degradation mechanisms of CMOS APS image sensors are analyzed. The mean dark signal increase due to neutron displacement damage appears to be proportional to displacement damage dose. The dark images from CMOS APS image sensors irradiated by neutrons are presented to investigate the generation of dark signal spike

The Design of Cooling System Model on The AP1000 Containment

International Nuclear Information System (INIS)

Daddy Setyawan; Yerri Noer Kartiko; Aryadi Suwono; Ari Darmawan Pasek; Nathanael P Tandian; Efrizon Umar

2009-01-01

The policy of national energy leads to the utilization of new energy as nuclear energy, and also contains some efforts to increase reactor safety and optimizing in the design of safety system component such as passive cooling system on reactor containment tank. Because of this, the assessment of safety level to passive safety system needs to be made. To increase the understanding it, the design of cooling system model on containment tank should be done to get safety level on cooling system in the AP1000 containment. To reach the similar model with reality and inexpensive cost, we should make assessment about similarity and dimensionless number. While the heat transfer of air natural circulation and water spray cooling system are a result of gravity approach, we can calculate Grashof modification number and Reynolds number respectively. By this approach, we have a factor of forty for laboratory model. From this model, we hope that we get characteristic correlation to heat transfer on the containment of AP1000 for both air natural circulation and water spray result from gravity. Finally, we can assess the safety level of passive cooling system on the AP1000 containment. (author)

Comparative analysis between radiographic views for knee osteoarthrosis (bipedal AP versus monopedal AP

Directory of Open Access Journals (Sweden)

Rodrigo Pires e Albuquerque

2013-08-01

Full Text Available OBJECTIVE: A comparative analysis by applying the criteria of the original classification Ahlbäck in the anteroposterior (AP bipedal knee in extension and anteroposterior (AP monopodal knee in symptomatic knee arthrosis. With this analysis we intend to observe the agreement, any advantage or difference between the incidence and degree of joint involvement between the orthopedic surgeons and radiologists with the referring physician. METHODS: From January 2012 to March 2012, was a prospective study of 60 symptomatic arthrosis knees (60 patients, clinically selected group of outpatient knee and radiographic proposals submitted to the search. Of the 60 patients, 39 were female and 21 male, mean age 64 years (ranging from 50 to 84 years. Of the 60 knees studied, 37 corresponded to the right side and 23 on the left side. Statistical analysis was performed by Kappa statistics, which evaluates the interobserver agreement for qualitative data. RESULTS: According to the scale of Ahlbäck, there was a significant agreement (p < 0.0001 intra-observer in the classification of knee osteoarthritis among the five evaluators. There was a significant agreement (p < 0.0001 with inter-observer referring physician in the incidence of AP monopodal and AP bipedal for the four raters. CONCLUSION: The study found no difference between the incidence in the AP monopodal versus AP bipedal in osteoarthritis of the knee.

The biological basis of plutonium safety standards

International Nuclear Information System (INIS)

Mole, R.H.

1976-01-01

Since no radiation injury or cancer in man can, as yet, be directly attributed to Pu, all safety standards for Pu must be determined by reference to other safety standards, development of which is discussed. A system of safety standards must be based on links with real damage, such as the requirement for 226 Ra in bone. The type of biological information required for making standards realistic is considered in relation to Pu and Ra in bone. Also considered are the possible effects of Pu in soft tissue such as bone marrow. Not only dose, but also the number of cells exposed to the dose are important biologically and cellular aspects are examined. Since there is no positive evidence of Pu toxicity relevant information on other α emitters must be examined. The observed effectiveness of Ra, daughters of 222 Ra and 232 Th in causing mutations and cancer, is surveyed. Reference is made to the necessity of improving the ICRP system, currently based on the critical organ concept, by recognising the need for summation of risks in other organs where exposure to Pu is concerned. Improved biological understanding particularly that of hereditary damage, in recent years leads to less pessimistic thinking on the effects of ionizing radiations. The immediate need appears to be for consistency in safety standards. (U.K.)

Elevating standards, improving safety.

Science.gov (United States)

Clarke, Richard

2014-08-01

In our latest 'technical guidance' article, Richard Clarke, sales and marketing director at one of the UK's leading lift and escalator specialists, Schindler, examines some of the key issues surrounding the specification, maintenance, and operation of lifts in hospitals to help ensure the highest standards of safety and reliability.

Arrangement between the US Nuclear Regulatory Commission (USNRC) and the Belgian Government for Exchange of Technical Information in Regulatory Matters and in Cooperation in Safety Research and in Standards Development

International Nuclear Information System (INIS)

1978-01-01

This Arrangement was concluded on 6 June 1978 between the United States Nuclear Regulatory Commission and the Belgian Government for exchange of technical information in regulatory matters and in co-operation in safety research and in standards development. Both Parties agree to exchange, as available, technical information related to the regulation of safety and the environmental impact of designated nuclear energy facilities and to safety research of designated types of nuclear facilities. As regards co-operation in safety research, the execution of joint programmes and projects under which activities are divided between the two Parties will be agreed on a case by case basis. The Parties further agree to co-operate in the development of regulatory standards applicable to the designated nuclear facilities. The Arrangement is valid for 5 years and may be extended. (NEA) [fr

29 CFR 1926.2 - Variances from safety and health standards.

Science.gov (United States)

2010-07-01

... from safety and health standards. (a) Variances from standards which are, or may be, published in this... 29 Labor 8 2010-07-01 2010-07-01 false Variances from safety and health standards. 1926.2 Section 1926.2 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION...

76 FR 23255 - Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and Associated Equipment

Science.gov (United States)

2011-04-26

... petitions for reconsideration from Harley-Davidson Motor Company (January 18, 2008) and Ford Motor Company... [Docket No. NHTSA-2007-28322] Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and... part, the petitions for reconsideration of the December 4, 2007, final rule reorganizing Federal Motor...

Identification and characterisation of the IL-27 p28 subunits in fish: Cloning and comparative expression analysis of two p28 paralogues in Atlantic salmon Salmo salar.

Science.gov (United States)

Husain, Mansourah; Martin, Samuel A M; Wang, Tiehui

2014-11-01

Interleukin (IL)-27 is an IL-6/IL-12 family member with pro-inflammatory and anti-inflammatory properties. It is a heterodimeric cytokine composed of an α-chain p28 and a β-chain Ebi3 (Epstein-Barr virus induce gene 3). The p28 subunit can also be secreted as a monomer and function as IL-30 that acts as an inhibitor of IL-27 signalling. At present, the p28 gene has only been described in mammals. Thus, for the first time outwith mammals, we have identified seven p28 molecules in six divergent teleost fish species, Atlantic salmon, two cichlids, two cyprinids and a yellowtail. The fish p28 molecules have higher similarities to mammalian p28 than other IL-6/12 family members. Critical residues involved in the interaction with Ebi3 and the receptor gp130 are highly conserved. The prediction that these are true orthologues is supported by phylogenetic and synteny analysis. Two p28 paralogues (p28a and p28b) sharing 72% aa identity have been identified and characterised in Atlantic salmon. There are multiple upstream ATGs in the 5'-UTR and ATTTA motifs in the 3'-UTR of both cDNA sequences, suggesting regulation at the post-transcriptional and translational level. Both salmon p28 genes are highly expressed in immune relevant tissues, such as thymus, gills, spleen and head kidney. Conversely salmon Ebi3 is highly expressed in other organs, such as liver and caudal kidney. The expression of p28 but not Ebi3 was induced by PAMPs and recombinant cytokines in head kidney cells, and in spleen by Poly I:C challenge in vivo. The dissociation of the expression and modulation of p28 and Ebi3 suggest that both p28 and Ebi3 may be secreted alone or with other partners. Copyright © 2014 Elsevier Ltd. All rights reserved.

Packaging design criteria, transfer and disposal of 102-AP mixer pump

International Nuclear Information System (INIS)

Carlstrom, R.F.

1994-01-01

A mixer pump installed in storage tank 241-AP-102 (102-AP) has failed. This pump is referred to as the 102-AP mixer pump (APMP). The APMP will be removed from 102-AP 1 and a new pump will be installed. The main purpose of the Packaging Design Criteria (PDC) is to establish criteria necessary to design and fabricate a shipping container for the transfer and storage of the APMP from 102-AP. The PDC will be used as a guide to develop a Safety Evaluation for Packaging (SEP)

International basic safety standards for protecting against ionizing radiation and for the safety of radiation sources

International Nuclear Information System (INIS)

1996-01-01

The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation (hereinafter termed radiation) and for the safety of radiation sources that may deliver such exposure. The Standards have been developed from widely accepted radiation protection and safety principles, such as those published in the Annals of the ICRP and the IAEA Safety Series. They are intended to ensure the safety of all types of radiation sources and, in doing so, to complement standards already developed for large and complex radiation sources, such as nuclear reactors and radioactive waste management facilities. For the sources, more specific standards, such as those issued by the IAEA, are typically needed to achieve acceptable levels of safety. As these more specific standards are generally consistent with the Standards, in complying with them, such more complex installations will also generally comply with the Standards. The Standards are limited to specifying basic requirements of radiation protection and safety, with some guidance on how to apply them. General guidance on applying some of the requirements is available in the publications of the Sponsoring Organizations and additional guidance will be developed as needed in the light of experience gained in the application of the Standards. Tabs

International basic safety standards for protecting against ionizing radiation and for the safety of radiation sources

International Nuclear Information System (INIS)

1997-01-01

The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation (hereinafter termed radiation) and for the safety of radiation sources that may deliver such exposure. The Standards have been developed from widely accepted radiation protection and safety principles, such as those published in the Annals of the ICRP and the IAEA Safety Series. They are intended to ensure the safety of all types of radiation sources and, in doing so, to complement standards already developed for large and complex radiation sources, such as nuclear reactors and radioactive waste management facilities. For the sources, more specific standards, such as those issued by the IAEA, are typically needed to achieve acceptable levels of safety. As these more specific standards are generally consistent with the Standards, in complying with them, such more complex installations will also generally comply with the Standards. The Standards are limited to specifying basic requirements of radiation protection and safety, with some guidance on how to apply them. General guidance on applying some of the requirements is available in the publications of the Sponsoring Organizations and additional guidance will be developed as needed in the light of experience gained in the application of the Standards

19 CFR 12.80 - Federal motor vehicle safety standards.

Science.gov (United States)

2010-04-01

... 19 Customs Duties 1 2010-04-01 2010-04-01 false Federal motor vehicle safety standards. 12.80...; DEPARTMENT OF THE TREASURY SPECIAL CLASSES OF MERCHANDISE Motor Vehicles and Motor Vehicle Equipment Manufactured on Or After January 1, 1968 § 12.80 Federal motor vehicle safety standards. (a) Standards...

Emerging standards with application to accelerator safety systems

International Nuclear Information System (INIS)

Mahoney, K.L.; Robertson, H.P.

1997-01-01

This paper addresses international standards which can be applied to the requirements for accelerator personnel safety systems. Particular emphasis is given to standards which specify requirements for safety interlock systems which employ programmable electronic subsystems. The work draws on methodologies currently under development for the medical, process control, and nuclear industries

Mutation of CD2AP and SH3KBP1 Binding Motif in Alphavirus nsP3 Hypervariable Domain Results in Attenuated Virus

Directory of Open Access Journals (Sweden)

Margit Mutso

2018-04-01

Full Text Available Infection by Chikungunya virus (CHIKV of the Old World alphaviruses (family Togaviridae in humans can cause arthritis and arthralgia. The virus encodes four non-structural proteins (nsP (nsP1, nsp2, nsP3 and nsP4 that act as subunits of the virus replicase. These proteins also interact with numerous host proteins and some crucial interactions are mediated by the unstructured C-terminal hypervariable domain (HVD of nsP3. In this study, a human cell line expressing EGFP tagged with CHIKV nsP3 HVD was established. Using quantitative proteomics, it was found that CHIKV nsP3 HVD can bind cytoskeletal proteins, including CD2AP, SH3KBP1, CAPZA1, CAPZA2 and CAPZB. The interaction with CD2AP was found to be most evident; its binding site was mapped to the second SH3 ligand-like element in nsP3 HVD. Further assessment indicated that CD2AP can bind to nsP3 HVDs of many different New and Old World alphaviruses. Mutation of the short binding element hampered the ability of the virus to establish infection. The mutation also abolished ability of CD2AP to co-localise with nsP3 and replication complexes of CHIKV; the same was observed for Semliki Forest virus (SFV harbouring a similar mutation. Similar to CD2AP, its homolog SH3KBP1 also bound the identified motif in CHIKV and SFV nsP3.

46 CFR 62.35-10 - Flooding safety.

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Flooding safety. 62.35-10 Section 62.35-10 Shipping... Requirements for Specific Types of Automated Vital Systems § 62.35-10 Flooding safety. (a) Automatic bilge.... (b) Remote controls for flooding safety equipment must remain functional under flooding conditions to...

Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

International Nuclear Information System (INIS)

2014-01-01

The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-10) in Okinawa, Japan is sponsored by Atomic Energy Society of Japan, in cooperation with the International Atomic Energy Agency, and co-sponsored by American Nuclear Society Thermal Hydraulics Division among others. Enhanced safety and reducing cost are going together, which can be achieved through continued research and development efforts. NUTHOS keeps you abreast of the most updated information in the advancement of science and technology in nuclear thermal hydraulics, operations and safety, and provides you insights into the future. (J.P.N.)

Adjustment of the Brazilian radioprotection standards to the safety principles of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Pereira, Wagner de S.; Py Junior, Delcy de A.

2013-01-01

The International Atomic Energy Agency (IAEA) has a recommendation with 10 basic safety principles (Fundamental Safety Principles Safety Fundamentals series, number SF-1), which are: 1) Responsibility for safety; 2) Role for government; 3) Leadership and management for safety; 4) Justification of facilities and activities; 5) Optimization of protection; 6) Limitation of risk to individuals; 7) Protection of present and futures generations; 8) Prevention of accidents; 9) Emergency preparedness and response and 10) Protection actions to reduce existing or unregulated radiations risk. The aim of this study is to verify that the Brazilian standards of radiation protection meet the principles described above and how well suited to them. The analysis of the national radiation protection regulatory system, developed and deployed by the National Nuclear Energy Commission (CNEN), showed that out of the ten items, two are covered partially, the number 2 and 10. The others are fully met. The item 2 the fact that the regulatory body (CNEN) be stock controller of a large company in the sector put in check its independence as a regulatory body. In item 10 the Brazilian standard of radiation protection does not provide explicit resolution of environmental liabilities

Discovery of potent, reversible MetAP2 inhibitors via fragment based drug discovery and structure based drug design-Part 1.

