History of Research Reactor Fuel Fabrication at Babcock and Wilcox

International Nuclear Information System (INIS)

Freim, J.B.

1983-01-01

1982 was a year of tremendous growth for Babcock and Wilcox and its Research Reactor Fuel Facility. The Division has progressed from essentially being a non-competitor to a position where we are growing in strength. This paper describes some of the general aspects of past history and where B and W is now

Multiloop Integral System Test (MIST): MIST Facility Functional Specification

International Nuclear Information System (INIS)

Habib, T.F.; Koksal, C.G.; Moskal, T.E.; Rush, G.C.; Gloudemans, J.R.

1991-04-01

The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock ampersand Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the Once Through Integral System (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST Functional Specification documents as-built design features, dimensions, instrumentation, and test approach. It also presents the scaling basis for the facility and serves to define the scope of work for the facility design and construction. 13 refs., 112 figs., 38 tabs

Radioactive waste shipments to Hanford retrievable storage from Babcock and Wilcox, Leechburg, Pennsylvania

International Nuclear Information System (INIS)

Duncan, D.R.

1994-01-01

This report characterizes, as far as possible, the solid radioactive wastes generated by Babcock and Wilcox's Park Township Plutonium Facility near Leechburg, Pennsylvania that were sent to retrievable storage at the Hanford Site. Solid waste as defined in this document is any containerized or self-contained material that has been declared waste. The objective is a description of characteristics of solid wastes that are or will be managed by the Restoration and Upgrades Program; gaseous or liquid effluents are discussed only at a summary level This characterization is of particular interest in the planning of transuranic (TRU) waste retrieval operations, including the Waste Receiving and Processing (WRAP) Facility, because Babcock and Wilcox generated greater than 2.5 percent of the total volume of TRU waste currently stored at the Hanford Site

Production of leu high density fuels at Babcock and Wilcox

International Nuclear Information System (INIS)

Freim, J.B.

1983-01-01

A large number of fuel elements of all types are produced for both international and domestic customers by Nuclear Fuel Division of Babcock and Wilcox. A brief history of the division, included previous and present research reactor fuel element fabrication experience is discussed. The manufacturing facilities are briefly described. The fabrication of LEU fuels and economic analysis of the production are included. (A.J.)

New usable technical specifications

International Nuclear Information System (INIS)

Webster, S.A.; Tomasi, L.T.; Bernier, R.A.

1989-01-01

After 2 yr of preparation, 1988 finally saw the nuclear industry writing operator-oriented technical specifications. This effort is a continuation of previous efforts to develop improved and usable standard technical specifications (STSs), and is being conducted by the four nuclear steam supply system vendor owners' groups under the auspices of the Nuclear Management Resources Council. Each participant is currently preparing a set of improved STSs based on a writer's guide that was developed through a combined industry effort. In May of 1987, a Human Factors Improvements to Technical Specifications (HFITS) task group was formed to prepare a writer's guide for improved, industrywide STSs. This task group was composed of two representatives from each owners' group, one with a human factors background and one with some operations background. Two documents were prepared in 6 months, a human factors report laying the groundwork for the considerations to go into technical specifications and a writer's guide for their preparation. This paper reports on the application of this writer's guide to the writing of improved STS

ATR Technical Specification Upgrade Program

International Nuclear Information System (INIS)

McCracken, R.T.; Durney, J.L.; Freund, G.A.

1990-01-01

The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Improvements to Technical Specifications surveillance requirements

International Nuclear Information System (INIS)

Lobel, R.; Tjader, T.R.

1992-12-01

In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power

Babcock & Wilcox technologies for power plant stack emissions control

Energy Technology Data Exchange (ETDEWEB)

Polster, M.; Nolan, P.S.; Batyko, R.J. [Babcock & Wilcox, Barberton, OH (United States)

1994-12-31

The current status of sulfur dioxide control in power plants is reviewed with particular emphasis on proven, commercial technologies. This paper begins with a detailed review of Babcock & Wilcox commercial wet flue gas desulfurization (FGD) systems. This is followed by a brief discussion of B&W dry FGD technologies, as well as recent full-scale and pilot-scale demonstration projects which focus on lower capital cost alternatives to conventional FGD systems. A comparison of the economics of several of these processes is also presented. Finally, technology selections resulting from recent acid rain legislation in various countries are reviewed.

Standard technical specifications combustion engineering plants

International Nuclear Information System (INIS)

1992-09-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

Transient response of Babcock and Wilcox-designed reactors

International Nuclear Information System (INIS)

1980-05-01

On February 26, 1980, the Crystal River Unit No. 3 Nuclear Generating Plant, designed by the Babcock and Wilcox Company (B and W), experienced an incident involving a malfunction in an instrumentation and control system power supply. Faced with the Crystal River Unit 3 incident and the apparently high frequency of such near similar types of transients in other B and W designed plants, a special Task Force was established within the Office of Nuclear Reactor Regulation to provide an assessment of the apparent sensitivity of the B and W designed plants to such transients and the consequences of malfunctions and failures of the integrated control system and non-nuclear instrumentation. This report provides an assessment of these issues

Technical specification improvement through safety margin considerations

International Nuclear Information System (INIS)

Howard, R.C.; Jansen, R.L.

1986-01-01

Westinghouse has developed an approach for utilizing safety analysis margin considerations to improve plant operability through technical specification revision. This approach relies on the identification and use of parameter interrelations and sensitivities to identify acceptable operating envelopes. This paper summarizes technical specification activities to date and presents the use of safety margin considerations as another viable method to obtain technical specification improvement

Review of technical specifications

International Nuclear Information System (INIS)

Bedrich, M.; Scholz, D.

1980-01-01

The present paper deals with position and function of technical specifications before and during the manufacturing of reactor components, their structure and reasons for specific regulations due to safety philosophy and explains the cooperation of supplier, manufacturer, utilities and supervisory organizations. (RW)

Trojan technical specification verification project

International Nuclear Information System (INIS)

Bates, L.; Rickenback, M.

1991-01-01

The Trojan Technical Specification Verification (TTSV) project at the Trojan plant of Portland General Electric Company was motivated by the recognition that many numbers in the Trojan technical specifications (TTS) potentially lacked the consideration of instrument- and/or process-related errors. The plant setpoints were known to consider such errors, but many of the values associated with the limiting conditions for operation (LCO) did not. In addition, the existing plant instrument error analyses were based on industry values that do not reflect the Trojan plant-specific experience. The purpose of this project is to ensure that the Trojan plant setpoint and LCO values include plant-specific instrument error

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

Opening remarks: regulatory initiatives toward improved technical specifications

International Nuclear Information System (INIS)

Edison, G.E.

1985-01-01

In order to deal with the numerous problems that have evolved over the years with nuclear power plant technical specifications, the Nuclear Regulatory Commission has undertaken some initiatives for improvement: 1) new operating licenses, 2) change to existing operating reactor technical specifications, 3) a broad-scoped reconsideration of the content of technical specifications, and 4) rule changes. It is believed that reliability and risk assessment techniques can be used in conjunction with manufacturer's recommendations and engineering judgment to better define the appropriate scope and depth for technical specification resulting in focusing attention on high risk-worth systems and avoidance of plant shutdown transients both intentionally and unintentionally through provisions of technical specifications

Risk-informed approach in US-APWR technical specifications

International Nuclear Information System (INIS)

Saji, Etsuro; Tanaka, Futoshi; Kuroiwa, Katsuya; Kawai, Katsunori

2009-01-01

The Risk-Managed Technical Specifications and the Surveillance Frequency Control Program have been adopted in the US-APWR Technical Specifications. These risk-informed approaches are unique among the technical specifications for the advanced light water reactor designs adopted by planned nuclear power stations in the United States. (author)

Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Preparation of radiological effluent technical specifications for nuclear power plants. a guidance manual for users of standard technical specifications

International Nuclear Information System (INIS)

Boegli, J.S.; Bellamy, R.R.; Britz, W.L.; Waterfield, R.L.

1978-10-01

The purpose of this manual is to describe methods found acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for the calculation of certain key values required in the preparation of proposed radiological effluent Technical Specifications using the Standard Technical Specifications for light-water-cooled nuclear power plants. This manual also provides guidance to applicants for operating licenses for nuclear power plants in the preparation of proposed radiological effluent Technical Specifications or in preparing requests for changes to existing radiological effluent Technical Specifications for operating licenses. The manual additionally describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems

Technical specifications for the Pajarito Site Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.; Paxton, H.C.

1980-12-01

This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

McMunn, et al. v. Babcock and Wilcox Power Generation Group, Inc., et al.: The long road to dismissal

International Nuclear Information System (INIS)

Berger, Marjorie

2016-01-01

McMunn, et al. v Babcock and Wilcox Power Generation Group, Inc., et al. was one of 17 related public liability actions filed between 2010 and 2015 by individuals living and/or working in the vicinity of two former fuel fabrication facilities who alleged that releases of radioactive materials from those facilities contaminated the air, soil, surface water and groundwater in the surrounding communities, causing them personal injury and property damage. The plaintiffs in all 17 cases claimed they had contracted various cancers and their property was contaminated with uranium. Plaintiffs brought their claims pursuant to the Price-Anderson Amendments Act (PAA) and the Atomic Energy Act of 1954, as amended (AEA), and also asserted related state law claims of negligence, negligence per se, strict liability, civil conspiracy, and wrongful death and survival. The defendants, Babcock and Wilcox Power Generation Group, Inc., B and W Technical Services, Inc. and Atlantic Richfield Company (ARCO), were unrelated companies who, at different times, owned and operated those facilities. The PAA, which became law on 2 September 1957, is a federal statute that governs claims for personal injury and property damage 'arising from the activities of NRC licensees and DOE contractors'. These claims are defined in the PAA as public liability actions. In order to prevail in a public liability action, plaintiffs must establish through expert evidence that the defendants released radiation into the environment in excess of the limits then permitted by federal regulations and that the plaintiffs were exposed to those releases. They must also establish that their respective exposures to radionuclides were capable of causing their illnesses and that the doses of radiation they received did in fact cause their illnesses

Procedures for evaluating technical specifications (PETS)

International Nuclear Information System (INIS)

Samanta, P.K.; Boccio, J.L.; Vesely, W.E.

1987-01-01

In this paper, aspects of technical specifications relating to Generic Issues B-56 and B-61 are discussed from a risk-standpoint. These primarily deal with the risk issues associated with (1) adaptive diesel test requirements/surveillance test intervals, and (2) the effectiveness of cumulative outage time requirements for controlling downtime risk. Risk and reliability approaches are presented which (1) allow risk-acceptable test intervals to be determined for any diesel and (2) show the potential risk-control capability of prescribed allowed cumulative outage times. This work was conducted through NRC's Procedures for Evaluating Technical Specifications (PETS) Program. The overall objective of this program is to develop and demonstrate methodologies that utilize risk insights and reliability techniques for evaluating the scope, detailed requirements, and safety impact of plant technical specifications

Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

International Nuclear Information System (INIS)

Kimura, C.Y.

1989-01-01

This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications

Risk management through dynamic technical specifications

International Nuclear Information System (INIS)

Klopp, George T.; Petersen, Thomas A.

2004-01-01

The wide deployment of plant specific probabilistic risk assessments for nuclear power plants has provided the means to effect a fresh risk management perspective and a fresh, risk based, regulatory outlook on nuclear power. There has been a great deal of conversation on risk based regulation within the U. S. nuclear power industry but, curiously, very little on effective risk management. This paper proposes a means to link the two subjects through the plant Technical Specifications. A revised concept for Technical Specifications is suggested which is based on deterministic analyses and probabilistic risk assessments for each plant. The revised Technical Specifications would consider, on a real-time basis, the exact state of the plant in terms of the status of key components and systems. It would depict current plant risk levels and compare those levels to the desired and limiting (alert/action) levels. It would advise the plant operator on the risk impact of proposed actions through a simple query system and illustrate the impact of such actions on plant status relative to designated risk values. The basis for the proposed approach lies in realistic deterministic plant analyses and probabilistic risk assessment (PRA) deployment tools being developed, in parallel, by a number of parties in the U.S. today. These PRAs are based primarily on the existing plant responses to Generic Letter 88-20, 'Individual Plant Examinations' (IPEs). Each of these tools allows the plant operator to input, on a real-time basis, the status of key equipment and systems. The tools then provide explicit illustrations of dependency effects; updated, 'real-time' risk status indications such as core damage frequency; and, in some cases, allow the operator to assess the risk impact of removing from service selected components for maintenance or testing. These systems generally operate on personal computers and provide nearly instantaneous responses to plant queries. Moving from these tools to

Technical specifications and performance of CANDU fuel

International Nuclear Information System (INIS)

Sejnoha, R.

1997-01-01

The relations between Technical Specifications and fuel performance are discussed in terms of design limits and margins. The excellent performance record of CANDU reactor fuel demonstrates that the fuel design defined in the Technical Specifications (and with it other components of the procurement cycle, such as fuel manufacturing), satisfy the requirements. New requirements, changing conditions of fuel application and accumulating experience make periodic updates of the Technical Specifications necessary. Under the CANDU Owners Group (COG) Working Party 9, a Work Package has been conducted to support the review of the Specifications and the documentation of the rationales for their requirements. So far, the review has been completed for 4 Specifications: 1 for Zircaloy tubing, and 3 for uranium dioxide powder. It is planned to complete the review of all 11 currently used specifications by 1999. The paper summarizes the results achieved to mid 1997. (author)

Technical specification optimization program - engineered safety features

International Nuclear Information System (INIS)

Andre, G.R.; Jansen, R.L.

1986-01-01

The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

Conversion of NEK standard technical specifications into improved technical specifications

International Nuclear Information System (INIS)

Glaser, B.

2003-01-01

Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are

Synergy of Technical Specification, functional specifications and scenarios in requirements specifications

NARCIS (Netherlands)

Miedema, J.; van der Voort, Mascha C.; Lutters, Diederick; van Houten, Frederikus J.A.M.; Krause, Frank-Lothar

2007-01-01

In the (mechanical) design process, the requirements specification is a formal registration of the conditions that are imposed on a new or altered product design, both preceding as well as during the corresponding product development cycle. For a long time, the use of technical specifications has

Palisades technical specification conversion from custom to new industry standard

International Nuclear Information System (INIS)

Foley, D.J.; Young, B.

1990-01-01

Consumers Power Company's (CPCo) Palisades plant is in the process of converting from custom technical specifications to the new industry standard, Restructured Standard Technical Specifications (RSTS). Custom technical specifications were the precursor to standard technical specifications, being issued to plants built prior to 1972. In May 1989, each of the four light water reactor owners' groups completed topical reports presenting their version of Restructured Standard Technical Specifications to the Nuclear Regulatory Commission (NRC). After approval of the owners' groups versions of the RSTs by the NRC, individual operating reactors will begin to make the conversion to the RSTS. Each owners' group has designated a lead plant, which will be the first of that vendor type to convert. All of the lead plants currently operate under standard technical specifications. The content of the RSTS was determined by comparing the standard technical specifications with selection criteria specified in the Commissions Interim Policy Statement

Guidelines for writing user friendly technical specifications

International Nuclear Information System (INIS)

Webster, S.A.; Braun, J.C.; Pearce, R.T.

1986-01-01

This study investigates some of the ergonomic considerations of writer's guides for the preparation of instructions. It is a precedent for the preparation of such a writer's guide for technical specifications for nuclear power plants. This writer's guide will be part of a revision to the industry's standard ANSI/ANS 58.4, Criteria for Technical Specifications for Nuclear Power Stations

Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

HFBR: Review of the technical specifications against the FSAR

International Nuclear Information System (INIS)

Rao, D.V.; Boss, S.B.; Claiborne, E.R.; Darby, J.L.; Clark, R.A.

1990-01-01

The purpose of this review is to determine the adequacy of the High Flux Beam Reactor (HFBR) Technical Specifications for 40 MW operation by comparison with the HFBR Final Safety Analysis Report, particularly the accident analyses chapter. Specifically, the Technical Specifications were compared against the Design Basis Accident (DBA) Analyses presented in the Addendum to the HFBR FSAR for 60 MW Operation. The 60 MW DBA analyses was used since it is more current and complete than the analyses presented in the original FSAR which is considered obsolete. A listing of the required systems and equipment was made for each of the accidents analyzed. Additionally, the Technical Specification instrument setpoints were compared to the DBA analyses parametric values. Also included in this review was a comparison of the Technical Specification Bases against the FSAR and the identification of any differences. The HFBR Operations Procedures Manual (OPM) was also reviewed for any inconsistencies between the FSAR or the Technical Specifications. Upon completion of this review it was determined that the Technical Specifications are well written and the items commented on should not delay the low power restart (40 MW). Additionally, the OPM is also well written and does not require further modification before restart

Babcock and Wilcox version of PDQ07: user's manual

International Nuclear Information System (INIS)

Hassan, H.H.; Wittkopf, W.A.; Mullan, W.H.

1977-01-01

The Babcock and Wilcox version of PDQ07 solves the neutron diffusion depletion problem in one, two, and three dimensions and in up to five lethargy groups. Adjoint and boundary value calculations may also be performed. Geometries available are rectangular, cylindrical, spherical, and hexagonal. Special capabilities of the code include thermal-hydraulic feedback with subcooled boiling effects, boron iteration, rod bank placement, automatic partial rod movement, and flux synthesis. Time-independent group diffusion equations are solved by Gaussian elimination in one dimension, single-line cyclic Chebyshev semi-iterative technique in two dimensions, and a modified block Gauss-Siedel in three dimensions. Diffusion coefficients, macroscopic data, and depletion use a modified HARMONY system. Thermal feedback effects use an iterative approach based on relative power density in the core. Flux synthesis uses two-dimensional trial functions to solve three-dimensional problems

Comparison of licensing activities for operating plants designed by Babcock and Wilcox

International Nuclear Information System (INIS)

Thoma, J.O.

1985-01-01

This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

Approval Procedure for Technical Specifications for Procurement by Quotation and Tender

International Nuclear Information System (INIS)

Shaharum Ramli; Izhar Abu Hussin; Ying, K.K.

2015-01-01

Technical specifications for procurement requires the approval of the Jawatankuasa Penyemak Spesifikasi Teknikal Tender/ Sebutharga Agensi Nuklear Malaysia. This paper provides guidance for those who have to prepare a technical specification. In addition, the technical specification online library is introduced to facilitate them to re-use old technical specifications for new procurements or to make those the bases for drafting new specifications. (author)

Technical specifications requirements: Automated reasoning applications

International Nuclear Information System (INIS)

Lidsky, L.M.; Dobrzeniecki, A.B.

1990-03-01

Several software systems were developed and tested to determine what advantages could be gained from explicitly translating complicated regulatory requirements into computerized relationships. The Technical Specifications for US nuclear power plants were chosen as the test-bed application domain, and two analysis systems were developed to monitor plant compliance with operational limits, and track and schedule equipment test and maintenance activities mandated by Technical Specifications. Choosing PROLOG as the computer language to represent these regulatory requirements resulted in a natural match between the semantic structure of the written specifications and the corollary coded rules. Additional research results affirmed the utility of declarative programming styles, explicit management of problem complexity, and attention to the robustness and flexibility of the overall software systems. 5 refs., 2 figs

Seismic risk analysis for the Babcock and Wilcox facility, Leechburg, Pennsylvania

International Nuclear Information System (INIS)

1977-01-01

The results of a detailed seismic risk analysis of the Babcock and Wilcox Plutonium Fuel Fabrication facility at Leechburg, Pennsylvania are presented. This report focuses on earthquakes; the other natural hazards, being addressed in separate reports, are severe weather (strong winds and tornados) and floods. The calculational method used is based on Cornell's work (1968); it has been previously applied to safety evaluations of major projects. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. The results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented, expressed as return period accelerations. The best estimate curve indicates that the Babcock and Wilcox facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The bounding curves roughly represent the one standard deviation confidence limits about the best estimate, reflecting the uncertainty in certain of the input. Detailed examination of the results show that the accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and that each of the source regions contributes almost equally to the cumulative risk at the site. If required for structural analysis, acceleration response spectra for the site can be constructed by scaling the mean response spectrum for alluvium in WASH 1255 by these peak accelerations

Feasibility assessment of a risk-based approach to technical specifications

International Nuclear Information System (INIS)

Atefi, B.; Gallagher, D.W.

1991-05-01

To assess the potential use of risk and reliability techniques for improving the effectiveness of the technical specifications to control plant operational risk, the Technical Specifications Branch of the Nuclear Regulatory Commission initiated an effort to identify and evaluate alternative risk-based approaches that could bring greater risk perspective to these requirements. In the first phase four alternative approaches were identified and their characteristics were analyzed. Among these, the risk-based approach to technical specifications is the most promising approach for controlling plant operational risk using technical specifications. The second phase of the study concentrated on detailed characteristics of the real time risk-based approach. It is concluded that a real time risk-based approach to technical specifications has the potential to improve both plant safety and availability. 33 figs., 5 figs., 6 tabs

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

Prototype for an automated technical specification information system

International Nuclear Information System (INIS)

Quinn, E.L.; Mills, R.H.; Groves, J.E.

1985-01-01

The Southern California Edison (SCE) Automated Technical Specification Information System (ATSIS) at the San Onofre nuclear generating station (SONGS) has been developed as a prototype for an on-line information management system. This system provides an appropriate level of update, inquiry, and report generation capabilities to help support plant operators at SONGS in their efforts to anticipate, identify, document, and track certain actions and activities associated with plant technical specifications and associated limiting conditions of operation (LCOs). Substantially increased emphasis is being placed on adherence to nuclear regulatory requirements and commitments contained on the operating licenses of nuclear power plants. Additionally, as each year passes, such requirements are becoming increasingly detailed and complex, making it more and more difficult to track and ensure total compliance with the many and varied requirements. To assist the operations department at SONGs in meeting their regulatory commitments, in January 1985 SCE commenced gathering together the leading technical expertise available in the industry to develop a computerized system to track all technical specification-related equipment for operability and impact on LCOs

Technical specifications: Tower Shielding Reactor II

International Nuclear Information System (INIS)

1979-02-01

The technical specifications define the key limitations that must be observed for safe operation of the Tower Shielding Reactor II (TSR-II) and an envelope of operation within which there is reasonable assurance that these limits cannot be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

Technical specifications: Health Physics Research Reactor

International Nuclear Information System (INIS)

1979-02-01

The technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

High Flux Isotope Reactor technical specifications

International Nuclear Information System (INIS)

1985-11-01

This report gives technical specifications for the High Flux Isotope Reactor (HFIR) on the following: safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

Operating experience feedback report: Technical specifications: Commercial power reactors

International Nuclear Information System (INIS)

O'Reilly, P.D.; Plumlee, G.L. III.

1989-03-01

This report documents a trends and patterns analysis of technical specification (TS)-related licensee event reports (LERs) conducted by the Nuclear Regulatory Commission's (NRC's) Office for Analysis and Evaluation of Operational Data (AEOD). The objectives of this analysis were (1) to identify and catalog technical specification-related LERs, (2) to categorize and evaluate the events reported in these a LERs, (3) to identify any issues arising from the evaluation which appear to have generic safety significance, or which relate to the on-going Technical Specification Improvement Program, and (4) to trend the results obtained from the analysis of the data obtained in (1) through (3). 9 refs., 9 figs., 22 tabs

Case studies: Risk-based analysis of technical specifications

International Nuclear Information System (INIS)

Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

1987-01-01

The SOCRATES computer program uses the results of a Probabilistic Risk Assessment (PRA) or a system level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at a plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns with no adverse impacts on risk. Three summaries of case study applications are included to demonstrate the types of results that can be achieved through risk-based evaluation of technical specifications. (orig.)

Risk-based technical specifications program: Site interview results

International Nuclear Information System (INIS)

Andre, G.R.; Baker, A.J.; Johnson, R.L.

1991-08-01

The Electric Power Research Institute and Pacific Gas and Electric Company are sponsoring a program directed at improving Technical Specifications using risk-based methods. The major objectives of the program are to develop risk-based approaches to improve Technical Specifications and to develop an Interactive Risk Advisor (IRA) prototype. The IRA is envisioned as an interactive system that is available to plant personnel to assist in controlling plant operation. Use of an IRA is viewed as a method to improve plant availability while maintaining or improving plant safety. In support of the program, interviews were conducted at several PWR and BWR plant sites, to elicit opinions and information concerning risk-based approaches to Technical Specifications and IRA requirements. This report presents the results of these interviews, including the functional requirements of an IRA. 2 refs., 6 figs., 2 tabs

Technical specifications for PWR secondary water chemistry

International Nuclear Information System (INIS)

Weeks, J.R.; van Rooyen, D.

1977-08-01

The bases for establishing Technical Specifications for PWR secondary water chemistry are reviewed. Whereas extremely stringent control of secondary water needs to be maintained to prevent denting in some units, sound bases for establishing limits that will prevent stress corrosion, wastage, and denting do not exist at the present time. This area is being examined very thoroughly by industry-sponsored research programs. Based on the evidence available to date, short term control limits are suggested; establishment of these or other limits as Technical Specifications is not recommended until the results of the research programs have been obtained and evaluated

Regulatory aspects of the use of PSA to evaluate technical specifications

International Nuclear Information System (INIS)

Rumpf, J.

1991-01-01

Based on experiences gained in PSA activities the regulatory body of the GDR initiated a programme to investigate the feasibility of using PSA for the evaluation of technical specifications. This programme is just under work. In addition, to improve PSA, the GDR takes part in a programme which is aimed at performing plant specific level 1, PSA as well as and which enables operating organizations to carry out PSA on their own. The most important of some preliminary general findings presented in this paper are: - Technical specifications form a well established envelope of operational conditions and procedures. A total re-evaluation is not considered necessary; Probabilistic evaluation of technical specifications should be an integrated part of PSA activities (at least level 1). Single assessment is not considered reasonable; Probabilistic evaluation of technical specifications has to be based on plant specific information and realistic accident sequence calculations; Up to now no quantitative probabilistic criteria for technical specifications have been established. (author)

Computer-aided System of Semantic Text Analysis of a Technical Specification

OpenAIRE

Zaboleeva-Zotova, Alla; Orlova, Yulia

2008-01-01

The given work is devoted to development of the computer-aided system of semantic text analysis of a technical specification. The purpose of this work is to increase efficiency of software engineering based on automation of semantic text analysis of a technical specification. In work it is offered and investigated the model of the analysis of the text of the technical project is submitted, the attribute grammar of a technical specification, intended for formalization of limited Ru...

Assessment of ISLOCA risk: Methodology and application to a Babcock and Wilcox nuclear power plant

International Nuclear Information System (INIS)

Galyean, W.J.; Gertman, D.I.

1992-04-01

This report presents information essential to understanding the risk associated with inter-system loss-of-coolant accidents (ISLOCAs). The methodology developed and presented in the report provides a state-of-the-art method for identifying and evaluating plant-specific hardware design, human performance issues, and accident consequence factors to relevant to the prediction of the ISLOCA risk. This ISLOCA methodology was developed and then applied to a Babcock and Wilcox (B ampersand W) nuclear power plants. The results from this application are described in detail. For this particular B ampersand W reference plant, the assessment indicated that the probability of a severe ISLOCA is approximately 2.2E-06/reactor-year. This document Volume 3 provides appendices A--H of the report. Topics are: Historical experience related to ISLOCA events; component failure rates; reference B ampersand W plant system descriptions; reference B ampersand W plant ISLOCA event trees; Human reliability analysis for the B ampersand W ISLOCA probabilistic risk assessment; thermal hydraulic calculations; bounding core uncovery time calculations; and system rupture probability

Assessment of the technical specifications for a flip-standard TRIGA core

International Nuclear Information System (INIS)

Feltz, D.E.; Randall, J.D.

1974-01-01

The Technical Specifications for the Texas A and M University mixed, FLIP-Standard TRIGA core were the first submitted and approved under the draft version of Standard ANS-15.1. According to one AEC official these were the best Technical Specifications ever issued to a Research Reactor. The Technical Specifications are evaluated after operating under them for over seven months. (author)

Assessment of the technical specifications for a flip-standard TRIGA core

Energy Technology Data Exchange (ETDEWEB)

Feltz, D E; Randall, J D [Texas A and M University (United States)

1974-07-01

The Technical Specifications for the Texas A and M University mixed, FLIP-Standard TRIGA core were the first submitted and approved under the draft version of Standard ANS-15.1. According to one AEC official these were the best Technical Specifications ever issued to a Research Reactor. The Technical Specifications are evaluated after operating under them for over seven months. (author)

Technical specifications: Health Physics Research Reactor

International Nuclear Information System (INIS)

1986-03-01

These technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded

Technical specifications for the Bulk Shielding Reactor

International Nuclear Information System (INIS)

1982-04-01

Technical specifications are presented concerning the safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

Methodology for risk-based analysis of technical specifications

International Nuclear Information System (INIS)

Vesely, W.E.; Gaertner, J.P.; Wagner, D.P.

1985-01-01

Part of the effort by EPRI to apply probabilistic risk assessment methods and results to the solution of utility problems involves the investigation of methods for risk-based analysis of technical specifications. The culmination of this investigation is the SOCRATES computer code developed by Battelle's Columbus Laboratories to assist in the evaluation of technical specifications of nuclear power plants. The program is designed to use information found in PRAs to re-evaluate risk for changes in component allowed outage times (AOTs) and surveillance test intervals (STIs). The SOCRATES program is a unique and important tool for technical specification evaluations. The detailed component unavailability model allows a detailed analysis of AOT and STI contributions to risk. Explicit equations allow fast and inexpensive calculations. Because the code is designed to accept ranges of parameters and to save results of calculations that do not change during the analysis, sensitivity studies are efficiently performed and results are clearly displayed

Uranium silicide activities at Babcock and Wilcox

International Nuclear Information System (INIS)

Noel, W.W.; Freim, J.B.

1983-01-01

Babcock and Wilcox, Naval Nuclear Fuel Division (NNFD) in conjunction with Argonne National Laboratory (ANL) is actively involved in the Reduced Enrichment Research Test Reactor (RERTR) Program to produce low enriched fuel elements for research reactors. B and W and ANL have undertaken a joint effort in which NNFD will fabricate two low enriched uranium (LEU), Oak Ridge Reactor (ORR) elements with uranium silicide fuel furnished by ANL. These elements are being fabricated for irradiation testing at Oak Ridge National Laboratory (ORNL). Concurrently with this program, NNFD is developing and implementing the uranium silicide and uranium aluminide fuel fabrication technology. NNFD is fabricating the uranium silicide ORR elements in a two-phase program, Development and Production. To summarize: 1. Full size fuel plates can be made with U 3 SiAl but the fabricator must prevent oxidation of the compact prior to hot roll bonding; 2. Providing the ANL U 3 Si x irradiation results are successful, NNFD plans to provide two ORR elements during February 1983; 3. NNFD is developing and implementing U 3 Si x and UAI x fuel fabrication technology to be operational in 1983; 4. NNFD can supply U 3 O 8 high enriched uranium (HEU) or low enriched uranium (LEU) research reactor elements; 5. NNFD is capable of providing high quality, cost competitive LEU or HEU research reactor elements to meet the needs of the customer

Development of technical specifications for research reactors

International Nuclear Information System (INIS)

Anon.

1983-01-01

This standard identifies and establishes the content of technical specifications for research reactors. Areas addressed are: definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features and administrative controls. Sufficient detail is incorporated so that applicable specifications can be derived or extracted

Feasibility assessment of a risk-based approach to technical specifications

International Nuclear Information System (INIS)

Atefi, B.; Gallagher, D.W.

1991-05-01

The first phase of the assessment concentrates on (1) identification of selected risk-based approaches for improving current technical specifications, (2) appraisal of characteristics of each approach, including advantages and disadvantages, and (3) recommendation of one or more approaches that might result in improving current technical specification requirements. The second phase of the work concentrates on assessment of the feasibility of implementation of a pilot program to study detailed characteristics of the preferred approach. The real time risk-based approach was identified as the preferred approach to technical specifications for controlling plant operational risk. There do not appear to be any technical or institutional obstacles to prevent initiation of a pilot program to assess the characteristics and effectiveness of such an approach. 2 tabs

Technical specification upgrading at the Fast Flux Test Facility (FFTF)

International Nuclear Information System (INIS)

Baird, Q.L.; Franz, G.R.; Absher, K.R.

1985-01-01

The FFTF Technical Specifications were generated in 1977 and 1978 following submittal of the FSAR in 1976. A phased implementation program served to prepare the specifications for each stage of the plant startup with the complete specifications approved and implemented late in 1980 for the first ascent to full power. In January, 1983 WHC undertook an upgrading effort to implement changes to the FFTF technical specifications. This program has been pursued with appropriate attention to the CFR and industry standards and practice. Examples of these changes, discussion of the methods and planned activities for the future will be presented. Technical data will be provided to support the impact of specific limits. The benefits of changes and the criteria for change will be elaborated

Remote inspection manipulators for AGR II: Babcock Power's interstitial manipulator

International Nuclear Information System (INIS)

Whyley, S.R.

1985-01-01

The interstitial manipulator has been designed and built by Babcock Power for the remote visual inspection of AGR II reactors at Heysham and Torness. Its five drives are operated from a console local to the manipulator on the pile cap, or from a similar console located remotely. The need to operate from an interstitial ISI standpipe has restricted the size of the components entering the reactor, and this has consequently provided the major design constraint. A detailed structural assessment of the manipulator was carried out to demonstrate the ability to operate with payloads in excess of the largest camera weight of 13.6 kg. The manipulator finite element model was also used to determine static deflections, and, as a consequence, has provided data from which the control system is able to predict accurately the camera's position. Other computer aided design techniques have enabled the step by step sequences of manipulator deployment, in the restricted space available, to be successfully demonstrated. (author)

Risk-based analysis methods applied to nuclear power plant technical specifications

International Nuclear Information System (INIS)

Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

1989-01-01

A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

Technical specifications for the Oak Ridge Critical Experiments Facility

International Nuclear Information System (INIS)

Stinnett, R.M.

1986-01-01

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

Technical specifications for the pool critical assembly

International Nuclear Information System (INIS)

1978-07-01

Technical specifications for the ORNL-PCA Reactor are presented concerning safety limits and limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls

A study on decision-making framework for developing risk-informed technical specifications

International Nuclear Information System (INIS)

Kim, Beom Seock

2002-02-01

The utility and the nuclear research institutes in Korea have conduct research for improving inefficient requirements in technical specifications using the results of probability risk assessments and information associated with risk. However, the guidance for reviewing the improved technical specifications has not been developed. Thus, the objective of this study is to develop a decision-making framework for investigating and reviewing the documents associated with the changes of technical specifications. This work has been done for helping the regulation agency to review the improved technical specifications as well as to make decisions whether the remedy is accepted or not. The contents of this study include: 1. Surveys on Technical Specification regulations in foreign countries as well as those in Korea 2. Surveys on the state- of- the- art methodology for Risk Informed Technical Specifications and their uses in Korea 3. Development of a decision-making framework in both the licensee and the regulation agency position 4. Development and applications of a decision-making framework using Influence Diagrams. The decision-making framework for RITS using Influence Diagrams are developed and applied to an example problem in this study. This work might contribute to developing the risk informed regulation guidance for improving the quality of the current technical specifications

PVUSA model technical specification for a turnkey photovoltaic power system

Energy Technology Data Exchange (ETDEWEB)

Dows, R.N.; Gough, E.J.

1995-11-01

One of the five objectives of PVUSA is to offer U.S. utilities hands-on experience in designing, procuring, and operating PV systems. The procurement process included the development of a detailed set of technical requirements for a PV system. PVUSA embodied its requirements in a technical specification used as an attachment to its contracts for four utility-scale PV systems in the 200 kW to 500 kW range. The technical specification has also been adapted and used by several utilities. The PVUSA Technical Specification has now been updated and is presented here as a Model Technical Specification (MTS) for utility use. The MTS text is also furnished on a computer disk in Microsoft Word 6.0 so that it may be conveniently adapted by each user. The text includes guidance in the form of comments and by the use of parentheses to indicate where technical information must be developed and inserted. Commercial terms and conditions will reflect the procurement practice of the buyer. The reader is referred to PG&E Report Number 95-3090000. 1, PVUSA Procurement, Acceptance and Rating Practices for Photovoltaic Power Plants (1995) for PVUSA experience and practice. The MTS is regarded by PVUSA as a use-proven document, but needs to be adapted with care and attention to detail.

TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

Energy Technology Data Exchange (ETDEWEB)

BERGLIN, E J

2003-06-23

This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

Computer Support of Semantic Text Analysis of a Technical Specification on Designing Software

OpenAIRE

Zaboleeva-Zotova, Alla; Orlova, Yulia

2009-01-01

The given work is devoted to development of the computer-aided system of semantic text analysis of a technical specification. The purpose of this work is to increase efficiency of software engineering based on automation of semantic text analysis of a technical specification. In work it is offered and investigated a technique of the text analysis of a technical specification is submitted, the expanded fuzzy attribute grammar of a technical specification, intended for formaliza...

Shutdown decay heat removal analysis of a Babcock and Wilcox pressurized water reactor: Case study

International Nuclear Information System (INIS)

Cramond, W.R.; Ericson, D.M. Jr.; Sanders, G.A.

1987-03-01

This is one of six case studies for USI A-45 Decay Heat Removal (DHR) Requirements. The purpose of this study is to identify any potential vulnerabilities in the DHR systems of a typical Babcock and Wilcox PWR, to suggest possible modifications to improve the DHR capability, and to assess the value and impact of the most promising alternatives to the existing DHR systems. The systems analysis considered small LOCAs and transient internal initiating events, and seismic, fire, extreme wind, internal and external flood, and lightning external events. A full-scale systems analysis was performed with detailed fault trees and event trees including support system dependencies. The system analysis results were extrapolated into release categories using applicable past PRA phenomenological results and improved containment failure mode probabilities. Public consequences were estimated using site specific CRAC2 calculations. The Value-Impact (VI) analysis of possible alternatives considered both onsite and offsite impacts arriving at several risk measures such as averted population dose out to a 50-mile radius and dollars per person rem averted. Uncertainties in the VI analysis are discussed and the issues of feed and bleed and secondary blowdown are analyzed

Technical specifications for mechanical recycling of agricultural plastic waste

International Nuclear Information System (INIS)

Briassoulis, D.; Hiskakis, M.; Babou, E.

2013-01-01

Highlights: • Technical specifications for agricultural plastic wastes (APWs) recycling proposed. • Specifications are the base for best economical and environmental APW valorisation. • Analysis of APW reveals inherent characteristics and constraints of APW streams. • Thorough survey on mechanical recycling processes and industry as it applies to APW. • Specifications for APW recycling tested, adjusted and verified through pilot trials. - Abstract: Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project “LabelAgriWaste” revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process (“Quality I”) and another one for plastic profile production process (“Quality II”). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities

Risk based technique for improving technical specifications

International Nuclear Information System (INIS)

Kim, I. S.; Jae, M. S.; Kim, B. S.; Hwang, S. W.; Kang, K. M.; Park, S. S.; Yu, Y. S.

2001-03-01

The objective of this study is to develop the systematic guidance for reviewing the documents associated with the changes of technical specifications. The work done in this fiscal year is the following : surveys in TS requirements, TS improvements and TS regulations in foreign countries as well as Korea, surveys on the state-of-the-art of RITSs and their use in Korea, development of a decision-making framework for both the licensee and the regulation agency, description of risk measures, assessment methodology on STI/AOT, and adverse effects caused by periodic maintenance, which are explained in appendix. The results of this study might contribute to enhancing the quality of the current technical specifications and contribute to preparing the risk informed regulation program using the decision-making framework developed in this study

USER SPECIFICATIONS FOR PRESSURE VESSELS AND TECHNICAL INTEGRITY

Directory of Open Access Journals (Sweden)

K.S. Johnston

2012-01-01

Full Text Available

ENGLISH ABSTRACT: Specifications translated from user requirements are prescribed in an attempt to capture and incorporate best practices with regards to the design, fabrication, testing, and operation of pressure vessels. The question as to whether these requirements affect the technical integrity of pressure vessels is often a subjective matter. This paper examines typical user requirement specifications against technical integrity of pressure vessels.
The paper draws on a survey of a convenience sample of practising engineers in a diversified petrochemical company. When compared with failures on selected pressure vessels recorded by Phillips and Warwick, the respondent feedback confirms the user specifications that have the highest impact on technical integrity.

AFRIKAANSE OPSOMMING: Gebruikersbehoeftes word saamgevat in spesifikasies wat lei tot goeie praktyk vir ontwerp, vervaarding, toetsing en bedryf van drukvate. Subjektiwiteit van die gebruikersbehoeftes mag soms die tegniese integriteit van ‘n drukvat beinvloed.
Die navorsing maak by wyse van monsterneming gebruik van die kennis van ingenieurs wat werk in ‘n gediversifiseerde petrochemiese bedryf. Die terugvoering bevestig dat bogenoemde spesifikasies inderdaad die grootste invloed het op tegniese integriteit.

Technical specifications for the Oak Ridge Research Reactor

International Nuclear Information System (INIS)

1982-03-01

Technical specifications are presented concerning safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

Summary description of the Babcock and Wilcox integrated nuclear design system

International Nuclear Information System (INIS)

Wittkopf, W.A.

1976-03-01

The Babcock and Wilcox integrated nuclear design system is divided into three broad areas: basic nuclear data processing, applications data processing, and nuclear design calculations. In basic nuclear data processing, basic nuclear data are collected, evaluated, and processed into a specified fine-energy mesh multigroup data file called a Master Library. In applications data processing, data for selected materials are retrieved from the Master Library and processed into an optimally structured, multigroup Production Library. Using these data and input descriptions of cells or regions, neutron spectra are generated and few-group constants are computed and fitted as a function of fuel burnup, initial enrichment, temperature, etc. In nuclear design calculations, few-group cross-section fits and descriptions of each core region and core geometry are input to a diffusion-depletion program or a nodal program that computes core reactivity, core power distribution, control rod worth, fuel cycle studies, core operating limitations, etc

Technical specifications for the bulk shielding reactor

International Nuclear Information System (INIS)

1986-05-01

This report provides information concerning the technical specifications for the Bulk Shielding Reactor. Areas covered include: safety limits and limiting safety settings; limiting conditions for operation; surveillance requirements; design features; administrative controls; and monitoring of airborne effluents. 10 refs

A nuclear power unit with a Babcock type steam generating system-analysis of the break-down in the Three Mile Island power plant

International Nuclear Information System (INIS)

Werner, A.

1980-01-01

Installations of the primary and the secondary circuits and basic automatic control and protection systems for a nuclear power unit with Babcock type vertical, once-through steam generator are described. On this background the course of the break-down in the Three Mile Island power plant at Harrisburg is presented and analysed. (author)

Standardized Technical Specifications for Westinghouse PWRs

International Nuclear Information System (INIS)

1978-01-01

This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants (1) with either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. The format of the STS addresses the categories required by 10 CFR 50 and consists of six sections covering the areas of: Definitions, Safety Limits and Limiting Safety System Settings, Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls

Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

The use of PROLOG for computerized Technical Specifications

International Nuclear Information System (INIS)

Lidsky, L.M.; Lanning, D.D.; Dobrzeniecki, A.B.; Meyers, K.; Reese, T.G.

1987-01-01

The task of deciding whether a particular nuclear plant condition is in compliance with its Technical Specifications is, in principle, algorithmic. However, the implicit algorithm is so complex and the required level of confidence in code validity is so high that traditional methods of computerized analysis have proven unsatisfactory. PROLOG provides a close match to the explicit semantic structure of the written specifications, a good tool for analysis of the implicit subsystem operability trees and, by virtue of its declarative style and imbedded logical structure, greatly simplifies the problem of code validation. LCOM, a PROLOG representation of a subset of BWR Technical Specifications, was developed to explore the applicability of PROLOG in this problem domain and to provide benchmark data for full-scale implementations. The declarative style and built-in unification mechanism of PROLOG does substantially simplify the process of program construction and validation. Extrapolations indicate processing times for a complete Tech Spec implementation of ≤ 1 minute in systems capable of ≥ 20 KLIPS

Technical specifications for mechanical recycling of agricultural plastic waste.

Science.gov (United States)

Briassoulis, D; Hiskakis, M; Babou, E

2013-06-01

Technical specifications appropriate for the recycling of agricultural plastic wastes (APWs), widely accepted by the recycling industry were developed. The specifications establish quality standards to be met by the agricultural plastics producers, users and the agricultural plastic waste management chain. They constitute the base for the best economical and environmental valorisation of the APW. The analysis of the APW streams conducted across Europe in the framework of the European project "LabelAgriWaste" revealed the inherent characteristics of the APW streams and the inherent constraints (technical or economical) of the APW. The APW stream properties related to its recycling potential and measured during pilot trials are presented and a subsequent universally accepted simplified and expanded list of APW recycling technical specifications is proposed and justified. The list includes two sets of specifications, applied to two different quality categories of recyclable APW: one for pellet production process ("Quality I") and another one for plastic profile production process ("Quality II"). Parameters that are taken into consideration in the specifications include the APW physical characteristics, contamination, composition and degradation. The proposed specifications are focused on polyethylene based APW that represents the vast majority of the APW stream. However, the specifications can be adjusted to cover also APW of different materials (e.g. PP or PVC) that are found in very small quantities in protected cultivations in Europe. The adoption of the proposed specifications could transform this waste stream into a labelled commodity traded freely in the market and will constitute the base for the best economical and environmental valorisation of the APW. Copyright © 2013 Elsevier Ltd. All rights reserved.

A THREE-DIMENSIONAL BABCOCK-LEIGHTON SOLAR DYNAMO MODEL

International Nuclear Information System (INIS)

Miesch, Mark S.; Dikpati, Mausumi

2014-01-01

We present a three-dimensional (3D) kinematic solar dynamo model in which poloidal field is generated by the emergence and dispersal of tilted sunspot pairs (more generally bipolar magnetic regions, or BMRs). The axisymmetric component of this model functions similarly to previous 2.5 dimensional (2.5D, axisymmetric) Babcock-Leighton (BL) dynamo models that employ a double-ring prescription for poloidal field generation but we generalize this prescription into a 3D flux emergence algorithm that places BMRs on the surface in response to the dynamo-generated toroidal field. In this way, the model can be regarded as a unification of BL dynamo models (2.5D in radius/latitude) and surface flux transport models (2.5D in latitude/longitude) into a more self-consistent framework that builds on the successes of each while capturing the full 3D structure of the evolving magnetic field. The model reproduces some basic features of the solar cycle including an 11 yr periodicity, equatorward migration of toroidal flux in the deep convection zone, and poleward propagation of poloidal flux at the surface. The poleward-propagating surface flux originates as trailing flux in BMRs, migrates poleward in multiple non-axisymmetric streams (made axisymmetric by differential rotation and turbulent diffusion), and eventually reverses the polar field, thus sustaining the dynamo. In this Letter we briefly describe the model, initial results, and future plans

The water treatment in the dual-purpose nuclear plants of Babcock and Wilcox with straight pipes

International Nuclear Information System (INIS)

Martynova, O.I.

1978-01-01

A report is given on water processing and water chemistry in the dual-purpose nuclear power plants (as compared to the single-purpose nuclear power plants) of Babcock and Wilcox, with flow steam generators with straight pipes. The most important materials, especially regarding their corrosion resistance, and the water composition during 'hot' start-up of the Okonie-I power plant, the quality factors of the feedwater, the water quality factors of the steam generator with fast start-up and the experience with numerous corrosion-caused defects in steam generator pipes are dealt with from the aspect of optimum water processing and successful continuous operation. (HK) [de

Technical Specification action statements requiring shutdown

International Nuclear Information System (INIS)

Mankamo, T.; Kim, I.S.; Samanta, P.K.

1993-11-01

When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements

Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

Study of the technical specifications for the diesels generator of Juragua NPP

International Nuclear Information System (INIS)

Vilaragut Llanes, J.J.

1996-01-01

The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analysis and engineering judgement. The Probabilistic safety Assessment, constitutes a tool to analyze of the risk effect in the Technical Specifications Rules, and makes possible a relative comparison of the rules from the risk point of view. This paper studies the technical specifications for the diesels generators of Juragua Nuclear Power Plant and for that was used the probabilistic methodology . It is presented the evaluation of the some parameters as surveillance testing, test interval, repairs time, diesel degradation and AOT

Audit of Wolf Creek Generating Station, Unit 1 technical specifications. Final technical evaluation report

International Nuclear Information System (INIS)

Stromberg, H.M.

1985-07-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Wolf Creek Generating Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, the requirements of the Safety Evaluation Report (SER) as supplemented, and the Comments and Responses to the Wolf Creek Technical Specification Draft Inspection Report. A comparative audit of the FSAR as amended, the SER as supplemented, and the Draft Inspection Report was performed with the Wolf Creek T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Wolf Creek Generating Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR, SER, and Draft Inspection Report

Utilization of a technical review group during a BWR owners group technical specification improvement study

International Nuclear Information System (INIS)

Hansell, H.F.; Moyer, D.P.

1986-01-01

A BWR Owners' Group Technical Specification Improvement (TSI) Committee was formed in late 1983. A primary goal of this Committee was to encourage the development of a probabilistic methodology for technical specification improvements which could be readily applied by utilities. The TSI Committee elected to hire a Contractor to develop and demonstrate a method. After the Contractor was selected and has started work, the committee decided to establish a Technical Review Group (TRG) to efficiently and effectively review the Contractor's analyses. The TRG met frequently with the Contractor as the analyses were being performed. These meetings were held at the Contractor's facility in order to allow direct contact between reviewers and individuals performing the work. The TRG was also involved with all major interactions with the NRC. The significance and merit of using a peer review group in this manner is the theme of this paper. In order to present a discussion of the significance and merit of the TRG, the activities are described. The summary of the analytical approach is provided to more full understand the TRG activities

Modeling operator actions during a small break loss-of-coolant accident in a Babcock and Wilcox nuclear power plant

International Nuclear Information System (INIS)

Ghan, L.S.; Ortiz, M.G.

1991-01-01

A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B ampersand W) nuclear power plant was modeled using RELAP5/MOD3. This work was performed as part of the United States Regulatory Commission's (USNRC) Code, Scaling, Applicability and Uncertainty (CSAU) study. The break was initiated by severing one high pressure injection (HPI) line at the cold leg. Thus, the small break was further aggravated by reduced HPI flow. Comparisons between scoping runs with minimal operator action, and full operator action, clearly showed that the operator plays a key role in recovering the plant. Operator actions were modeled based on the emergency operating procedures (EOPs) and the Technical Bases Document for the EOPs. The sequence of operator actions modeled here is only one of several possibilities. Different sequences of operator actions are possible for a given accident because of the subjective decisions the operator must make when determining the status of the plant, hence, which branch of the EOP to follow. To assess the credibility of the modeled operator actions, these actions and results of the simulated accident scenario were presented to operator examiners who are familiar with B ampersand W nuclear power plants. They agreed that, in general, the modeled operator actions conform to the requirements set forth in the EOPs and are therefore plausible. This paper presents the method for modeling the operator actions and discusses the simulated accident scenario from the viewpoint of operator actions

Comparison of methods applicable to evaluation of nuclear power plant technical specifications

International Nuclear Information System (INIS)

Cho, N.Z.; Bozoki, G.E.; Youngblood, R.W.

1986-01-01

This study compares three probabilistic methods based on the static fault tree analysis, time-dependent unavailability analysis, and Markov analysis, which can be used to evaluate technical specifications in nuclear power plants. They are tested on a sample problem which was devised to closely represent the important and essential characteristics that should be addressed in determination and evaluation of the technical specifications

Analysis of Technical Specifications of the Egyptian and French Electronic Storybooks (e-Storybook)

Science.gov (United States)

Atta, Mohammed Mahmoud; Abd El Wahab, Shaimaa Mahmoud

2015-01-01

This research aims at analysing technical specifications in a sample of Egyptian and French electronic storybooks (e-storybooks), to identify similarities and differences in technical specifications of children's e-storybooks and create a verified analysis list to be used for evaluation of e-storybooks. For this purpose, 32 e-storybooks in CD…

Use of probabilistic methods for the improvement of technical specifications

International Nuclear Information System (INIS)

Gros, G.; Mattei, J.M.

1987-11-01

The technical specifications set the requirements related to the availability of equipment. In order to limit the risk when an unavailability is noticed during power operation, an allowed outage time is determined based on a fixed limit imposed on the increase of calculated core melt probability when the equipment is considered as unavailable. An example related to the main electric equipment is presented. In case of cold shutdown condition, the operations carried out lead to numerous programmed unavailabilities of equipment. For the examination of a project of technical specifications defining the necessary equipment in the diffrent phases encountered, evaluation of the increase of the core melt probability due to the unavaibilities has been made

Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Savannah River Site production reactor technical specifications. K Production Reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

Risk-based technical specifications: Development and application of an approach to the generation of a plant specific real-time risk model

International Nuclear Information System (INIS)

Puglia, B.; Gallagher, D.; Amico, P.; Atefi, B.

1992-10-01

This report describes a process developed to convert an existing PRA into a model amenable to real time, risk-based technical specification calculations. In earlier studies (culminating in NUREG/CR-5742), several risk-based approaches to technical specification were evaluated. A real-time approach using a plant specific PRA capable of modeling plant configurations as they change was identified as the most comprehensive approach to control plant risk. A master fault tree logic model representative of-all of the core damage sequences was developed. Portions of the system fault trees were modularized and supercomponents comprised of component failures with similar effects were developed to reduce the size of the model and, quantification times. Modifications to the master fault tree logic were made to properly model the effect of maintenance and recovery actions. Fault trees representing several actuation systems not modeled in detail in the existing PRA were added to the master fault tree logic. This process was applied to the Surry NUREG-1150 Level 1 PRA. The master logic mode was confirmed. The model was then used to evaluate frequency associated with several plant configurations using the IRRAS code. For all cases analyzed computational time was less than three minutes. This document Volume 2, contains appendices A, B, and C. These provide, respectively: Surry Technical Specifications Model Database, Surry Technical Specifications Model, and a list of supercomponents used in the Surry Technical Specifications Model

Effect of flow leakage on the benchmarking of FLOWTRAN with Mark-22 mockup flow excursion test data from Babcock and Wilcox

International Nuclear Information System (INIS)

Chen, Kuo-Fu.

1992-10-01

This report presents a revised analysis of the Babcock and Wilcox (B and W) downflow flow excursion tests that accounts for leakage between flow channels in the test assembly. Leak rates were estimated by comparing results from the downflow tests with those for upflow tests conducted using an identical assembly with some minor modifications. The upflow test assembly did not contain leaks. This revised analyses shows that FLOWTRAN with the SRS working criterion conservatively predicts onset of flow instability without using a local peaking factor to model heat transfer variations near the ribs

Comparison of implementation of selected TMI action plan requirements on operating plants designed by Babcock and Wilcox

International Nuclear Information System (INIS)

Thoma, J.O.

1984-05-01

This report provides the results of a study conducted by the US Nuclear Regulatory Commission staff to compare the degree to which eight Babcock and Wilcox (B and W) designed licensed nuclear power plants have complied with the requirements in NUREG-0737, Clarification of TMI Action Plan Requirements. The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1). The purpose of this audit was to establish the progress of the TMI-1 licensee, General Public Utilities (GPU) Nuclear Corporation, in completing the long-term requirements in NUREG-0737 relative to the other B and W licensees examined

Probabilistic analysis of 900 MWe PWR. Shutdown technical specifications

International Nuclear Information System (INIS)

Mattei, J.M.; Bars, G.

1987-11-01

During annual shutdown, preventive maintenance and modifications which are made on PWRs cause scheduled unavailabilities of equipment or systems which might harm the safety of the installation, in spite of the low level of decay heat during this period. The pumps in the auxiliary feedwater system, component cooling water system, service water system, the water injection arrays (LPIS, HPIS, CVCS), and the containment spray system may have scheduled unavailability, as well as the power supply of the electricity boards. The EDF utility is aware of the risks related to these situations for which accident procedures have been set up and hence has proposed limiting downtime for this equipment during the shutdown period, through technical specifications. The project defines the equipment required to ensure the functions important for safety during the various shutdown phases (criticality, water inventory, evacuation of decay heat, containment). In order to be able to judge the acceptability of these specifications, the IPSN, the technical support of the Service Central de Surete des Installations Nucleaires, has used probabilistic methodology to analyse the impact on the core melt probability of these specifications, for a French 900 MWe PWR

Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes

Technical and quality assurance specifications for dosimetry services

International Nuclear Information System (INIS)

1989-01-01

The Canadian Atomic Energy Control Board (AECB) requires its licensees to establish a program to determine or estimate the radiation doses received by workers exposed to radiation as a result of the licensee's activities. The determination of radiation dose is a two-part process. First a measurement is made; then this measurement is used in a dosimetric model to calculate the dose. This document is concerned only with the first step of the process. It gives guidance on the technical specifications for dosimetry services and the quality assurance program that provides confidence that these specifications are achieved. (L.L.)

Standard technical specifications for Westinghouse pressurized water reactors

International Nuclear Information System (INIS)

Wagner, P.C.

1979-07-01

This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse plants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants with (1) either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of the STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

Technical evaluation report on the proposed amendment to the technical specifications on the reactor protection system and the engineered safety features actuation system for Ft. Calhoun, Unit No. 1

International Nuclear Information System (INIS)

Selan, J.C.

1982-01-01

This report documents the technical evaluation of the application to amend the Technical Specifications for the Ft. Calhoun Unit No. 1 Nuclear Generating Plant. The review criteria are based on the Technical Specifications of St. Lucie and Calvert Cliffs, IEEE Standards, Combustion Engineering Standard Technical Specifications, and the Code of Federal Regulations. The evaluation compares the submittal made by the licensee with the NRC staff position and the review criteria and presents the reviewer's conclusion on the acceptability of the application to amend the Technical Specifications

Optimisation of technical specifications using probabilistic methods

International Nuclear Information System (INIS)

Ericsson, G.; Knochenhauer, M.; Hultqvist, G.

1986-01-01

During the last few years the development of methods for modifying and optimising nuclear power plant Technical Specifications (TS) for plant operations has received increased attention. Probalistic methods in general, and the plant and system models of probabilistic safety assessment (PSA) in particular, seem to provide the most forceful tools for optimisation. This paper first gives some general comments on optimisation, identifying important parameters and then gives a description of recent Swedish experiences from the use of nuclear power plant PSA models and results for TS optimisation

The impact of technical specification surveillance requirements and allowable outage times on plant availability

International Nuclear Information System (INIS)

Webster, S.A.; Finnicum, D.J.