Science.gov (United States)

Cheruvallath, Zacharia; Tang, Mingnam; McBride, Christopher; Komandla, Mallareddy; Miura, Joanne; Ton-Nu, Thu; Erikson, Phil; Feng, Jun; Farrell, Pamela; Lawson, J David; Vanderpool, Darin; Wu, Yiqin; Dougan, Douglas R; Plonowski, Artur; Holub, Corine; Larson, Chris

2016-06-15

Methionine aminopeptidase 2 (MetAP2) is an enzyme that cleaves an N-terminal methionine residue from a number of newly synthesized proteins. Pre-clinical and clinical studies suggest that MetAP2 inhibitors could be used as a novel treatment for obesity. Herein we describe our use of fragment screening methods and structural biology to quickly identify and elaborate an indazole fragment into a series of reversible MetAP2 inhibitors with <10nM potency, excellent selectivity, and favorable in vitro safety profiles. Copyright © 2016 Elsevier Ltd. All rights reserved.

77 FR 12182 - Safety Standard for Portable Bed Rails: Final Rule

Science.gov (United States)

2012-02-29

... comply with the registration card requirements. 76 FR 68668. In the Federal Register of April 11, 2011... normal disassembly (see Fig. 1). [GRAPHIC] [TIFF OMITTED] TR29FE12.004 3.1.6 consumer adjustment, n... arms are rotated 180 degrees above the vertical axis (Fig. 9). [[Page 12189

22 CFR 901.10 - Act.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Act. 901.10 Section 901.10 Foreign Relations FOREIGN SERVICE GRIEVANCE BOARD GENERAL Meanings of Terms As Used in This Chapter § 901.10 Act. Act means the Foreign Service Act of 1980 (Pub. L. 96-465, October 17, 1980), as amended. [56 FR 55458, Oct. 28...

75 FR 21666 - Canadian Standards Association; Application for Expansion of Recognition

Science.gov (United States)

2010-04-26

...] Canadian Standards Association; Application for Expansion of Recognition AGENCY: Occupational Safety and... the Canadian Standards Association for expansion of its recognition and presents the Agency's... Office's normal business hours, 8:15 a.m.-4:45 p.m., e.t. Instructions: All submissions must include the...

International Safety Regulation and Standards for Space Travel and Commerce

Science.gov (United States)

Pelton, J. N.; Jakhu, R.

The evolution of air travel has led to the adoption of the 1944 Chicago Convention that created the International Civil Aviation Organization (ICAO), headquartered in Montreal, Canada, and the propagation of aviation safety standards. Today, ICAO standardizes and harmonizes commercial air safety worldwide. Space travel and space safety are still at an early stage of development, and the adoption of international space safety standards and regulation still remains largely at the national level. This paper explores the international treaties and conventions that govern space travel, applications and exploration today and analyzes current efforts to create space safety standards and regulations at the national, regional and global level. Recent efforts to create a commercial space travel industry and to license commercial space ports are foreseen as means to hasten a space safety regulatory process.

28 CFR 513.10 - Purpose and scope.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Purpose and scope. 513.10 Section 513.10 Judicial Administration BUREAU OF PRISONS, DEPARTMENT OF JUSTICE GENERAL MANAGEMENT AND ADMINISTRATION ACCESS TO RECORDS Production or Disclosure of FBI/NCIC Information § 513.10 Purpose and scope. This...

Relative toxicity of bifenthrin to Hyalella azteca in 10 day versus 28 day exposures.

Science.gov (United States)

Anderson, Brian S; Phillips, Bryn M; Voorhees, Jennifer P; Petersen, Megan A; Jennings, Lydia L; Fojut, Tessa L; Vasquez, Martice E; Siegler, Catherine; Tjeerdema, Ronald S

2015-04-01

4.23 and 4.28 ng/L for the 10 d and 28 d tests, respectively. In addition, a set of 10 d and 28 d tests were conducted at 15 °C to assess the relative toxicity of bifenthrin at a lower temperature than the standard 23 °C test temperature. These results showed that bifenthrin was more toxic at the lower temperature, with LC50s of 5.1 and 3.4 ng/g bifenthrin in 10 d and 28 d tests, respectively. Amphipod growth at 15 °C after a 28 d exposure resulted in the lowest effect concentration of all experiments conducted (IC20 = 0.61 ng/g). This article discusses how bifenthrin dose-response data from 10 d and 28 d exposures inform development of sediment quality criteria for this pesticide for California Central Valley watersheds. © 2015 SETAC.

76 FR 78 - Federal Motor Vehicle Safety Standard; Engine Control Module Speed Limiter Device

Science.gov (United States)

2011-01-03

... [Docket No. NHTSA-2007-26851] Federal Motor Vehicle Safety Standard; Engine Control Module Speed Limiter... occupants. IIHS stated that on-board electronic engine control modules (ECM) will maintain the desired speed... be equipped with an electronic control module (ECM) that is capable of limiting the maximum speed of...

Rethinking wood dust safety standards

OpenAIRE

Ratnasingam, Jega; Wai, Lim Tau; Ramasamy, Geetha; Ioras, Florin; Tadin, Ishak; Universiti Putra Malaysia; Buckinghamshire New University; Centre for Occupational Safety and Health Singapore

2015-01-01

The current universal work safety and health standards pertaining to wood dust in factories lack the localisation required. As a study has shown, there is a urgent need to reevaluate the current guidelines and practices.

Standards: An international framework for nuclear safety

International Nuclear Information System (INIS)

Versteeg, J.

2000-01-01

The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

76 FR 10898 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

Science.gov (United States)

2011-02-28

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory..., Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th Street, SW., Room..., Public Safety and Homeland Security Bureau. [FR Doc. 2011-4398 Filed 2-25-11; 8:45 am] BILLING CODE 6712...

The IAEA safety standards for radiation, waste and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, Abel J.

1997-01-01

This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

76 FR 41181 - Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and Associated Equipment

Science.gov (United States)

2011-07-13

... to restore the blue and green color boundaries to Federal Motor Vehicle Safety Standard (FMVSS) No... number in the heading of this document, by any of the following methods: Federal eRulemaking Portal: Go... comment, if submitted on behalf of an association, business, labor union, etc.). You may review DOT's...

Assessment of Safety Standards for Automotive Electronic Control Systems

Science.gov (United States)

2016-06-01

This report summarizes the results of a study that assessed and compared six industry and government safety standards relevant to the safety and reliability of automotive electronic control systems. These standards include ISO 26262 (Road Vehicles - ...

77 FR 16471 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

Science.gov (United States)

2012-03-21

... Registry of Pipeline and Liquefied Natural Gas Operators AGENCY: Pipeline and Hazardous Materials Safety... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts... Register (75 FR 72878) titled: ``Pipeline Safety: Updates to Pipeline and Liquefied Natural Gas Reporting...

Three-Catheter Technique for Ablation of Left-Sided Accessory Pathways in Wolff-Parkinson-White is Less Expensive and Equally Successful When Compared to a Five-Catheter Technique.

Science.gov (United States)

Capone, Christine A; Ceresnak, Scott R; Nappo, Lynn; Gates, Gregory J; Schechter, Clyde B; Pass, Robert H

2015-12-01

To compare the efficacy, safety, and cost-effectiveness of a three-catheter approach with a conventional five-catheter approach for the mapping and ablation of supraventricular tachycardia in pediatric patients with Wolff-Parkinson-White Syndrome (WPW) and concealed accessory pathways (APs). A retrospective review from 2008 to 2012 of patients less than 21 years with WPW who underwent a three-catheter radiofrequency (RF) ablation of a left-sided AP (ablation, right ventricular [RV] apical, and coronary sinus [CS] decapolar catheters) was performed. The three-catheter group was compared to a control group who underwent a standard five-catheter (ablation, RV apical, CS decapolar, His catheter, and right atrial catheter) ablation for the treatment of left-sided WPW or concealed AP. Demographics, ablation outcomes, and costs were compared between groups. Twenty-eight patients met inclusion criteria with 28 control patients. The groups did not differ in gender, age, weight, or body surface area. Locations of the AP on the mitral annulus were similar between the groups. All patients were ablated via transseptal approach. Note that 28 of 28 in the three-catheter group (100%) and 27 of 28 (96%) controls were acutely successfully ablated (P = 0.31). No complications were encountered. There was no difference in procedural time, time to loss of AP conduction, or number of RF applications. Use of the three-catheter technique resulted in a total savings of $2,465/case, which includes the $680 savings from using fewer catheters as well as the savings from a shortened procedure time. Ablation in patients with WPW and a left-sided AP can be performed using three catheters with similar efficacy and safety while offering significant cost savings compared to a conventional five-catheter approach. © 2015 Wiley Periodicals, Inc.

28 CFR 550.10 - Purpose and scope.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Purpose and scope. 550.10 Section 550.10... Alcohol Testing § 550.10 Purpose and scope. The Bureau of Prisons maintains a surveillance program in..., or who are considered high risks based on behavior observed or on information received by staff. (a...

Multi-domain comparison of safety standards

International Nuclear Information System (INIS)

Baufreton, Ph.; Derrien, J.C.; Ricque, B.; Blanquart, J.P.; Boulanger, J.L.; Delseny, H.; Gassino, J.; Ladier, G.; Ledinot, E.; Leeman, M.; Quere, Ph.

2011-01-01

This paper presents an analysis of safety standards and their implementation in certification strategies from different domains such as aeronautics, automation, automotive, nuclear, railway and space. This work, performed in the context of the CG2E ('Club des Grandes Entreprises de l'Embarque'), aims at identifying the main similarities and dissimilarities, for potential cross-domain harmonization. We strive to find the most comprehensive 'trans-sectorial' approach, within a large number of industrial domains. Exhibiting the 'true goals' of their numerous applicable standards, related to the safety of system and software, is a first important step towards harmonization, sharing common approaches, methods and tools whenever possible. (authors)

Vehicle track interaction safety standards

Science.gov (United States)

2014-04-02

Vehicle/Track Interaction (VTI) Safety Standards aim to : reduce the risk of derailments and other accidents attributable : to the dynamic interaction between moving vehicles and the : track over which they operate. On March 13, 2013, the Federal : R...

The A.P Møller shares, the US dollar and the price of oil

DEFF Research Database (Denmark)

Risager, Ole

2003-01-01

1. Brief IntroductionThe two companies D/S Svendborg and D/S 1912 have for almost a century been the parent companiesof the A.P. Møller Group. These companies were founded by Mr. Arnold Peter Møller and his fatherCaptain Peter Mærsk Møller. They were in the beginning entirely into shipping. In 1912...

Instructional Design Changes in an Undergraduate A&P Course to Facilitate Student Engagement and Interest

Science.gov (United States)

Hurtt, Barbekka; Bryant, Jennifer

2016-01-01

We describe changes in an undergraduate anatomy and physiology (A&P) curriculum designed to address educational goals at a private, comprehensive university. Educational goals included making course material more relevant to students' future career interests, exposing students to professionals in their careers of interest, and incorporating…

Evaluation excitation functions for "2"8Si(n,p)"2"8Al, "3"1P(n,p)"3"1Si, and "1"1"3In(n,γ)"1"1"4"mIn reactions

International Nuclear Information System (INIS)

Zolotarev, K.I.

2014-10-01

Cross section data for "2"8Si(n,p)"2"8Al, "3"1P(n,p)"3"1Si and "1"1"3In(n,γ)"1"1"4"mIn reactions are needed for solving a wide spectrum of scientific and technical tasks. The excitation function of "2"8Si(n,p)"2"8Al reaction refers to the nuclear data involved in fusion reactor design calculations. The "2"8Si(n,p)"2"8Al reaction is interesting also as the monitor reaction for measurements at fusion facilities. Activation detectors on the basis of the 31P(n,p)31Si reaction are commonly used in the reactor dosimetry. The "1"1"3In(n,γ)"1"1"4"mIn reaction is promising regarding reactor dosimetry application for two reasons. First, due to the "1"1"4"mIn decay parameters which are rather suitable for activation measurements. Half-life of "1"1"4"mIn is equal to T_1/_2 = (49.51 ± 0.01) days and gamma spectrum accompanying decay has only one line with energy 190.27 keV and intensity (15.56 ± 0.15)%. Second, the "1"1"3In(n,γ)"1"1"4"mIn reaction rate may be measured by using one activation detector simultaneously with the "1"1"5In(n,γ)"1"1"6"mIn reaction. Preliminary analysis of existing evaluated excitation functions for "2"8Si(n,p)"2"8Al, "3"1P(n,p)"3"1Si and "1"1"3In(n,γ)"1"1"4"mIn reactions show that new evaluations are needed for all above mentioned reactions. This report is devoted to the preparation of the new evaluations of cross sections data and related covariance matrixes of uncertainties for the "2"8Si(n,p)"2"8Al, "3"1P(n,p)"3"1Si and "1"1"3In(n,γ)"1"1"4"mIn reactions.

Reduction of mercury (II) by humic substances-influence of pH, salinity of aquatic system

Digital Repository Service at National Institute of Oceanography (India)

Chakraborty, P.; Vudamala, K.; Coulibaly, M.; Ramteke, D.; Chennuri, K.; Lean, D.

60 80 pH 4.0 pH 7.0 pH 8.0 pH 9.0 Time (h-1) 0 20 40 60 80 100 120 140 160 0 10 20 30 40 pH 4.0 pH 5.0 pH 6.0 pH 7.0 pH 8.0 pH 9.0 Figure 5 a b c Pe rc en ta ge o f t he to ta l d is so lv ed H g re du ce d b y H S an d tr ap ed in o xi di... humic substances (wt %) 0.42 0.44 0.46 0.48 0.50 0.52 0.54 0.56 Fr ac tio n (p er ce nt ag e) o f t ot al H g re du ce d by H S 20 30 40 50 60 70 Salinity = 5 PSU Salinity = 10 PSU Salinity = 15 PSU Salinity = 20PSU Salinity = 30 PSU 0.42 0...

75 FR 67450 - Pipeline Safety: Control Room Management Implementation Workshop

Science.gov (United States)

2010-11-02

... regulations to address human factors and other aspects of control room management for certain pipelines where controllers use supervisory control and data acquisition (SCADA) systems. Under the final rule, pipeline... Washington, DC on October 22, 2010. Jeffrey D. Wiese, Associate Administrator for Pipeline Safety. [FR Doc...

40 CFR 258.10 - Airport safety.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Airport safety. 258.10 Section 258.10 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES CRITERIA FOR MUNICIPAL SOLID WASTE LANDFILLS Location Restrictions § 258.10 Airport safety. (a) Owners or operators of new...

77 FR 65824 - Calcium Gluconate; Exemption From the Requirement of a Tolerance

Science.gov (United States)

2012-10-31

..., rabbit and hamster with LD 50 values ranging from >2,000 milligrams/kilogram (mg/kg) to 7,850 mg/kg... gluconate was not mutagenic in an in vitro chromosome aberration test, bacterial gene mutation test. In...- ....... Sequestrant. 28-5). * * * * * * * * * * [FR Doc. 2012-26523 Filed 10-30-12; 8:45 am] BILLING CODE 6560-50-P ...

Probabilistic analysis of safety in industrial irradiation plants

International Nuclear Information System (INIS)

Alderete, F.; Elechosa, C.

2006-01-01

The Argentinean Nuclear Regulatory Authority is carrying out the Probabilistic Safety Analysis (PSA) of the two industrial irradiation plants existent in the country. The objective of this presentation is to show from the regulatory point of view, the advantages of applying this tool, as well as the appeared difficulties; for it will be made a brief description of the facilities, of the method and of the normative one. Both plants are multipurpose facilities classified as 'industrial irradiator category IV' (panoramic irradiator with source deposited in pool). Basically, the execution of an APS consists of the following stages: 1. Identification of initiating events. 2. Modeling of Accidental Sequences (Event Trees). 3. Analysis of Systems (Fault trees). 4. Quantification of Accidental Sequences. The argentine normative doesn't demand to these facilities the realization of an APS, however the basic standard of Radiological Safety establishes that in the design of this type of facilities in the cases that is justified, should make sure that the annual probability of occurrence of an accidental sequence and the resulting dose in a person gives as result an radiological risk inferior to the risk limit adopted as acceptance criteria. On the other hand the design standard specifies for these irradiators it demands a maximum fault rate of 10 -2 for the related components with the systems of radiological safety. In our case, the possible initiating events have been identified that carried out to not wanted situations (about people exposure, radioactive contamination). Then, for each one of the significant initiating events, the corresponding accidental sequences were modeled and the safety systems that intervene in this sequences by means of fault trees were analyzed, for then to determine the fault probabilities of the same ones. At the moment they are completing these fault trees, but the difficulty resides in the impossibility of obtaining real data of the reliability

Analytical similarity assessment of rituximab biosimilar CT-P10 to reference medicinal product.

Science.gov (United States)

Lee, Kyoung Hoon; Lee, Jihun; Bae, Jin Soo; Kim, Yeon Jung; Kang, Hyun Ah; Kim, Sung Hwan; Lee, So Jung; Lim, Ki Jung; Lee, Jung Woo; Jung, Soon Kwan; Chang, Shin Jae

2018-04-01

CT-P10 (Truxima™) was recently approved as the world's first rituximab biosimilar product in the European Union (EU) and South Korea. To demonstrate biosimilarity of CT-P10 with the reference medicinal product (RMP), extensive 3-way similarity assessment has been conducted between CT-P10, EU-Rituximab and US-Rituximab, focusing on the physicochemical and biological quality attributes. A multitude of state-of-the-art analyses revealed that CT-P10 has identical primary and higher order structures compared to the original product. Purity/impurity profiles of CT-P10 measured by the levels of aggregates, fragments, non-glycosylated form and process-related impurities were also found to be comparable with those of RMPs. In terms of the post-translational modification, CT-P10 contains slightly less N-terminal pyro-glutamate variant, which has been known not to affect product efficacy or safety. Oligosaccharide profiling has revealed that, although CT-P10 contains the same conserved glycan species and relative proportion with the RMPs, the content of total afucosylated glycan in CT-P10 was slightly higher than in EU- or US-Rituximab. Nevertheless, the effect of the observed level of afucosylation in CT-P10 drug product on Fc receptor binding affinity or antibody-dependent cell-mediated cytotoxicity was found to be negligible based on the spiking study with highly afucosylated sample. Arrays of biological assays representative of known and putative mechanisms of action for rituximab have shown that biological activities of CT-P10 are within the quality range of RMPs. Recent results of clinical studies have further confirmed that the CT-P10 exhibits equivalent clinical efficacy and safety profiles compared to EU- and US-Rituximab. The current 3-way similarity assessment together with clinical study results confidently demonstrate that CT-P10 is highly similar with EU- and US-Rituximab in terms of physicochemical properties, biological activities, efficacy, and safety for

Reduced recurrence of late hemorrhagic radiation cystitis by WF10 therapy in cervical cancer patients

International Nuclear Information System (INIS)

Veerasarn, Vutisiri; Khorprasert, Chonlakiet; Lorvidhaya, Vicharn; Sangruchi, Supatra; Tantivatana, Thanatip; Narkwong, Ladawan; Kongthanarat, Yongyut; Chitapanarux, Imjai; Tesavibul, Chanawat; Panichevaluk, Apichart; Puribhat, Sirisak; Sangkittipaiboon, Somphob; Sookpreedee, Lak; Lertsanguansinchai, Prasert; Phromratanapongse, Pramook; Rungpoka, Poonkiat; Trithratipvikul, Supamitr; Lojanapiwat, Bannakij; Ruangdilokrat, Sathit; Ngampanprasert, Pichai

2004-01-01

Background and purpose: To evaluate the efficacy and the safety of WF10 as adjunct to standard treatment in the management of late hemorrhagic radiation cystitis compared to standard treatment alone. Patients and methods: Cervical cancer patients with Grade 2 or 3 late hemorrhagic radiation cystitis, were randomized and treated with WF10 0.5 ml/kg body weight, diluted in physiological saline or 5% dextrose water 250 ml, intravenous infusions over 2 h on 5 consecutive days, every 3 weeks for 2 cycles plus standard treatment (WF10 group) or standard treatment alone (control group). Fifty patients in each group were evaluated by questioning; urinalysis and cystoscopy during a 1 year follow up. Results: At week 7, 37 patients (74%) in the WF10 group and 32 patients (64%) in the control group showed complete resolution in objective hematuria (P=0.28). Significantly lower use of antibiotics (P=0.002) and antispasmodics (P<0.001) was found in the WF10 group. Among the responders, 24 patients (77%) in the control group experienced recurrent objective hematuria, whereas in the WF10 group only 17 patients (47%) experienced a recurrence (P=0.01). Recurrence of objective hematuria occurred significantly faster in the control group as evidenced by Kaplan-Meier and log-rank statistics (P=0.004), suggesting a long-term effect of WF10. Cystoscopy, at the end of the treatment period and after the one year follow up showed overall improvement without significant difference between two groups. No severe toxicity was monitored. Conclusions: WF10 therapy is a safe, non-invasive and convenient method in the management of late hemorrhagic radiation cystitis. WF10 therapy, as adjunct to standard treatment, has significantly reduced recurrence of objective hematuria, compared to standard treatment alone, during a one year follow up

AP1000: Meeting economic goals in a competitive world. Annex 7

International Nuclear Information System (INIS)

Davis, G.; Cummins, E.; Winters, J.

2002-01-01

In the U.S., conditions are becoming more favorable for considering the nuclear option again for new baseload generation. While oil and natural gas prices have risen, the cost of operating the existing fleet of nuclear plants has decreased. Furthermore, an advanced 1000 MWe nuclear plant that will be even more cost-competitive with fossil fuels and natural gas will be available by 2005. Westinghouse, in an effort to further improve on the AP600's cost competitiveness, has developed the AP1000, a two-loop, 1000 MWe, advanced pressurized water reactor (PWR) with passive safety features and extensive plant simplifications to enhance the construction, operation, and maintenance. Like the AP600, the AP1000 uses proven technology that builds on over 30 years of operating PWR experience. Westinghouse has completed design studies that demonstrate that it is feasible to increase the power output of the AP600 to at least 1000 MWe, maintaining its current design configuration and licensing basis. To maximize the cost savings, the AP1000 has been designed within the space constraints of the AP600, while retaining the credibility of proven components and substantial safety margins. The affect on the plant's overnight cost of the increased major components that is required to uprate the AP600 to 1000 MWe is small. This overall cost addition is on the order of 11 percent, while the overall power increase is almost 80 percent. This paper describes the changes made to uprate the AP600 and gives an overview of the plant design. (author)

28 CFR 16.10 - Preservation of records.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 1 2010-07-01 2010-07-01 false Preservation of records. 16.10 Section 16.10 Judicial Administration DEPARTMENT OF JUSTICE PRODUCTION OR DISCLOSURE OF MATERIAL OR INFORMATION... title 44 of the United States Code or the National Archives and Records Administration's General Records...

Final characterization and safety screen report of double shell tank 241-AP-104 for 242-A evaporator, campaign 96-1

International Nuclear Information System (INIS)

Miller, G.L.

1996-01-01

This data package satisfies the requirement for a format IV, final report. It is a follow-up to the 45-day safety screen report for tank AP-104. Evaporator candidate feed from tank 241-AP-104 (hereafter referred to as AP-104) was characterized for physical, inorganic, organic and radiochemical parameters by the Westinghouse Hanford Company, 222-S Laboratory, and by the Battelle Pacific Northwest National Laboratory (PNNL), Analytical Chemistry Laboratory (ACL) as directed by the Tank Sample and Analysis Plan (TSAP), References 1 through 4. Preliminary data in the form of summary analytical tables were provided to the project in advance of this final report to enable early estimation of evaporator operational parameters, using the Predict modeling program. Laboratory analyses at ACL Laboratory was performed according to the TSAP. Analyses were performed at the 222-S Laboratory as defined and specified in the TSAP and the Laboratory's Quality Assurance Plan, References 5 and 6. Any deviations from the instructions documented in the TSAP are discussed in this narrative and are supported with additional documentation. SAMPLING The TSAP, section 2, provided sampling information for waste samples collected from tank AP-104. The bottle-on-a-string method was used to collect liquid grab samples from the tank. Each glass sample bottle was amber, precleaned, and contained approximately 100 milliliters. Each bottle was closed with a teflon seal cap (or teflon septum for volatile organic analysis samples). Field blank samples were prepared by placing deionized water into sampling bottles, lowering the unclosed bottles into the riser for a period of time, retrieving them from the riser, and then closing the bottles with the same types of caps used for the tank samples. None of the samples were preserved by acidification. Upon receipt, the sample bottles destined for organic analyses were placed in a refrigerator. No attempt was made during sampling to assure the complete

The main requirements of the International Basic Safety Standards

International Nuclear Information System (INIS)

Webb, G.A.M.

1998-01-01

The main requirements of the new international basic safety standards are discussed, including such topics as health effects of ionizing radiations, the revision of basic safety standards, the requirements for radiation protection practices, the requirements for intervention,and the field of regulatory infrastructures. (A.K.)

A 28 GHz FR-4 Compatible Phased Array Antenna for 5G Mobile Phone Applications

DEFF Research Database (Denmark)

Ojaroudiparchin, Naser; Shen, Ming; Pedersen, Gert F.

2015-01-01

The design of a 28 GHz phased array antenna for future fifth generation (5G) mobile-phone applications has been presented in this paper. The proposed antenna can be implemented using low cost FR-4 substrates, while maintaining good performance in terms of gain and efficiency. This is achieved...

New quantitative safety standards : Different techniques, different results?

NARCIS (Netherlands)

Rouvroye, J.L.; Brombacher, A.C.; Lydersen, S.; Hansen, G.K.; Sandtor, H.

1998-01-01

Safety Instrumented Systems (SIS) are used in the process industry to perform safety functions. Many parameters can influence the safety of a SIS like system layout, diagnostics, testing and repair. In standards like the German DIN [DIN19250, DIN0801] no quantitative analysis was demanded. The

OSHA Laboratory Standard: Driving Force for Laboratory Safety!

Science.gov (United States)

Roy, Kenneth R.

2000-01-01

Discusses the Occupational Safety and Health Administration's (OSHA's) Laboratory Safety Standards as the major driving force in establishing and maintaining a safe working environment for teachers and students. (Author)

Effects of environmental estrogenic chemicals on AP1 mediated transcription with estrogen receptors alpha and beta.

Science.gov (United States)

Fujimoto, Nariaki; Honda, Hiroaki; Kitamura, Shigeyuki

2004-01-01

There has been much discussion concerning endocrine disrupting chemicals suspected of exerting adverse effects in both wildlife and humans. Since the majority of these compounds are estrogenic, a large number of in vitro tests for estrogenic characteristics have been developed for screening purpose. One reliable and widely used method is the reporter gene assay employing estrogen receptors (ERs) and a reporter gene with a cis-acting estrogen responsive element (ERE). Other elements such as AP1 also mediate estrogenic signals and the manner of response could be quite different from that of ERE. Since this has yet to be explored, the ER mediated AP1 activity in response to a series of environmental estrogens was investigated in comparison with ERE findings. All the compounds exhibited estrogenic properties with ERE-luc and their AP1 responses were quite similar. These was one exception, however, p,p'-DDT (1,1,1,-trichloro-2,2-bis(p-chlorophenyl)ethane) did not exert any AP1-luc activity, while it appeared to be estrogenic at 10(-7) to 10(-5)M with the ERE action. None of the compounds demonstrated ER beta:AP1 activity. These data suggest that significant differences can occur in responses through the two estrogen pathways depending on environmental chemicals.

77 FR 62150 - Approval and Promulgation of Implementation Plans; Kentucky; Approval of Revisions to the...

Science.gov (United States)

2012-10-12

....34 Standard of 10/23/01 66 FR 53661 05/15/91 Performance for Existing Pneumatic Rubber Tire... Abbreviations and 11/19/02 67 FR 69688 05/15/02 Acronyms. 1.04 Performance Tests... 10/23/01 66 FR 53660 11/19... 10/23/01 66 FR 53660 06/13/79 Requirements. Reg 6--Standards of Performance for Existing Affected...