1985-01-01

Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

Standard technical specifications for combustion engineering pressurized water reactors

International Nuclear Information System (INIS)

1979-08-01

This Standard Technical Specification (STS) has been structured for the broadest possible use on Combustion Engineering plants currently being reviewed for an Operating License. Two separate and discrete containment specification sections are provided for each of the following containment types: Atmospheric and Dual. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. Alternate specifications are provided in a limited number of cases to cover situations where alternate specification requirements are necessary on a generic basis because of design differences. This revision of STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

77 FR 45282 - NRC Position on the Relationship Between General Design Criteria and Technical Specification...

Science.gov (United States)

2012-07-31

... Position on the Relationship Between General Design Criteria and Technical Specification Operability AGENCY... relationship between the general design criteria (GDC) for nuclear power plants and technical specification... Communications Branch, Division of Policy and Rulemaking, Office Nuclear Reactor Regulation, Mail Stop: OWFN-12-D...

Standard technical specifications for General Electric boiling water reactors

International Nuclear Information System (INIS)

1979-08-01

This Standard Technical Specification (STS) has been structured for the broadest possible use on General Electric plants currently being reviewed for an Operating License. Optional specifications are provided for those features and systems which may be included in individual plant designs but are not generic in their scope of application. This revision of the GE-STS does not typically include requirements which may be added or revised as a result of the NRC staff's further review of the Three Mile Island incident

Technical specifications for the successful fabrication of laminated seismic isolation bearings

Energy Technology Data Exchange (ETDEWEB)

Kulak, R F [Argonne National Laboratory, Argonne, IL (United States)

1992-07-01

High damping steel-laminated elastomeric seismic isolation bearings are becoming a preferred device for isolating large buildings and structures. In the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearings are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring thatthe bearings meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper. (author)

Technical specification improvements to containment heat removal and emergency core cooling systems: Final report

International Nuclear Information System (INIS)

Sullivan, W.P.; Ha, C.; Pentzien, D.C.; Visweswaran, S.

1988-07-01

This report presents the results of an analysis for technical specification improvements to the emergency core cooling systems (ECCS) and containment heat removal systems (EPRI Research Project 2142-3). The objective of this project is to further develop a reliability- and risk-based methodology to provide improvements by considering groups of surveillance test intervals and allowed out-of-service times jointly. This was done for the technical specifications for the ECCS, containment heat removal equipment, and supporting systems of a boiling water reactor plant. The project (1) developed a methodology for optimizing groups of surveillance test intervals and allowed out-of-service times jointly, (2) applied the methodology in a case study of a specific operating plant, Hatch-2, and (3) evaluated benefits of the application. The results of the case study demonstrate that beneficial technical specification improvements can be realized with application of the methodology. By tightening a small group of sensitive surveillance test intervals (STIs) and allowed out-of-service times (AOTs), a larger group of less sensitive STIs and AOTs can be extended resulting in an overall plant operating cost improvement without reducing the plant safety. The reliability- and risk-based methodology and results from this project can be effectively applied for technical specification improvements at other operating plants

Technical specification for transferring tank construction data to the Oak Ridge Environmental Information System (OREIS)

International Nuclear Information System (INIS)

1996-06-01

The primary goal of this technical specification is to meet the consolidated environmental data requirements defined by the Federal Facility Agreement (FFA) and the Tennessee Oversight Agreement as they pertain to tank construction data maintained in Oak Ridge, Tennessee, by the US Department of Energy's Maintenance and Operations contractor Lockheed Martin Energy Systems, Inc., and prime contractors to the Department of Energy. This technical specification describes the organizational responsibilities for loading tank construction data into OREIS, describes the logical and physical data transfer files, addresses business rules and submission rules, addresses configuration control of this technical specification, and addresses required changes to the current OREIS data base structure based on site requirements. This technical specification addresses the tank construction data maintained by the Y-12, K-25, and ORNL sites that will be sent to OREIS. The initial submission of data will include only inactive Environmental Restoration tanks as specified by the FFA

Technical specifications for the successful fabrication of laminated seismic isolation bearings

International Nuclear Information System (INIS)

Kulak, R.F.

1992-01-01

High damping laminated elastomeric bearings are becoming one of the preferred devices for isolating large buildings and structures. IN the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearing are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings that are installed under nuclear structures meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper

Technical specifications for the successful fabrication of laminated seismic isolation bearings

International Nuclear Information System (INIS)

Kulak, R.F.

1992-01-01

High damping steel-laminated elastomeric seismic isolation bearings are becoming a preferred device for isolating large buildings and structures. In the United States, the current reference design for the Advanced Liquid Metal Reactor uses laminated bearings for seismic isolation. These bearings are constructed from alternating layers of rubber and steel plates. They are typically designed for shear strains between 50 to 100 percent and expected to sustain two to three times these levels for beyond design basis loading considerations. The technical specifications used to procure these bearings are an important factor in assuring that the bearings meet the performance requirements of the design. The key aspects of the current version of the Technical Specifications are discussed in this paper. (author)

Sealed radionuclide sources - new technical specifications and current practice

Energy Technology Data Exchange (ETDEWEB)

Brabec, D

1987-03-01

Basic technical specifications are discussed valid in Czechoslovakia for sealed radionuclide sources, based on international ISO and CMEA standards. Described are the standardization of terminology, relationships of tests, testing methods, types of sealed sources and their applications, relations to Czechoslovak regulations on radiation protection and to IAEA specifications for radioactive material shipment, etc. Practical impact is shown of the introduction of the new standards governing sealed sources on the national economy, and the purpose is explained of various documents issued with sealed sources. (author). 2 figs., 45 refs.

Procurement in the Imaging Department: The Need for Understanding Technical Specifications

International Nuclear Information System (INIS)

Bwonya, N.S.M.

2015-01-01

Procurement is the function responsible for the acquisition of goods, works or services in an Organization. The Governments has three main ways of purchasing: Cash Imprest, Invitation of Quotation and Open National Tender. A Tenderer is a domestic, foreign, legal or natural person offering to supply goods, services or perform work assignments. Procurement involves needs identified by users, the procurement will seek approval from the AIE holder after which Preparation of specifications, Identifification of supplier (source) for delivering of the item to be stored after proper marking and verification. Specifications or Specs is a term mainly used in the acquisition of many items and in a Radiology department these include equipment, supplies and contrast media. A specification is a technical standard, tailored to perform certain functions and It is a set of requirements satisfied by a material, design, product or service. A technical evaluation team sets specifications and ideally will comprise of the following; a Radiologist, Senior Radiographer; an Engineer, Supplies professional and a Senior person (Nurse) whose department will need Radiological Services

Standard technical specifications: Combustion engineering plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Risk based optimization of technical specifications for operation of nuclear power plants

International Nuclear Information System (INIS)

1993-12-01

The objective of the report is to present an overview of the risk and reliability based approaches (using a probabilistic safety assessment (PSA)) for improving nuclear power plant technical specifications (TS). In that case, it will provide an information base to the Member States in seeking PSA based applications to enhance the effectiveness of their technical specifications. To achieve this objective, the report discusses the basic objectives and reasons for seeking TS changes, the methods, data requirements and uses of different types of applications, and an overview of different applications that have been completed, including detailed descriptions of selected applications. Refs, figs and tabs

Standard technical specifications for Westinghouse pressurized water reactors (revision issued Fall 1981). Technical report

International Nuclear Information System (INIS)

Virgilio, M.J.

1981-11-01

The Standard Technical Specifications for Westinghouse Pressurized Water Reactors (W-STS) is a generic document prepared by the U.S. NRC for use in the licensing process of current Westinghouse Pressurized Water Reactors. The W-STS sets forth the Limits, Operating Conditions and other requirements applicable to nuclear reactor facility operation as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical evaluation report on the proposed design modifications and technical-specification changes on grid voltage degradation for the San Onofre Nuclear Genetating Station, Unit 1

International Nuclear Information System (INIS)

Selan, J.C.

1982-01-01

This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the San Onofre Nuclear Generating Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the proposed design modifications and Technical Specification changes will ensure that the Class 1E equipment will be protected from sustained voltage degradation

Optimization of technical specifications by use of probabilistic methods

International Nuclear Information System (INIS)

Laakso, K.

1990-01-01

The Technical Specifications of a nuclear power plant specify the limits for plant operation from the safety point of view. These operational safety rules were originally defined on the basis of deterministic analyses and engineering judgement. As experience has accumulated, it has proved necessary to consider problems and make specific modifications in these rules. Developments in probabilistic safety assessment have provided a new tool to analyse, present and compare the risk effects of proposed rule modificatons. The main areas covered in the project are operational decisions in failure situations, preventive maintenance during power operation and surveillance tests of standby safety systems. (author)

Central Solenoid Insert Technical Specification

Energy Technology Data Exchange (ETDEWEB)

Martovetsky, Nicolai N [ORNL; Smirnov, Alexandre [ORNL

2011-09-01

The US ITER Project Office (USIPO) is responsible for the ITER central solenoid (CS) contribution to the ITER project. The Central Solenoid Insert (CSI) project will allow ITER validation the appropriate lengths of the conductors to be used in the full-scale CS coils under relevant conditions. The ITER Program plans to build and test a CSI to verify the performance of the CS conductor. The CSI is a one-layer solenoid with an inner diameter of 1.48 m and a height of 4.45 m between electric terminal ends. The coil weight with the terminals is approximately 820 kg without insulation. The major goal of the CSI is to measure the temperature margin of the CS under the ITER direct current (DC) operating conditions, including determining sensitivity to load cycles. Performance of the joints, ramp rate sensitivity, and stability against thermal or electromagnetic disturbances, electrical insulation, losses, and instrumentation are addressed separately and therefore are not major goals in this project. However, losses and joint performance will be tested during the CSI testing campaign. The USIPO will build the CSI that will be tested at the Central Solenoid Model Coil (CSMC) Test Facility at the Japan Atomic Energy Agency (JAEA), Naka, Japan. The industrial vendors (the Suppliers) will report to the USIPO (the Company). All approvals to proceed will be issued by the Company, which in some cases, as specified in this document, will also require the approval of the ITER Organization. Responsibilities and obligations will be covered by respective contracts between the USIPO, called Company interchangeably, and the industrial Prime Contractors, called Suppliers. Different stages of work may be performed by more than one Prime Contractor, as described in this specification. Technical requirements of the contract between the Company and the Prime Contractor will be covered by the Fabrication Specifications developed by the Prime Contractor based on this document and approved by

The applies specific technical requirements to the services of radiological protection according to the 17025

Energy Technology Data Exchange (ETDEWEB)

Marrero Garcia, M.; Fernandez Gomez, I. M.; Prendes Alonso, M.; Molina Perez, D.

2004-07-01

The employment in the Center of Radiation Protection and Hygiene (CRPH) of Cuba, of the standard 17025 for the administration of the quality of the calibration laboratories and test that offer services of radiological protection requires of a technical complement to really determine the technical competence. In the standard 17025, the specific requirements, are mentioned in the annex B (with informative character), where it points out that: {sup T}he requirements specified in the standard 17025 are established in general terms and, although they can be applied to all the test laboratories and applications, they could be necessary applications{sup .} In the CRPH these applications are translated in indispensable technical requirements to evaluate the performance of the services of radiological protection that offers, specifically those of personal monitoring, the calibration of instruments and the metrology of radionuclides. Although the standard 17025 is quite rigorous in the evaluation of technical requirements, to have specific materials not serves alone of tool to the laboratories, but also for the body of accreditation . In the CRPH the permanent employment of this tool has not constituted a practice, but had been good before our clients certain nonconformities to evaluate the performance of the laboratory and to achieve the recovery of the trust in its results. With this work we seek to expose some of these experiences. The experiences of the application of some of the technical requirements, in our case, they have been applied to the service of personal monitoring that offers the Laboratory of Personal Dosimetry. This laboratory is accredited by the National Accreditation Board of the Republic of Cuba (NABC) and besides fulfilling that settled down in 17025, the Approaches of Accreditation for test laboratories and calibration and it should also implant that settled down as specific technical requirements for the recognition of technical competence. (Author

Standard Technical Specifications for Westinghouse pressurized water reactors

International Nuclear Information System (INIS)

Virgilio, M.J.

1980-09-01

The Standard Technical Specifications for Westinghouse Pressurized Water Reactors (W-STS) is a generic document prepared by the U.S. NRC for use in the licensing process of current Westinghouse Pressurized Water Reactors. The W-STS sets forth the Limits, Operating Conditions and other requirements applicable to nuclear reactor facility operation as set forth in by Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. This document is revised periodically to reflect current licensing requirements

Mental Fatigue Impairs Soccer-Specific Physical and Technical Performance.

Science.gov (United States)

Smith, Mitchell R; Coutts, Aaron J; Merlini, Michele; Deprez, Dieter; Lenoir, Matthieu; Marcora, Samuele M

2016-02-01

To investigate the effects of mental fatigue on soccer-specific physical and technical performance. This investigation consisted of two separate studies. Study 1 assessed the soccer-specific physical performance of 12 moderately trained soccer players using the Yo-Yo Intermittent Recovery Test, Level 1 (Yo-Yo IR1). Study 2 assessed the soccer-specific technical performance of 14 experienced soccer players using the Loughborough Soccer Passing and Shooting Tests (LSPT, LSST). Each test was performed on two occasions and preceded, in a randomized, counterbalanced order, by 30 min of the Stroop task (mentally fatiguing treatment) or 30 min of reading magazines (control treatment). Subjective ratings of mental fatigue were measured before and after treatment, and mental effort and motivation were measured after treatment. Distance run, heart rate, and ratings of perceived exertion were recorded during the Yo-Yo IR1. LSPT performance time was calculated as original time plus penalty time. LSST performance was assessed using shot speed, shot accuracy, and shot sequence time. Subjective ratings of mental fatigue and effort were higher after the Stroop task in both studies (P motivation was similar between conditions. This mental fatigue significantly reduced running distance in the Yo-Yo IR1 (P performance time were not different between conditions; however, penalty time significantly increased in the mental fatigue condition (P = 0.015). Mental fatigue also impaired shot speed (P = 0.024) and accuracy (P performance.

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

International Nuclear Information System (INIS)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

2004-01-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

2004-07-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Technical specifications: Seabrook Station, Unit 1 (Docket No. 50-443)

International Nuclear Information System (INIS)

1990-03-01

The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Babcock experience of automated ultrasonic non-destructive testing of PWR pressure vessels during manufacture

International Nuclear Information System (INIS)

Dikstra, B.J.; Farley, J.M.; Scruton, G.

1990-01-01

Major developments in ultrasonic techniques, equipment and systems for automated inspection have lead, over a period of about ten years, to the regular application of sophisticated computer-controlled systems during the manufacture of nuclear reactor pressure vessels. Ten years ago the use of procedures defined in a code such as ASME XI might have been considered sufficient, but it is now necessary, as was demonstrated by the results of the UKAEA defect detection trials and the PISC II trials, to apply more comprehensive arrays of probes and higher test sensitivities. The ultrasonic techniques selected are demonstrated to be adequate by modelling or test-block exercises, the automated systems applied are subject to stringent quality assurance testing, and very rigorous inspection procedures are used in conjunction with a high degree of automation to ensure reproducibility of inspection quality. The state-of-the-art in automated ultrasonic testing of pressure vessels by Babcock is described. Current developments by the company, including automated flaw recognition, integrated modelling of inspection capability, and the use of electronically scanned variable-angle probes are reviewed. Examples quoted include the automated ultrasonic inspections of the Sizewell B pressurized water reactor vessel. (author)

Calculation of particulate dispersion in a design-basis tornadic storm from the Babcock and Wilcox Plant, Leechburg, Pennsylvania

Energy Technology Data Exchange (ETDEWEB)

Pepper, D.W.

1978-03-01

A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Babcock and Wilcox Plutonium Fabrication Facility at Leechburg, Pennsylvania. Plutonium particles lss than 20 ..mu..m in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The quasi-Lagrangian method of moments is used to model the transport of concentration within a grid cell volume.

Calculation of particulate dispersion in a design-basis tornadic storm from the Babcock and Wilcox Plant, Leechburg, Pennsylvania

International Nuclear Information System (INIS)

Pepper, D.W.

1978-03-01

A three-dimensional numerical model is used to calculate ground-level air concentration and deposition (due to precipitation scavenging) after a hypothetical tornado strike at the Babcock and Wilcox Plutonium Fabrication Facility at Leechburg, Pennsylvania. Plutonium particles lss than 20 μm in diameter are assumed to be lifted into the tornadic storm cell by the vortex. The rotational characteristics of the tornadic storm are embedded within the larger mesoscale flow of the storm system. The design-basis translational wind values are based on probabilities associated with existing records of tornado strikes in the vicinity of the plant site. Turbulence exchange coefficients are based on empirical values deduced from experimental data in severe storms and from theoretical assumptions obtained from the literature. The quasi-Lagrangian method of moments is used to model the transport of concentration within a grid cell volume

Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.

1979-12-01

The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

Risk impact of BWR technical specifications requirements during shutdown

International Nuclear Information System (INIS)

Staple, B.D.; Kirk, H.K.; Yakle, J.

1994-10-01

This report presents an application of probabilistic models and risk based criteria for determining the risk impact of the Limiting Conditions of Operations (LCOs) in the Technical Specifications (TSs) of a boiling water reactor during shutdown. This analysis studied the risk impact of the current requirements of Allowed Outage Times (AOTs) and Surveillance Test Intervals (STIs) in eight Plant Operational States (POSs) which encompass power operations, shutdown, and refueling. This report also discusses insights concerning TS action statements

The EDF catalogue of technical specifications (reference HN), standardization center; Catalogue des specifications techniques EDF (reference HN) centre de normalisation

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

A list of EDF technical specifications, valid at the 01/01/1996 date, is presented. Specifications domains such as electrical installations, equipment and materials, uninsulated and insulated conductors, measurement, control and command, electric power generating or transforming equipment, electrical appliances, telecommunications, electronic and computer systems, are covered

Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved ST or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume I contains the Specifications for all chapters and sections of the improved STS. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4-3.10 of the improved STS

Use of experience for the improvement of technical specifications for operation

International Nuclear Information System (INIS)

Schweitz, J.P.; Seveon, J.J.

1987-11-01

The lessons drawn from experience led EdF to define in 1980 a national specification standard, to be applied to the first standardized series of 900 MWe units and to be adapted to the later 1300 MWe units. This document is periodically revised, every two years or so, to take into account new trends in safety thinking and lessons learnt from operating experience. In this paper we present the main developments in the field of technical specifications, particularly: the definition of rules applicable in the event of unavailability of safety-related equipment, the integration of plant unit operating feedback for specifications optimization

Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2 (Docket No. 50-336)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

Technical specifications review of nuclear power plants: a risk-informed evaluation

International Nuclear Information System (INIS)

Saldanha, Pedro Luiz da Cruz; Sousa, Anna Leticia; Frutuoso e Melo, Paulo Fernando Ferreira; Duarte, Juliana Pacheco

2012-01-01

The use of risk information by a regulatory body as part of an integrated decision making process addresses the way in which risk information is being used as part of an integrated process in making decisions about safety issues at nuclear plants – commonly referred to as risk-informed decision making. The risk-informed approach aims to integrate in a systematic manner quantitative and qualitative, deterministic and probabilistic safety considerations to obtain a balanced decision. Probabilistic Safety Assessment (PSA) is a methodology that can be applied to provide a structured analysis process to evaluate the frequency and consequences of accidents scenarios in nuclear power plants. Technical Specifications (TS) are specifications regarding the characteristics of nuclear power plants (variables, systems or components) of overriding importance to nuclear safety and radiation protection, which is an integral part of plant operation authorization. Limiting Conditions of Operation (LCO) are the minimum levels of performance or capacity or operating system components required for the safe operation of nuclear plants, as defined in technical specifications. The Maintenance Rule (MR) is a requirement established by the U. S. Nuclear Regulatory Commission (NRC) to check the effectiveness of maintenance carried out in nuclear plants, and plant configuration control. The control of plant configuration is necessary to verify the impact of the maintenance of a safety device out of service on plant safety. The Electric Power Research Institute (EPRI) has assessed the role of probabilistic safety analysis in the regulation of nuclear power plants with the following objectives: a) to provide utilities with an approach for developing and implementing nuclear power station risk-managed technical specification programs; and b) to complement and supplement existing successful configuration risk management applications such as MR. This paper focuses on the evaluation of EPRI

Technical evaluation report on the 120 Vac vital instrument buses and inverter Technical Specifications Issue B71

International Nuclear Information System (INIS)

St Leger-Barter, G.; White, R.L.

1982-01-01

The operation of a Pressurized Water Reactor (PWR) with one of its 120 Vac vital buses energized in an off-normal mode was analyzed. A Probabilistic Risk Assessment was made to determine the increment of risk by energizing a vital bus from an off-site source directly vs energizing it from its normal, uninterruptible source (i.e., a battery/inverter arrangement). The calculations were made based on uninterruptible source energized vital buses as the normal mode. The analysis indicated that a reduction in the incremental risk increase (caused by plant operation with a vital bus being energized in an off-normal mode) can be accomplished by limiting the time permitted in that condition. Currently, the time that a vital bus can be energized in the off-normal mode is not universally time-limited by plant Technical Specifications. Several alternatives for the reduction in incremental risk were examined and their value/impacts were derived. These data indicate that a recommendation be made for a Technical Specification time limitation of 72 hours per year for off-normal energizing a vital bus during operation of a PWR

Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors

International Nuclear Information System (INIS)

Vito, D.J.

1980-12-01

The Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors (CE-STS) is a generic document prepared by the US NRC for use in the licensing process of current Combustion Engineering Pressurized Water Reactors. The CE-STS sets forth the limits, operating conditions, and other requirements applicable to nuclear reactor facility operation as set forth by Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public. The document is revised periodically to reflect current licensing requirements

Waste management issues and their potential impact on technical specifications of CANDU fuel materials

International Nuclear Information System (INIS)

Tait, J.C.; Johnson, L.H.

1997-01-01

The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO 2 impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to 14 C and 36 C1, which after 129 I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

Waste management issues and their potential impact on technical specifications of CANDU fuel materials

Energy Technology Data Exchange (ETDEWEB)

Tait, J.C.; Johnson, L.H. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

1997-07-01

The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO{sub 2} impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to {sup 14}C and {sup 36}C1, which after {sup 129}I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

Latest design of gate valves

Energy Technology Data Exchange (ETDEWEB)

Kurzhofer, U.; Stolte, J.; Weyand, M.

1996-12-01

Babcock Sempell, one of the most important valve manufacturers in Europe, has delivered valves for the nuclear power industry since the beginning of the peaceful application of nuclear power in the 1960s. The latest innovation by Babcock Sempell is a gate valve that meets all recent technical requirements of the nuclear power technology. At the moment in the United States, Germany, Sweden, and many other countries, motor-operated gate and globe valves are judged very critically. Besides the absolute control of the so-called {open_quotes}trip failure,{close_quotes} the integrity of all valve parts submitted to operational forces must be maintained. In case of failure of the limit and torque switches, all valve designs have been tested with respect to the quality of guidance of the gate. The guidances (i.e., guides) shall avoid a tilting of the gate during the closing procedure. The gate valve newly designed by Babcock Sempell fulfills all these characteristic criteria. In addition, the valve has cobalt-free seat hardfacing, the suitability of which has been proven by friction tests as well as full-scale blowdown tests at the GAP of Siemens in Karlstein, West Germany. Babcock Sempell was to deliver more than 30 gate valves of this type for 5 Swedish nuclear power stations by autumn 1995. In the presentation, the author will report on the testing performed, qualifications, and sizing criteria which led to the new technical design.

Technical specification for transferring National Pollutant Discharge Elimination System water data to the Oak Ridge Environmental Information System

International Nuclear Information System (INIS)

1996-11-01

The primary goal of this technical specification is to meet the consolidated environmental data requirements defined by the Federal Facility (FFA) and the Tennessee Oversight Agreement (TOA) as they pertain to NPDES surface water data maintained in Oak Ridge, Tennessee, by the Department of Energy's Maintenance and Operations (M ampersand O) contractor Martin Marietta Energy Systems and prime contractors to DOE. This technical specification describes the organizational responsibilities for getting NPDES data into OREIS, describes the logical data transfer file required from NPDES, addresses business rules and submission rules, describes the physical data transfer file, addresses configuration control of this technical specification, and addresses required changes to the current OREIS data base structure due to the requirements of NPDES

Catalogue of EDF`s technical specifications (HN reference). Centre of standardization; Catalogue des specifications techniques EDF (reference HN). Centre de normalisation

Energy Technology Data Exchange (ETDEWEB)

1998-12-31

This document edited by Electricite de France (EdF), is a catalogue of the French standard documents relative to any type of electrical material and equipment and which contain the technical specifications of these materials and equipments. A brief description of these specifications is given for each type of material or equipment listed. (J.S.)

An aerial radiological survey of the Babcock and Wilcox Nuclear Facilities and surrounding area, Lynchburg, Virginia

International Nuclear Information System (INIS)

Guss, P.P.

1993-04-01

An aerial radiological survey was conducted from July 18 through July 25, 1988, over a 41-square-kilometer (16-square-mile) area surrounding the Babcock and Wilcox nuclear facilities located near Lynchburg, Virginia. The survey was conducted at a nominal altitude of 61 meters (200 feet) with line spacings of 91 meters (300 feet). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter above ground level (AGL) was prepared and overlaid on an aerial photograph. The terrestrial exposure rates varied from 8 to 12 microroentgens per hour (μR/h). A search of the data for man-made radiation sources revealed the presence of three areas of high count rates in the survey area. Spectra accumulated over the main plant showed the presence of cobalt-60 ( 60 Co) and cesium-137 ( 137 Cs). A second area near the main plant indicated the presence of uranium-235 ( 235 U). Protactinium-234m ( 234m Pa) and 60 Co Were detected over a building to the east of the main plant. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries in support of the aerial data

A comparison of three self-tuning control algorithms developed for the Bristol-Babcock controller

International Nuclear Information System (INIS)

Tapp, P.A.

1992-04-01

A brief overview of adaptive control methods relating to the design of self-tuning proportional-integral-derivative (PID) controllers is given. The methods discussed include gain scheduling, self-tuning, auto-tuning, and model-reference adaptive control systems. Several process identification and parameter adjustment methods are discussed. Characteristics of the two most common types of self-tuning controllers implemented by industry (i.e., pattern recognition and process identification) are summarized. The substance of the work is a comparison of three self-tuning proportional-plus-integral (STPI) control algorithms developed to work in conjunction with the Bristol-Babcock PID control module. The STPI control algorithms are based on closed-loop cycling theory, pattern recognition theory, and model-based theory. A brief theory of operation of these three STPI control algorithms is given. Details of the process simulations developed to test the STPI algorithms are given, including an integrating process, a first-order system, a second-order system, a system with initial inverse response, and a system with variable time constant and delay. The STPI algorithms' performance with regard to both setpoint changes and load disturbances is evaluated, and their robustness is compared. The dynamic effects of process deadtime and noise are also considered. Finally, the limitations of each of the STPI algorithms is discussed, some conclusions are drawn from the performance comparisons, and a few recommendations are made. 6 refs

Technical Specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

International Nuclear Information System (INIS)

1989-08-01

The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

International Nuclear Information System (INIS)

1989-07-01

The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical-evaluation report on the proposed technical-specification changes on degraded grid-voltage protection for the Rancho Seco Nuclear Generating Plant (Docket No. 50-312)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This Technical Evaluation Report is a revision and contains supplemental information to the Technical Evaluations documented in previous LLNL reports dated October 1980 (UCID-18690), November 10, 1981 (UCID-19113), and July 15, 1983 (UCID-19708). These reports encompass the NRC requirements on Degraded Grid Voltage Protection and Adequacy of Station Electric Distribution System Voltages. The evaluation finds that the proposed Technical Specification changes on the undervoltage/overvoltage trip setpoints and Limiting Conditions for Operation provide the required protection to the Class 1E Equipment from sustained abnormal voltages

HPCG Benchmark Technical Specification

Energy Technology Data Exchange (ETDEWEB)

Heroux, Michael Allen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dongarra, Jack [Univ. of Tennessee, Knoxville, TN (United States); Luszczek, Piotr [Univ. of Tennessee, Knoxville, TN (United States)

2013-10-01

The High Performance Conjugate Gradient (HPCG) benchmark [cite SNL, UTK reports] is a tool for ranking computer systems based on a simple additive Schwarz, symmetric Gauss-Seidel preconditioned conjugate gradient solver. HPCG is similar to the High Performance Linpack (HPL), or Top 500, benchmark [1] in its purpose, but HPCG is intended to better represent how today’s applications perform. In this paper we describe the technical details of HPCG: how it is designed and implemented, what code transformations are permitted and how to interpret and report results.

10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

Science.gov (United States)

2010-01-01

...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors..., including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor... the design, construction, and operation of nuclear power reactors indicates that compliance with the...

Technical specification for the Quality Information Management System (QIMS) Pilot Project

Energy Technology Data Exchange (ETDEWEB)

Hall, R.C.; Claussen, L.M.; Thurston, I.

1992-01-01

This document contains implementation details for the Quality Information Management System (QIMS) Pilot Project, which has been released for VAX/VMS systems using the INGRES RDBMS. The INGRES Applications-By-Forms (ABF) software development tool was used to define the modules and screens which comprise the QIMS Pilot application. These specifications together with the QIMS information model and corresponding database definition constitute the QIMS technical specification and implementation description presented herein. The QIMS Pilot Project represents a completed software product which has been released for production use. Further extension projects are planned which will release new versions for QIMS. These versions will offer expanded and enhanced functionality to meet further customer requirements not accommodated by the QIMS Pilot Project.

Automation of technical specification monitoring for nuclear power plants

International Nuclear Information System (INIS)

Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

1986-01-01

The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation

International Nuclear Information System (INIS)

1992-10-01

This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs

Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-07-01

This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

Handbook of methods for risk-based analysis of technical specifications

International Nuclear Information System (INIS)

Samanta, P.K.; Kim, I.S.; Mankamo, T.; Vesely, W.E.