Existing and future international standards for the safety of radioactive waste disposal

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

VERIFICATION OF THE FOOD SAFETY MANAGEMENT SYSTEM IN DEEP FROZEN FOOD PRODUCTION PLANT

Directory of Open Access Journals (Sweden)

Peter Zajác

2010-07-01

Full Text Available In work is presented verification of food safety management system of deep frozen food. Main emphasis is on creating set of verification questions within articles of standard STN EN ISO 22000:2006 and on searching of effectiveness in food safety management system. Information were acquired from scientific literature sources and they pointed out importance of implementation and upkeep of effective food safety management system. doi:10.5219/28

Conformational Landscape of the p28-Bound Human Proteasome Regulatory Particle.

Science.gov (United States)

Lu, Ying; Wu, Jiayi; Dong, Yuanchen; Chen, Shuobing; Sun, Shuangwu; Ma, Yong-Bei; Ouyang, Qi; Finley, Daniel; Kirschner, Marc W; Mao, Youdong

2017-07-20

The proteasome holoenzyme is activated by its regulatory particle (RP) consisting of two subcomplexes, the lid and the base. A key event in base assembly is the formation of a heterohexameric ring of AAA-ATPases, which is guided by at least four RP assembly chaperones in mammals: PAAF1, p28/gankyrin, p27/PSMD9, and S5b. Using cryogenic electron microscopy, we analyzed the non-AAA structure of the p28-bound human RP at 4.5 Å resolution and determined seven distinct conformations of the Rpn1-p28-AAA subcomplex within the p28-bound RP at subnanometer resolutions. Remarkably, the p28-bound AAA ring does not form a channel in the free RP and spontaneously samples multiple "open" and "closed" topologies at the Rpt2-Rpt6 and Rpt3-Rpt4 interfaces. Our analysis suggests that p28 assists the proteolytic core particle to select a specific conformation of the ATPase ring for RP engagement and is released in a shoehorn-like fashion in the last step of the chaperone-mediated proteasome assembly. Copyright © 2017 Elsevier Inc. All rights reserved.

DOE standard: Firearms safety

International Nuclear Information System (INIS)

1996-02-01

Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements

DOE standard: Firearms safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements.

10 CFR 830.202 - Safety basis.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Safety basis. 830.202 Section 830.202 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Safety Basis Requirements § 830.202 Safety basis. (a) The contractor responsible for a hazard category 1, 2, or 3 DOE nuclear facility must establish and maintain the safety basis...

10 CFR 1.28 - Office of Public Affairs.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Office of Public Affairs. 1.28 Section 1.28 Energy NUCLEAR... Office of Public Affairs. The Office of Public Affairs— (a) Develops policies, programs, and procedures for the Chairman's approval for informing the public of NRC activities; (b) Prepares, clears, and...

Landbaserade godstransporter, klimat och styrmedel : underlagsrapporter 1-10

OpenAIRE

Carlén, Björn; Hultkrantz, Lars; Liu, Xing; Lunander, Anders; Mandell, Svante; Mellin, Anna; Nilsson, Jan-Eric; Pyddoke, Roger; Sorkina, Edith; Vierth, Inge

2014-01-01

VTI notat 28-2014 innehåller de tio underlagsrapporter som ligger till grund för VTI rapport 831: ”Landbaserade godstransporter, klimat och styrmedel – Sammanfattande rapport”. I VTI rapport 831 diskuterar forskarna flera dimensioner av hur växthusgaserna från godstransportsektorn ska kunna minskas, till exempel med hjälp av så kallade Gröna korridorer. Vidare diskuteras hur man ska se på de klimatpolitiska konsekvenserna av överflyttning från väg till järnväg eller elektrifierade fordon på v...

Best Practices in Physics Program Assessment: Should APS Provide Accreditation Standards for Physics?

Science.gov (United States)

Hodapp, Theodore

The Phys21 report, ``Preparing Physics Students for 21st Century Careers,'' provides guidance for physics programs to improve their degree programs to make them more relevant for student career choices. Undertaking such changes and assessing impact varies widely by institution, with many departments inventing assessments with each periodic departmental or programmatic review. American Physical Society has embarked on a process to integrate information from Phys21, the results of other national studies, and educational research outcomes to generate a best-practices guide to help physics departments conduct program review, assessment, and improvement. It is anticipated that departments will be able to use this document to help with their role in university-level accreditation, and in making the case for improvements to departmental programs. Accreditation of physics programs could stem from such a document, and I will discuss some of the thinking of the APS Committee on Education in creating this guide, and how they are advising APS to move forward in the higher education landscape that is increasingly subject to standards-based evaluations. I will describe plans for the design, review, and dissemination of this guide, and how faculty can provide input into its development. This material is based upon work supported by the National Science Foundation under Grant No. 1540570. Opinions expressed do not necessarily reflect those of the NSF.

A new standard for multidisciplinary health and safety technicians

International Nuclear Information System (INIS)

Trinoskey, P.A.; Fry, L.A.; Egbert, W.F.

2000-01-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

A new standard for multidisciplinary health and safety technicians

Energy Technology Data Exchange (ETDEWEB)

Trinoskey, P.A.; Fry, L.A. [Lawrence Livermore National Laboratory, Univ. of California, CA (United States); Egbert, W.F. [Lawrence Livermore National Laboratory, Allied Signal Technical Corporation (United States)

2000-05-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

The Agency's Safety Standards and Measures

International Nuclear Information System (INIS)

1976-04-01

The Agency's Health and Safety Measures were first, approved by the Board of Governors on 31 March 1960 in implementation of Articles III.A.6 and XII of the Statute of the Agency. On the basis of the experience gained from applying those measures to projects carried out by Members under agreements concluded with the Agency, the Agency's Health and Safety Measures were revised in 1975 and approved by the Board of Governors on 25 February 1976. The Agency's Safety Standards and Measures as revised are reproduced in this document for the information of all Members

Study of the D(p,π+)T and 9Be(p,π+)10Be from 400 to 800MeV

International Nuclear Information System (INIS)

Aslanides, E.; Bauer, T.; Bertini, R.; Beurtey, R.; Bimbot, L.; Bing, O.; Boudard, A.; Brochard, F.; Bruge, G.; Catz, H.; Chaumeaux, A.; Couvert, P.; Duchazeaubeneix, J.C.; Duhm, H.; Garreta, D.; Gorodetzky, P.; Habault, J.; Hibou, F.; Igo, G.; Le Bornec, Y.; Lugol, J.C.; Matoba, M.; Tatischeff, B.; Terrien, Y.

Pion production on CD 2 and 9 Be targets has been observed using the high resolution, energy loss, spectrometer SPES I. Differential cross sections for the D(p,π + ) reaction have been determined at 410, 605 and 809MeV and for the 9 Be(p,π + ) reaction at 410 and 605MeV. The 3.37MeV (2 + ) state in 10 Be is populated preferentially, but a significant part of the transition strength seems to populate the ground state and the higher lying multiplets at about 6.1MeV, 7.4MeV and 9.4MeV [fr

Confirmatory analysis of the AP1000 passive residual heat removal heat exchanger with 3-D computational fluid dynamic analysis

International Nuclear Information System (INIS)

Schwall, James R.; Karim, Naeem U.; Thakkar, Jivan G.; Taylor, Creed; Schulz, Terry; Wright, Richard F.

2006-01-01

The AP1000 is an 1100 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 received final design approval from the US-NRC in 2004. The AP1000 design is based on the AP600 design that received final design approval in 1999. Wherever possible, the AP1000 plant configuration and layout was kept the same as AP600 to take advantage of the maturity of the design and to minimize new design efforts. As a result, the two-loop configuration was maintained for AP1000, and the containment vessel diameter was kept the same. It was determined that this significant power up-rate was well within the capability of the passive safety features, and that the safety margins for AP1000 were greater than those of operating PWRs. A key feature of the passive core cooling system is the passive residual heat removal heat exchanger (PRHR HX) that provides decay heat removal for postulated LOCA and non-LOCA events. The PRHR HX is a C-tube heat exchanger located in the in-containment refueling water storage tank (IRWST) above the core promoting natural circulation heat removal between the reactor cooling system and the tank. Component testing was performed for the AP600 PRHR HX to determine the heat transfer characteristics and to develop correlations to be used for the AP1000 safety analysis codes. The data from these tests were confirmed by subsequent integral tests at three separate facilities including the ROSA facility in Japan. Owing to the importance of this component, an independent analysis has been performed using the ATHOS-based computational fluid dynamics computer code PRHRCFD. Two separate models of the PRHR HX and IRWST have been developed representing the ROSA test geometry and the AP1000 plant geometry. Confirmation of the ROSA test results were used to validate PRHRCFD, and the AP1000 plant model

Memoranda by A.P. Uspensky to the Council of Ministers of the Provisional Siberian government

OpenAIRE

Sukhanov Aleksandr

2015-01-01

This publication offers a previously unknown memoranda by representative of the diocesan assembly of deputies of the clergy and laity of the Tomsk diocese A. P. Uspensky, addressed to the Council of Ministers of the Provisional Siberian government in July 1918. A.P. Uspensky solicited for formation of the Ministry of confessions in the Provisional Siberian government. Memoranda are initiative documents to the Statute on the Chief Administration of religious denominations adopted by the Council...

Catalogue of standards at the Safety Analysis department library, the first of March 1987

International Nuclear Information System (INIS)

1987-01-01

This report is a compilation of ANS and ANSI/ANS, ANSI/ASME american standards, Regulatory guides (Power Reactor Division), IEEE standards, to which are added ANSI american standards, AFNOR french standards, all of them being updated until to day. This computed compilation is divided into three parts: 1) main descriptor categories; 2) list of american standards in chronological order, list of AFNOR french standards, list of Regulatory guides in numerical order. 3) list of descriptors in alphabetic order [fr

Segurança e efetividade da fisioterapia respiratória em abscesso pulmonar: estudo de casos Safety and effectiveness of chest physiotherapy in lung abscess: a two-case study

Directory of Open Access Journals (Sweden)

Josy Davidson

2010-12-01

Full Text Available O abscesso pulmonar é uma lesão necrótica geralmente devida a germes piogênicos. A fisioterapia respiratória (FR é indicada, porém há poucos relatos na literatura, não havendo consenso quanto ao uso e às técnicas de FR para esse caso. O objetivo deste estudo de dois casos foi verificar a segurança e efetividade da FR no tratamento do abcesso pulmonar. O caso 1 foi um paciente de 30 anos, internado; a terapia consistiu em posicioná-lo em Trendelenburg semi-lateral direito para ventral por 30 minutos, três vezes ao dia, com saída de grande quantidade de secreção. Após 5 dias, o radiograma de tórax demonstrou redução de 90% do nível hidroaéreo, verificando-se o esvaziamento completo do abscesso após 14 dias de internação. O caso 2 foi uma paciente de 28 anos igualmente com diagnóstico de abscesso pulmonar, também tratada com drenagem postural, nos mesmos posicionamento e freqüência que o caso 1, sendo drenada grande quantidade de secreção amarelada e fluida. Após 7 dias de tratamento evidenciou-se redução importante do nível líquido do abscesso pulmonar. Conclui-se que a drenagem postural isoladamente é uma técnica de fisioterapia efetiva e segura no tratamento do abcesso pulmonar.Lung abscess is a necrotic lesion mostly caused by pyogenic germs. Chest physical therapy (CPT is indicated, but there are few studies available and no consensus on CPT use and techniques for theses cases. The purpose of this study was to assess safety and effectiveness of postural drainage in treating lung abscess in two cases. Patient 1, male, 30 years old, was laid in Trendelenburg, in semi-lateral to ventral decubitus for 30 minutes, three times a day. After five days of therapy, X-ray showed a 90% decrease of sputum, and on the 14th day full drainage was achieved. Case 2 was a female patient, 28 years old, treated at the same position and frequency as case 1. After seven days of therapy, exams showed a great decrease of pus from

75 FR 72664 - System Personnel Training Reliability Standards

Science.gov (United States)

2010-11-26

...--Staffing). \\2\\ Mandatory Reliability Standards for the Bulk-Power System, Order No. 693, 72 FR 16416 (Apr... on the North American bulk electric system are competent to perform those reliability-related tasks... PER-004-2 will achieve a significant improvement in the reliability of the Bulk- Power System and...

Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

CERN Document Server

Smith, David J

2010-01-01

Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

77 FR 42988 - Updating OSHA Construction Standards Based on National Consensus Standards; Head Protection...

Science.gov (United States)

2012-07-23

.... OSHA-2011-0184] RIN 1218-AC65 Updating OSHA Construction Standards Based on National Consensus... Administration (OSHA), Department of Labor. ACTION: Direct final rule; correction. SUMMARY: OSHA is correcting a... confusion resulting from a drafting error. OSHA published the DFR on June 22, 2012 (77 FR 37587). OSHA also...

39 CFR 111.3 - Amendments to the Mailing Standards of the United States Postal Service, Domestic Mail Manual.

Science.gov (United States)

2010-07-01

... 39 Postal Service 1 2010-07-01 2010-07-01 false Amendments to the Mailing Standards of the United.... 39 June 16, 1991 56 FR 56015 40 September 15, 1991 56 FR 56013 41 December 15, 1991 57 FR 21611 42... July 1, 1997 62 FR 30457 53 January 1, 1998 62 FR 63851 54 January 10, 1999 64 FR 39 55 January 10...

Comparison of Size Modulation Standard Automated Perimetry and Conventional Standard Automated Perimetry with a 10-2 Test Program in Glaucoma Patients.

Science.gov (United States)

Hirasawa, Kazunori; Takahashi, Natsumi; Satou, Tsukasa; Kasahara, Masayuki; Matsumura, Kazuhiro; Shoji, Nobuyuki

2017-08-01

This prospective observational study compared the performance of size modulation standard automated perimetry with the Octopus 600 10-2 test program, with stimulus size modulation during testing, based on stimulus intensity and conventional standard automated perimetry, with that of the Humphrey 10-2 test program in glaucoma patients. Eighty-seven eyes of 87 glaucoma patients underwent size modulation standard automated perimetry with Dynamic strategy and conventional standard automated perimetry using the SITA standard strategy. The main outcome measures were global indices, point-wise threshold, visual defect size and depth, reliability indices, and test duration; these were compared between size modulation standard automated perimetry and conventional standard automated perimetry. Global indices and point-wise threshold values between size modulation standard automated perimetry and conventional standard automated perimetry were moderately to strongly correlated (p 33.40, p modulation standard automated perimetry than with conventional standard automated perimetry, but the visual-field defect size was smaller (p modulation-standard automated perimetry than on conventional standard automated perimetry. The reliability indices, particularly the false-negative response, of size modulation standard automated perimetry were worse than those of conventional standard automated perimetry (p modulation standard automated perimetry than with conventional standard automated perimetry (p = 0.02). Global indices and the point-wise threshold value of the two testing modalities correlated well. However, the potential of a large stimulus presented at an area with a decreased sensitivity with size modulation standard automated perimetry could underestimate the actual threshold in the 10-2 test protocol, as compared with conventional standard automated perimetry.