1996-01-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operations (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analyses and engineering judgments. Improvements in these requirements are facilitated by the availability of plant-specific Probabilistic Risk Assessments (PRAs). The US Nuclear Regulatory Commission (USNRC) Office of Research sponsored research to develop systematic, risk-based methods to improve various aspects of TS requirements. A handbook of methods summarizing such risk-based approaches has been completed in 1994. It is expected that this handbook will provide valuable input to NRC's present work in developing guidance for using PRA in risk-informed regulation. The handbook addresses reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), managing plant configurations, and scheduling maintenance

Generic evaluation of small break loss-of-coolant accident behavior in Babcock and Wilcox designed 177-FA operating plants

International Nuclear Information System (INIS)

1980-01-01

Slow system depressurization resulting from small break loss-of-coolant accidents (LOCAs) in the reactor coolant system have not, until recently, received detailed analytical study comparable to that devoted to large breaks. Following the TMI-2 accident, the staff had a series of meetings with Babcock and Wilcox (B and W) and the B and W licensees. The staff requested that B and W and the licensees: (1) systematically evaluate plant response for small break loss-of-coolant accidents; (2) address each of the concerns documented in the Michelson report; (3) validate the computer codes used against the TMI-2 accident; (4) extend the break spectrum analysis to very small breaks, giving special consideration to failure of pressurizer valves to close; (5) analyze degraded conditions where AFW is not available; (6) prepare design changes aimed at reducing the probability of loss-of-coolant accidents produced by the failure of a PORV to close; and (7) develop revised emergency procedures for small breaks. This report describes the review of the generic analyses performed by B and W based on the requests stated above

Evaluation of River Bend Station Unit 1 Technical Specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the River Bend Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the River Bend T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The River Bend Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Technical evaluation report on the proposed design modifications and technical specification changes on grid voltage degradation for the Millstone Nuclear Power Station, Unit 1

International Nuclear Information System (INIS)

Selan, J.C.

1982-01-01

This report documents the technical evaluation of the proposed design modifications and Technical Specification change for protection of Class 1E equipment from grid voltage degradation for the Millstone Nuclear Power Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the licensee has not provided sufficient information on the undervoltage protection system to allow a complete evaluation into the adequacy of protecting the Class 1E equipment from sustained voltage degradation

Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Pilgrim Nuclear Power Station, Unit 1

International Nuclear Information System (INIS)

White, R.L.

1980-01-01

This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Pilgrim Nuclear Power Station. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/5)

International Nuclear Information System (INIS)

Bottimore, R.R.

1980-12-01

The Standard Technical Specifications for General Electric Boiling Water Reactors (GE-STS) is a generic document prepared by the US NRC for use in the licensing process of current General Electric Boiling Water Reactors. The GE-STS sets forth the limits, operating conditions, and other requirements applicable to nuclear reactor facility operation as set forth by Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. The document is revised periodically to reflect current licensing requirements

Knowledge Sharing for Common Understanding of Technical Specifications Through Artifactual Culture

DEFF Research Database (Denmark)

Zahedi, Mansooreh; Babar, Muhammad Ali

2014-01-01

Context: Software engineering is a knowledge intensive activity that is supported by documenting and sharing the required knowledge through a wide variety of artifacts. Global Software Development (GSD) teams heavily rely on artifacts as a vital means of knowledge sharing. However, there is little...... empirical knowledge about the key reasons and practices of using artifacts in GSD for knowledge sharing to support common understanding of technical specifications. Objective: This study aims at empirically studying the key motivators, practices, and drawbacks of artifact-based knowledge sharing...... specification knowledge. We also present the practices that make up the artifact-based knowledge sharing system in the studied case. Finally, we shed some light on the caveats of knowledge sharing practices adopted by the studied company. The findings can provide useful insights into the artifact...

Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test

International Nuclear Information System (INIS)

Cowell, B.S.

1997-06-01

This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy

Impact of shutdown risk on risk-based assessment of technical specifications

International Nuclear Information System (INIS)

Deriot, S.

1992-10-01

This paper describes the current work performed by the Research and Development Division of EDF concerning risk-based assessment of Operating Technical Specifications (OTS). The current risk-based assessment of OTS at EDF is presented. Then, the level 1 Probabilistic Safety Assessment of unit 3 of the Paluel nuclear power station (called PSA 1300) is described. It is fully computerized and takes into account the risk in shutdown states. A case study is presented. It shows that the fact of considering shutdown risk suggests that the current OTS should be modified

Alternative approaches to risk-based technical specifications

International Nuclear Information System (INIS)

Atefi, B.; Gallagher, D.W.; Liner, R.T.; Lofgren, E.V.

1987-01-01

Four alternative risk-based approaches to Technical Specifications are identified. These are: a Probabilistic Risk Assessment (PRA) oriented approach; a reliability goal-oriented approach; an approach based on configuration control; a data-oriented approach. Based on preliminary results, the PRA-oriented approach, which has been developed further than the other approaches, seems to offer a logical, quantitative basis for setting Allowed Outage Times (AOTs) and Surveillance Test Intervals (STIs) for some plant components and systems. The most attractive feature of this approach is that it directly links the AOTs and STIs with the risk associated with the operation of the plant. This would focus the plant operator's and the regulatory agency's attention on the most risk-significant components of the plant. A series of practical issues related to the level of detail and content of the plant PRAs, requirements for the review of these PRAs, and monitoring cf the plant's performance by the regulatory agency must be resolved before the approach could be implemented. Future efforts will examine the other three approaches and their practicality before firm conclusions are drawn regarding the viability of any of these approaches

Safety evaluation report related to Babcock and Wilcox Owners Group Plant Reassessment Program: [Final report

International Nuclear Information System (INIS)

1987-11-01

After the accident of Three Mile Island, Unit 2, nuclear power plant owners made a number of improvements to their nuclear facilities. Despite these improvements, the US Nuclear Regulatory Commission (NRC) staff is concerned that the number and complexity of events at Babcock and Wilcox (B and W) nuclear plants have not decreased as expected. This concern was reinforced by the June 9, 1985 total-loss-of-feedwater event at Davis-Besse Nuclear Power Station and the December 26, 1985 overcooling transient at Rancho Seco Nuclear Generating Station. By letter dated January 24, 1986, the Executive Director for Operations (EDO) informed the Chairman of the B and W Owners Group (BWOG) that a number of recent events at B and W-designed reactors have led the NRC staff to conclude that the basic requirements for B and W reactors need to be reexamined. In its February 13, 1986 response to the EDO's letter, the BWOG committed to lead an effort to define concerns relative to reducing the frequency of reactor trips and the complexity of post-trip response in B and W plants. The BWOG submitted a description of the B and W program entitled ''Safety and Performance Improvement Program'' (BAW-1919) on May 15, 1986. Five revisions to BAW-1919 have also been submitted. The NRC staff has reviewed BAW-1919 and its revisions and presents its evaluation in this report. 2 figs., 34 tabs

Optimization Strategy of the APR+ BOP Technical Specifications

International Nuclear Information System (INIS)

Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum

2016-01-01

The BOP is one of the key factors for successful project implementation of NPP. In constructing the APR1400 NPP, the BOP procurement has been one of the biggest concerns. Due to the design changes and increased capacity of equipment in NPP, lots of BOPs should be ‘first supplied equipment’ [hereinafter, ‘FSE’]. The manufacture-ability, and the performances of FSEs have not been fully proved and tested, manufacturers and suppliers are requested to submit Reports for Equipment Qualification Evaluation in accordance with 10 CFR 50.49, IEEE 323. They need at least 1-2 years’ tests for Environment Qualification (EQ) and Seismic Qualification (SQ). This study is focused how to prepare the BOP purchase specifications in order to control the FSEs, especially in safety class equipment. With the optimization plan for BOP packages of this study, the FSEs’ occurrence can be reasonably controlled as low as possible. For successful NPP project, the concerns in procuring BOPs shall be fully analyzed beforehand. Now Korea is preparing new era of APR+, with closing the time of APR1400. The technical specification of APR+ BOPs can be developed and prepared successfully and very effectively according to this optimization plan. This will be a great contribution not only in constructing APR+ in time, but also in exporting APR+ overseas, all over the world in the future

Optimization Strategy of the APR+ BOP Technical Specifications

Energy Technology Data Exchange (ETDEWEB)

Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

The BOP is one of the key factors for successful project implementation of NPP. In constructing the APR1400 NPP, the BOP procurement has been one of the biggest concerns. Due to the design changes and increased capacity of equipment in NPP, lots of BOPs should be ‘first supplied equipment’ [hereinafter, ‘FSE’]. The manufacture-ability, and the performances of FSEs have not been fully proved and tested, manufacturers and suppliers are requested to submit Reports for Equipment Qualification Evaluation in accordance with 10 CFR 50.49, IEEE 323. They need at least 1-2 years’ tests for Environment Qualification (EQ) and Seismic Qualification (SQ). This study is focused how to prepare the BOP purchase specifications in order to control the FSEs, especially in safety class equipment. With the optimization plan for BOP packages of this study, the FSEs’ occurrence can be reasonably controlled as low as possible. For successful NPP project, the concerns in procuring BOPs shall be fully analyzed beforehand. Now Korea is preparing new era of APR+, with closing the time of APR1400. The technical specification of APR+ BOPs can be developed and prepared successfully and very effectively according to this optimization plan. This will be a great contribution not only in constructing APR+ in time, but also in exporting APR+ overseas, all over the world in the future.

Technical Specifications, Comanche Peak Steam Electric Station, Unit 1 (Docket No. 50-445)

International Nuclear Information System (INIS)

1990-04-01

The Technical Specifications for Comanche Peak Steam Electric Station, Unit 1 were prepared by the US Nuclear Regulatory Commission. They set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility, as set forth in Section 50.36 of Title 10 of the Code of Federal Regulations Part 50, for the protection of the health and safety of the public

Understanding the technical content of requirements in specification document

DEFF Research Database (Denmark)

Sudin, Mohd Nizam Bin; Ahmed-Kristensen, Saeema

2011-01-01

development process, is essential to be devised in advance. To achieve this aim, understanding how to formulate a good requirement is necessary and it is only possible if design engineers understand the technical content of a requirement. In aiming to understand the technical content of a requirement...

Evaluation of Watts Bar Nuclear Plant Unit 1 Technical Specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Evaluation of Shoreham Nuclear Power Station, Unit 1 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-08-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Evaluation of Waterford Steam Electric Station Unit 3 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-09-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Waterford Steam Electric Station Unit 3 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Waterford T/S. Several discrepancies were identified and subsequently resolved by the cognizant NRC reviewer. Pending completion of the resolutions noted in Part 3 of this report, the Waterford Steam Electric Station Unit 3 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

International Nuclear Information System (INIS)

Samanta, P.K.; Kim, I.S.; Vesely, W.E.

1992-01-01

Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

Evaluation of Perry Nuclear Power Plant Unit 1 technical specifications

International Nuclear Information System (INIS)

Baxter, D.E.; Bruske, S.J.

1985-11-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Perry Nuclear Power Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the requirements of the Final Safety Analysis Report (FSAR) as amended, and the requirements of the Safety Evaluation Report (SER) as supplemented. A comparative audit of the FSAR as amended, and the SER as supplemented was performed with the Perry T/S. Several discrepancies were identified and subsequently resolved through telephone conversations with the staff reviewer and the utility representative. Pending completion of the resolutions noted in Parts 3 and 4 of this report, the Perry Nuclear Power Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

Differential and Integral Calculus in careers of technical sciences. Specificities of their teaching

Directory of Open Access Journals (Sweden)

Iván Javier Villamar-Alvarado

2017-12-01

Full Text Available The Differential and Integral Calculus has great relevance for the professionals of the technical sciences since it provides them with a solid theoretical-conceptual body to process information, to use models that simulate real processes, to solve technical problems, to work in multidisciplinary projects and to communicate with precision. In spite of this relevance, there are numerous international dissatisfactions related to their learning by training engineers. The objective was to unveil the specificities of the teaching-learning process of this discipline that favor a successful appropriation of its content by the future engineers. The result was to unveil the didactic need to resolve the dialectical contradiction that manifests itself between the systematization of the engineering functionality of the aforementioned content and its contextualized interdisciplinary generalization. As a consequence, the need arises to create new didactic proposals that overcome this contradiction, as a way to perfect the teaching-learning process of this discipline in the engineering careers.

A Preliminary Investigation of General and Technique-specific Assessments for the Evaluation of Laparoscopic Technical Skills.

Science.gov (United States)

Vergis, Ashley; Steigerwald, Sarah

2017-10-07

Background  Both general and technique-specific assessments of technical skill have been validated in surgical education. The purpose of this study was to assess the correlation between the objective structured assessment of technical skills (OSATS) and the global operative assessment of laparoscopic skills (GOALS) rating scales using a high-fidelity porcine laparoscopic cholecystectomy model. Methods Post-graduate year-one general surgery and urology residents (n=14) performed a live laparoscopic porcine cholecystectomy. Trained surgeons rated their performance using OSATS and GOALS assessment scales. Results Pearson's correlation coefficient between OSATS and GOALS was 0.96 for overall scores. It ranged from 0.78 - 0.89 for domains that overlapped between the two scales. Conclusion There is a very high correlation between OSATS and GOALS. This implies that they likely measure similar constructs and that either may be used for summative-type assessments of trainee skill. However, further investigation is needed to determine if technique-specific assessments may provide more useful feedback in formative evaluation.

Solar Cycle Variability Induced by Tilt Angle Scatter in a Babcock-Leighton Solar Dynamo Model

Science.gov (United States)

Karak, Bidya Binay; Miesch, Mark

2017-09-01

We present results from a three-dimensional Babcock-Leighton (BL) dynamo model that is sustained by the emergence and dispersal of bipolar magnetic regions (BMRs). On average, each BMR has a systematic tilt given by Joy’s law. Randomness and nonlinearity in the BMR emergence of our model produce variable magnetic cycles. However, when we allow for a random scatter in the tilt angle to mimic the observed departures from Joy’s law, we find more variability in the magnetic cycles. We find that the observed standard deviation in Joy’s law of {σ }δ =15^\\circ produces a variability comparable to the observed solar cycle variability of ˜32%, as quantified by the sunspot number maxima between 1755 and 2008. We also find that tilt angle scatter can promote grand minima and grand maxima. The time spent in grand minima for {σ }δ =15^\\circ is somewhat less than that inferred for the Sun from cosmogenic isotopes (about 9% compared to 17%). However, when we double the tilt scatter to {σ }δ =30^\\circ , the simulation statistics are comparable to the Sun (˜18% of the time in grand minima and ˜10% in grand maxima). Though the BL mechanism is the only source of poloidal field, we find that our simulations always maintain magnetic cycles even at large fluctuations in the tilt angle. We also demonstrate that tilt quenching is a viable and efficient mechanism for dynamo saturation; a suppression of the tilt by only 1°-2° is sufficient to limit the dynamo growth. Thus, any potential observational signatures of tilt quenching in the Sun may be subtle.

Technical specifications: Hope Creek Generating Station (Docket No. 50-354). Appendix A to License No. NPF-50

International Nuclear Information System (INIS)

1986-04-01

Information is provided on the technical specifications for the Hope Creek Nuclear Power Station. Areas of interest discussed in this report include: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

Multiloop integral system test (MIST): Final report, Inter-group comparisons

Energy Technology Data Exchange (ETDEWEB)

Gloudemans, J.R.

1989-07-01

The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The individual tests are described in detail in Volumes 2 through 8 and Volume 11, and are summarized in Volume 1. Inter-group comparisons are addressed in this document, Volume 9. These comparisons are grouped as follows: mapping versus SBLOCA transients, SBLOCA, pump effects, and the effects of noncondensible gases. Appendix A provides an index and description of the microfiched plots for each test, which are enclosed with the corresponding Volumes 2 through 8. 147 figs., 5 tabs.

Multiloop integral system test (MIST)

International Nuclear Information System (INIS)

Gloudemans, J.R.

1989-07-01

The multiloop integral system test (MIST) was part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox-designed plants. MIST was sponsored by the US Nuclear Regulatory Commission, the Babcock and Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral system facilities to address the thermal-hydraulic SBLOCA questions. MIST and two other supporting facilities were specifically designed and constructed for this program, and an existing facility -- the once-through integral system (OTIS) -- was also used. Data from MIST and the other facilities will be used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The individual tests are described in detail in Volumes 2 through 8 and Volume 11, and are summarized in Volume 1. Inter-group comparisons are addressed in this document, Volume 9. These comparisons are grouped as follows: mapping versus SBLOCA transients, SBLOCA, pump effects, and the effects of noncondensible gases. Appendix A provides an index and description of the microfiched plots for each test, which are enclosed with the corresponding Volumes 2 through 8. 147 figs., 5 tabs

Effects of natural phenomena on the Babcock and Wilcox Co. Plutonium Fabrication Plant at the Parks Township site, Leechburg, Pennsylvania. Docket No. 70-364

International Nuclear Information System (INIS)

1979-03-01

The proposed action is to issue a renewal to the full-term Special Nuclear Material License No. SNM-414 (Docket No. 70-364) authorizing the Nuclear Material Division of the Babcock and Wilcox Company (BandW) to operate nuclear-fuel-fabrication facilities located in Leechburg, Pennsylvania. The plutonium fuel facility is presently being used to fabricate fuel for the fast test reactor under construction at the Hanford Reservation near Richland, Washington. Implicit in Sections 70.22 and 70.23 of 10CFR70 is a requirement that existing plutonium fabrication plants be examined with the objective of improving, to the extent practicable, their abilities to withstand adverse natural phenomena without loss of capability to protect the public. In accordance with these regulations, an analysis was initiated of the effects of natural phenomena on the BandW Plutonium Fabrication Plant. Following completion of the analysis, a condensation was prepared of the effects of natural phenomena on the facility

Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system

International Nuclear Information System (INIS)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data

The key to technical translation, v.1 concept specification

CERN Document Server

Hann, Michael

1992-01-01

This handbook for German/English/German technical translators at all levels from student to professional covers the root terminologies of the spectrum of scientific and engineering fields. The work is designed to give technical translators direct insight into the main error sources occurring in their profession, especially those resulting from a poor understanding of the subject matter and the usage of particular terms to designate different concepts in different branches of technology. The style is easy to read and suitable for nonnative English speakers and translators with no engineering ex

STEPS: source term estimation based on plant status phase 0 - the technical specifications of the containment module

International Nuclear Information System (INIS)

Vamanu, D.V.

1998-01-01

In the framework of Project RODOS (Real-Time On-Line Decision Support System for Nuclear Emergencies in Europe), the European Atomic Energy Community (EAEC) of the Commission of the European Communities has commissioned the development of a unified concept, body of knowledge, models and software package meant to assist the evaluation of the source term of severe nuclear accidents in light water reactors of the types prevailing on the Continent. Code-named STEPS, for 'Source Term Estimation based on Plant Status', the project has evolved as Contract RODOS D (FI4P-CT96-0048), between EAEC and consortium of expert European centres including Commissariat a l'Energie Atomique, Institut de Protection et de Surete Nucleaire, (CEA-DPI-SEAC) as Coordinator and Forschungszentrum Karlsruhe GmbH (FZK-INR), the Finnish Centre for Radiation and Nuclear Safety, (STUK-NSD), the Technical Research Centre of Finland, Energy, Nuclear Energy (VTT-ET-NE), and Eidgenossische Technische Hochschule - ETH Zurich, Centre of Excellence (ETH-CERS) as Contractors. For the Phase 0 of the project, an IFIN-HH expert has been assigned by ETH-CERS to develop the Technical Specifications of the delivery component of the intended STEPS package, the CONTAINMENT Module. Sponsored by ETH-CERS headquarters in Zurich, the work was done on the premises and with the logistic support of CEA D PI-SEAC at Fontenay-aux-Roses, with the feedback processing and computer code development subsequently performed in Bucharest. The Technical Specifications of the STEPS CONTAINMENT Module were guided by specific terms of reference, including: (i) the capability of the software to function as a source term interface between targeted nuclear power plants and the RODOS System; (ii) the comparable capability of the system to be operated as a stand-alone assessment and decision support tool for a comprehensive variety of plants, nuclear emergency classes. On the technical side, the specifications had to focus on the possible

Vitrification of low-level radioactive waste in a slagging combustor

International Nuclear Information System (INIS)

Holmes, M.J.; Downs, W.; Higley, B.A.

1995-07-01

The suitability of a Babcock ampersand Wilcox cyclone furnace to vitrify a low-level radioactive liquid waste was evaluated. The feed stream contained a mixture of simulated radioactive liquid waste and glass formers. The U.S. Department of Energy is testing technologies to vitrify over 60,000,000 gallons of this waste at the Hanford site. The tests reported here demonstrated the technical feasibility of Babcock ampersand Wilcox's cyclone vitrification technology to produce a glass for near surface disposal. Glass was produced over a period of 24-hours at a rate of 100 to 150 lb/hr. Based on glass analyses performed by an independent laboratory, all of the glass samples had leachabilities at least as low as those of the laboratory glass that the recipe was based upon. This paper presents the results of this demonstration, and includes descriptions of feed preparation, glass properties, system operation, and flue gas composition. The paper also provides discussions on key technical issues required to match cyclone furnace vitrification technology to this U.S. Department of Energy Hanford site application

Handbook of methods for risk-based analyses of technical specifications

International Nuclear Information System (INIS)

Samanta, P.K.; Kim, I.S.; Mankamo, T.; Vesely, W.E.

1994-12-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while a few may not be conducive to safety. The US Nuclear Regulatory Commission (USNRC) Office of Research has sponsored research to develop systematic risk-based methods to improve various aspects of TS requirements. This handbook summarizes these risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), scheduled or preventive maintenance, action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), and management of plant configurations resulting from outages of systems, or components. For each topic, the handbook summarizes analytic methods with data needs, outlines the insights to be gained, lists additional references, and gives examples of evaluations

Handbook of methods for risk-based analyses of technical specifications

Energy Technology Data Exchange (ETDEWEB)

Samanta, P.K.; Kim, I.S. [Brookhaven National Lab., Upton, NY (United States); Mankamo, T. [Avaplan Oy, Espoo (Finland); Vesely, W.E. [Science Applications International Corp., Dublin, OH (United States)

1994-12-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while a few may not be conducive to safety. The US Nuclear Regulatory Commission (USNRC) Office of Research has sponsored research to develop systematic risk-based methods to improve various aspects of TS requirements. This handbook summarizes these risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), scheduled or preventive maintenance, action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), and management of plant configurations resulting from outages of systems, or components. For each topic, the handbook summarizes analytic methods with data needs, outlines the insights to be gained, lists additional references, and gives examples of evaluations.

Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation.

Nuclear Regulatory Commission issuances, January 1995. Volume 41, Number 1

International Nuclear Information System (INIS)

1995-01-01

This book contains issuances of the Atomic Safety and Licensing Boards for January 1995. The issuances include Babcock and Wilcox Company materials license; Hydro Resources, Inc. application for uranium mining; low-level waste storage in Utah; communication of emerging and existing generic, technical issues with PWR owners groups; and radioactive waste management by Sierra Nuclear Corporation

Technical specification for fabrication of HANARO pool cover

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Woo, Sang Ik

2001-06-01

This technical specification details the requirements and the acceptance criteria for design, seismic analysis, function test, installation and quality assurance for HANARO pool cover which will be installed at the top of reactor pool. The pool cover is classified as non-nuclear safety, seismic category II and quality class T. The basic design of the pool cover for increasing HANARO applications has been carried out for supporting the driving devices which can load, unload and rotate the irradiation targets in the in-core and out-core vertical irradiation holes under on-power operation. The comments of HANARO user group related with irradiation tests have optimally considered in the process of design. The interference between fuel handling and control absorber units in the reactor pool and activities to load, unload and rotate the irradiation targets at the top of the reactor pool have been minimized. The pool cover can be moved for maintenance and can protect the reactor pool from unexpected drop of foreign materials. It provides the space to vertical access of driving devices for NTD, CT/IR and OR4/OR5 under on-power operation. And the pool cover assembly must maintain its structural integrity under seismic load. Based on the above design concept, the HANARO pool cover has been proposed as supporting structure of driving devices for NTD, fission moly and RI production under on-power operation.

Scientific profile and professional responsibility of Court-appointed Medical Technical Consultants in Italy: time for a specific educational curriculum?

Science.gov (United States)

Conti, Andrea Alberto

2014-08-20

Court-appointed Technical Consultants (CTCs) are fundamental figures in the Italian judicial system. CTCs are experts appointed by judges in order to supplement their activities by ascertaining, collecting and analyzing facts concerning the specific subject of a lawsuit. These experts formulate opinions, gather motivations and perform checks to provide clear, objective and irrefutable answers to the questions posed by judges. With direct reference to the medical field, while police doctors (specialists in forensic medicine) follow an academic, dedicated, well-structured educational curriculum, the University specialty school in Forensic Medicine, other medical CTCs, though not infrequently luminaries with one or many medical specialties and professional acknowledgments, may have no specific legal-medicine and juridical expertise, precisely because a similar expertise is not formally required of them. In the light of these considerations, in Italy some professionals of the legal world, and of the health context too, have proposed for medical CTCs targeted educational pathways, which would provide these experts with formal specific qualifications. In synthesis and in conclusion, a full knowledge and a rigorous respect of the rules of legal proceedings emerge as increasingly important characteristics for current and future Court-appointed Technical Consultants, together with a specific educational curriculum.

Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

International Nuclear Information System (INIS)

White, R.L.

1981-01-01

This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443): Appendix ''A'' to License No. NPF-67

International Nuclear Information System (INIS)

1989-05-01

The Seabrook Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical specification for vacuum systems

International Nuclear Information System (INIS)

Khaw, J.

1987-01-01

The vacuum systems at the Stanford Linear Accelerator Center (SLAC) are primarily of all-metal construction and operate at pressures from 10 -5 to 10 -11 Torr. The primary gas loads during operation result from thermal desorption and beam-induced desorption from the vacuum chamber walls. These desorption rates can be extremely high in the case of hydrocarbons and other contaminants. These specifications place a major emphasis on eliminating contamination sources. The specifications and procedures have been written to insure the cleanliness and vacuum integrity of all SLAC vacuum systems, and to assist personnel involved with SLAC vacuum systems in choosing and designing components that are compatible with existing systems and meet the quality and reliability of SLAC vacuum standards. The specification includes requirements on design, procurement, fabrication, chemical cleaning, clean room practices, welding and brazing, helium leak testing, residual gas analyzer testing, bakeout, venting, and pumpdown. Also appended are specifications regarding acceptable vendors, isopropyl alcohol, bakeable valve cleaning procedure, mechanical engineering safety inspection, notes on synchrotron radiation, and specifications of numerous individual components

Technical Specifications, Clinton Power Station, Unit No. 1 (Docket No. 50-461). Appendix ''A'' to License No. NPF-55

International Nuclear Information System (INIS)

1986-09-01

This report presents information on the technical specifications of the Clinton Unit No. 1 Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

Non-process instrumentation surveillance and test reduction

International Nuclear Information System (INIS)

Ferrell, R.; LeDonne, V.; Donat, T.; Thomson, I.; Sarlitto, M.

1993-12-01

Analysis of operating experience, instrument failure modes, and degraded instrument performance has led to a reduction in Technical Specification surveillance and test requirements for nuclear power plant process instrumentation. These changes have resulted in lower plant operations and maintenance (O ampersand M) labor costs. This report explores the possibility of realizing similar savings by reducing requirements for non-process instrumentation. The project team reviewed generic Technical Specifications for the four major US nuclear steam supply system (NSSS) vendors (Westinghouse, General Electric, Combustion Engineering, and Babcock ampersand Wilcox) to identify nonprocess instrumentation for which surveillance/test requirements could be reduced. The team surveyed 10 utilities to identify specific non-process instrumentation at their plants for which requirements could be reduced. The team evaluated utility analytic approaches used to justify changes in surveillance/test requirements for process equipment to determine their applicability to non-process instrumentation. The report presents a prioritized list of non-process instrumentation systems suitable for surveillance/test requirements reduction. The top three systems in the list are vibration monitors, leak detection monitors, and chemistry monitors. In general, most non-process instrumentation governed by Technical Specification requirements are candidates for requirements reduction. If statistical requirements are somewhat relaxed, the analytic approaches previously used to reduce requirements for process instrumentation can be applied to non-process instrumentation. The report identifies as viable the technical approaches developed and successfully used by Southern California Edison, Arizona Public Service, and Boston Edison

Technical specifications: Perry Nuclear Power Plant, unit no. 1 (Docket no. 50-440): Appendix ''A'' to license no. NPF-58

International Nuclear Information System (INIS)

1986-11-01

This report presents technical specifications for the Perry-1 Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

Recommendations for the treatment of aging in standard technical specifications

International Nuclear Information System (INIS)

Orton, R.D.; Allen, R.P.

1995-09-01

As part of the US Nuclear Regulatory Commission's Nuclear Plant Aging Research Program, Pacific Northwest Laboratory (PNL) evaluated the standard technical specifications for nuclear power plants to determine whether the current surveillance requirements (SRs) were effective in detecting age-related degradation. Nuclear Plant Aging Research findings for selected systems and components were reviewed to identify the stressors and operative aging mechanisms and to evaluate the methods available to detect, differentiate, and trend the resulting aging degradation. Current surveillance and testing requirements for these systems and components were reviewed for their effectiveness in detecting degraded conditions and for potential contributions to premature degradation. When the current surveillance and testing requirements appeared ineffective in detecting aging degradation or potentially could contribute to premature degradation, a possible deficiency in the SRs was identified that could result in undetected degradation. Based on this evaluation, PNL developed recommendations for inspection, surveillance, trending, and condition monitoring methods to be incorporated in the SRs to better detect age- related degradation of these selected systems and components

Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

Technical specifications, Vogtle Electric Generating Plant, Unit No. 1 (Docket No. 50-424): Appendix ''A'' to license No. NPF-61

International Nuclear Information System (INIS)

1987-01-01

This technical specifications report presents information concerning the Vogtle Electric Generating Plant in the following areas: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

On-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

International Nuclear Information System (INIS)

Davis, E.; Rasmussen, B.