76 FR 70885 - Updating Fire Safety Standards

Science.gov (United States)

2011-11-16

... effect on the economy of $100 million or more or adversely affect in a material way the economy, a sector of the economy, productivity, competition, jobs, the environment, public health or safety, or State...; 64.018, Sharing Specialized Medical Resources; 64.019, Veterans Rehabilitation Alcohol and Drug...

Task Force on Catastrophic Antiphospholipid Syndrome (APS) and Non-criteria APS Manifestations (I): catastrophic APS, APS nephropathy and heart valve lesions.

Science.gov (United States)

Cervera, R; Tektonidou, M G; Espinosa, G; Cabral, A R; González, E B; Erkan, D; Vadya, S; Adrogué, H E; Solomon, M; Zandman-Goddard, G; Shoenfeld, Y

2011-02-01

The objectives of the 'Task Force on Catastrophic Antiphospholipid Syndrome (APS) and Non-criteria APS Manifestations' were to assess the clinical utility of the international consensus statement on classification criteria and treatment guidelines for the catastrophic APS, to identify and grade the studies that analyse the relationship between the antiphospholipid antibodies and the non-criteria APS manifestations and to present the current evidence regarding the accuracy of these non-criteria APS manifestations for the detection of patients with APS. This article summarizes the studies analysed on the catastrophic APS, APS nephropathy and heart valve lesions, and presents the recommendations elaborated by the Task Force after this analysis.

Developing international safety standards for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Metcalf, P.

2001-01-01

In the context of the International Atomic Energy Agency's (IAEA) programme to create a corpus of internationally accepted Radioactive Waste Safety Standards (RADWASS), focus is currently being placed on establishing standards for the 'geological disposal of radioactive waste'. This is a challenging task and to help the standards development process there is a need to stimulate discussion of some of the associated scientific and technical issues. A number of position papers developed in recent years by a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, address many of the relevant issues. These include a common safety based framework for radioactive waste disposal, appropriate time frames for safety assessment, different possible indicators of long-term safety, the safety implications of reversibility and retrievability, the assessment of possible human intrusion into the repository, the role and limitations of institutional control, establishing reference critical groups and biospheres for long-term assessment, and what is meant by 'compliance' with the standards. These papers will be discussed at a Specialists Meeting to be held at the IAEA in June 2001 as a means of establishing the extent to which they enjoy the general support of experts. In order to broaden that consensus, the conclusions reached at the Specialists Meeting on the issues listed above will be presented and discussed with participants at a number of international meetings. Later this year, a draft safety standard on the geological disposal of radioactive waste which takes account of the consensus positions reached through the various consultations will be submitted for the consideration of Waste Safety Standards Committee (WASSC), the officially approved body within the IAEA for the review and approval of waste safety standards. The Committee is made up of government appointed radioactive waste regulators

TWG-FR Activity Report for the Period May 2011 – May 2012

International Nuclear Information System (INIS)

Monti, Stefano

2012-01-01

Recent Recommendations of the TWG-FR & implementation: ⇨ Increase the efforts to make more countries participating in its activities → Sweden became full member of TWG-FR this year. ⇨ Concentrate all research and technical activities related to FR under the TWG-FR umbrella. An efficient and effective interface between INPRO and TWG-FR should be established to avoid duplication/overlapping of activities → done. ⇨ Closer cooperation links should be established with FR-related activities implemented within the framework of other international programmes (e.g. GIF, INPRO, OECD/NEA, ESNII) → systematic collaboration with INPRO, interface with GIF, participation to NEA-TF on SFR, member of External Advisory Committee of some Euratom projects. ⇨ Continue to secure training and education in the field of Fast Neutron System Physics, Technology and Applications, and respective Schools/Seminars should be held on a regular basis → 4 events: 2 in 2011 and 2 in 2012 (Trieste, Bariloche). ⇨ Launch new CRPs in the field of safety of FR with special emphasis on severe accidents → launch of EBR-II CRP + 4 related Workshops/TMs. ⇨ The IAEA, with technical inputs from the TWG-FR, should produce international safety standards relevant to fast reactors → Initiated discussion with Department of Nuclear Safety and Security + INPRO/GIF for SFR Safety Design Criteria

AP1000 will meet the challenges of near-term deployment

International Nuclear Information System (INIS)

Matzie, Regis A.

2008-01-01

The world demand for energy is growing rapidly, particularly in developing countries that are trying to raise the standard of living for billions of people, many of whom do not have access to electricity or clean water. Climate change and the concern for increased emissions of green house gases have brought into question the future primary reliance of fossil fuels. With the projected worldwide increase in energy demand, concern for the environmental impact of carbon emissions, and the recent price volatility of fossil fuels, nuclear energy is undergoing a rapid resurgence. This 'nuclear renaissance' is broad based, reaching across Asia, North America, Europe, as well as selected countries in Africa and South America. Many countries have publicly expressed their intentions to pursue the construction of new nuclear energy plants. Some countries that have previously turned away from commercial nuclear energy are reconsidering the advisability of this decision. This renaissance is facilitated by the availability of more advanced reactor designs than are operating today, with improved safety, economy, and operations. One such design, the Westinghouse AP1000 advanced passive plant, has been a long time in the making! The development of this passive technology started over two decades ago from an embryonic belief that a new approach to design was needed to spawn a nuclear renaissance. The principal challenges were seen as ensuring reactor safety by requiring less reliance on operator actions and overcoming the high plant capital cost of nuclear energy. The AP1000 design is based on the use of innovative passive technology and modular construction, which require significantly less equipment and commodities that facilitate a more rapid construction schedule. Because Westinghouse had the vision and the perseverance to continue the development of this passive technology, the AP1000 design is ready to meet today's challenge of near-term deployment

Advanced passive technology: A global standard for nuclear plant requirements

International Nuclear Information System (INIS)

Novak, V.

1994-01-01

Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

Advanced passive technology: A global standard for nuclear plant requirements

Energy Technology Data Exchange (ETDEWEB)

Novak, V

1994-12-31

Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

European and International Standards on health and safety in welding

International Nuclear Information System (INIS)

Howe, A

2009-01-01

A number of European and International Standards on health and safety in welding have been published in recent years and work on several more is nearing completion. These standards have been prepared jointly by the International Standards Organization (ISO) and the European Committee for Standardization (CEN). The standards development work has mostly been led by CEN/TC 121/SC 9, with excellent technical input from experts within Europe; but work on the revision of published standards, which has recently gathered pace, is now being carried out by ISO/TC 44/SC 9, with greater international involvement. This paper gives an overview of the various standards that have been published, are being revised or are under development in this field of health and safety in welding, seeking to (i) increase international awareness of published standards, (ii) encourage wider participation in health and safety in welding standards work and (iii) obtain feedback and solicit comments on standards that are currently under development or revision. Such an initiative is particularly timely because work is currently in progress on the revision of one of the more important standards in this field, namely EN ISO 10882:2001 Health and safety in welding and allied processes- Sampling of airborne particles and gases in the operator's breathing zone - Part 1: Sampling of airborne particles.

75 FR 16748 - Final Voluntary Product Standard; DOC PS 20-10 “American Softwood Lumber Standard”

Science.gov (United States)

2010-04-02

...-0146-02] Final Voluntary Product Standard; DOC PS 20-10 ``American Softwood Lumber Standard'' AGENCY... of Standards and Technology (NIST) announces voluntary product standard DOC PS 20-10 ``American Softwood Lumber Standard'' which will supersede DOC PS 20-05. The Standard establishes standard sizes and...

[Comparison of the Efficacy and Safety of Icotinib with Standard Second-line 
Chemotherapy in Previously Treated Advanced Non-small Cell Lung Cancer].

Science.gov (United States)

Yao, Shuyang; Qian, Kun; Wang, Ruotian; Li, Yuanbo; Zhang, Yi

2015-06-01

This study compared the efficacy and safety of icotinib with standard second-line chemotherapy (single-agent docetaxel or pemetrexed) in previously treated advanced non-small cell lung cancer (NSCLC). Thirty-two consecutive patients treated with icotinib and 33 consecutive patients treated with standard second-line chemotherapy in Xuanwu Hospital from January 2012 to July 2013 were enrolled in our retrospective research. The Response Evaluation Criteria in Solid Tumors were used to evaluate the tumor responses, and the progression-free survival (PFS) was evaluated by Kaplan-Meier method. Icotinib was comparable with standard second-line chemotherapy for advanced NSCLC in terms of overall response rate (ORR) (28.1% vs 18.2%, P=0.341), disease control rate (DFS)(43.8% vs 45.5%, P=0.890), and PFS (4.3 months vs 3.8 months, P=0.506). In the icotinib group, the ORR of epidermal growth factor receptor (EGFR) mutant was significantly higher than that of EGFR unknown or wild type (P=0.017). In multivariate analysis, age, gender, histology, and the optimum first-line treatment response were dependent prognostic factors based on the PFS of the icotinib group. The incidence of adverse events was significantly fewer in the icotinib group than in the chemotherapy group (P=0.001). Compared with the standard second-line chemotherapy, icotinib is active in the treatment of advanced NSCLC patients, especially with EGFR unknown in the second line, with an acceptable adverse event profile.

49 CFR 231.28 - Box and other house cars with roof hatches built or placed in service after October 1, 1966.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Box and other house cars with roof hatches built... RAILROAD SAFETY APPLIANCE STANDARDS § 231.28 Box and other house cars with roof hatches built or placed in... other house cars with roof hatches. Box and other house cars with roof hatches built on or before April...

Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

International Nuclear Information System (INIS)

Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

2005-01-01

Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

Radiation safety standards and regulations

International Nuclear Information System (INIS)

Ermolina, E.P.; Ivanov, S.I.

1993-01-01

Radiation protection laws of Russia concerning medical application of ionizing radiation are considered. Main concepts of the documents and recommendations are presented. Attention was paid to the ALARA principle, safety standrds for paietients, personnel and population, radiation protection. Specific feature of the standardization of radiation factors is the establishment of two classes of norms: main dose limits and permissible levels. Maximum dose commitment is the main standard. Three groups of critical organs and three categories of the persons exposed to radiation are stated. Main requirements for radiation protection are shown

78 FR 73112 - Monitoring System Conditions-Transmission Operations Reliability Standards; Interconnection...

Science.gov (United States)

2013-12-05

...\\ \\8\\ Mandatory Reliability Standards for the Bulk-Power System, Order No. 693, 72 FR 16416 (Apr. 4... operators and reliability coordinators to ``plan and operate the interconnected Bulk Electric System in a... mandated in the currently- effective standards, thereby improving reliability of the bulk power system...

Compulsão alimentar antes e após a cirurgia bariátrica Binge eating before and after bariatric surgery

Directory of Open Access Journals (Sweden)

Cristiane Evangelista Machado

2008-12-01

Full Text Available RACIONAL: A obesidade é distúrbio de origem multifatorial complexa que congrega aspectos de ordem psicológica, social, biológica e requer abordagem multidisciplinar. É considerada fator de risco para a compulsão alimentar, de modo que a dinâmica emocional do obeso contribuiria para desencadear o ato compulsivo. OBJETIVO: Analisar os indícios de compulsão alimentar em pacientes submetidos à cirurgia bariátrica, antes e dois anos após a operação. MÉTODOS: Foi realizado estudo prospectivo em 50 pacientes submetidos à cirurgia bariátrica pela técnica de Fobi-Capella. Os instrumentos de avaliação psicológica, aplicados antes e após dois anos, foram o teste das Pirâmides Coloridas de Max Pfister e entrevista clínica semi-estruturada. O teste foi aplicado antes e após a operação para identificar indícios de compulsão. A entrevista somente no pós-operatório. RESULTADOS: Citando somente os dados principais, os dados mostraram estabilidade e capacidade para lidar com conflitos em 16% dos pacientes antes da operação e em 10% após. Para a capacidade de controle e adaptação, 36% dos pacientes apresentavam fortes indícios de atitude de controle e rigidez antes da operação e 32% após. Quanto aos indicadores de impulsividade, agressividade e irritabilidade, houve fortes indícios de atitudes agressivas e impulsivas em 28% antes da operação e em 36% após. Quanto ao comportamento beliscador, eram presentes em 94% dos pacientes no pré-operatório e em 60% no pós. Quanto à preferência alimentar, foi a por alimentos calóricos sem menção à bebidas alcoólicas no pré-operatório, e no pós-operatório por alimentos de fácil ingestão. Quanto ao motivo atribuído aos episódios compulsivos, antes da operação 4% dos pacientes relataram estado de nervosismo, 24% afirmaram distúrbios de humor e 52% identificaram sentimentos de impotência ou submissão. No pós, foram 10%, 28% e 38%. Quanto às respostas compensat

Intermediate-break LOCA analyses for the AP600 design

International Nuclear Information System (INIS)

Boyack, B.E.; Lime, J.F.

1995-01-01

A postulated double-ended guillotine break of a direct-vessel-injection line in an AP600 plant has been analyzed. This event is characterized as an intermediate break loss-of-coolant accident (IBLOCA). Most of the insights regarding the response of the AP600 safety systems to the postulated accident are derived from calculations performed with the TRAC-PFl/MOD2 code. However, complementary insights derived from a scaled experiment conducted in the ROSA facility, as well as insights based upon calculations by other codes, are also presented. The key processes occurring in an AP600 during a IBLOCA are primary coolant system depressurization, inventory depletion, inventory replacement via emergency core coolant injection, continuous core cooling, and long-term decay heat rejection to the atmosphere. Based upon the calculated and experimental results, the AP600 will not experience a core heat up and will reach a safe shutdown state using only safety-class equipment. Only the early part of the long-term cooling period initiated by In-containment Refueling Water Storage Tank injection was evaluated Thus, the observation that the core is continuously cooled should be verified for the latter phase of the long-term cooling period, the interval when sump injection and containment cooling processes are important

28 CFR 73.2 - Exceptions.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Exceptions. 73.2 Section 73.2 Judicial... GOVERNMENTS § 73.2 Exceptions. (a) The exemption provided in 18 U.S.C. 951(d)(4) for a “legal commercial...-89, 54 FR 46608, Nov. 6, 1989, as amended by Order No. 3018-2008, 73 FR 73182, Dec. 2, 2008] ...