2004-01-01

This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system

Methodology for technical risk assessment

International Nuclear Information System (INIS)

Waganer, L.M.; Zuckerman, D.S.

1983-01-01

A methodology has been developed for and applied to the assessment of the technical risks associated with an evolving technology. This methodology, originally developed for fusion by K. W. Billman and F. R. Scott at EPRI, has been applied to assess the technical risk of a fuel system for a fusion reactor. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications (i.e. probability of failure). The individual steps in the technical risk assessment are summarized. The first step in this methodology is to clearly and completely quantify the technical requirements for the particular system being examined. The next step is to identify and define subsystems and various options which appear capable of achieving the required technical performance. The subsystem options are then characterized regarding subsystem functions, interface requirements with the subsystems and systems, important components, developmental obstacles and technical limitations. Key technical subsystem performance parameters are identified which directly or indirectly relate to the system technical specifications. Past, existing and future technical performance data from subsystem experts are obtained by using a Bayesian Interrogation technique. The input data is solicited in the form of probability functions. Thus the output performance of the system is expressed as probability functions

Technical Submission Form: Technical Specification of a Wave Energy Farm.

Energy Technology Data Exchange (ETDEWEB)

Roberts, Jesse D.; Kim Nielsen; Ben Kennedy; Bull, Diana L; Costello, Ronan Patrick; Jochem Weber

2017-04-01

The Wave - SPARC project developed the Technology Performance Level (TPL) assessment procedure based on a rigorous Systems Engineering exercise. The TPL assessment allows a whole system evaluation of Wave Energy Conversion Technology by measuring it against the requirements determined through the Systems Engineering exercise. The TPL assessment is intended to be useful in technology evaluation; in technology innovation; in allocation of public or priva te investment, and; in making equipment purchasing decisions. This Technical Submission Form (TSF) serves the purpose of collecting relevant and complete information, in a technology agnostic way, to allow TPL assessment s to be made by third party assessor s. The intended usage of this document is that the organization or people that are performing the role of developers or promoters of a particular technology will use this form to provide the information necessary for the organization or people who are perf orming the assessor role to use the TPL assessment.

Handbook of methods for risk-based analysis of technical specification requirements

International Nuclear Information System (INIS)

Samanta, P.K.; Vesely, W.E.

1994-01-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: Quantitatively evaluate the risk and justify changes based on objective risk arguments; Provide a defensible basis for these requirements for regulatory applications. The US NRC Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

Handbook of methods for risk-based analysis of Technical Specification requirements

International Nuclear Information System (INIS)

Samanta, P.K.; Vesely, W.E.

1993-01-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: quantitatively evaluate the risk impact and justify changes based on objective risk arguments. Provide a defensible basis for these requirements for regulatory applications. The United States Nuclear Regulatory Commission (USNRC) Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

Manual of engineering drawing technical product specification and documentation to British and international standards

CERN Document Server

Simmons, Colin H; Simmons, Colin

2012-01-01

Manual of Engineering Drawing is a comprehensive guide for experts and novices for producing engineering drawings and annotated 3D models that meet the recent BSI and ISO standards of technical product documentation and specifications. This fourth edition of the text has been updated in line with recent standard revisions and amendments. The book has been prepared for international use, and includes a comprehensive discussion of the fundamental differences between the ISO and ASME standards, as well as recent updates regarding legal components, such as copyright, patents, and other legal considerations. The text is applicable to CAD and manual drawing, and it covers the recent developments in 3D annotation and surface texture specifications. Its scope also covers the concepts of pictorial and orthographic projections, geometrical, dimensional and surface tolerancing, and the principle of duality. The text also presents numerous examples of hydraulic and electrical diagrams, applications, bearings, adhesives, ...

Training of technical staff and technical staff managers

International Nuclear Information System (INIS)

Moody, G.F.

1991-01-01

The purpose of Technical Staff and Technical Staff Managers training is to provide job skills enhancement to individuals selected to fill key technical positions within a nuclear utility. This training is unique in that unlike other training programs accredited by the National Academy for Nuclear Training, it does not lead to specific task qualification. The problems encountered when determining the student population and curriculum are a direct result of this major difference. Major problems encountered are determining who should attend the training, what amount of training is necessary and sufficient, and how to obtain the best feedback in order to effect substantive program improvements. These topics will be explored and possible solutions discussed

ON-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

Energy Technology Data Exchange (ETDEWEB)

E Davis, B Rasmussen

2004-12-31

This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system.

Technical specifications for the provision of heat and steam sources for INPP and Visaginas. Final report

International Nuclear Information System (INIS)

2003-01-01

In October 1999, the National Energy Strategy was approved by the Lithuanian Parliament. The National Energy Strategy included the decision to close Unit-1 of INPP before 2005. Later is has been decided to close Unit 2 before the end of 2009 as well. The closure and decommissioning will have heavy impact on the heat supply for the city of Visaginas. Unit 1 and Unit 2 of INPP supplies hot water and steam to INPP for process purposes and for space heating of residential and commercial buildings. When Unit 1 is permanently shut down, reliable heat and steam sources independent of the power plants own heat and steam generation facilities are required for safety reasons in the event of shutdown of the remaining unit for maintenance or in an emergency. These steam and heat sources must be operational before single unit operation is envisaged. Provision of a reliable independent heat and steam source is therefore urgent. After both reactors are shut down permanently, a steam source will be needed at the plant for radioactive waste storage and disposal. INPP and DEA has performed a feasibility study for the provision of a reliable heat source for Ignalina Nuclear Power Plant and Visaginas, and the modernisation of Visaginas district heating system. The objective of this project is to prepare technical specifications for the provision of new heat and steam sources for INPP and Visaginas, and for rehabilitation of the heat transmission pipeline between INPP, the back-up boiler station and Visaginas City. The results of the study are presented in detail in the reports and technical specifications: 1. Transient analysis for Visaginas DH system, 2. Non-destructive testing of boiler stations, pump stations and transmission lines, 3. Conceptual design, 4. Technical specifications, Package 1 to 6. The study has suggested: 1. Construction of new steam boiler station, 2. Construction of new heat only boiler station, 3. Renovation of existing back-up heat only boiler station, 4

OSH technical reference manual

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

In an evaluation of the Department of Energy (DOE) Occupational Safety and Health programs for government-owned contractor-operated (GOCO) activities, the Department of Labor`s Occupational Safety and Health Administration (OSHA) recommended a technical information exchange program. The intent was to share written safety and health programs, plans, training manuals, and materials within the entire DOE community. The OSH Technical Reference (OTR) helps support the secretary`s response to the OSHA finding by providing a one-stop resource and referral for technical information that relates to safe operations and practice. It also serves as a technical information exchange tool to reference DOE-wide materials pertinent to specific safety topics and, with some modification, as a training aid. The OTR bridges the gap between general safety documents and very specific requirements documents. It is tailored to the DOE community and incorporates DOE field experience.

Technical specifications: Grand Gulf Nuclear Station, Unit No. 1. Docket No. 50-416, Appendix A to License No. NPF-13

International Nuclear Information System (INIS)

1982-06-01

Technical specifications are presented concerning safety limits; limiting safety system settings; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; site; and administrative controls

Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data.

Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

International Nuclear Information System (INIS)

Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

2010-01-01

SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

Writing a technical note.

Science.gov (United States)

Ng, K H; Peh, W C G

2010-02-01

A technical note is a short article giving a brief description of a specific development, technique or procedure, or it may describe a modification of an existing technique, procedure or device applicable to medicine. The technique, procedure or device described should have practical value and should contribute to clinical diagnosis or management. It could also present a software tool, or an experimental or computational method. Technical notes are variously referred to as technical innovations or technical developments. The main criteria for publication will be the novelty of concepts involved, the validity of the technique and its potential for clinical applications.

Using a site-specific technical error to establish training responsiveness: a preliminary explorative study.

Science.gov (United States)

Weatherwax, Ryan M; Harris, Nigel K; Kilding, Andrew E; Dalleck, Lance C

2018-01-01

Even though cardiorespiratory fitness (CRF) training elicits numerous health benefits, not all individuals have positive training responses following a structured CRF intervention. It has been suggested that the technical error (TE), a combination of biological variability and measurement error, should be used to establish specific training responsiveness criteria to gain further insight on the effectiveness of the training program. To date, most training interventions use an absolute change or a TE from previous findings, which do not take into consideration the training site and equipment used to establish training outcomes or the specific cohort being evaluated. The purpose of this investigation was to retrospectively analyze training responsiveness of two CRF training interventions using two common criteria and a site-specific TE. Sixteen men and women completed two maximal graded exercise tests and verification bouts to identify maximal oxygen consumption (VO 2 max) and establish a site-specific TE. The TE was then used to retrospectively analyze training responsiveness in comparison to commonly used criteria: percent change of >0% and >+5.6% in VO 2 max. The TE was found to be 7.7% for relative VO 2 max. χ 2 testing showed significant differences in all training criteria for each intervention and pooled data from both interventions, except between %Δ >0 and %Δ >+7.7% in one of the investigations. Training nonresponsiveness ranged from 11.5% to 34.6%. Findings from the present study support the utility of site-specific TE criterion to quantify training responsiveness. A similar methodology of establishing a site-specific and even cohort specific TE should be considered to establish when true cardiorespiratory training adaptations occur.

48 CFR 12.211 - Technical data.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Technical data. 12.211... ACQUISITION OF COMMERCIAL ITEMS Special Requirements for the Acquisition of Commercial Items 12.211 Technical data. Except as provided by agency-specific statutes, the Government shall acquire only the technical...

Technical Specifications: Clinton Power Station, Unit No. 1 (Docket No. 50-461): Appendix ''A'' to License No. NPF-62

International Nuclear Information System (INIS)

1987-04-01

The Clinton Power Station, Unit No. 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

Facilitating Site Specific and Citizens Advisory Boards: Running Effective Meetings that Involve Complex Technical Issues

International Nuclear Information System (INIS)

Freeman, J.

2009-01-01

Environmental cleanup issues at federal sites are more often than not on the agendas of meetings of the Site Specific Advisory Boards (SSABs), also called Citizens Advisory Boards (CABs), that exist at most U.S. Department of Energy (DOE) sites with an Environmental Management (EM) mission. In 1994, when Congress established these committees comprised of local citizens, it enabled community stakeholders to become more directly involved in DOE EM cleanup decisions. This involvement is to help the agency make cost-effective and environmentally sound decisions which lead to faster, safer cleanups. Eight local Boards that fall under the Federal Advisory Committee Act-chartered EM SSAB charter are found in Hanford, Washington; Idaho; Northern New Mexico; Nevada; Oak Ridge, Tennessee; Paducah, Kentucky; Portsmouth, Ohio; and at the Savannah River Site in South Carolina. These boards provide advice and recommendations about EM site-specific issues such as cleanup standards (how clean is clean?), environmental restoration, waste management, the stabilization and disposal of non-stockpile nuclear materials, future land use and long-term stewardship, risk assessment and management, and cleanup science and technology activities. These issues are, by their very nature, loaded with complicated technical terms and strategies, scientific data and interpretations, and long histories of studies and reports. The members of SSABs and CABs rotate on and off the Boards according to defined terms of office, thereby routinely opening the Boards' ranks to new members, many of whom are new to the issues. In addition, members of the public who have access to public comment periods at each Board meeting run up against the same daunting menu of obscure acronyms, scientific terms and notations, and an historical trail which is not always evident except to those involved with the issues over many years. How does a facilitator effectively guide such a group of citizens, each of whom arrives to

[Formulation of technical specification for national survey of Chinese materia medica resources].

Science.gov (United States)

Guo, Lan-Ping; Lu, Jian-Wei; Zhang, Xiao-Bo; Zhao, Run-Huai; Zhang, Ben-Gang; Sun, Li-Ying; Huang, Lu-Qi

2013-04-01

According to the process of the technical specification (TS) design for the fourth national survey of the Chinese materia medica resources (CMMR), we analyzed the assignment and objectives of the national survey and pointed out that the differences about CMMR management around China, the distribution of CMMR and their habitat, the economic and technological level, and even enthusiasm and initiative of the staff, etc. are the most difficult points for TS design. And we adopt the principle of combination of the mandatory and flexibility in TS design. We fixed the key points which would affect the quality of national survey first, then proposed the framework of TS which including 3 parts of organization and 11 parts of technique itself. The framework will serve and lead the TS preparation, which will not only provide an action standard to the national survey but will also have a profound influence to the popularization and application of the survey technology of CMMR. [Key words

Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 2 (Docket No. 50-529). Appendix A to License No. NPF-51

International Nuclear Information System (INIS)

1986-04-01

Information is presented concerning the technical specifications for the Palo Verde-2 Reactor. Areas of interest discussed in this report include: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls. 19 figs., 62 tabs

Heat transfer calculations for the High Flux Isotope Reactor (HFIR). Technical specifications: bases for safety limits and limiting safety system settings

International Nuclear Information System (INIS)

Sims, T.M.; Swanks, J.H.

1977-09-01

Heat transfer analyses, in support of the preparation of the HFIR technical specifications, were made to establish the bases for the safety limits and limiting safety system settings applicable to the HFIR. The results of these analyses, along with the detailed bases, are presented

Crew Transportation Technical Standards and Design Evaluation Criteria

Science.gov (United States)

Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

2015-01-01

Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

Radiation Dose Effects into LCO in Technical Specification by Iodine in Hanul units 1,2

Energy Technology Data Exchange (ETDEWEB)

Lee, Hye Min; Lee, Seung Chan [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-05-15

This study estimates the impact of the 1-th coolant system in NPP to the LCO (Limiting Condition of Operation) limits which is in the site boundary. Dose limit is merged into the effective dose from whole body and thyroid dose limits, that is possible to combine the two LCOs to a unified LCO. To estimate the limits, the radiation dose of one of the designed accidents should be chosen to check the radiation dose response. The selected accident is based on Seung Chan Lee's study at KHNP in 2011. Using the selected accident, Iodine dose effect is reviewed depending on the LCO limiting responsibility and the specific behavior. In order to evaluate the radiation dose effect in Technical Specification of Hanul 1,2, SGTR is selected for some sensitivity analysis. From the results, in Hanul site, the case of LOOP plus ADV plus GIS is the most severe case and the dose limit margin is about 110% in LCO.

WHO Working Group on Technical Specifications for Manufacture and Evaluation of Yellow Fever Vaccines, Geneva, Switzerland, 13-14 May 2009.

Science.gov (United States)

Ferguson, Morag; Shin, Jinho; Knezevic, Ivana; Minor, Philip; Barrett, Alan

2010-12-06

In May 2009, WHO convened a meeting of Working Group on Technical Specifications for Manufacturing and Evaluating Yellow Fever (YF) Vaccines, Geneva, Switzerland to initiate revision of the WHO Recommendations (formerly, Requirements) for YF vaccine published in WHO Technical Report Series number 872 (1998). The Working Group, consisting of experts from academia, industry, national regulatory authorities and national control laboratories, reviewed the latest issues of safety, efficacy and quality of YF vaccines and agreed that (i) the revision should focus on live attenuated YF vaccine virus 17D lineage; and that (ii) nonclinical and clinical guidelines for new vaccines prepared from 17D lineage be developed. Copyright © 2010. Published by Elsevier Ltd.. All rights reserved.

Technical specifications: Susquehanna Steam Electric Station, Unit No. 2 (Docket No. 50-388). Appendix A to License No. NPF-22

International Nuclear Information System (INIS)

1984-03-01

Susquehanna Steam Electric Station, Unit 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical specifications for Grand Gulf Nuclear Station, Unit 1 (Docket No. 50-416). Appendix A to License No. NPF-13

International Nuclear Information System (INIS)

1984-08-01

The Grand Gulf Nuclear Station, Unit 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR part 50 for the protection of the health and safety of the public

Apollo decommissioning project, Apollo, Pennsylvania. Final technical report

International Nuclear Information System (INIS)

1997-01-01

In November, 1991 Babcock and Wilcox (B and W) received a grant to partially fund the decommissioning of the former Apollo Nuclear Fuel Facility. The decommissioning was performed in accordance with a Nuclear Regulatory Commission (NRC) approved decommissioning plan. This report summarizes the decommissioning of the Apollo Nuclear Fuel Facility and the radiological surveying of the site to demonstrate that these decommissioning activities were effective in reducing residual activity well below NRC's criteria for release for unrestricted use. The Apollo Nuclear Fuel Facility was utilized by the Nuclear Materials and Equipment Corporation (NUMEC) and B and W for nuclear research and production under Atomic Energy Commission and Department of Energy (DOE) contracts during 20 plus years of nuclear fuel manufacturing operations

Nuclear technology. All in good hands

International Nuclear Information System (INIS)

Mueller, Michaela

2011-01-01

Babcock Noell GmbH (BNG) has more than 40 years of practical experience and fundamental know-how in the field of nuclear technology and thus is well equipped to meet future challenges. This applies to building new nuclear power plants, upgrading and decommissioning existing facilities as well as to conditioning and storage of radioactive waste. BNG is a supplier of, among other things, components for machine technology, personnel and materials transfer locks, safety enclosures and pool liners. Outstanding, technically demanding reference projects have demonstrated BNG's capabilities. BNG is a reliable service and assembly partner to the operators of nuclear power plants and nuclear facilities. This sector of activities has as its backbone a separate team of experienced service and assembly personnel. The synergies of engineering and service competence intensively utilized by Babcock Noell GmbH are employed, inter alia, in the development and advanced development, respectively, of nuclear technology products fit for practical use, such as personnel and materials transfer locks. (orig.)

Technical Specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-76

International Nuclear Information System (INIS)

1988-03-01

The South Texas Project, Unit No. 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public. This report is Appendix A to License No. NPF-76

Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

Directory of Open Access Journals (Sweden)

Tolkachev E.N.

2017-03-01

Full Text Available The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

OpenAIRE

Tolkachev E.N.

2017-01-01

The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

International Nuclear Information System (INIS)

Anderson, F.D.

1984-06-01

Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

Technical resource documents and technical handbooks for hazardous-wastes management

Energy Technology Data Exchange (ETDEWEB)

Schomaker, N.B.; Bliss, T.M.

1986-07-01

The Environmental Protection Agency is preparing a series of Technical Resource Documents (TRD's) and Technical Handbooks to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) respectively. These documents and handbooks are basically compilation of research efforts of the Land Pollution Control Division (LPCD) to date. The specific areas of research being conducted under the RCRA land disposal program relate to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The technical handbooks provide the EPA Program Offices and Regions, as well as the states and other interested parties, with the latest information relevant to remedial actions.

Technical specifications, Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322): Appendix ''A'' to License No. NPF-82

International Nuclear Information System (INIS)

1989-04-01

The Shoreham, Unit 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 20 figs., 75 tabs

48 CFR 227.7102-2 - Rights in technical data.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Rights in technical data... Technical Data 227.7102-2 Rights in technical data. (a) The clause at 252.227-7015, Technical Data—Commercial Items, provides the Government specific license rights in technical data pertaining to commercial...

Mechanical Engineering Department Technical Review

International Nuclear Information System (INIS)

Carr, R.B.; Denney, R.M.

1981-01-01

The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication

Reviewing PSA-based analyses to modify technical specifications at nuclear power plants

International Nuclear Information System (INIS)

Samanta, P.K.; Martinez-Guridi, G.; Vesely, W.E.

1995-12-01

Changes to Technical Specifications (TSs) at nuclear power plants (NPPs) require review and approval by the United States Nuclear Regulatory Commission (USNRC). Currently, many requests for changes to TSs use analyses that are based on a plant's probabilistic safety assessment (PSA). This report presents an approach to reviewing such PSA-based submittals for changes to TSs. We discuss the basic objectives of reviewing a PSA-based submittal to modify NPP TSs; the methodology of reviewing a TS submittal, and the differing roles of a PSA review, a PSA Computer Code review, and a review of a TS submittal. To illustrate this approach, we discuss our review of changes to allowed outage time (AOT) and surveillance test interval (STI) in the TS for the South Texas Project Nuclear Generating Station. Based on this experience gained, a check-list of items is given for future reviewers; it can be used to verify that the submittal contains sufficient information, and also that the review has addressed the relevant issues. Finally, recommended steps in the review process and the expected findings of each step are discussed

PSA-based optimization of technical specifications for the Borssele nuclear power plant

International Nuclear Information System (INIS)

Seebregts, A.J.; Schoonakker, H.A.

1996-01-01

The Borssele Nuclear Power Plant (NPP) is a Siemens/KWU 472 MWe Pressurized Water Reactor which has been in operation since 1973. In 1989, a Probabilistic Safety Assessment (PSA) program was initiated to complement deterministic safety studies and operational experience in forming a plant safety concept. In 1993, the PSA-MER model was completed and used to determine the effects a package of proposed modifications would have on plant safety and risks to the environment. This model was used to start retrospective risks profile and allowed outage times (AOTs) analyses, which both concerned the calculation of the change in total core damage frequency (TCDF) given a change in configuration. The main problems identified and reported in this paper are: (i) How to calculate the change in TCDF (ΔTCDF)? (section 3); and (ii) How to set practical decision criteria and how to use the PSA as extension to Technical Specifications (TS) AOTs? (section 4). Finally, a pilot study was conducted in order to optimize surveillance test intervals (STIs) which are also part of the TS (section 5). (orig.)

Babcock and Wilcox model for predicting in-reactor densification

International Nuclear Information System (INIS)

Buescher, B.J.; Pegram, J.W.

1975-06-01

The B and W fuel densification model is used to describe the extent and kinetics of in-reactor densification in B and W production fuel. The model and approach are qualified against an extensive data base available through B and W's participation in the EEI Fuel Densification Program. Out-of-reactor resintering tests on representative pellets from each batch of fuel are used to provide input parameters to the B and W densification model. The B and W densification model predicts in-reactor densification very accurately for pellets operated at heat rates above 5 kW/ft and with considerable conservation for pellets operated at heat rates less than 5 kW/ft. This model represents a technically rigorous and conservative basis for predicting the extent and kinetics of in-reactor densification. 9 references. (U.S.)

ITER co-ordinated technical activities

International Nuclear Information System (INIS)

2001-01-01

As agreed upon between the ITER Engineering Design Activities (EDA) Parties 'Co-ordinated Technical Activities' (CTA) means technical activities which are deemed necessary to maintain the integrity of the international project, so as to prepare for the ITER joint implementation. The scope of these activities includes design adaptation to the specific site conditions, safety analysis and licensing preparation that are based on specific site offers, evaluation of cost and construction schedule, preparation of procurement documents and other issues raised by the Parties collectively, whilst assuring the coherence of the ITER project including design control

Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 1 (Docket No. 50-528). Appendix A to License No. NPF-34

International Nuclear Information System (INIS)

1984-12-01

Technical specifications are presented concerning operating safety limits for reactivity control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring; design features of the reactor site, containment, reactor core, coolant system, and fuel storage; and administrative controls

Technical Specification action statements requiring shutdown. A risk perspective with application to the RHR/SSW systems of a BWR

Energy Technology Data Exchange (ETDEWEB)

Mankamo, T. [Avaplan Oy, Espoo (Finland); Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States)

1993-11-01

When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements.

Non-technical skills in histopathology: definition and discussion.

Science.gov (United States)

Johnston, Peter W; Fioratou, Evie; Flin, Rhona

2011-09-01

Health care is a high-risk industry, with most documented adverse incidents being associated with 'human factors' including cognitive and social skills termed 'non-technical skills'. Non-technical skills complement the diagnostic and specialist skills and professional attributes required by medical practitioners, including histopathologists, and can enhance the quality of practice and delivery of health-care services and thus contribute to patient safety. This review aims to introduce histopathologists to non-technical skills and how these pertain to everyday histopathological practice. Drawing from other domains in medicine, specifically anaesthesia and surgery, a variety of non-technical skills are identified and described in the context of histopathology to illustrate the role each plays, often collectively, in daily practice. The generic non-technical skills are defined as situation awareness, decision-making, communication, teamwork, leadership, managing stress and coping with fatigue. Example scenarios from histopathology are presented and the contributions to outcomes made by non-technical skills are explained. Consideration of these specific non-technical skills as a component in histopathology training may benefit practitioners as well as assuring patient safety. © 2011 Blackwell Publishing Limited.

Map Specifications and Exchange of Geographical Information

DEFF Research Database (Denmark)

Frederiksen, Poul

1999-01-01

Specifications for Technical Maps 1993 – 99 are described giving an overview of the specification structure including the object description of the latest version: TK99.The technical map specifications are related to the standards for topographical maps - especially the TOP10DK standard. Common...... object definitions are essential for the standards. Technical as well as topographical map information is exchangeable through the Danish developed “Standard for Exchange of Digital Map Information”, known as the DSFL-format....

Risk-based evaluation of technical specification problems at the La Salle County Nuclear Station: Final report

International Nuclear Information System (INIS)

Bizzak, D.J.; Trainer, J.E.; McClymont, A.S.

1987-06-01

Probabilistic risk assessment (PRA) methods are used to evaluate alternatives to existing requirements for three operationally burdensome technical specifications at La Salle Nuclear Station. The study employs a decision logic to minimize the detailed analysis necessary to show compliance with given acceptance criteria; in this case, no risk increase resulting from a proposed change. The analyses provide insights to choose from among alternative options. The SOCRATES computer code was used for the probabilistic analysis. Results support a change to less frequent diesel generator testing, eliminations of one reactor scram setpoint, and establishing an allowed out-of-service time for valves in a reactor scram system. In each case, the change would result in a safety improvement

Comparing effectiveness and efficiency in technical specifications and maintenance optimization

International Nuclear Information System (INIS)

Martorell, Sebastian; Sanchez, Ana; Carlos, Sofia; Serradell, Vicente

2002-01-01

Optimization of technical specification requirements and maintenance (TS and M) has been found interesting from the very beginning at Nuclear Power Plants (NPPs). However, the resolution of such a kind of optimization problem has been limited often to focus only on individual TS and M-related parameters (STI, AOT, PM frequency, etc.) and/or adopting an individual optimization criterion (availability, costs, plant risks, etc.). Nevertheless, a number of reasons exist (e.g. interaction, similar scope, etc.) that justify the interest to focus on the coordinated optimization of all of the relevant TS and M-related parameters based on multiple criteria. The purpose of this paper is on signifying benefits and improvement areas in performing the coordinated optimization of TS and M through reviewing the effectiveness and efficiency of common strategies for optimizing TS and M at system level. A case of application is provided for a stand-by safety-related system to demonstrate the basic procedure and to extract a number of conclusions and recommendations from the results achieved. Thus, it is concluded that the optimized values depend on the particular TS and M-related parameters being involved and the solutions with the largest benefit (minimum risk or minimum cost) are achieved when considering the simultaneous optimization of all of them, although increased computational resources are also required. Consequently, it is necessary to analyze not only the value reached but also the performance of the optimization procedure through effectiveness and efficiency measures which lead to recommendations on potential improvement areas

Technical specifications for monitoring Community trends in zoonotic agents in foodstuffs and animal populations on request from EFSA

DEFF Research Database (Denmark)

Borck Høg, Birgitte; Chriél, Mariann; Korsgaard, Helle

of criteria for the selection of the zoonotic agent/animal or food category combinations where trend analyses would be justified. Based on data available from 2004 to 2007, the following combinations are suggested for trend analyses: Salmonella in fresh broiler and pig meat, flocks of laying hens and broilers......Technical specifications are proposed for the monitoring of temporal trends in zoonotic agents in animal and food populations at Community or Member State group level in the framework of Directive 2003/99/EC. Two types of trend monitoring are identified: trend watching, which covers general...

Technical specification for design, fabrication, use and maintenance of tie-down system

International Nuclear Information System (INIS)

Curcuruto, S.; Palmieri, G.; Trivelloni, S.; Orsini, A.

1993-01-01

IAEA Safety Series ndeg6 states that to ensure compliance with the Regulation the programs of quality assurance must be put in practice either for design, manufacture, testing, documentation, use and maintenance and inspection of all packages or for transport and intransit storage operations. Therefore in view of a standardization coming from Q.A. criteria, the Italian Competent Authority for transport of radioactive material (ENEA-DISP) is preparing a technical guide for the design, construction, use and maintenance of tie-down system for road transport of packages containing radioactive materials. The paper shows some phases of the program started by ENEA-DISP for the redaction of the technical guide. (J.P.N.)

How to be an Effective Technical Writer?