AP600 containment purge radiological analysis

Energy Technology Data Exchange (ETDEWEB)

O`Connor, M.; Schulz, J.; Tan, C. [Bechtel Power Corporation (United States)] [and others

1995-02-01

The AP600 Project is a passive pressurized water reactor power plant which is part of the Design Certification and First-of-a-Kind Engineering effort under the Advanced Light Water Reactor program. Included in this process is the design of the containment air filtration system which will be the subject of this paper. We will compare the practice used by previous plants with the AP600 approach to meet the goals of industry standards in sizing the containment air filtration system. The radiological aspects of design are of primary significance and will be the focus of this paper. The AP600 Project optimized the design to combine the functions of the high volumetric flow rate, low volumetric flow rate, and containment cleanup and other filtration systems into one multi-functional system. This achieves a more simplified, standardized, and lower cost design. Studies were performed to determine the possible concentrations of radioactive material in the containment atmosphere and the effectiveness of the purge system to keep concentrations within 10CFR20 limits and within offsite dose objectives. The concentrations were determined for various reactor coolant system leakage rates and containment purge modes of operation. The resultant concentrations were used to determine the containment accessibility during various stages of normal plant operation including refueling. The results of the parametric studies indicate that a dual train purge system with a capacity of 4,000 cfm per train is more than adequate to control the airborne radioactivity levels inside containment during normal plant operation and refueling, and satisfies the goals of ANSI/ANS-56.6-1986 and limits the amount of radioactive material released to the environment per ANSI/ANS 59.2-1985 to provide a safe environment for plant personnel and offsite residents.

Ap/sub 4/A interactions with a multiprotein form of DNA polymerase. cap alpha. - primase from HeLa cells

Energy Technology Data Exchange (ETDEWEB)

Baril, E F; Owen, M W; Vishwanatha, J K; Zamecnik, P C

1984-06-01

In previous studies, it was shown that Ap/sub 4/A can function as a primer for in vitro DNA synthesis by the multiprotein form of DNA polymerase ..cap alpha.. with single-stranded DNA and an octadecamer double-stranded DNA template. In these studies, the authors show that Ap/sub 4/A that is greater than 99% pure by high performance liquid chromatography also stimulates the incorporation of (..cap alpha../sup 32/P)ATP into the 10-15 oligoribonucleotide primer with poly(dT) template by the primase that is resolved from the polymerase ..cap alpha.. core enzyme. Other dinucleotides or dinucleotide polyphosphates (e.g. ApA, Ap/sub 2/A or Ap/sub 3/A) do not enhance the incorporation of (..cap alpha../sup 32/P)ATP in this reaction. The results from phosphate transfer experiments demonstrate a covalent linkage between (/sup 3/H)Ap/sub 4/A and the /sup 32/P-labeled oligoriboadenylate that is synthesized by the primase.

24 CFR 51.203 - Safety standards.

Science.gov (United States)

2010-04-01

... Conventional Fuels or Chemicals of an Explosive or Flammable Nature § 51.203 Safety standards. The following... facilities or areas shall not exceed 0.5 psi. (c) If a hazardous substance constitutes both a thermal...

Standard test method for measuring pH of soil for use in corrosion testing

CERN Document Server

American Society for Testing and Materials. Philadelphia

1995-01-01

1.1 This test method covers a procedure for determining the pH of a soil in corrosion testing. The principle use of the test is to supplement soil resistivity measurements and thereby identify conditions under which the corrosion of metals in soil may be accentuated (see G 57 - 78 (1984)). 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

40 CFR Appendix L to Subpart G of... - Substitutes Listed in the January 27, 2003, Final Rule, Effective March 28, 2003

Science.gov (United States)

2010-07-01

... be in accordance with the safety guidelines in the latest edition of the NFPA 2001 Standard for Clean... potential risks of combustion by-products be labelled on the extinguisher (see UL 2129) [68 FR 4010, Jan. 27...

28 CFR 66.20 - Standards for financial management systems.

Science.gov (United States)

2010-07-01

... financial reporting requirements of the grant or subgrant. (2) Accounting records. Grantees and subgrantees... advances to the grantees. (c) An awarding agency may review the adequacy of the financial management system... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Standards for financial management...

Critical Review of Commercial Secondary Lithium-Ion Battery Safety Standards

Science.gov (United States)

Jones, Harry P.; Chapin, Thomas, J.; Tabaddor, Mahmod

2010-09-01

The development of Li-ion cells with greater energy density has lead to safety concerns that must be carefully assessed as Li-ion cells power a wide range of products from consumer electronics to electric vehicles to space applications. Documented field failures and product recalls for Li-ion cells, mostly for consumer electronic products, highlight the risk of fire, smoke, and even explosion. These failures have been attributed to the occurrence of internal short circuits and the subsequent thermal runaway that can lead to fire and explosion. As packaging for some applications include a large number of cells, the risk of failure is likely to be magnified. To address concerns about the safety of battery powered products, safety standards have been developed. This paper provides a review of various international safety standards specific to lithium-ion cells. This paper shows that though the standards are harmonized on a host of abuse conditions, most lack a test simulating internal short circuits. This paper describes some efforts to introduce internal short circuit tests into safety standards.

16 CFR 1115.8 - Compliance with product safety standards.

Science.gov (United States)

2010-01-01

... applicable mandatory consumer product safety standards and to report to the Commission any products which do.... 1115.8 Section 1115.8 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SUBSTANTIAL PRODUCT HAZARD REPORTS General Interpretation § 1115.8 Compliance with...

Safety implications of standardized continuous quality improvement programs in community pharmacy.

Science.gov (United States)

Boyle, Todd A; Ho, Certina; Mackinnon, Neil J; Mahaffey, Thomas; Taylor, Jeffrey M

2013-06-01

Standardized continuous quality improvement (CQI) programs combine Web-based technologies and standardized improvement processes, tools, and expectations to enable quality-related events (QREs) occurring in individual pharmacies to be shared with pharmacies in other jurisdictions. Because standardized CQI programs are still new to community pharmacy, little is known about how they impact medication safety. This research identifies key aspects of medication safety that change as a result of implementing a standardized CQI program. Fifty-three community pharmacies in Nova Scotia, Canada, adopted the SafetyNET-Rx standardized CQI program in April 2010. The Institute for Safe Medication Practices (ISMP) Canada's Medication Safety Self-Assessment (MSSA) survey was administered to these pharmacies before and 1 year into their use of the SafetyNET-Rx program. The nonparametric Wilcoxon signed-rank test was used to explore where changes in patient safety occurred as a result of SafetyNETRx use. Significant improvements occurred with quality processes and risk management, staff competence, and education, and communication of drug orders and other information. Patient education, environmental factors, and the use of devices did not show statistically significant changes. As CQI programs are designed to share learning from QREs, it is reassuring to see that the largest improvements are related to quality processes, risk management, staff competence, and education.

Multiple independent genetic factors at NOS1AP modulate the QT interval in a multi-ethnic population.

Directory of Open Access Journals (Sweden)

Dan E Arking

Full Text Available Extremes of electrocardiographic QT interval are associated with increased risk for sudden cardiac death (SCD; thus, identification and characterization of genetic variants that modulate QT interval may elucidate the underlying etiology of SCD. Previous studies have revealed an association between a common genetic variant in NOS1AP and QT interval in populations of European ancestry, but this finding has not been extended to other ethnic populations. We sought to characterize the effects of NOS1AP genetic variants on QT interval in the multi-ethnic population-based Dallas Heart Study (DHS, n = 3,072. The SNP most strongly associated with QT interval in previous samples of European ancestry, rs16847548, was the most strongly associated in White (P = 0.005 and Black (P = 3.6 x 10(-5 participants, with the same direction of effect in Hispanics (P = 0.17, and further showed a significant SNP x sex-interaction (P = 0.03. A second SNP, rs16856785, uncorrelated with rs16847548, was also associated with QT interval in Blacks (P = 0.01, with qualitatively similar results in Whites and Hispanics. In a previously genotyped cohort of 14,107 White individuals drawn from the combined Atherosclerotic Risk in Communities (ARIC and Cardiovascular Health Study (CHS cohorts, we validated both the second locus at rs16856785 (P = 7.63 x 10(-8, as well as the sex-interaction with rs16847548 (P = 8.68 x 10(-6. These data extend the association of genetic variants in NOS1AP with QT interval to a Black population, with similar trends, though not statistically significant at P<0.05, in Hispanics. In addition, we identify a strong sex-interaction and the presence of a second independent site within NOS1AP associated with the QT interval. These results highlight the consistent and complex role of NOS1AP genetic variants in modulating QT interval.

78 FR 2797 - Federal Motor Vehicle Safety Standards; Minimum Sound Requirements for Hybrid and Electric Vehicles

Science.gov (United States)

2013-01-14

... Sound Requirements for Hybrid and Electric Vehicles; Draft Environmental Assessment for Rulemaking To Establish Minimum Sound Requirements for Hybrid and Electric Vehicles; Proposed Rules #0;#0;Federal Register...-0148] RIN 2127-AK93 Federal Motor Vehicle Safety Standards; Minimum Sound Requirements for Hybrid and...

Nuclear AP4A-binding activity of sea urchin embryos changes in relation to the initiation of S phase

International Nuclear Information System (INIS)

Morioka, M.; Shimada, H.

1986-01-01

The AP 4 A-binding activity of sea urchin embryos was studied using radioactively labelled diadenosine 5', 5'''-P 1 ,P 4 -tetraphosphate (Ap 4 A). Among various subcellular components that can bind [ 3 H]AP 4 A, nuclei alone showed the highly specific Ap 4 A-binding activity which was not influenced by the presence of AP 4 A, AP 5 A and GP 4 G. The addition of an excess amount of ATP only slightly reduced the binding of [ 3 H]AP 4 A to the nuclei. It was found that AP 4 A binds to the residual proteinaceous structure of nuclei which was resistant to the extraction with 2 M NaCl. The nuclear AP 4 A-binding activity fluctuated cyclically during each cell cycle, with at transient increase at the beginning of S phase followed by an abrupt-decrease within 10 min. When the initiation of S phase was blocked, the increase in the AP 4 A-binding activity was also prevented. It seems that the binding of AP 4 A to the nuclear structural protein is involved in the initiation of S phase

Application case study of AP1000 automatic depressurization system (ADS) for reliability evaluation by GO-FLOW methodology

Energy Technology Data Exchange (ETDEWEB)

Hashim, Muhammad, E-mail: hashimsajid@yahoo.com; Hidekazu, Yoshikawa, E-mail: yosikawa@kib.biglobe.ne.jp; Takeshi, Matsuoka, E-mail: mats@cc.utsunomiya-u.ac.jp; Ming, Yang, E-mail: myang.heu@gmail.com

2014-10-15

Highlights: • Discussion on reasons why AP1000 equipped with ADS system comparatively to PWR. • Clarification of full and partial depressurization of reactor coolant system by ADS system. • Application case study of four stages ADS system for reliability evaluation in LBLOCA. • GO-FLOW tool is capable to evaluate dynamic reliability of passive safety systems. • Calculated ADS reliability result significantly increased dynamic reliability of PXS. - Abstract: AP1000 nuclear power plant (NPP) utilized passive means for the safety systems to ensure its safety in events of transient or severe accidents. One of the unique safety systems of AP1000 to be compared with conventional PWR is the “four stages Automatic Depressurization System (ADS)”, and ADS system originally works as an active safety system. In the present study, authors first discussed the reasons of why four stages ADS system is added in AP1000 plant to be compared with conventional PWR in the aspect of reliability. And then explained the full and partial depressurization of RCS system by four stages ADS in events of transient and loss of coolant accidents (LOCAs). Lastly, the application case study of four stages ADS system of AP1000 has been conducted in the aspect of reliability evaluation of ADS system under postulated conditions of full RCS depressurization during large break loss of a coolant accident (LBLOCA) in one of the RCS cold legs. In this case study, the reliability evaluation is made by GO-FLOW methodology to determinate the influence of ADS system in dynamic reliability of passive core cooling system (PXS) of AP1000, i.e. what will happen if ADS system fails or successfully actuate. The GO-FLOW is success-oriented reliability analysis tool and is capable to evaluating the systems reliability/unavailability alternatively to Fault Tree Analysis (FTA) and Event Tree Analysis (ETA) tools. Under these specific conditions of LBLOCA, the GO-FLOW calculated reliability results indicated

Trust Management in P2P systems using Standard TuLiP

NARCIS (Netherlands)

Czenko, M.R.; Doumen, J.M.; Etalle, Sandro

2008-01-01

In this paper we introduce Standard TuLiP - a new logic based Trust Management system. In Standard TuLiP, security decisions are based on security credentials, which can be issued by different entities and stored at different locations. Standard TuLiP directly supports the distributed credential

Trust management in P2P systems using standard TuLiP

NARCIS (Netherlands)

Czenko, M.; Doumen, J.M.; Etalle, S.; Karabulut, Y.; Mitchell, J.C.; Herrmann, P.; Jensen, C.D.

2008-01-01

In this paper we introduce Standard TuLiP - a new logic based Trust Management system. In Standard TuLiP, security decisions are based on security credentials, which can be issued by different entities and stored at different locations. Standard TuLiP directly supports the distributed credential

Trust Management in P2P Systems Using Standard TuLiP

NARCIS (Netherlands)

Czenko, M.R.; Doumen, J.M.; Etalle, Sandro

2008-01-01

In this paper we introduce Standard TuLiP - a new logic based Trust Management system. In Standard TuLiP, security decisions are based on security credentials, which can be issued by different entities and stored at different locations. Standard TuLiP directly supports the distributed credential

Tank characterization report for double-shell tank 241-AP-105

International Nuclear Information System (INIS)

DeLorenzo, D.S.; Simpson, B.C.