Directory of Open Access Journals (Sweden)

M Solaiman Ali

2012-07-01

Full Text Available Abstract--This paper has focused on technical writing as a skill for engineers. It has sought to define technical writing and throw light on the content and technique of writing the various components of successful technical reports (for example, articles, papers, or research reports, such as theses and dissertations. Then, it has highlighted other special features and principles of effective technical writing. The material in this paper is divided into seven major parts. Part 1 (Technical writing for engineers stresses that a successful engineering career requires strong writing skills. Part 2 (How to write the major sections or elements of a report describes the techniques of writing the abstract, introduction, literature review, procedure/methods & materials, results, discussion, conclusion, and recommendations. Part 3 (Special features of technical writing brings into focus some of the special features of technical writing such as tables & graphs in the text, graphics in instructions, team writing, ethics (plagiarism, document sources, three citation styles and IEEE reference style. Part 4 (Technical usage deals with writing abbreviations, initialisms and acronyms, numbers, units of measurement, and equations.Part 5 (Technical style highlights the imperative writing style and other features of technical writing such as the use of active and passive voices, plain vs. complex syntax, avoiding redundant or superfluous expressions, and vague generalities, using words or expressions with visual impact, the past tense to describe experimental work, the present tense to describe hypotheses, principles, theories and truths, and breaking up the text of the report into short sections. Part 6 (Document specifications emphasizes the technical writer’s need to conform to such document specifications as word count, format, font, number of words per line of text imposed. Part 7 (Reader-friendly technical writing suggests choosing the varied writing modes

Urology technical and non-technical skills development: the emerging role of simulation.

Science.gov (United States)

Rashid, Prem; Gianduzzo, Troy R J

2016-04-01

To review the emerging role of technical and non-technical simulation in urological education and training. A review was conducted to examine the current role of simulation in urology training. A PUBMED search of the terms 'urology training', 'urology simulation' and 'urology education' revealed 11,504 titles. Three hundred and fifty-seven abstracts were identified as English language, peer reviewed papers pertaining to the role of simulation in urology and related topics. Key papers were used to explore themes. Some cross-referenced papers were also included. There is an ongoing need to ensure that training time is efficiently utilised while ensuring that optimal technical and non-technical skills are achieved. Changing working conditions and the need to minimise patient harm by inadvertent errors must be taken into account. Simulation models for specific technical aspects have been the mainstay of graduated step-wise low and high fidelity training. Whole scenario environments as well as non-technical aspects can be slowly incorporated into the curriculum. Doing so should also help define what have been challenging competencies to teach and evaluate. Dedicated time, resources and trainer up-skilling are important. Concurrent studies are needed to help evaluate the effectiveness of introducing step-wise simulation for technical and non-technical competencies. Simulation based learning remains the best avenue of progressing surgical education. Technical and non-technical simulation could be used in the selection process. There are good economic, logistic and safety reasons to pursue the process of ongoing development of simulation co-curricula. While the role of simulation is assured, its progress will depend on a structured program that takes advantage of what can be delivered via this medium. Overall, simulation can be developed further for urological training programs to encompass technical and non-technical skill development at all stages, including

Technical writing versus technical writing

Science.gov (United States)

Dillingham, J. W.

1981-01-01

Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

Yucca Mountain Site Characterization Project Technical Data Catalog

International Nuclear Information System (INIS)

1992-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear, Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

Yucca Mountain Site Characterization Project technical data catalog

International Nuclear Information System (INIS)

1992-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

Technical normalization in the geoinformatics branch

Directory of Open Access Journals (Sweden)

Bronislava Horáková

2006-09-01

Full Text Available A basic principle of the technical normalisation is to hold the market development by developing unified technical rules for all concerned subjects. The information and communication technological industry is characterised by certain specific features contrary to the traditional industry. These features bring to the normalisation domain new demands, mainly the flexibility enabling to reflect the rapidly development market of ICT elastic way. The goal of the paper is to provide a comprehensive overview of the current process of technical normalization in the geoinformatic branch

Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

International Nuclear Information System (INIS)

Kim, I.S.; Samanta, P.K.

1994-01-01

When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require ''immediate'' shutdown of the plant. In this paper, the authors present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion

Improving the action requirements of technical specifications: A risk-comparison of continued operation and plant shutdown

Energy Technology Data Exchange (ETDEWEB)

Kim, I.S.; Samanta, P.K. [Brookhaven National Lab., Upton, NY (United States); Mankamo, T.

1995-04-01

When the systems needed to remove decay heat are inoperable or degraded, the risk of shutting down the plant may be comparable to, or even higher than, that of continuing power operation with the equipment inoperable while giving priority to repairs. This concern arises because the plant may not have sufficient capability for removing decay heat during the shutdown. However, Technical Specifications (TSs) often require {open_quotes}immediate{close_quotes} shutdown of the plant. In this paper, we present risk-based analyses of the various operational policy alternatives available in such situations, with an example application to the standby service water (SSW) system of a BWR. These analyses can be used to define risk-effective requirements for those standby safety systems under discussion.

Herd-specific interventions to reduce antimicrobial usage in pig production without jeopardising technical and economic performance.

Science.gov (United States)

Collineau, L; Rojo-Gimeno, C; Léger, A; Backhans, A; Loesken, S; Nielsen, E Okholm; Postma, M; Emanuelson, U; Beilage, E Grosse; Sjölund, M; Wauters, E; Stärk, K D C; Dewulf, J; Belloc, C; Krebs, S

2017-09-01

Pig farmers are strongly encouraged to reduce their antimicrobial usage in order to reduce the risk of antimicrobial resistance. Herd-level intervention is needed to achieve national and European reduction targets. Alternative, especially preventive measures, have to be implemented to reduce the need for antimicrobial treatments. However, little is known about the feasibility, effectiveness and return on investment of such measures. The objective of this study was to assess, across four countries, the technical and economic impact of herd-specific interventions aiming at reducing antimicrobial usage in pig production while implementing alternative measures. An intervention study was conducted between February 2014 and August 2015 in 70 farrow-to-finish pig farms located in Belgium, France, Germany and Sweden. Herd-specific interventions were defined together with the farmer and the herd veterinarian. Farms were followed over one year and their antimicrobial usage and technical performance were compared with values from the year before intervention. Compliance with the intervention plan was also monitored. Changes in margin over feed cost and net farm profit were estimated in a subset of 33 Belgian and French farms with sufficient data, using deterministic and stochastic modeling. Following interventions, a substantial reduction in antimicrobial use was achieved without negative impact the overall farm technical performance. A median reduction of 47.0% of antimicrobial usage was achieved across four countries when expressed in terms of treatment incidence from birth to slaughter, corresponding to a 30.5% median reduction of antimicrobial expenditures. Farm compliance with intervention plans was high (median: 93%; min-max: 20; 100) and farms with higher compliance tended to achieve bigger reduction (ρ=-0.18, p=0.162). No association was found between achieved reduction and type or number of alternative measures implemented. Mortality in suckling piglets, weaners and

CT-guided Bipolar and Multipolar Radiofrequency Ablation (RF Ablation) of Renal Cell Carcinoma: Specific Technical Aspects and Clinical Results

Energy Technology Data Exchange (ETDEWEB)

Sommer, C. M., E-mail: christof.sommer@med.uni-heidelberg.de [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Lemm, G.; Hohenstein, E. [Minimally Invasive Therapies and Nuclear Medicine, SLK Kliniken Heilbronn GmbH, Clinic for Radiology (Germany); Bellemann, N.; Stampfl, U. [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Goezen, A. S.; Rassweiler, J. [Clinic for Urology, SLK Kliniken Heilbronn GmbH (Germany); Kauczor, H. U.; Radeleff, B. A. [University Hospital Heidelberg, INF 110, Department of Diagnostic and Interventional Radiology (Germany); Pereira, P. L. [Minimally Invasive Therapies and Nuclear Medicine, SLK Kliniken Heilbronn GmbH, Clinic for Radiology (Germany)

2013-06-15

Purpose. This study was designed to evaluate the clinical efficacy of CT-guided bipolar and multipolar radiofrequency ablation (RF ablation) of renal cell carcinoma (RCC) and to analyze specific technical aspects between both technologies. Methods. We included 22 consecutive patients (3 women; age 74.2 {+-} 8.6 years) after 28 CT-guided bipolar or multipolar RF ablations of 28 RCCs (diameter 2.5 {+-} 0.8 cm). Procedures were performed with a commercially available RF system (Celon AG Olympus, Berlin, Germany). Technical aspects of RF ablation procedures (ablation mode [bipolar or multipolar], number of applicators and ablation cycles, overall ablation time and deployed energy, and technical success rate) were analyzed. Clinical results (local recurrence-free survival and local tumor control rate, renal function [glomerular filtration rate (GFR)]) and complication rates were evaluated. Results. Bipolar RF ablation was performed in 12 procedures and multipolar RF ablation in 16 procedures (2 applicators in 14 procedures and 3 applicators in 2 procedures). One ablation cycle was performed in 15 procedures and two ablation cycles in 13 procedures. Overall ablation time and deployed energy were 35.0 {+-} 13.6 min and 43.7 {+-} 17.9 kJ. Technical success rate was 100 %. Major and minor complication rates were 4 and 14 %. At an imaging follow-up of 15.2 {+-} 8.8 months, local recurrence-free survival was 14.4 {+-} 8.8 months and local tumor control rate was 93 %. GFR did not deteriorate after RF ablation (50.8 {+-} 16.6 ml/min/1.73 m{sup 2} before RF ablation vs. 47.2 {+-} 11.9 ml/min/1.73 m{sup 2} after RF ablation; not significant). Conclusions. CT-guided bipolar and multipolar RF ablation of RCC has a high rate of clinical success and low complication rates. At short-term follow-up, clinical efficacy is high without deterioration of the renal function.

Decomposing productivity growth allowing efficiency gains and price-induced technical progress

NARCIS (Netherlands)

Oude Lansink, A.G.J.M.; Silva, E.; Stefanou, S.

2000-01-01

Time- and firm-specific output technical efficiency measures are generated within a price-induced technological change framework. The firm-specific production frontier incorporates past prices as an argument encouraging innovation and a time trend to account for exogenous technical change. The

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-08-10

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre

TECHNICAL RISK RATING OF DOE ENVIRONMENTAL PROJECTS - 9153

International Nuclear Information System (INIS)

Cercy, M.; Fayfich, Ronald; Schneider, Steven P.

2008-01-01

The U.S. Department of Energy's Office of Environmental Management (DOE-EM) was established to achieve the safe and compliant disposition of legacy wastes and facilities from defense nuclear applications. The scope of work is diverse, with projects ranging from single acquisitions to collections of projects and operations that span several decades and costs from hundreds of millions to billions US$. The need to be able to manage and understand the technical risks from the project to senior management level has been recognized as an enabler to successfully completing the mission. In 2008, DOE-EM developed the Technical Risk Rating as a new method to assist in managing technical risk based on specific criteria. The Technical Risk Rating, and the criteria used to determine the rating, provides a mechanism to foster open, meaningful communication between the Federal Project Directors and DOE-EM management concerning project technical risks. Four indicators (technical maturity, risk urgency, handling difficulty and resolution path) are used to focus attention on the issues and key aspects related to the risks. Pressing risk issues are brought to the forefront, keeping DOE-EM management informed and engaged such that they fully understand risk impact. Use of the Technical Risk Rating and criteria during reviews provides the Federal Project Directors the opportunity to openly discuss the most significant risks and assists in the management of technical risks across the portfolio of DOE-EM projects. Technical Risk Ratings can be applied to all projects in government and private industry. This paper will present the methodology and criteria for Technical Risk Ratings, and provide specific examples from DOE-EM projects

Simulation-based ureteroscopy skills training curriculum with integration of technical and non-technical skills: a randomised controlled trial.

Science.gov (United States)

Brunckhorst, Oliver; Shahid, Shahab; Aydin, Abdullatif; McIlhenny, Craig; Khan, Shahid; Raza, Syed Johar; Sahai, Arun; Brewin, James; Bello, Fernando; Kneebone, Roger; Khan, Muhammad Shamim; Dasgupta, Prokar; Ahmed, Kamran

2015-09-01

Current training modalities within ureteroscopy have been extensively validated and must now be integrated within a comprehensive curriculum. Additionally, non-technical skills often cause surgical error and little research has been conducted to combine this with technical skills teaching. This study therefore aimed to develop and validate a curriculum for semi-rigid ureteroscopy, integrating both technical and non-technical skills teaching within the programme. Delphi methodology was utilised for curriculum development and content validation, with a randomised trial then conducted (n = 32) for curriculum evaluation. The developed curriculum consisted of four modules; initially developing basic technical skills and subsequently integrating non-technical skills teaching. Sixteen participants underwent the simulation-based curriculum and were subsequently assessed, together with the control cohort (n = 16) within a full immersion environment. Both technical (Time to completion, OSATS and a task specific checklist) and non-technical (NOTSS) outcome measures were recorded with parametric and non-parametric analyses used depending on the distribution of our data as evaluated by a Shapiro-Wilk test. Improvements within the intervention cohort demonstrated educational value across all technical and non-technical parameters recorded, including time to completion (p technical and non-technical skills teaching is both educationally valuable and feasible. Additionally, the curriculum offers a validated simulation-based training modality within ureteroscopy and a framework for the development of other simulation-based programmes.

The development of technical literature for the specification of fume extraction systems

Energy Technology Data Exchange (ETDEWEB)

Gibbons, A [Plastic Fabrications and Environmental Technology Ltd., Armagh (United Kingdom)

1996-12-31

The processes involved in producing technical literature to assist in the selection of fans are discussed. Desktop publishing has been found to provide an effective method of matching the detail of the literature to the needs of the customer. (author)

Resolution 127/012. It approve the fuel quality 50-S Oil Gas characteristics within the framework of Technical Quality Specifications Rules for liquid fuel

International Nuclear Information System (INIS)

2012-01-01

This resolution approves the initiative of Ancap fuel quality 50-S Oil Gas characteristics within the framework of Technical Quality Specifications Rules for liquid fuel. This resolution is according to the opinion of the National Energy Regulatory Unit and the Energy and Water Services in relation with the requirements of the current rule.

Career and Technical Education Administration: Requirements, Certification/Licensure, and Preparation

Science.gov (United States)

Zirkle, Christopher J.; Jeffery, Jeremy O.

2017-01-01

The current climate of career and technical administration requirements in all 50 states was detailed and explored. An increasing number of states are not requiring specific career-technical administration certification/licensure in order to oversee secondary career and technical education (CTE) programs, with more states moving towards a general…

The general technical regulation and the standardization

International Nuclear Information System (INIS)

Laverie, Michel; Houze, Christian; Lebouleux, Philippe

1980-01-01

Through a certain number of procedures, the thorough appreciation of the safety of a nuclear installation relies more on a specific appreciation taking into account the references as a whole, than on a technical regulation which claims to cover all the problems. Nevertheless, a French technical regulation structure regarding the safety domain must be built up progressively. The authors consider the principles of such a structure, and together they make the inventory of the works, finished, in progress or contemplated. The description of this specifically French approach emphazises the multiple and complementary forms given to statutory implements [fr

CT-guided Bipolar and Multipolar Radiofrequency Ablation (RF Ablation) of Renal Cell Carcinoma: Specific Technical Aspects and Clinical Results

International Nuclear Information System (INIS)

Sommer, C. M.; Lemm, G.; Hohenstein, E.; Bellemann, N.; Stampfl, U.; Goezen, A. S.; Rassweiler, J.; Kauczor, H. U.; Radeleff, B. A.; Pereira, P. L.

2013-01-01

Purpose. This study was designed to evaluate the clinical efficacy of CT-guided bipolar and multipolar radiofrequency ablation (RF ablation) of renal cell carcinoma (RCC) and to analyze specific technical aspects between both technologies. Methods. We included 22 consecutive patients (3 women; age 74.2 ± 8.6 years) after 28 CT-guided bipolar or multipolar RF ablations of 28 RCCs (diameter 2.5 ± 0.8 cm). Procedures were performed with a commercially available RF system (Celon AG Olympus, Berlin, Germany). Technical aspects of RF ablation procedures (ablation mode [bipolar or multipolar], number of applicators and ablation cycles, overall ablation time and deployed energy, and technical success rate) were analyzed. Clinical results (local recurrence-free survival and local tumor control rate, renal function [glomerular filtration rate (GFR)]) and complication rates were evaluated. Results. Bipolar RF ablation was performed in 12 procedures and multipolar RF ablation in 16 procedures (2 applicators in 14 procedures and 3 applicators in 2 procedures). One ablation cycle was performed in 15 procedures and two ablation cycles in 13 procedures. Overall ablation time and deployed energy were 35.0 ± 13.6 min and 43.7 ± 17.9 kJ. Technical success rate was 100 %. Major and minor complication rates were 4 and 14 %. At an imaging follow-up of 15.2 ± 8.8 months, local recurrence-free survival was 14.4 ± 8.8 months and local tumor control rate was 93 %. GFR did not deteriorate after RF ablation (50.8 ± 16.6 ml/min/1.73 m 2 before RF ablation vs. 47.2 ± 11.9 ml/min/1.73 m 2 after RF ablation; not significant). Conclusions. CT-guided bipolar and multipolar RF ablation of RCC has a high rate of clinical success and low complication rates. At short-term follow-up, clinical efficacy is high without deterioration of the renal function.

77 FR 284 - Change in Bank Control Notices; Acquisitions of Shares of a Bank or Bank Holding Company

Science.gov (United States)

2012-01-04

... Affairs Officer) 90 Hennepin Avenue, Minneapolis, Minnesota 55480-0291: 1. Gladys E. Youse Trust and.... Additionally, The Gladys E. Youse Trust, and its trustee, Madolyn Y. Babcock, propose to join the Babcock...

Instrument and Survey Analysis Technical Report: Program Implementation Survey. Technical Report #1112

Science.gov (United States)

Alonzo, Julie; Tindal, Gerald

2011-01-01

This technical document provides guidance to educators on the creation and interpretation of survey instruments, particularly as they relate to an analysis of program implementation. Illustrative examples are drawn from a survey of educators related to the use of the easyCBM learning system. This document includes specific sections on…

Technical Support Document for Version 3.6.1 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2009-09-29

This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards.

Human research ethics committees in technical universities.

Science.gov (United States)

Koepsell, David; Brinkman, Willem-Paul; Pont, Sylvia

2014-07-01

Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although mandated in the United States, the United Kingdom, Canada, and Australia, non-medical research involving humans need not receive ethics review in much of Europe, Asia, Latin America, and Africa. Our survey of the top 50 technical universities in the world shows that, where not specifically mandated by law, most technical universities do not employ ethics committees to review human studies. As the domains of basic and applied sciences expand, ethics committees are increasingly needed to guide and oversee all such research regardless of legal requirements. We offer as examples, from our experience as an ethics committee in a major European technical university, ways in which such a committee provides needed services and can help ensure more ethical studies involving humans outside the standard medical context. We provide some arguments for creating such committees, and in our supplemental article, we provide specific examples of cases and concerns that may confront technical, engineering, and design research, as well as outline the general framework we have used in creating our committee. © The Author(s) 2014.

The role of non-technical skills in surgery.

Science.gov (United States)

Agha, Riaz A; Fowler, Alexander J; Sevdalis, Nick

2015-12-01

Non-technical skills are of increasing importance in surgery and surgical training. A traditional focus on technical skills acquisition and competence is no longer enough for the delivery of a modern, safe surgical practice. This review discusses the importance of non-technical skills and the values that underpin successful modern surgical practice. This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

The role of non-technical skills in surgery

Science.gov (United States)

Agha, Riaz A.; Fowler, Alexander J.; Sevdalis, Nick

2015-01-01

Non-technical skills are of increasing importance in surgery and surgical training. A traditional focus on technical skills acquisition and competence is no longer enough for the delivery of a modern, safe surgical practice. This review discusses the importance of non-technical skills and the values that underpin successful modern surgical practice. This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care. PMID:26904193

Hanford Site technical baseline database. Revision 1

International Nuclear Information System (INIS)

Porter, P.E.

1995-01-01

This report lists the Hanford specific files (Table 1) that make up the Hanford Site Technical Baseline Database. Table 2 includes the delta files that delineate the differences between this revision and revision 0 of the Hanford Site Technical Baseline Database. This information is being managed and maintained on the Hanford RDD-100 System, which uses the capabilities of RDD-100, a systems engineering software system of Ascent Logic Corporation (ALC). This revision of the Hanford Site Technical Baseline Database uses RDD-100 version 3.0.2.2 (see Table 3). Directories reflect those controlled by the Hanford RDD-100 System Administrator. Table 4 provides information regarding the platform. A cassette tape containing the Hanford Site Technical Baseline Database is available

Evaluation of safety implications of control systems in LWR nuclear power plants

International Nuclear Information System (INIS)

Szukiewicz, A.J.

1989-06-01

An in-depth evaluation was performed on non-safety-related control systems (see Section 1) that are typically used during normal plant operation on four nuclear steam supply system plants: a General Electric Company boiling-water reactor, a Westinghouse 3-loop pressurized-water reactor (PWR), a Babcock ampersand Wilcox Co. (B ampersand W) once-through steam generator PWR, and a Combustion Engineering PWR design. A study was also conducted to determine the generic applicability of the results to the class of plants represented by the specific plants analyzed. Generic conclusions were then developed. Steam generator and reactor vessel overfill events and reactor vessel overcooling events were identified as major classes of events having the potential to be more severe than previously analyzed. Specific substasks of this issue were to study these events to determine the need for preventive and/or mitigating design measures. This report describes the technical studies performed by the laboratories, the NRC staff assessment of the results, the generic applicability of the evaluations, and the technical findings resulting from these studies. This final report contains the staff's responses to, and resolution of, the public comments that were solicited and received before September 16,1988, in response to the draft reports issued for public comment on May 27, 1988. 39 refs, 1 fig., 7 tabs

Final Technical Report: Hydrogen Codes and Standards Outreach

Energy Technology Data Exchange (ETDEWEB)

Hall, Karen I.

2007-05-12

This project contributed significantly to the development of new codes and standards, both domestically and internationally. The NHA collaborated with codes and standards development organizations to identify technical areas of expertise that would be required to produce the codes and standards that industry and DOE felt were required to facilitate commercialization of hydrogen and fuel cell technologies and infrastructure. NHA staff participated directly in technical committees and working groups where issues could be discussed with the appropriate industry groups. In other cases, the NHA recommended specific industry experts to serve on technical committees and working groups where the need for this specific industry expertise would be on-going, and where this approach was likely to contribute to timely completion of the effort. The project also facilitated dialog between codes and standards development organizations, hydrogen and fuel cell experts, the government and national labs, researchers, code officials, industry associations, as well as the public regarding the timeframes for needed codes and standards, industry consensus on technical issues, procedures for implementing changes, and general principles of hydrogen safety. The project facilitated hands-on learning, as participants in several NHA workshops and technical meetings were able to experience hydrogen vehicles, witness hydrogen refueling demonstrations, see metal hydride storage cartridges in operation, and view other hydrogen energy products.

TurboTech Technical Evaluation Automated System

Science.gov (United States)

Tiffany, Dorothy J.

2009-01-01

TurboTech software is a Web-based process that simplifies and semiautomates technical evaluation of NASA proposals for Contracting Officer's Technical Representatives (COTRs). At the time of this reporting, there have been no set standards or systems for training new COTRs in technical evaluations. This new process provides boilerplate text in response to interview style questions. This text is collected into a Microsoft Word document that can then be further edited to conform to specific cases. By providing technical language and a structured format, TurboTech allows the COTRs to concentrate more on the actual evaluation, and less on deciding what language would be most appropriate. Since the actual word choice is one of the more time-consuming parts of a COTRs job, this process should allow for an increase in quantity of proposals evaluated. TurboTech is applicable to composing technical evaluations of contractor proposals, task and delivery orders, change order modifications, requests for proposals, new work modifications, task assignments, as well as any changes to existing contracts.

Resolution 197/012. It replaces the wording of Annex III of the Regulation of Technical Specifications for Quality of Liquid Fuels, approved by Resolution of the URSEA 150/008

International Nuclear Information System (INIS)

2012-01-01

This resolution is about modifications made in the regulation of technical specifications in the quality of liquid fuels, approved by Resolution of the URSEA 150/008. These modifications concern to the Especial Oil gas

Technical Specifications, Byron Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Appendix A to license No. NPF-37

International Nuclear Information System (INIS)

1985-02-01

The Byron Station, Unit No. 1 and Unit No. 2 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. Specifications are presented for limiting conditions for operation for the reactor control system, power distribution limits, instrumentation, primary coolant circuit, ECCS, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring

Iteration and Prototyping in Creating Technical Specifications.

Science.gov (United States)

Flynt, John P.

1994-01-01

Claims that the development process for computer software can be greatly aided by the writers of specifications if they employ basic iteration and prototyping techniques. Asserts that computer software configuration management practices provide ready models for iteration and prototyping. (HB)

Fuel element production at BWX technologies

International Nuclear Information System (INIS)

Pace, Brett

1997-01-01

Effective July 1, 1997, the Government Group portion of the Babcock and Wilcox company was incorporated separately to become BWX Technologies, Inc. (BWXT) a wholly-owned subsidiary of the Babcock and Wilcox Company. The names of the divisions and other business units of the former Babcock and Wilcox Government Group (Advanced Systems Operations, Naval Nuclear Fuel Division, and Nuclear Equipment Division) will remain unchanged, but they are now known as divisions or business units of BWXT. The management of all units and their reporting relationships will likewise remain unchanged. (author)

Technical presentation

CERN Multimedia

GS Department

2010-01-01

10 March 2010 DYNEOS 10:00 – 12:00 - Main Building, Room B, 61-1-009 Dyneos AG is active in the fields of photonics, laser and high-precision positioning. Our highly qualified engineer team has more than 30 years of experience in electro-optical solutions sales. The engineers are supported by a technical and administrative team. We are focused on the Swiss market and represent six suppliers (Coherent, PI Physik Instrumente, SIOS, Nanonics Imaging, APE, Ekspla) in order to give a qualified sales and service support to our customers. Our products are dedicated to the research field as well as to industry. In addition to standard catalog products, we offer custom designs to fulfill the specific needs of OEM customers or specific applications.

Radon-technical design methods based on radon classification of the soil

International Nuclear Information System (INIS)

Kettunen, A.V.

1993-01-01

Radon-technical classification of the foundation soil divides the foundation soil into four classes: negligible, normal, high and very high. Separate radon-technical designing methods and radon-technical solutions have been developed for each class. On regions of negligible class, no specific radon-technical designing methods are needed. On regions of normal radon class, there is no need for actual radon-technical designing based on calculations, whereas existing radon-technical solutions can be used. On regions of high and very high radon class, a separate radon-technical designing should be performed in each case, where radon-technical solutions are designed so that expected value for indoor radon content is lower than the maximum allowable radon content. (orig.). (3 refs., 2 figs., 2 tabs.)

Technical specifications, Braidwood Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-70

International Nuclear Information System (INIS)

1987-05-01

The Braidwood Station, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 18 figs., 55 tabs

Emergency operating procedures guidelines for pressurized water reactors - a progress report

International Nuclear Information System (INIS)

Lyon, W.C.

1984-01-01

Emergency Operating Procedures (EOPs) contain the instructions the operator will follow to control a nuclear plant whenever a condition exists that potentially jeopardizes the fuel cladding, the reactor coolant system (RCS) pressure boundary, or the containment. The EOPs are prepared from guidelines which contain the major operator instructions that will be in the EOPs. Guidelines have been prepared by owners' groups having Babcock and Wilcox (BandW), Combustion Engineering (CE), General Electric (GE), and Westinghouse (W) plants. These guidelines cover many aspects of full power operation. Future effort is anticipated to complete coverage of transient events, including severe accidents, all power conditions, and shutdown. This paper describes the philosophy which has guided NRC technical review of guidelines, progress achieved in providing comprehensive coverage of emergency conditions for PWRs, and anticipated future technical activities

Safety of RBMK reactors: Setting the technical framework

International Nuclear Information System (INIS)

Lederman, L.

1996-01-01

This article reviews major efforts for improving the safety of RBMK reactors through a co-operative IAEA programme initiated in 1992. Specifically covered are technical findings of safety reviews related to the design and operation of the plants, and the documentation of findings through an Agency database intended to facilitate the technical co-ordination of ongoing national and international efforts for improving RBMK safety

[Evaluation of residual osteomuscular function using computerised movement analysis for building sector workers: specificity and technical problem].

Science.gov (United States)

D'Orso, M I; Centemeri, R; Latocca, R; Riva, M; Cesana, G

2012-01-01

Occupational Health Doctors active in building sector firms frequently have to evaluate residual workers' osteomuscular function in patients coming back to work after an accident happened during work time or free time. Definition of their specific individual work suitability is usually carried out utilizing semeiotic tests in which subjective evaluation of every single Medical Doctor is real important in definition of final results and this fact can cause legal controversies. In our research we describe the application of computerised movement analysis on 10 workers of building sector. In every patient examined this technical method has been able to study objectively the tridimensional ranges of motion of most important osteomuscular districts. The possibility to have an objective evaluation of residual osteomuscular function has a relevant importance both in definition of workers' work suitability at the moment in which they start again their activities and in possible future legal conflicts.

Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

International Nuclear Information System (INIS)

Baeckstroem, Ola; Haeggstroem, Anna; Maennistoe, Ilkka

2010-04-01

This report presents guidance for evaluation of Technical Specification conditions with PSA. It covers quality in PSA, how to verify that the PSA model is sufficiently robust and sufficiently complete and general requirements on methods. Acceptance criteria for evaluation of changes in the TS conditions are presented. As the probabilistic safety assessment (PSA) has developed over the years, it has demonstrated to constitute a useful tool for evaluating many aspects of the TS from a risk point of view. and in that way making the PSAs as well as the decision tools better. This also means that it will be possible to take credit for safety system overcapacity as well as inherent safety features and strength of non-safety classed systems. However, PSA is only one of the tools that shall be used in an evaluation process of TS changes (strengthening/relaxation). PSA is an excellent tool to be used to verify the importance, and thereby possibly relaxation, of TS requirements. But, since PSA is only one tool in the evaluation, it is not sufficient in itself for defining which equipment that shall or shall not have TS requirements. The purpose of this guidance document is to provide general requirements, requirements on methods and acceptance criteria on risk-informed evaluation of TS changes based on PSA. The purpose is not to provide a single solution. As part of the review of the TS conditions this guidance specify requirements on: - Quality verification of the PSA model; - Verification that the PSA model is sufficiently robust with regard to SSCs for which requirements both are and are not defined by the TS; - Verification that the SSCs, for which TS demands are to be evaluated, are modelled in a sufficient manner; - Methods for performing the evaluation; - Which evaluation criteria that shall be used (and how that is verified to be correct); - Acceptance criteria: This guidance also briefly discusses the documentation of the analysis of the TS changes. This guidance

Guidance to risk-informed evaluation of technical specifications using PSA

International Nuclear Information System (INIS)

Baeckstroem, O.; Haeggstroem, A.; Maennistoe, I.