1994-01-01

Double-Shell Tank 241-AP-105 is a radioactive waste tank most recently sampled in March of 1993. Sampling and characterization of the waste in Tank 241-AP-105 contributes toward the fulfillment of Milestone M-44-05 of the Hanford Federal Facility Agreement and Consent Order (Ecology, EPA, and DOE, 1993). Characterization is also needed tot evaluate the waste's fitness for safe processing through an evaporator as part of an overall waste volume reduction program. Tank 241-AP-105, located in the 200 East Area AP Tank Farm, was constructed and went into service in 1986 as a dilute waste receiver tank; Tank 241AP-1 05 was considered as a candidate tank for the Grout Treatment Facility. With the cancellation of the Grout Program, the final disposal of the waste in will be as high- and low-level glass fractions. The tank has an operational capacity of 1,140,000 gallons, and currently contains 821,000 gallons of double-shell slurry feed. The waste is heterogeneous, although distinct layers do not exist. Waste has been removed periodically for processing and concentration through the 242-A Evaporator. The tank is not classified as a Watch List tank and is considered to be sound. There are no Unreviewed Safety Questions associated with Tank 241-AP-105 at this time. The waste in Tank 241-AP-105 exists as an aqueous solution of metallic salts and radionuclides, with limited amounts of organic complexants. The most prevalent soluble analytes include aluminum, potassium, sodium, hydroxide, carbonate, nitrate, and nitrite. The calculated pH is greater than the Resource Conservation and Recovery Act established limit of 12.5 for corrosivity. In addition, cadmium, chromium, and lead concentrations were found at levels greater than their regulatory thresholds. The major radionuclide constituent is 137 Cs, while the few organic complexants present include glycolate and oxalate. Approximately 60% of the waste by weight is water

Trust Management in P2P systems using Standard TuLiP

OpenAIRE

Czenko, M.R.; Doumen, J.M.; Etalle, Sandro

2008-01-01

In this paper we introduce Standard TuLiP - a new logic based Trust Management system. In Standard TuLiP, security decisions are based on security credentials, which can be issued by different entities and stored at different locations. Standard TuLiP directly supports the distributed credential storage by providing a sound and complete Lookup and Inference AlgoRithm (LIAR). In this paper we focus on (a) the language of Standard TuLiP and (b) on the practical considerations which arise when d...

Avaliação dos efeitos a curto prazo de programas de conscientização e de terapia com pravastatina em indivíduos de alto risco para doença cardiovascular provenientes de consultórios particulares The evaluation of short term effects of awareness programs and pravastatin therapy on subjects from private clinics at high risk for cardiovascular disease

Directory of Open Access Journals (Sweden)

Raul D. Santos

1997-10-01

Full Text Available OBJETIVO: Avaliar a eficácia de programas de conscientização (PC sobre o controle de fatores de risco (FR para doença cardiovascular (DCV. MÉTODOS: Pacientes hipercolesterolêmicos de alto risco para DCV foram divididos em 2 grupos durante 16 semanas. O grupo A (n=417, 54,3±10,0 anos, 55% homens recebeu orientação verbal e escrita sobre controle de FR, e o grupo B (n=180, 54,4±10,9 anos, 45% homens apenas orientação verbal. Todos os participantes receberam 10mg/dia de pravastatina por 12 semanas. Avaliaram-se o peso, pressão arterial, o colesterol total (CT e frações, triglicérides, índices I e II de Castelli (CT/HDL-C e LDL-C/HDL-C e escores de Framingham. RESULTADOS: No basal, A diferiu de B no HDL-C (40,0±11,0 vs 43,0±11,0mg/dl, p=0,013 e no índice I (8,2±3,0 vs 7,6±2,3, p=0,008. Após 16 semanas as variações % foram maiores em A do que B no CT (-28,0 vs -25,0, pPURPOSE: To evaluate short-term efficacy of awareness programs (AP in reducing coronary heart disease risk factors (CHDRF. METHODS: High risk hypercholesterolemic patients were divided in 2 groups during 16 weeks. Group A (n=417, 54.3±10.0 years, 55% males received verbal and written orientation on CHDRF control, and group B (n=180, 54.4±10.9 years, 45% males received only verbal orientation. All participants received pravastatin 10mg q.d. for 12 weeks. The evolution of body weight, arterial pressure, lipid profile, Castelli's I and II indexes (TC/HDL and LDL/HDL, and Framingham scores were evaluated. RESULTS: At baseline, A had a lower HDL-C (40.0±11.0 vs 43.0±11.0mg/dl, p=0.013 and a higher index I (8.2±3.0 vs 7.6±2.3, p=0.008 than B. After 16 weeks, A had greater change than B in TC (-28.0 vs -25.0, p<0.05, LDL-C (-29.0 vs -27.6, p<0.05, HDL-C levels (+13.7 vs +10.8, p<0.05 and in the Castelli's Index (-39.0 vs -33.0; p<0.05. In both groups pravastatin use potentialized the effects of diet on the lipid profile. CONCLUSION: The AP seemed to be more

Memoranda by A.P. Uspensky to the Council of Ministers of the Provisional Siberian government

Directory of Open Access Journals (Sweden)

Sukhanov Aleksandr

2015-06-01

Full Text Available This publication offers a previously unknown memoranda by representative of the diocesan assembly of deputies of the clergy and laity of the Tomsk diocese A. P. Uspensky, addressed to the Council of Ministers of the Provisional Siberian government in July 1918. A.P. Uspensky solicited for formation of the Ministry of confessions in the Provisional Siberian government. Memoranda are initiative documents to the Statute on the Chief Administration of religious denominations adopted by the Council of Ministers of the Russian government on December 27, 1918.

Optimization of Phenanthrene-degradation by Dietzia Cinnamea AP for Bioremediation Applications

Directory of Open Access Journals (Sweden)

Zahra Fathi

2016-07-01

Full Text Available Background: This study focused on isolation and identification of a Phenanthrene (Phe degrader bacterium and optimization of environmental conditions for Phe degradation. Materials and Methods: Enrichment technique was used for isolation and the most effective isolate; named AP was selected based on its Phe biodegradation abilities. The isolate was identified using morphological and biochemical tests as well as16S rDNA sequencing. The effects of various factors such as temperature, pH and C/N on bacterial growth and Phe degradation were investigated using protein assay (Bradford and Gas Chromatography (GC, respectively. Results: The selected isolate was identified as Dietzia cinnamea AP. It was able to degrade Phe at pH 6-10 (optimum at 8, temperatures of 25 -45 °C (optimum at 35 °C and NH4Cl concentrations of 0.5-2.5 gL-1 (optimum at 2 g L-1. By optimization of environmental parameters, within 10 days of fermentation, Phe degradation rate increased by more than 1.2 fold (from 60% to 73%. Conclusion: D. cinnamea AP was found to be an appropriate candidate for bioremediation applications. To the best of our knowledge, this is the first report of D. cinnamea species that can degrade Phe.

CGM ApS Årsberetning til DANAK

DEFF Research Database (Denmark)

De Chiffre, Leonardo

Denne årsberetning omfatter CGM ApS' akkrediterede virksomhed i kalenderåret 2003. Årsberetningen er udarbejdet til DANAK (Dansk Akkreditering, ErhvervsfremmeStyrelsen), som led i opfyldelsen af laboratoriets informationspligt i henhold til gældende regler.......Denne årsberetning omfatter CGM ApS' akkrediterede virksomhed i kalenderåret 2003. Årsberetningen er udarbejdet til DANAK (Dansk Akkreditering, ErhvervsfremmeStyrelsen), som led i opfyldelsen af laboratoriets informationspligt i henhold til gældende regler....

Protection of environment, health and safety using risk management

Energy Technology Data Exchange (ETDEWEB)

Abraham, G [Ghafari Associates, Inc. 17101 Michegan Avenue Dearborn, MI 48126-2736 (United States); Kummler, R H [Department of Chemical engineering Wayne Stae University Detroit, MI 48202 (United States); louvar, J [Research Services Basf Corporation Wyandotte, MI 48192 (United States)

1997-12-31

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA`s PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility`s need for compliance and review the regulations for risk management.

Protection of environment, health and safety using risk management

International Nuclear Information System (INIS)

Abraham, G.; Kummler, R.H.; louvar, J.

1996-01-01

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA's PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility's need for compliance and review the regulations for risk management

Renal involvement in the antiphospholipid syndrome (APS)-APS nephropathy.

Science.gov (United States)

Tektonidou, Maria G

2009-06-01

Although the kidney represents a major target organ in antiphospholipid syndrome (APS), renal involvement in APS was poorly recognized until recently. The most well-recognized renal manifestations of APS are the renal artery thrombosis/stenosis, renal infarction, hypertension, renal vein thrombosis, end-stage renal disease, increased allograft vascular thrombosis, some types of glomerular disease, and a small-vessel vaso-occlusive nephropathy, recently defined as APS nephropathy. APS nephropathy was first described in primary APS patients, characterized by acute thrombotic lesions in glomeruli and/or arterioles (thrombotic microangiopathy) and chronic vascular lesions such as fibrous intimal hyperplasia of arterioles and interlobular arteries, organized thrombi with or without recanalization, and fibrous arterial and arteriolar occlusions or focal cortical atrophy. APS nephropathy was also detected in further studies including patients with systemic lupus erythematosus (SLE)-related APS and SLE/non-APS patients with positive antiphospholipid antibodies, independently of lupus nephritis. The same histologic lesions, especially thrombotic mictroangiopathy, were also observed in patients with catastrophic APS. The most frequent clinical and laboratory characteristics of APS nephropathy in all the above groups of patients are hypertension (often severe), proteinuria (ranging from mild to nephrotic range), hematuria, and acute or chronic renal insufficiency.

Safety Signs Perception and Adoption with the ISO and ANSI Standards

Directory of Open Access Journals (Sweden)

Amir Hossein Davoudian Talab

2017-10-01

Full Text Available Background One way of controlling hazards in the work environment is a use of safety signs. Safety signs are among the safe information group; hence, if these signs are not understood properly it could cause an injury or even death. Objectives The aim of this study is surveying perception of safety signs and adoption with ISO and ANSI standards. Methods This cross-sectional study was conducted during 2013 to 2014 in the 3 provinces of Khuzestan, Fars, and Tehran. The study population included 370 non-monochromatic employees working in the industries. For collecting information, the standard questionnaire of the international organization for standard (ISO 9186-1 and demographic information was used. A total of 13 safety signs were utilized for determination of perception. Stratified - Random sampling method was used, then, the obtained data were utilized using SPSS-16 software and applying descriptive statistics. Results In this study, the overall rate of perception of safety signs was 78.4% with a standard deviation of 15.1%. The lowest percentage of perception was related to the sign “face shield must be worn” (53.5%. In the assessment of safety signs based on ANSI Z5353 and ISO 9186-1 standard, 62.5% and 69.2% of signs can be reached to limit of acceptable perception. Conclusions The perception patterns of safety signs are different. Assessing perception of signs show a moderate level of perception in accordance with ISO standard; however, to reach ANSI standard, implementation of intervention programs (Judgment test is suggested due to perceptual adaptation with target population and redesign of sign with low perception.

Prevalence and Risk Factors of Hypertension in Adults in an Urban Slum, Tirupati, A.P.

Directory of Open Access Journals (Sweden)

Reddy S

2005-01-01

Full Text Available Research question : What is the prevalence of hypertension and its risk factors among adults aged 20-60 years residing years residing in an urban slum area of Tirupati town, A.P.? Objective : To study the prevalence of hypertension and its risk factors as well as its extent of diagnosis and management among adults aged 20-60 years residing in an urban slum area of Tirupati. Study design : Cross sectional. Study setting : Channa Reddy Colony (Urban slum area in Tirupati town, A.P. Study subjects : 1000 adults in the age group of 20-60 years (Males-500; Females-500 residing in an urban slum area of Tirupati town, A.P. Study variables : Age, sex, occupation, family history of hypertension, history of cerebrovascular/cardiovascular events, diabetes mellitus, saturated fat intake, intake of excess salt, smoking, alcohol intake and regular physical exercise. Outcome Variables : Number of hypertensives and mean blood pressure level estimations. Statistical analysis : Proportions, Chi--square tests, ′F′ ratios, ′t′ tests, Odds ratios and 95% confidence intervals. Results : The overall prevalence of hypertension was found to be 8.6%. Out of the 86 hypertensives, 72 (83.7% were aware of their hypertension; all of those aware were under treatment; among the treated, only 30 (41.7% had satisfactory control of their hypertension. Higher prevalence of hypertension was found with history of cerbrovascular/cardiovascular events (50.0%, diabetes mellitus (33.3%, family history of hypertension (23.3%, smoking (22.4%, age more than 50 years (22.2%, alcohol intake (20.0%, lack of physical exercise (15.8%, B.M.I.>25 (14.9%, male sex (9.6, non-vegetarian diet (8.8% and saturated fat intake (8.8%. The mean systolic as well as diastolic blood pressures were found to be higher among men, higher age groups, and in business occupation of the respondents. Conclusions : Despite treatment, most of the hypertensives had not achieved satisfactory control of blood

Comparison of the Efficacy and Safety of Icotinib with Standard Second-line 
Chemotherapy in Previously Treated Advanced Non-small Cell Lung Cancer

Directory of Open Access Journals (Sweden)

Shuyang YAO

2015-06-01

Full Text Available Background and objective This study compared the efficacy and safety of icotinib with standard second-line chemotherapy (single-agent docetaxel or pemetrexed in previously treated advanced non-small cell lung cancer (NSCLC. Methods Thirty-two consecutive patients treated with icotinib and 33 consecutive patients treated with standard second-line chemotherapy in Xuanwu Hospital from January 2012 to July 2013 were enrolled in our retrospective research. The Response Evaluation Criteria in Solid Tumors were used to evaluate the tumor responses, and the progression-free survival (PFS was evaluated by Kaplan-Meier method. Results Icotinib was comparable with standard second-line chemotherapy for advanced NSCLC in terms of overall response rate (ORR (28.1% vs 18.2%, P=0.341, disease control rate (DFS(43.8% vs 45.5%, P=0.890, and PFS (4.3 months vs 3.8 months, P=0.506. In the icotinib group, the ORR of epidermal growth factor receptor (EGFR mutant was significantly higher than that of EGFR unknown or wild type (P=0.017. In multivariate analysis, age, gender, histology, and the optimum first-line treatment response were dependent prognostic factors based on the PFS of the icotinib group. The incidence of adverse events was significantly fewer in the icotinib group than in the chemotherapy group (P=0.001. Conclusion Compared with the standard second-line chemotherapy, icotinib is active in the treatment of advanced NSCLC patients, especially with EGFR unknown in the second line, with an acceptable adverse event profile.