2010-10-01

This report presents guidance for evaluation of Technical Specification conditions with PSA. It covers quality in PSA, how to verify that the PSA model is sufficiently robust and sufficiently complete and general requirements on methods. Acceptance criteria for evaluation of changes in the TS conditions are presented. As the probabilistic safety assessment (PSA) has developed over the years, it has demonstrated to constitute a useful tool for evaluating many aspects of the TS from a risk point of view. and in that way making the PSAs as well as the decision tools better. This also means that it will be possible to take credit for safety system overcapacity as well as inherent safety features and strength of non-safety classed systems. However, PSA is only one of the tools that shall be used in an evaluation process of TS changes (strengthening/relaxation). PSA is an excellent tool to be used to verify the importance, and thereby possibly relaxation, of TS requirements. But, since PSA is only one tool in the evaluation, it is not sufficient in itself for defining which equipment that shall or shall not have TS requirements. The purpose of this guidance document is to provide general requirements, requirements on methods and acceptance criteria on risk-informed evaluation of TS changes based on PSA. The purpose is not to provide a single solution. As part of the review of the TS conditions this guidance specify requirements on: - Quality verification of the PSA model; - Verification that the PSA model is sufficiently robust with regard to SSCs for which requirements both are and are not defined by the TS; - Verification that the SSCs, for which TS demands are to be evaluated, are modelled in a sufficient manner; - Methods for performing the evaluation; - Which evaluation criteria that shall be used (and how that is verified to be correct); - Acceptance criteria: This guidance also briefly discusses the documentation of the analysis of the TS changes. This guidance

NPSAG/NKS: Interpretation and evaluation of the technical specification criteria

Energy Technology Data Exchange (ETDEWEB)

Baeckstroem, O.; Haeggstroem, A. (Relcon Scandpower AB, Sundbyberg (Sweden)); Simola, K. (VTT (Finland))

2008-07-15

The use of risk-informed methods has been discussed since the late 1980s. in the Nordic countries. However, at that time the industry and authorities were not ready for the use of these methods and the use of them have been limited. The common understanding right now is that the industry and authorities are ready for adoption of risk-informed strategies, and the use of risk informed methods in daily operation at the nuclear power plants (NPPs) as well as for long term evaluation and definition of rules and regulations is increasing. The authorities are strengthening the rules and regulations with regard to redundancy and diversification in the safety systems. There are several ongoing projects at the NPPs, such as modernization, power upgrade etc. These projects will require modification of the Technical Specifications (TS). The requirements on a risk analysis to verify exceptions will be a natural part of the TS update. To summarize; there are both activities and trends at the plants that will result in TS changes (modernizations, increase of electrical power, risk informed strategies). At the same time, authorities are increasing the requirements on risk informed evaluation of the TS. TS evaluation from a risk point of view raises several questions: 1) How shall the TS conditions be evaluated? 2) What aspects shall be taken into consideration? 3) Can a prolonged/shortened surveillance test interval (STI) or allowed outage time (AOT) affect the experienced importance of the equipment? 4) What do the conditions in the TS with regard to AOT really represent? Are they conditions that shall be used when spare part storage and/or maintenance strategies are developed or do they represent how a real situation (unavailable component) shall be managed? To form an idea of the opinion on these questions phase 1 of the project is based on a literature study and interviews with persons at the Swedish and Finnish utilities and authorities. A short background to the current TS

NPSAG/NKS: Interpretation and evaluation of the technical specification criteria

International Nuclear Information System (INIS)

Baeckstroem, O.; Haeggstroem, A.; Simola, K.

2008-07-01

The use of risk-informed methods has been discussed since the late 1980s. in the Nordic countries. However, at that time the industry and authorities were not ready for the use of these methods and the use of them have been limited. The common understanding right now is that the industry and authorities are ready for adoption of risk-informed strategies, and the use of risk informed methods in daily operation at the nuclear power plants (NPPs) as well as for long term evaluation and definition of rules and regulations is increasing. The authorities are strengthening the rules and regulations with regard to redundancy and diversification in the safety systems. There are several ongoing projects at the NPPs, such as modernization, power upgrade etc. These projects will require modification of the Technical Specifications (TS). The requirements on a risk analysis to verify exceptions will be a natural part of the TS update. To summarize; there are both activities and trends at the plants that will result in TS changes (modernizations, increase of electrical power, risk informed strategies). At the same time, authorities are increasing the requirements on risk informed evaluation of the TS. TS evaluation from a risk point of view raises several questions: 1) How shall the TS conditions be evaluated? 2) What aspects shall be taken into consideration? 3) Can a prolonged/shortened surveillance test interval (STI) or allowed outage time (AOT) affect the experienced importance of the equipment? 4) What do the conditions in the TS with regard to AOT really represent? Are they conditions that shall be used when spare part storage and/or maintenance strategies are developed or do they represent how a real situation (unavailable component) shall be managed? To form an idea of the opinion on these questions phase 1 of the project is based on a literature study and interviews with persons at the Swedish and Finnish utilities and authorities. A short background to the current TS

Guidance to risk-informed evaluation of technical specifications using PSA

Energy Technology Data Exchange (ETDEWEB)

Baeckstroem, O.; Haeggstroem, A. (Scandpower AB, Stockholm (Sweden)); Maennistoe, I. (VTT, Helsingfors (Finland))

2010-04-15

This report presents guidance for evaluation of Technical Specification conditions with PSA. It covers quality in PSA, how to verify that the PSA model is sufficiently robust and sufficiently complete and general requirements on methods. Acceptance criteria for evaluation of changes in the TS conditions are presented. As the probabilistic safety assessment (PSA) has developed over the years, it has demonstrated to constitute a useful tool for evaluating many aspects of the TS from a risk point of view. and in that way making the PSAs as well as the decision tools better. This also means that it will be possible to take credit for safety system overcapacity as well as inherent safety features and strength of non-safety classed systems. However, PSA is only one of the tools that shall be used in an evaluation process of TS changes (strengthening/relaxation). PSA is an excellent tool to be used to verify the importance, and thereby possibly relaxation, of TS requirements. But, since PSA is only one tool in the evaluation, it is not sufficient in itself for defining which equipment that shall or shall not have TS requirements. The purpose of this guidance document is to provide general requirements, requirements on methods and acceptance criteria on risk-informed evaluation of TS changes based on PSA. The purpose is not to provide a single solution. As part of the review of the TS conditions this guidance specify requirements on: - Quality verification of the PSA model; - Verification that the PSA model is sufficiently robust with regard to SSCs for which requirements both are and are not defined by the TS; - Verification that the SSCs, for which TS demands are to be evaluated, are modelled in a sufficient manner; - Methods for performing the evaluation; - Which evaluation criteria that shall be used (and how that is verified to be correct); - Acceptance criteria: This guidance also briefly discusses the documentation of the analysis of the TS changes. This guidance

Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

Energy Technology Data Exchange (ETDEWEB)

Baeckstroem, Ola; Haeggstroem, Anna (Scandpower AB, Stockholm (Sweden)); Maennistoe, Ilkka (VTT, Helsingfors (Finland))

2010-04-15

This report presents guidance for evaluation of Technical Specification conditions with PSA. It covers quality in PSA, how to verify that the PSA model is sufficiently robust and sufficiently complete and general requirements on methods. Acceptance criteria for evaluation of changes in the TS conditions are presented. As the probabilistic safety assessment (PSA) has developed over the years, it has demonstrated to constitute a useful tool for evaluating many aspects of the TS from a risk point of view. and in that way making the PSAs as well as the decision tools better. This also means that it will be possible to take credit for safety system overcapacity as well as inherent safety features and strength of non-safety classed systems. However, PSA is only one of the tools that shall be used in an evaluation process of TS changes (strengthening/relaxation). PSA is an excellent tool to be used to verify the importance, and thereby possibly relaxation, of TS requirements. But, since PSA is only one tool in the evaluation, it is not sufficient in itself for defining which equipment that shall or shall not have TS requirements. The purpose of this guidance document is to provide general requirements, requirements on methods and acceptance criteria on risk-informed evaluation of TS changes based on PSA. The purpose is not to provide a single solution. As part of the review of the TS conditions this guidance specify requirements on: - Quality verification of the PSA model; - Verification that the PSA model is sufficiently robust with regard to SSCs for which requirements both are and are not defined by the TS; - Verification that the SSCs, for which TS demands are to be evaluated, are modelled in a sufficient manner; - Methods for performing the evaluation; - Which evaluation criteria that shall be used (and how that is verified to be correct); - Acceptance criteria: This guidance also briefly discusses the documentation of the analysis of the TS changes. This guidance

Yucca Mountain Site Characterization Project: Technical data catalog,(quarterly supplement)

International Nuclear Information System (INIS)

1993-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year

Genetic diversity in 14 tomato (Lycopersicon esculentum Mill ...

African Journals Online (AJOL)

Administrator

2011-06-08

Jun 8, 2011 ... 1Department of Biosciences and Biotechnology, Babcock University, Ilishan Remo, Ogun State,PMB 21244, Ikeja,. Nigeria. 2Department of Agriculture and Industrial Technology, Babcock University, Ogun State, Nigeria. 3Department of Botany, University of Ibadan, Ibadan, Oyo State, Nigeria. Accepted 6 ...

Boosting INPO's programs with supplier know-how

International Nuclear Information System (INIS)

Matson, B.

1984-01-01

Nuclear industry suppliers, such as Stone and Webster and Babcock and Wilcox, are key participants in the Institute of Nuclear Power Operators (INPO) effort to promote technical information exchanges throughout the industry and to contribute to INPO training programs. Suppliers have 21 employees on loan to the Institute, although steps must be taken to protect proprietary information and to avoid breaking antitrust laws. Among the NUCLEAR NETWORK programs using supplier expertise is the Significant Event Evaluation and Information Network (SEE-IN), which reviews important reports involving their products. Suppliers benefit by observing evaluation teams at construction sites and plant start-ups

Nuclear snow job: utilities struggle to avoid credibility meltdown

International Nuclear Information System (INIS)

Feeney, A.

1979-01-01

Electric utilities and the US nuclear industry are criticized for giving a public relations response to safety concerns following the accident at Three Mile Island and for passing the cost of the response on to utility customers. The large amounts of money budgeted by Babcock and Wilcox, Bechtel Power Corporation, the Atomic Industrial Forum, Electric Power Research Institute, Nuclear Energy Women, and others to minimize the incident and counter anti-nuclear arguments with media events are seen here by Feeney as evidence that the utilities and nuclear industry are afraid of political consequences as their technical credibility vanishes

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

Method for the determination of technical specifications limiting temperature in EBR-II operation

International Nuclear Information System (INIS)

Chang, L.K.; Hill, D.J.; Ku, J.Y.

2004-01-01

The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analyses and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. Design safety criteria for steady-state normal and transient off-normal operations were developed to ensure structural integrity of the fuel pin. The maximum allowable coolant outlet temperatures and powers of subassemblies for steady-state normal operation conditions were first determined in a row-by-row basis by a thermal-hydraulic and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum subassembly coolant outlet temperatures and powers that satisfy the design safety criteria for steady-state normal operation conditions. The limiting steady-state temperature and power were then used as the initial subassembly thermal conditions for the off-normal transient analysis to assess the safety performance of the fuel pin for anticipated, unlikely and extremely unlikely events. If the design safety criteria for the off-normal events are not satisfied, then the initial steady-state subassembly temperatures and/or powers are reduced and an iterative procedure is employed until the design safety criteria for off-normal conditions are satisfied, and the initial subassembly outlet coolant temperature and power are the technical specification limits for reactor operation. (author)

Endogenous induced technical change and the costs of Kyoto

International Nuclear Information System (INIS)

Buonanno, Paolo; Carraro, Carlo; Galeotti, Marzio

2003-01-01

We present a model for climate change policy analysis which accounts for the possibility that technology evolves endogenously and that technical change can be induced by environmental policy measures. Both the output production technology and the emission-output ratio depend upon a stock of knowledge, which accumulates through R and D activities. Two versions of this model are studied, one with endogenous technical change but exogenous environmental technical change and the other with both endogenous and induced technical change. A third version also captures technological spillover effects. As an application, the model is simulated allowing for trade of pollution permits as specified in the Kyoto Protocol and assessing the implications in terms of cost efficiency, economic growth and R and D efforts of the three different specifications of technical change

Colonialism and Secondary Technical Education in Hong Kong: 1945-1997

Science.gov (United States)

Lau, Wai Wah; Kan, Flora

2011-01-01

This study examines the influence of the colonial experience (1945-1997) on the planning of secondary technical education in Hong Kong. Specifically, the origins of secondary technical institutions and their positioning in secondary education are examined. Primary source materials are used as the basis of investigation and analysis, supplemented…

Technical Specifications of Structural Health Monitoring for Highway Bridges: New Chinese Structural Health Monitoring Code

Directory of Open Access Journals (Sweden)

Fernando Moreu

2018-03-01

Full Text Available Governments and professional groups related to civil engineering write and publish standards and codes to protect the safety of critical infrastructure. In recent decades, countries have developed codes and standards for structural health monitoring (SHM. During this same period, rapid growth in the Chinese economy has led to massive development of civil engineering infrastructure design and construction projects. In 2016, the Ministry of Transportation of the People’s Republic of China published a new design code for SHM systems for large highway bridges. This document is the first technical SHM code by a national government that enforces sensor installation on highway bridges. This paper summarizes the existing international technical SHM codes for various countries and compares them with the new SHM code required by the Chinese Ministry of Transportation. This paper outlines the contents of the new Chinese SHM code and explains its relevance for the safety and management of large bridges in China, introducing key definitions of the Chinese–United States SHM vocabulary and their technical significance. Finally, this paper discusses the implications for the design and implementation of a future SHM codes, with suggestions for similar efforts in United States and other countries.

Reader-Centered Technical Writing

Science.gov (United States)

Narayanan, M.

2012-12-01

Technical writing is an essential part of professional communication and in recent years it has shifted from a genre-based approach. Formerly, technical writing primarily focused on generating templates of documents and sometimes it was creating or reproducing traditional forms with minor modifications and updates. Now, technical writing looks at the situations surrounding the need to write. This involves deep thinking about the goals and objectives of the project on hand. Furthermore, one observes that it is very important for any participatory process to have the full support of management. This support needs to be well understood and believed by employees. Professional writing may be very persuasive in some cases. When presented in the appropriate context, technical writing can persuade a company to improve work conditions ensuring employee safety and timely production. However, one must recognize that lot of professional writing still continues to make use of reports and instruction manuals. Normally, technical and professional writing addresses four aspects. Objective: The need for generating a given professionally written technical document and the goals the document is expected to achieve and accomplish. Clientele: The clientele who will utilize the technical document. This may include the people in the organization. This may also include "unintended readers." Customers: The population that may be affected by the content of the technical document generated. This includes the stakeholders who will be influenced. Environment: The background in which the document is created. Also, the nature of the situation that warranted the generation of the document. Swiss Psychologist Jean Piaget's view of Learning focuses on three aspects. The author likes to extend Jean Piaget's ideas to students, who are asked to prepare and submit Reader-Centered Technical Writing reports and exercises. Assimilation: Writers may benefit specifically, by assimilating a new object into

Dowel Bar Retrofit Mix Design and Specification : Technical Report

Science.gov (United States)

2012-01-01

Current INDOT specifications for repair materials to be used in dowel bar retrofit (DBR) applications (Sections 507.08 and 901.07 of INDOTs Book of Specifications) are based, in large part, on the requirements of ASTM C 928 and the manufacturer-pr...

Good Engineering + Poor Communication = Three Mile Island.

Science.gov (United States)

Mathes, J. C.

The accident at the Three Mile Island nuclear power plant resulted from a communication failure. Following an incident at an Ohio plant a year and a half earlier, B. M. Dunn, manager of Emergency Core Cooling Systems Analysis at Babcock and Wilcox (engineers), wrote a memorandum making specific recommendations on written instructions for nuclear…

Technical inefficiency of Vietnamese pangasius farming

NARCIS (Netherlands)

Anh Ngoc, Pham Thi; Gaitán-Cremaschi, D.; Meuwissen, Miranda P.M.; Le, Tru Cong; Bosma, Roel H.; Verreth, Johan; Lansink, Alfons Oude

2018-01-01

Vietnamese pangasius farming needs to produce efficiently to compete in world markets. This study investigates the input- and output-specific technical inefficiency of Vietnamese pangasius farmers. First, we used a Russell-type (input–output) directional distance function to estimate the input- and

TWRSview system requirements specification

International Nuclear Information System (INIS)

Caldwell, J.A.; Lee, A.K.

1995-12-01

This document provides the system requirements specification for the TWRSview software system. The TWRSview software system is being developed to integrate electronic data supporting the development of the TWRS technical baseline

Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

INMM Physical Protection Technical Working Group Workshops

International Nuclear Information System (INIS)

Williams, J.D.

1982-01-01

The Institute of Nuclear Materials Management (INMM) established the Physical Protection Technical Working Group to be a focal point for INMM activities related to the physical protection of nuclear materials and facilities. The Technical Working Group has sponsored workshops with major emphasis on intrusion detection systems, entry control systems, and security personnel training. The format for these workshops has consisted of a series of small informal group discussions on specific subject matter which allows direct participation by the attendees and the exchange of ideas, experiences, and insights. This paper will introduce the reader to the activities of the Physical Protection Technical Working Group, to identify the workshops which have been held, and to serve as an introduction to the following three papers of this session

Technical Specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-80

International Nuclear Information System (INIS)

1989-03-01

The South Texas Project, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

Technical specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-78

International Nuclear Information System (INIS)

1989-01-01

The South Texas Project, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

TECHNICAL TRAINING SEMINAR

CERN Multimedia

Davide Vitè

2002-01-01

Wednesday 6 March TECHNICAL TRAINING SEMINAR from 9:30 to 16:45 - IT Amphitheatre - bldg. 31.3.004 Analog Devices DSP Day Thorsten Kistler (Application Engineer), Steffen Boerner (Product Specialist) / ANALOG DEVICES Munich Trying to meet your design challenges, Analog Devices compiles application information and offers chipsets, software, reference designs and mixed-signal, application specific DSPs, for a range of real-time signal processing applications. This seminar will present the latest 16bit fixed-point and 32bit floating-point DSPs (roadmaps; internal architectures, blocks, features benchmarks), with their software, development kits and emulators: Fixed-Point DSP-Family, ADSP-218x and ADSP-219x Blackfin DSP SHARC-Family, 2106x and 2116x TigerSHARC Industrial Contact: François Caloz, Sasco-Spoerle GmbH Language: English Free seminar, no registration Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch Please read the full information on the Technical Training Seminars...

The role of non-technical skills in surgery

Directory of Open Access Journals (Sweden)

Riaz A. Agha

2015-12-01

This narrative review used a number of sources including written and online, there was no specific search strategy of defined databases. Modern surgical practice requires; technical and non-technical skills, evidence-based practice, an emphasis on lifelong learning, monitoring of outcomes and a supportive institutional and health service framework. Finally these requirements need to be combined with a number of personal and professional values including integrity, professionalism and compassionate, patient-centred care.

Modeling technical change in climate analysis: evidence from agricultural crop damages.

Science.gov (United States)

Ahmed, Adeel; Devadason, Evelyn S; Al-Amin, Abul Quasem

2017-05-01

This study accounts for the Hicks neutral technical change in a calibrated model of climate analysis, to identify the optimum level of technical change for addressing climate changes. It demonstrates the reduction to crop damages, the costs to technical change, and the net gains for the adoption of technical change for a climate-sensitive Pakistan economy. The calibrated model assesses the net gains of technical change for the overall economy and at the agriculture-specific level. The study finds that the gains of technical change are overwhelmingly higher than the costs across the agriculture subsectors. The gains and costs following technical change differ substantially for different crops. More importantly, the study finds a cost-effective optimal level of technical change that potentially reduces crop damages to a minimum possible level. The study therefore contends that the climate policy for Pakistan should consider the role of technical change in addressing climate impacts on the agriculture sector.

Technical notes for the conceptual design for an atmospheric fluidized-bed direct combustion power generating plant. [570 MWe plant

Energy Technology Data Exchange (ETDEWEB)

None

1978-04-01

The design, arrangement, thermodynamics, and economics of a 592 MW(e) (nominal gross) electric power generating plant equipped with a Babcock and Wilcox Company (B and W) atmospheric fluidized bed (AFB) boiler are described. Information is included on capital and operating costs, process systems, electrical systems, control and instrumentation, and environmental systems. This document represents a portion of an overall report describing the conceptual designs of two atmospheric fluidized bed boilers and balance of plants for the generation of electric power and the analysis and comparison of these conceptual designs to a conventional pulverized coal-fired electric power generation plant equipped with a wet limestone flue gas desulfurization system.

Technical specification of the NRPB Nuclear Emulsion Dosemeter

International Nuclear Information System (INIS)

Bartlett, D.T.; Bird, T.V.

1978-08-01

This document is a formal specification of the NRPB Nuclear Emulsion Dosemeter. The dosemeter specified in this report replaces the NRPB Fast Neutron Personal Dosemeter specified in NRPB-R50. (author)

Windows Calorimeter Control (WinCal) system configuration control board (SCCB) operating procedure

International Nuclear Information System (INIS)

Westsik, G.A.

1997-01-01

This document describes the operating procedure for the System Configuration Control Board (SCCB) performed in support of the Windows Calorimeter Control (WinCal) system. This board will consist of representatives from Babcock and Wilcox Hanford Company Babcock and Wilcox Protec, Inc.; and Lockheed Martin Services, Inc. In accordance with agreements for the joint use of the Babcock and Wilcox Hanford Company calorimeters located in the Hanford Site Plutonium Finishing Plant (PFP) Nondestructive Assay Laboratory, concurrence regarding changes to the WinCal system will be obtained from the International Atomic Energy Agency (IAEA). Further, changes to the WinCal software will be communicated to Los Alamos National Laboratory

INDOT Technical Training Plan : [Technical Summary

Science.gov (United States)

2012-01-01

A wide range of job classifications, increasing technical : performance expectations, licensing and certification requirements, : budget restrictions and frequent department : reorganization has made technical training of employees : more difficult, ...

Multidirectional analysis of technical efficiency for pig production systems

DEFF Research Database (Denmark)

Labajavo, Katarina; Hansson, Helena; Asmild, Mette

2016-01-01

Declining profitability and ongoing structural changes in the pig sector require thorough efficiency analysis of individual production factors. In this study we calculated technical efficiency indices for each input and output using multidirectional efficiency analysis and examined the relationship...... between ‘farm-specific characteristics’ and input and output technical efficiencies by production type (piglet, growing-finishing, finish-to-farrow). The results indicated that advisory services and farm location were not significantly correlated with technical efficiency. Similar results were obtained...... for ‘housing practices’, with the exception of the latest technology such as heated floors in relation to input labour technical efficiency for growing-finishing and finish-to-farrow productions. Use of written instructions for feeding for growing-finishing and finish-to-farrow production and written...

Dose measurements with a HPGe detector - a technical manual

Energy Technology Data Exchange (ETDEWEB)

Lidstroem, K.; Nordenfors, C.; Aagren, G

2000-06-01

This paper is a technical manual for estimations of dose based on a gamma spectrum. The method used is based on the Monte Carlo code EGS4. Since dose estimations from spectra are specific for each detector, this work is performed on two mobile HPGe detectors at FOA NBC Defence in Umeaa. This technical manual describes the method used in three steps: Part 1 explains how to construct a model of the detector geometry and the specific material for a new detector. Part 2 describes the underlying work of Monte Carlo simulations of a detector given geometry and material. Part 3 describes dose estimations from a gamma spectrum.

Status of Recent Developments in the Technical Standards of Japan

International Nuclear Information System (INIS)

Ahn, Hyung-Joon; Ahn, Sang-Kyu; Koh, Jae-Dong; Kim, Chang-Bum

2006-01-01

Japan has systematically revamped its technical standards for nuclear reactor facilities by formulating various performance regulations. Being part of a trend toward deregulation, such efforts toward social regulation is aimed at effectively operating administrative procedural laws to keep pace with global trends and enhance the benefits of deregulation under the principle of self-responsibility. Based on the collection of public opinions in February and March 2005, the Nuclear and Industrial Safety Agency(NISA) presented its position that it was required to promptly perform a flexible assessment of the technical feasibility of formulated society and association standards. Current, pressing issues are summarized as an early revision of technical standards regarding nuclear facilities for power generation, use of society and association standards, and the overhaul of nuclear safety regulations subject to performance regulations. Subjecting technical standards to performance regulations means stipulating the qualitative aspects of performance and the targets that certain facilities must achieve, which are not specific standards, but general compulsory standards. This study examines the early revision of technical standards on nuclear facilities for power generation and the status of the use of society and association standards, as well as introducing the details of revisions in the concrete containment vessel standards as specific examples

Modelling Social-Technical Attacks with Timed Automata

DEFF Research Database (Denmark)

David, Nicolas; David, Alexandre; Hansen, Rene Rydhof

2015-01-01

. In this paper we develop an approach towards modelling socio-technical systems in general and socio-technical attacks in particular, using timed automata and illustrate its application by a complex case study. Thanks to automated model checking and automata theory, we can automatically generate possible attacks...... in our model and perform analysis and simulation of both model and attack, revealing details about the specific interaction between attacker and victim. Using timed automata also allows for intuitive modelling of systems, in which quantities like time and cost can be easily added and analysed....

Technical and Technological Skills Assessment in Laparoscopic Surgery

Science.gov (United States)

Chang, Avril; Vincent, Charles

2006-01-01

Objectives: Surgical appraisal and revalidation are key components of good surgical practice and training. Assessing technical skills in a structured manner is still not widely used. Laparoscopic surgery also requires the surgeon to be competent in technological aspects of the operation. Methods: Checklists for generic, specific technical, and technological skills for laparoscopic cholecystectomies were constructed. Two surgeons with >12 years postgraduate surgical experience assessed each operation blindly and independently on DVD. The technological skills were assessed in the operating room. Results: One hundred operations were analyzed. Eight trainees and 10 consultant surgeons were recruited. No adverse events occurred due to technical or technological skills. Mean interrater reliability was kappa=0.88, P=technical and technological skills between trainee and consultant surgeons were significant, Mann-Whitney P=technical and technological skills can be measured to assess performance of laparoscopic surgeons. This technical and technological assessment tool for laparoscopic surgery seems to have face, content, concurrent, and construct validities and could be modified and applied to any laparoscopic operation. The tool has the possibility of being used in surgical training and appraisal. We aim to modify and apply this tool to advanced laparoscopic operations. PMID:17212881

Technical specifications on the welding in fuel reprocessing plants

Energy Technology Data Exchange (ETDEWEB)

Karino, Motonobu; Uryu, Mitsuru; Matsui, N.; Nakazawa, Fumio; Imanishi, Makoto; Koizumi; Kazuhiko; Sugawara, Junichi; Tanaka, Hideo

1999-04-01

The past specifications SGN of the welding in JNC was reexamined for the reprocessing plants in order to further promote the quality control. The specification first concerns the quality of raw materials, items of the quality tests, material management, and qualification standards of the welders. It extends over details of the welding techniques, welding design, welding testings, inspection and the judgment standards. (H. Baba)

Technical concept for a Greater Confinement Disposal test facility

International Nuclear Information System (INIS)

Hunter, P.H.

1982-01-01

For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in specific development of defense low-level waste management concepts for greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which was published in May of 1981 and the draft of the technical concept for Greater Confinement Disposal, with the latest draft published in November 1981. The final draft of the technical concept and design specifications are expected to be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year. The GCD Criteria Document, NVO-234 is considered to contain information complimentary and compatible with that being developed for the reserved section 10 CFR 61.51b of the NRCs proposed licensing rule for low level waste disposal facilities

Fuel Cycle of VVER-1000: technical and economic aspects

International Nuclear Information System (INIS)

Kosourov, E.; Pavlov, V.; Pavlovichev, A.

2009-01-01

The paper contains estimations of dependences of technical and economic characteristics of VVER-1000 fuel cycle on number of charged FAs and their enrichment. In the study following restrictions were used: minimum quantity of loaded fresh FAs is equal 36 FAs, a maximum one - 78 (79) FAs and fuel enrichment is limited by value 4,95 %. The following technical and economic characteristics are discussed: cycle length, average burnup of spent fuel, specific consumption of natural uranium, specific quantity of separative work, annual production of thermal energy, fuel component of electrical energy cost, electricity generation cost. Results of estimations are presented as dependences of researched characteristics on cycle length, quantity of loaded FAs and their enrichments. The presented information allows to show tendencies and ranges of technical and economic characteristics at change of fuel cycle parameters. This information can be useful for definition of the fuel cycle parameters which satisfy the requirements of power system and exploiting organizations. (authors)

The French Space Operation Act: Technical Regulations

Science.gov (United States)

Trinchero, J. P.; Lazare, B.