Standards in reliability and safety engineering

International Nuclear Information System (INIS)

O'Connor, Patrick

1998-01-01

This article explains how the highest 'world class' levels of reliability and safety are achieved, by adherence to the basic principles of excellence in design, production, support and maintenance, by continuous improvement, and by understanding that excellence and improvement lead to reduced costs. These principles are contrasted with the methods that have been developed and standardised, particularly military standards for reliability, ISO9000, and safety case regulations. The article concludes that the formal, standardised approaches are misleading and counterproductive, and recommends that they be replaced by a philosophy based on the realities of human performance

ANALISIS KONDISI TERAS REAKTOR DAYA MAJU AP1000 PADA KECELAKAAN SMALL BREAK LOCA

Directory of Open Access Journals (Sweden)

Andi Sofrany Ekariansyah

2015-06-01

, mixture level, temperatur kelongsong, small break LOCA, RELAP5.   ABSTRACT ANALYSIS ON THE CORE CONDITION OF AP1000 ADVANCED POWER REACTOR DURING SMALL BREAK LOCA. Accident due to the loss of coolant from the reactor boundary is an anticipated design basis event in the design of power reactor adopting the Generation II up to IV technology. Small break LOCA leads to more significant impact on safety compared to the large break LOCA as shown in the Three-Mile Island (TMI. The focus of this paper is the small break LOCA analysis on the Generation III+ advanced power reactor of AP1000 by simulating three different initiating events, which are inadvertent opening of Automatic Depressurization System (ADS, double-ended break on one of Direct Vessel Injection (DVI pipe, and 10 inch diameter split break on one of cold leg pipe. Methodology used is by simulating the events on the AP1000 model developed using RELAP5/SCDAP/Mod3.4. The impact analyzed is the core condition during the small break LOCA consisting of the mixture level occurrence and the fuel cladding temperature transient. The results show that the mixture level for all small break LOCA events are above the active core height, which indicates no core uncovery event. The development of the mixture level affect the fuel cladding temperature transient, which shows a decreasingly trend after the break, and the effectifeness of core cooling. Those results are identical with the results of other code of NOTRUMP. The resulted core cooling is also due to the function of coolant injection from passive safety feature, which is unique in the AP1000 design. In overall, the result of analysis shows that the AP1000 model developed by the RELAP5 can be used for analysis of design basis accident considered in the AP1000 advanced power reactor. Keywords: analysis, mixture level, fuel cladding temperature, small break LOCA, RELAP5.

Initial performance assessment of the Westinghouse AP600 containment design and related safety issues

International Nuclear Information System (INIS)

Nicolette, V.F.; Washington, K.E.; Tills, J.L.

1991-01-01

This work summarizes the Westinghouse AP600 advanced reactor design assessment calculations performed to date with the CONTAIN code. Correlations for modeling the important heat transfer phenomena are discussed as well. A CONTAIN model of the AP600 was constructed for design basis accident (DBA) calculations. Insights gained from modeling of the smaller-scale Westinghouse Integral Test Facility were incorporated in the development of the AP600 model. The results of the DBA calculations are compared to the results of other researchers to serve as a point of reference for future severe accident calculations. The CONTAIN calculations are reviewed to examine several parameters/phenomena of interest. The results of the calculations are also used to identify limitations of the CONTAIN code regarding application to advanced reactor containment designs. The most recent heat transfer correlations available in the literature are assessed for use in the flow regimes and geometries applicable to the AP600. Use of one of these correlations in CONTAIN may allow for a more accurate assessment of the AP600

Values of Kp Indices, Ap Indices, Cp Indices, C9 Indices, Sunspot Number, and 10.7 cm Flux

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data file consists of Kp indices, Ap indices, Cp indices, C9 indices, sunspot number, and 10.7 cm flux. The most often requested parameter of this file are the...

The development of international safety standards on geological disposal

International Nuclear Information System (INIS)

McCartin, T.

2005-01-01

The IAEA is developing a set of safety requirements for geologic disposal to be used by both developers and regulators for planning, designing, operating, and closing a geologic disposal facility. Safety requirements would include quantitative criteria for assessing safety of geologic disposal facilities as well as requirements for development of the facility and the safety strategy including the safety case. Geologic disposal facilities are anticipated to be developed over a period of at least a few decades. Key decisions, e.g., on the disposal concept, siting, design, operational management and closure, are expected to be made in a series of steps. Decisions will be made based on the information available at each step and the confidence that may be placed in that information. A safety strategy is important for ensuring that at each step during the development of the disposal facility, an adequate understanding of the safety implications of the available options is developed such that the ultimate goal of providing an acceptable level of operational and post closure safety will be met. A safety case for a geologic disposal facility would present all the safety relevant aspects of the site, the facility design and the managerial and regulatory controls. The safety case and its supporting assessments illustrates the level of protection provided and shall give reasonable assurance that safety standards will be met. Overall, the safety case provides confidence in the feasibility of implementing the disposal system as designed, convincing estimates of the performance of the disposal system and a reasonable assurance that safety standards will be met. (author)

Safety for Your Child: 10 Years

Science.gov (United States)

... Stages Listen Español Text Size Email Print Share Safety for Your Child: 10 Years Page Content Article ... out if your child's friends carry guns. Sports Safety At this age your child may be playing ...

SPES-2, the full-height, full-pressure, test facility simulating the AP600 plant: Main results from the experimental campaign

International Nuclear Information System (INIS)

Medich, C.; Rigamonti, M.; Martinelli, R.; Tarantini, M.; Conway, L.

1995-01-01

The SPES-2 is a full height, full pressure experimental test facility reproducing the Westinghouse AP600 reactor with a scaling factor of 1/395. The experimental plant, designed and operated by SIET in Piacenza, consists of a full simulation of the AP600 primary core cooling system including all the passive and active safety systems. In 1992, Westinghouse, in cooperation with ENEL, ENEA, SIET and ANSALDO developed an experimental program to test the integrated behavior of the AP600 passive safety systems. The SPES-2 test matrix, concluded in November 1994, has examined the AP600 passive safety system response for a range of small break LOCAs at different locations on the primary system and on the passive system lines; single steam generator tube ruptures with both passive and active non-safety systems, and a main steam line break transient to demonstrate the capability of passive safety systems for rapid cooldown. Each of the tests has provided detailed experimental results for verification of the capability of the analysis methods to predict the integrated passive safety system behavior

Pharmacogenetics of efficacy and safety of HCV treatment in HCV-HIV coinfected patients: significant associations with IL28B and SOCS3 gene variants.

Directory of Open Access Journals (Sweden)

Francesc Vidal

Full Text Available This was a safety and efficacy pharmacogenetic study of a previously performed randomized trial which compared the effectiveness of treatment of hepatitis C virus infection with pegylated interferon alpha (pegIFNα 2a vs. 2b, both with ribavirin, for 48 weeks, in HCV-HIV coinfected patients.The study groups were made of 99 patients (efficacy pharmacogenetic substudy and of 114 patients (safety pharmacogenetic substudy. Polymorphisms in the following candidate genes IL28B, IL6, IL10, TNFα, IFNγ, CCL5, MxA, OAS1, SOCS3, CTLA4 and ITPA were assessed. Genotyping was carried out using Sequenom iPLEX-Gold, a single-base extension polymerase chain reaction. Efficacy end-points assessed were: rapid, early and sustained virological response (RVR, EVR and SVR, respectively. Safety end-points assessed were: anemia, neutropenia, thrombocytopenia, flu-like syndrome, gastrointestinal disturbances and depression. Chi square test, Student's T test, Mann-Whitney U test and logistic regression were used for statistic analyses.As efficacy is concerned, IL28B and CTLA4 gene polymorphisms were associated with RVR (p<0.05 for both comparisons. Nevertheless, only polymorphism in the IL28B gene was associated with SVR (p = 0.004. In the multivariate analysis, the only gene independently associated with SVR was IL28B (OR 2.61, 95%CI 1.2-5.6, p = 0.01. With respect to safety, there were no significant associations between flu-like syndrome or depression and the genetic variants studied. Gastrointestinal disturbances were associated with ITPA gene polymorphism (p = 0.04. Anemia was associated with OAS1 and CTLA4 gene polymorphisms (p = 0.049 and p = 0.045, respectively, neutropenia and thromobocytopenia were associated with SOCS3 gene polymorphism (p = 0.02 and p = 0.002, respectively. In the multivariate analysis, the associations of the SOCS3 gene polymorphism with neutropenia (OR 0.26, 95%CI 0.09-0.75, p = 0.01 and thrombocytopenia (OR

Connoted hazard and perceived importance of fluorescent, neon, and standard safety colors.

Science.gov (United States)

Zielinska, O A; Mayhorn, C B; Wogalter, M S

2017-11-01

The perceived hazard and rated importance of standard safety, fluorescent, and neon colors are investigated. Colors are used in warnings to enhance hazard communication. Red has consistently been rated as the highest in perceived hazard. Orange, yellow, and black are the next highest in connoted hazard; however, there is discrepancy in their ordering. Safety standards, such as ANSI Z535.1, also list colors to convey important information, but little research has examined the perceived importance of colors. In addition to standard safety colors, fluorescent colors are more commonly used in warnings. Understanding hazard and importance perceptions of standard safety and fluorescent colors is necessary to create effective warnings. Ninety participants rated and ranked a total of 33 colors on both perceived hazard and perceived importance. Rated highest were the safety red colors from the American National Standard Institute (ANSI), International Organization for Standardization (ISO), and Federal Highway Administration (FHWA) together with three fluorescent colors (orange, yellow, and yellow-green) from 3 M on both dimensions. Rankings were similar to ratings except that fluorescent orange was the highest on perceived hazard, while fluorescent orange and safety red from the ANSI were ranked as the highest in perceived importance. Fluorescent colors convey hazard and importance levels as high as the standard safety red colors. Implications for conveying hazard and importance in warnings through color are discussed. Copyright © 2017 Elsevier Ltd. All rights reserved.

Reactor neutron activation analysis for aluminium in the presence of phosphorus and silicon. Contributions of /sup 28/Al activities from /sup 31/P (n,. cap alpha. ) /sup 28/Al and /sup 28/Si (n,p) /sup 28/Al reactions

Energy Technology Data Exchange (ETDEWEB)

Mizumoto, Yoshihiko (Kinki Univ., Higashi-Osaka, Osaka (Japan). Faculty of Science and Technology); Iwata, Shiro; Sasajima, Kazuhisa; Yoshimasu, Fumio; Yase, Yoshiro

1984-01-01

Reactor neutron activation analysis for aluminium in samples containing phosphorus and silicon was studied. The experiments were performed by using pneumatic tube of the Kyoto University Reactor (KUR). At first, the ratios of the /sup 28/Al activity produced from /sup 27/Al(n, ..gamma..) /sup 28/Al reaction by thermal neutrons to that from /sup 31/P(n, ..cap alpha..)/sup 28/Al reaction by fast neutrons, and to that from /sup 28/Si(n, p)/sup 28/Al reaction were measured by ..gamma..-ray spectrometry. With a ratio of about 5 for the thermal to fast neutron flux of KUR, the ratio of the /sup 28/Al activity from aluminium to that from phosphorus was to be 812 +- 7, and to that from silicon 282 +- 3. Secondly, the contributions of /sup 28/Al activities from phosphorus and silicon and the determination limit of aluminium were calculated for various parameters, such as fast neutron flux, thermal to fast neutron flux ratio, amounts of phosphorus and silicon, etc. Thirdly, on the basis of these results, aluminium contents in spinal cords and brains of amyotrophic lateral sclerosis, Parkinsonism-dementia complex and control cases were determined.

Standards and the design of the advanced photon source control system

International Nuclear Information System (INIS)

McDowell, W.P.; Knott, M.J.; Lenkszus, F.R.

1992-01-01

The Advanced Photon Source (APS), now under construction at Argonne National Laboratory (ANL), is a 7 GeV positron storage ring dedicated to research facilities using synchrotron radiation. This ring, along with its injection accelerators is to be controlled and monitored with a single, flexible, and expandable control system. This paper will cover the present status of the APS control system as well as discuss the design decisions which led us to use industrial standards and collaborations with other laboratories whenever possible to develop a control system. It will explain the APS control system and illustrate how the use of standards has allowed APS to design a control system whose implementation addresses these issues. (J.P.N.)

Resposta da taxa metabólica de repouso após 16 semanas de treinamento com pesos em mulheres na pós-menopausa

Directory of Open Access Journals (Sweden)

Valéria Bonganha

2011-10-01

Full Text Available INTRODUÇÃO: As alterações corporais provenientes da menopausa como a diminuição da massa magra (MM, aumento e redistribuição da gordura corporal e diminuição do gasto energético de repouso, colaboram para o aumento nas dimensões corporais e subsequente aumento da massa corporal total. Nesse sentido, os benefícios reconhecidos do treinamento com pesos (TP não estão atrelados apenas ao aumento da força e hipertrofia muscular, mas também à composição corporal e, consequentemente, na taxa metabólica de repouso (RMR. OBJETIVO: Avaliar a resposta da RMR após 16 semanas de TP em mulheres na pós-menopausa. MÉTODOS: Participaram 28 voluntárias, subdivididas em dois grupos: treinamento (GT n = 17 e controle (GC n = 11. O programa de TP foi realizado em três sessões semanais, em dias alternados e com duração de aproximadamente 60 min/sessão, por 16 semanas. A intensidade da carga foi determinada por meio de zona alvo de repetições máximas (RM, com reajuste semanal de carga. O consumo de oxigênio (O2 e da produção de gás carbônico (CO2, por meio de calorimetria indireta de circuito aberto, foi utilizado para cálculo da RMR segundo equação de Weir (1949. ANÁLISE ESTATÍSTICA: Foi utilizado pacote estatístico Bioestat na versão 5.0, com nível de significância de p < 0,05. RESULTADOS: Houve aumento significante dos valores de MM e força muscular, somente no GT. Não foram encontradas diferenças significantes para os valores da RMR após a intervenção para ambos os grupos. CONCLUSÃO: O programa de TP de 16 semanas foi eficiente para promover alterações na composição corporal e força muscular de mulheres na pós-menopausa; entretanto, não houve alteração da RMR após a intervenção.

Analysis of an AP600 intermediate-size loss-of-coolant accident

Energy Technology Data Exchange (ETDEWEB)