2010-09-01

The French Space Operation Act(FSOA) stipulates that a prime objective of the National technical regulations is to protect people, property, public health and the environment. Compliance with these technical regulations is mandatory as of 10 December 2010 for space operations by French space operators and for space operations from French territory. The space safety requirements and regulations governing procedures are based on national and international best practices and experience. A critical design review of the space system and procedures shall be carried out by the applicant, in order to verify compliance with the Technical Regulations. An independent technical assessment of the operation is delegated to CNES. The principles applied when drafting technical regulations are as follows: requirements must as far as possible establish the rules according to the objective to be obtained, rather than how it is to be achieved; requirements must give preference to international standards recognised as being the state of the art; requirements must take previous experience into account. Technical regulations are divided into three sections covering common requirements for the launch, control and return of a space object. A dedicated section will cover specific rules to be applied at the Guiana Space Centre. The main topics addressed by the technical regulations are: operator safety management system; study of risks to people, property, public health and the Earth’s environment; impact study on the outer space environment: space debris generated by the operation; planetary protection.

Exploring the relationship between anaesthesiologists' non-technical and technical skills.

Science.gov (United States)

Gjeraa, K; Jepsen, R M H G; Rewers, M; Østergaard, D; Dieckmann, P

2016-01-01

A combination of non-technical skills (NTS) and technical skills (TS) is crucial for anaesthetic patient management. However, a deeper understanding of the relationship between these two skills remains to be explored. We investigated the characteristics of trainee anaesthesiologists' NTS and TS in a simulated unexpected difficult airway management scenario. A mixed-method approach was used to explore the relationship between NTS and TS in 25 videos of 2nd year trainee anaesthesiologists managing a simulated difficult airway scenario. The videos were assessed using the customised version of the Anaesthetists' Non-Technical Skills System, ANTSdk, and an adapted TS checklist for calculating the correlation between NTS and TS. Written descriptions of the observed NTS were analysed using directed content analysis. The correlation between the NTS and the TS ratings was 0.106 (two-tailed significance of 0.613). Inter-rater reliability was substantial. Themes characterising good NTS included a systematic approach, planning and communicating decisions as well as responding to the evolving situation. A list of desirable, concrete NTS for the specific airway management situation was generated. This study illustrates that anaesthesiologist trainees' NTS and TS were not correlated in this setting, but rather intertwined and how the interplay of NTS and TS can impact patient management. Themes describing the characteristics of NTS and a list of desirable, concrete NTS were developed to aid the understanding, training and use of NTS. © 2015 The Acta Anaesthesiologica Scandinavica Foundation. Published by John Wiley & Sons Ltd.

Canister Storage Building (CSB) Technical Safety Requirements

International Nuclear Information System (INIS)

KRAHN, D.E.

2000-01-01

The purpose of this section is to explain the meaning of logical connectors with specific examples. Logical connectors are used in Technical Safety Requirements (TSRs) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TSRs are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings

Technical evaluation of RETS-required reports for the La Crosse boiling water reactor

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant-specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 5 refs

Specifications, quality control, manufacturing, and testing of accelerator magnets

CERN Document Server

Einfeld, D

2010-01-01

The performance of the magnets plays an important role in the functioning of an accelerator. Most of the magnets are designed at the accelerator laboratory and built by industry. The link between the laboratory and the manufacturer is the contract containing the Technical Specifications of the magnets. For an overview of the contents of the Technical Specifications, the specifications for the magnets of ALBA (bending, quadrupole, and sextupole) are described in this paper. The basic rules of magnet design are reviewed in Appendix A.

Technical Specifications: Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-79

International Nuclear Information System (INIS)

1989-02-01

The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

Technical Specifications, Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-81

International Nuclear Information System (INIS)

1989-03-01

The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

Technical evaluation of RETS-required reports for Turkey Point Units No. 3 and 4

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.; Henscheid, J.W.

1985-01-01

A review of the reports required by Federal regulations and the plant specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

FUNCTIONS OF THE IMAGE IN SHAPING THE TECHNICAL THINKING OF STUDENTS

Directory of Open Access Journals (Sweden)

Mariusz Śniadkowski

2014-11-01

Full Text Available The world of technology can be a tool to support development processes, primarily cognitive, emotional and motivational. Adoption issues shaping the image function in the technical thinking of students is justified in many ways: a – impact on the development of human image; b – multidimensional image and diversity of its media resources; c – the influence of the image on shaping the attitudes and behaviors of education; d – state of research on the evolution of technical thinking of youth. Development of the technical thinking is one of the objectives in the process of technical education. A picture taking part in it by building concepts and technical imagination fulfilling a significant role in the illustration and understanding of issues and technical products and the specific technical action. Technical education requires from teachers to enter a wide range of activities in the teaching process in the direction of the effective application and the use of image in the development of technical thinking and imagination of students. Pictures have a prominent role here.

Implementing and Evaluating a National Certification Technical Skills Examination: The Colorectal Objective Structured Assessment of Technical Skill.

Science.gov (United States)

de Montbrun, Sandra; Roberts, Patricia L; Satterthwaite, Lisa; MacRae, Helen

2016-07-01

To implement the Colorectal Objective Structured Assessment of Technical skill (COSATS) into American Board of Colon and Rectal Surgery (ABCRS) certification and build evidence of validity for the interpretation of the scores of this high stakes assessment tool. Currently, technical skill assessment is not a formal component of board certification. With the technical demands of surgical specialties, documenting competence in technical skill at the time of certification with a valid tool is ideal. In September 2014, the COSATS was a mandatory component of ABCRS certification. Seventy candidates took the examination, with their performance evaluated by expert colorectal surgeons using a task-specific checklist, global rating scale, and overall performance scale. Passing scores were set and compared using 2 standard setting methodologies, using a compensatory and conjunctive model. Inter-rater reliability and the reliability of the pass/fail decision were calculated using Cronbach alpha and Subkoviak methodology, respectively. Overall COSATS scores and pass/fail status were compared with results on the ABCRS oral examination. The pass rate ranged from 85.7% to 90%. Inter-rater reliability (0.85) and reliability of the pass/fail decision (0.87 and 0.84) were high. A low positive correlation (r= 0.25) was seen between the COSATS and oral examination. All individuals who failed the COSATS passed the ABCRS oral examination. COSATS is the first technical skill examination used in national surgical board certification. This study suggests that the current certification process may be failing to identify individuals who have demonstrated technical deficiencies on this standardized assessment tool.

BASIC TECHNICAL SKILLS (THROWS IN 17-19-YEAR-OLD JUDOKAS

Directory of Open Access Journals (Sweden)

Wladyslaw Jagiello

2014-12-01

Full Text Available Purpose: The purpose of the research was to determine basic technical skills (throws in 17-19-year-old judokas and the level of their performance. Material: The study involved 30 judo athletes (aged 17-19. Results: To determine the athletes’ basic technical skills (throws, an analysis of source materials and a diagnostic survey were used. To determine the level of technical skills, the method of expert assessment was applied. Statistical software package Statistica 8 was used in the statistical analysis. In the coaches’ opinion, 17-19-year-old judokas have a specific, characteristic of this age group, set of basic technical skills (throws aptly defining their technical preparation. Conclusions: The tested group of judokas exhibited the highest level of demonstrating throws of the koshi-waza (hip group, and the lowest one of the ashi-waza (foot group.

Engineering Technical Support Center Annual Report Fiscal ...

Science.gov (United States)

The United States Environmental Protection Agency (EPA or Agency) Office of Research and Development (ORD) created the Engineering Technical Support Center (ETSC) in 1987, one of several technical support centers created as part of the Technical Support Project (TSP). ETSC provides engineering expertise to Agency program and regional offices and remediation teams working at contaminated sites across the country. The ETSC is operated within ORD’s Land Remediation and Pollution Control Division (LRPCD) of the National Risk Management Research Laboratory (NRMRL) in Cincinnati, Ohio. The ETSC’s mission is to provide site-specific scientific and engineering technical support to Remedial Project Managers, On-Scene Coordinators, and other remediation personnel at contaminated sites. This allows local, regional, or national authorities to work more quickly, efficiently, and cost effectively, while also increasing the technical experience of the remediation team. Since its inception, the ETSC has supported countless projects across all EPA Regions in almost all states and territories. This report highlights significant projects the ETSC supported in fiscal year 2015 (FY15). These projects addressed an array of environmental scenarios, such as remote mining contamination, expansive landfill waste, cumulative impacts from multiple contamination sources, and persistent threats from abandoned industrial sites. Constructing and testing new and innovative treatment technol

Independent Electricity Market Operator integration management participant technical reference manual

International Nuclear Information System (INIS)

1999-01-01

The document provides potential participants with the essential technical information to permit them to participate in the IMO-administered markets, and is not intended to be a complete technical reference manual for all issues within the realm of electricity production, distribution, or consumption. Written for the participants, it provides only that information which is relevant to the participant for interfacing with the IMO and participating in the market. Written as a generic guide, all the information contained within it may not be relevant to all the participants. The document's intent is to provide participants with a description of the various facilities and interfaces required by market participants to take part in the IMO-administered markets. The document supplements the market rules and provides installation, set-up, and configuration information for the various tools and facilities that will be required for market participation as a supplier, carrier/delivery (transmitter/distributor), generator, or consumer in the market. Aspects considered include: participant workstation specifications, dispatch workstation specification, message exchange, remote terminal unit specification, AGC operational RTU specification, real time network connection specification, telephone connection specification, revenue administration specification, funds administration specification, data catalogues, market information, power grid connection requirements, and appendices

Technical requirements document for the waste flow analysis

International Nuclear Information System (INIS)

Shropshire, D.E.

1996-05-01

Purpose of this Technical Requirements Document is to define the top level customer requirements for the Waste Flow Analysis task. These requirements, once agreed upon with DOE, will be used to flow down subsequent development requirements to the model specifications. This document is intended to be a ''living document'' which will be modified over the course of the execution of this work element. Initial concurrence with the technical functional requirements from Environmental Management (EM)-50 is needed before the work plan can be developed

Predictors of employer satisfaction: technical and non-technical skills.

Science.gov (United States)

Danielson, Jared A; Wu, Tsui-Feng; Fales-Williams, Amanda J; Kirk, Ryan A; Preast, Vanessa A

2012-01-01

Employers of 2007-2009 graduates from Iowa State University College of Veterinary Medicine were asked to respond to a survey regarding their overall satisfaction with their new employees as well as their new employees' preparation in several technical and non-technical skill areas. Seventy-five responses contained complete data and were used in the analysis. Four technical skill areas (data collection, data interpretation, planning, and taking action) and five non-technical skill areas (interpersonal skills, ability to deal with legal issues, business skills, making referrals, and problem solving) were identified. All of the skill area subscales listed above had appropriate reliability (Cronbach's alpha>0.70) and were positively and significantly correlated with overall employer satisfaction. Results of two simultaneous regression analyses indicated that of the four technical skill areas, taking action is the most salient predictor of employer satisfaction. Of the five non-technical skill areas, interpersonal skills, business skills, making referrals, and problem solving were the most important skills in predicting employer satisfaction. Hierarchical regression analysis revealed that all technical skills explained 25% of the variation in employer satisfaction; non-technical skills explained an additional 42% of the variation in employer satisfaction.

Technical Training: CLEAN-2002: Working in a Cleanroom

CERN Multimedia

2004-01-01

If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch CERN Technical Training Programme: Learning for the LHC! CLEAN-2002 is a free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific ...

Technical standards in the law of technical safety

International Nuclear Information System (INIS)

Marburger, P.

1985-01-01

Technical standards are of great importance for the closer definition of inexact terms of law, for instance ''generally accepted technical rules'', ''state of the art'', ''state of science and technology'' or similar normative terms, in the law of technical safety. The paper discusses with whom the authority for regulating this sector of law rests, deals with the different ways of how technical standards are used by the law (''anticipated expert opinion'', reference to such standards in law and administration) and points out demands on the procedure of standardization. (orig.) [de

Technical specification for IR rig manufacture

Energy Technology Data Exchange (ETDEWEB)

Han Hyon Soo; Cho, W. K.; Kim, S. D.; Park, U. J.; Hong, S. B.; Yoo, K. M

2000-10-01

IR Rig is one of the equipments are required in HANARO core for a radioisotope target. The various conditions like high radiation, high heat, rapid flow and vibration may cause swelling, Brittleness and acceleration of corrosion in HANARO core. These specific problems can be prevented and the safety of such equipment are prerequisite as well as durableness and surveillance. Therefore, the selection of material has to be made on the basis of small cross-section area, low energy emission by the gamma ray due to the absorption of neutron and short half life. The body is consist of aluminum and Inconel-750 was used for the internal spring(coil) which is known to be durable. The whole production process including the purchase of accessory, mechanical processing, welding and assembly was carried out according to the standard procedure to meet the requirement. A design, manufacture, utilization of reactor core and the other relevant uses were fit to class ''T'' to certify the whole process as general. And design, fabrication, analytical test, materials and accessory were carried out based on the ASME, ASTM, ANSI, AWS, JIS and KS standard.

Tracing the History of Technical Communication from 1850-2000: Plus a Series of Survey Studies.

Science.gov (United States)

McDowell, Earl E.

This research focuses on the history of technical communication since 1850, with a specific focus on the technological changes that occurred between 1900 and 1950. This paper also discusses the development of professional technical communication organizations and the development of technical communication programs at the bachelor, masters, and…

Technical evaluation of RETS-required reports for Duane Arnold Energy Center Unit No. 1

International Nuclear Information System (INIS)

Young, T.E.; Magleby, E.H.; Henscheid, J.W.

1985-01-01

A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 8 refs

Technical specifications, Braidwood Station Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-72, [October 1986-July 1987

International Nuclear Information System (INIS)

1987-07-01

The Braidwood Station, Units 1 and 2, technical specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public

76 FR 64083 - Reliability Technical Conference; Notice of Technical Conference

Science.gov (United States)

2011-10-17

... Technical Conference; Notice of Technical Conference Take notice that the Federal Energy Regulatory Commission will hold a Technical Conference on Tuesday, November 29, 2011, from 1 p.m. to 5 p.m. and... reliability that were identified in earlier Commission technical conferences. The conference also will discuss...

Technical Requirements for Fabrication and Installation of Removable Shield for CNRF in HANARO

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Cho, Yeong Garp; Lee, Jung Hee; Shin, Jin Won

2008-04-15

This report details the technical requirements for the fabrication and installation of the removable shield for the Cold Neutron Research Facility (CNRF) in HANARO reactor hall. The removable shield is classified as non-nuclear safety (NNS), seismic category II, and quality class T. The main function of the removable shield is to do the biological shielding of neutrons and gamma from the CN port and the guides. The removable shield consists of block type walls and roofs that can be necessarily assembled, disassembled and moveable. These will be installed between the reactor pool wall and the CNS guide bunker in. This report describes technical requirements for the removable shield such as quality assurance, seismic analysis requirements, configuration, concrete compositions, fabrication and installation requirements, test and inspection, shipping, delivery, etc. Appendix is the technical specification of structural design and analysis. Attachments are composed of the technical specification for the fabrication of the removable shield, shielding design drawings and procurement quality requirements. These technical requirements will be provided to a contract for the manufacturing and installation.

Reactor analysis support package (RASP). Volume 7. PWR set-point methodology. Final report

International Nuclear Information System (INIS)

Temple, S.M.; Robbins, T.R.

1986-09-01

This report provides an overview of the basis and methodology requirements for determining Pressurized Water Reactor (PWR) technical specifications related setpoints and focuses on development of the methodology for a reload core. Additionally, the report documents the implementation and typical methods of analysis used by PWR vendors during the 1970's to develop Protection System Trip Limits (or Limiting Safety System Settings) and Limiting Conditions for Operation. The descriptions of the typical setpoint methodologies are provided for Nuclear Steam Supply Systems as designed and supplied by Babcock and Wilcox, Combustion Engineering, and Westinghouse. The description of the methods of analysis includes the discussion of the computer codes used in the setpoint methodology. Next, the report addresses the treatment of calculational and measurement uncertainties based on the extent to which such information was available for each of the three types of PWR. Finally, the major features of the setpoint methodologies are compared, and the principal effects of each particular methodology on plant operation are summarized for each of the three types of PWR

Chemical and radiochemical specifications - PWR power plants; Specifications chimiques et radiochimiques - Centrales REP

Energy Technology Data Exchange (ETDEWEB)

Stutzmann, A [Electricite de France (EDF), 93 - Saint-Denis (France)

1997-07-01

Published by EDF this document gives the chemical specifications of the PWR (Pressurized Water Reactor) nuclear power plants. Among the chemical parameters, some have to be respected for the safety. These parameters are listed in the STE (Technical Specifications of Exploitation). The values to respect, the analysis frequencies and the time states of possible drops are noticed in this document with the motion STE under the concerned parameter. (A.L.B.)

Teaching Technical Writing - Towards Technical Writing

DEFF Research Database (Denmark)

Kastberg, Peter

2000-01-01

In this paper I will present key aspects of the curriculum for the university degree in technical translation that I have designed for and subsequently implemented at the German Department of the Aarhus School of Business, Denmark. My starting point will be a critical discussion of the norm that ...... of technical writing.......In this paper I will present key aspects of the curriculum for the university degree in technical translation that I have designed for and subsequently implemented at the German Department of the Aarhus School of Business, Denmark. My starting point will be a critical discussion of the norm...... that used to govern what the quality of an LSP text should be as opposed to the standpoint, which I advocate. By way of summing up, I will show how a university curriculum is designed so that - upon graduation - the technical translator could also be methodological quite well suited to take on the challenge...

The Great Southwest of the Fred Harvey Company and the Santa Fe Railway, edited by Marta Weigle and Barbara A. Babcock. The Heard Museum, Pheonix (printed by The University of Arizona Press, Tucson, for The Heard Museum, 1996

Directory of Open Access Journals (Sweden)

Douglas R. Givens

1997-11-01

Full Text Available One of the more colorful eras in American Southwestern archaelogy is reflected in The Great Southwest of the Fred Harvey Company and the Santa Fe Railway. Marta Weigle and Barbara A. Babcock, editors of the volume, have done a superb job weaving in early Southwestern archaeological activities with the role of the Fred Harvey Company and the Santa Fe Railway in bring the American Southwest to those "east of the Mississippi River". Many early Southwestern archaeologists made their way throughout the Southwest on the Santa Fe Railway while the "outposts of civilization" that the Fred Harvey Company provided in many railroad stations served as a " bit of home" to the traveler. This book describes the collaboration of both Fred Harvey and the Santa Fe Railroad tourism in the American Southwest and provides an excellent look into the Native American artists and their comumnities which were transformed on a massive scale by the Fred Harvey Company as it bought, sold, and popularized Native American art. Also part of the volume is an excellent discussion of the network of major museums that hold art collections which were purchased through the Harvey Company's Indian Department.

Base compaction specification feasibility analysis.

Science.gov (United States)

2012-12-01

The objective of this research is to establish the technical engineering and cost : analysis concepts that will enable WisDOT management to objectively evaluate the : feasibility of switching construction specification philosophies for aggregate base...

Explicating the Sustainable Design of Technical Artefacts

DEFF Research Database (Denmark)

Vissonova, Karina

2016-01-01

afforded by the properties of artefacts. The study is a conceptual analysis and as such belongs to the field of epistemology of design. It offers three contributions to the design discipline: (1) a proposition of the definition of the sustainable design kind; (2) a proposition of the concept of technical......Sustainable design of technical artefacts is referred to as if it were a kind of design with some specific characteristics. However, in design research and practice alike, there appears to be a lack of shared conceptions of what such a design might entail. Furthermore, we have no clear grounds...... for evaluating what makes the sustainable design solutions permissible. The lack of shared conceptions is largely due to ambiguities associated with the notion of sustainability. In response to these challenges, the aim of my study is to offer a definition of sustainable design of technical artefacts. I argue...

Technical specifications of air handling system of the inspection of a field

International Nuclear Information System (INIS)

Kim, Seon Duk; Bang, Hong Sik; Oh, Yon Woo

2002-07-01

A T.A.B(Testing, Adjusting and Balancing) technique, the basic technique of air handling facility, is one of the essential technical items which workers in charge of operation of facilities have to acquire. Especially, through scientific and reasonable inspective procedures, the reduction of energy and guarantee of designed skill have become influential important problems in our time rather than in the past days. Entrepreneurs have required more thorough verify of performances and procedure of test in order to raise the investment efficiency and reduce expenditure. For that reason, I hope that co-operator acquire objective and substantial knowledges about air handling facility so that they are helped from them

The levels of edit. [technical writing in science

Science.gov (United States)

Vanburen, R.; Buehler, M. F.; Wallenbrock, D. (Editor)

1976-01-01

The editorial process is analyzed, and five levels of edit are identified. These levels represent cumulative combinations of nine types of edit: (1) coordination, (2) policy, (3) integrity, (4) screening, (5) copy clarification, (6) Mechanical Style, (7) Language, and (9) substantive. The levels and types of edit, although developed for specific use with external reports at the Jet Propulsion Laboratory, cover the general range of technical editing, especially as it applies to an in-house technical publications organization. Each type of edit is set forth in terms of groups of actions to be performed by the editor. The edit-level concept has enhanced understanding and communication among editors, authors, and publications managers concerning the specific editorial work to be done on each manuscript. It has also proved useful as a management tool for estimating and monitoring cost.

VIRTUAL PHILOSOPHER PROJECT: PHILOSOPHICAL, PEDAGOGICAL AND TECHNICAL ASPECTS

Directory of Open Access Journals (Sweden)

E. V. Kuchinov

2017-01-01

Full Text Available The article describes philosophical and pedagogical aspects of an idea of the ‘virtual philosopher’ project developed at creative sessions at Minin University and technically concretized during interaction with the Laboratory of Mobile Services. ‘Virtual philosopher’ is thought to deliver creative automation of routine operations; producing contingent matter for philosophical processing as well as elements of the philosophical artificial intelligence and forms of ‘artificial life’. Project implementation may lead to the creation of an unparalleled educational technology that functions on the principles of flexibility, nonlinearity, affective inclusion and gamification of the educational process. Based on specific character of problems raised, rhizomatic analysis of the philosophical communities’ requests, assessment of their technical feasibility and technical development, provisions are made on the feasibility, prospects and productivity of this project.

CERN Technical Training Programme: Learning for the LHC!

CERN Multimedia

2003-01-01

In collaboration with AS and AC divisions, the Technical Training Programme is launching EVM Hands-on Tutorials specifically designed for those people involved in the current EVM for LHC exercise. The goal of the EVM Hands-on Training Sessions is to provide insight in Earned Value Management as implemented at CERN. Following this course will enable you to understand the EVM methodology, the tools used at CERN, the procedures used for the data-collection and data-reporting and assist you in analysing cost & schedule variances. The course is an intensive 2-hour 'hands-on' training session. If you are interested in this course, please discuss with your supervisor or your DTO. More information and online registration by EDH are available from the Technical Training web pages: http://www.cern.ch/TechnicalTraining/

CERN Technical Training Programme: Learning for the LHC !

CERN Multimedia

2003-01-01

In collaboration with AS and AC divisions, the Technical Training Programme is launching EVM Hands-on Tutorials specifically designed for those people involved in the current EVM for LHC exercise. The goal of the EVM Hands-on Training Sessions is to provide insight in Earned Value Management as implemented at CERN. Following this course will enable you to understand the EVM methodology, the tools used at CERN, the procedures used for the data-collection and data-reporting and assist you in analysing cost & schedule variances. The course is an intensive 2-hour 'hands-on' training session. If you are interested in this course, please discuss with your supervisor or your DTO. More information and online registration by EDH are available from the Technical Training web pages: http://www.cern.ch/TechnicalTraining/

Organizational structure of technical and tactical training of skilled goalkeepers in football

Directory of Open Access Journals (Sweden)

Shamardin V.N.

2015-02-01

Full Text Available Purpose: to study the structure of technical and tactical training of skilled goalkeepers in football. Material : the study involved 40 goalkeepers in age from 21 to 39 years (team Premier League Championship of Ukraine. According to teacher’s observations were under direct competition activity of skilled goalkeepers. Results : It is shown that the technical and tactical activities goalkeeper characterized by two phases of the game: action to protect and attack. In turn, they include eight typical situations. It was found that in accordance with these typical situations goalkeeper applying a technical and tactical actions. Conclusions : It is recommended to increase the efficiency of the game keeper in protective and offensive actions to use specific and non-specific exercises in a variety of standard situations arising during the match.

78 FR 27963 - Reliability Technical Conference; Notice of Technical Conference

Science.gov (United States)

2013-05-13

... Technical Conference; Notice of Technical Conference Take notice that the Federal Energy Regulatory Commission will hold a Technical Conference on Tuesday, July 9, 2013 from 9:00 a.m. to 5:00 p.m. This... technical support for webcasts and offers the option of listening to the meeting via phone-bridge for a fee...

Yucca Mountain Site Characterization Project Technical Data Catalog (quarterly supplement)

International Nuclear Information System (INIS)

1993-01-01

The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated December 31, 1992, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1993

Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-03-31

The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.

Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed-in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.

A Development of Technical Specification of a Research Reactor with Plate Fuels Cooled by Upward Flow

International Nuclear Information System (INIS)

Park, Sujin; Kim, Jeongeun; Kim, Hyeonil

2016-01-01

The contents of the TS(Technical Specifications) are definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. TS for Nuclear Power Plants (NPPs) have been developed since many years until now. On the other hands, there are no applicable modernized references of TS for research reactors with many differences from NPPs in purpose and characteristics. Fuel temperature and Departure from Nuclear Boiling Ratio (DNBR) are being used as references from the thermal-hydraulic analysis point of view for determining whether the design of research reactors satisfies acceptance criteria for the nuclear safety or not. Especially for research reactors using plate-type fuels, fuel temperature and critical heat flux, however, are very difficult to measure during the reactor operation. This paper described the outline of main contents of a TS for open-pool research reactor with plate-type fuels using core cooling through passive systems, where acceptance criteria for nuclear safety such as CHF and fuel temperature cannot be directly measured, different from circumstances in NPPs. Thus, three independent variables instead of non-measurable acceptance criteria: fuel temperature and CHF are considered as safety limits, i.e., power, flow, and flow temperature

Do technical skills correlate with non-technical skills in crisis resource management: a simulation study.

Science.gov (United States)

Riem, N; Boet, S; Bould, M D; Tavares, W; Naik, V N

2012-11-01

Both technical skills (TS) and non-technical skills (NTS) are key to ensuring patient safety in acute care practice and effective crisis management. These skills are often taught and assessed separately. We hypothesized that TS and NTS are not independent of each other, and we aimed to evaluate the relationship between TS and NTS during a simulated intraoperative crisis scenario. This study was a retrospective analysis of performances from a previously published work. After institutional ethics approval, 50 anaesthesiology residents managed a simulated crisis scenario of an intraoperative cardiac arrest secondary to a malignant arrhythmia. We used a modified Delphi approach to design a TS checklist, specific for the management of a malignant arrhythmia requiring defibrillation. All scenarios were recorded. Each performance was analysed by four independent experts. For each performance, two experts independently rated the technical performance using the TS checklist, and two other experts independently rated NTS using the Anaesthetists' Non-Technical Skills score. TS and NTS were significantly correlated to each other (r=0.45, P<0.05). During a simulated 5 min resuscitation requiring crisis resource management, our results indicate that TS and NTS are related to one another. This research provides the basis for future studies evaluating the nature of this relationship, the influence of NTS training on the performance of TS, and to determine whether NTS are generic and transferrable between crises that require different TS.

Recent productivity developments and technical change in Danish organic farming - stagnation?

DEFF Research Database (Denmark)

Sauer, Johannes; Graversen, Jesper Tranbjerg; Park, Tim

This paper attempts to quantitatively measure the change in the productivity of Dan-ish organic farming in recent years by using panel data on 56 organic farms mainly engaged in milk production for the period 2002 to 2004. Based on a translog pro-duction frontier framework the technical and scale...... efficiency on farm level is ana-lysed by considering also curvature consistency. The total change in productivity for the reference period is measured by using the Malmquist total factor productivity in-dex approach based on a time trends as well as a general index model specification. Input specific bias...... in technical change as well elasticities of input substitution are analyzed. Fators for the development of technical change and the change in effi-ciency over time are investigated by applying a bootstrapped ITSUR technique. Fi-nally we try to conclude on the significance of subsidies for promoting long term...

Guide to good practices for the selection, training, and qualification of shift technical advisors

Energy Technology Data Exchange (ETDEWEB)

1993-02-01

The DOE Guide to Good Practices For The Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

Socio-technical Systems as Place-specific Matters of Concern

DEFF Research Database (Denmark)

Jensen, J. S.; Fratini, C. F.; Cashmore, M. A.

2016-01-01

that urban governance of the wastewater system was influenced by a particular concern with developing attractive and competitive urban spaces. The wastewater system emerged as a ‘place-bound’ and even ‘place-making’ governance concern; as such, the boundaries and functions of the system were subject...... to continuous redefinition at the city level. This urban framing conflicted with the national-level, efficiency-oriented framing of the wastewater system as homogenous, without regard to place-specific differences. The research findings suggest that a distinct characteristic of urban-level governance is concern...... for place-specific development; this concern can be transformative because it leads to ongoing reinterpretation of traditional boundaries and dependencies between large-scale systems and local contexts....

Chemistry of water and steam in power plants and related technologies. Glossary of terms and definitions English - German; German - English

Energy Technology Data Exchange (ETDEWEB)

Schmitz, H.P.; Teutenberg, U.

2006-07-01

This new edition of a technical dictionary is an evaluation of the technical terms found in the domestic and foreign literature and in information brochures of specialist firms, directives, guidelines, standards, etc. This dictionary contains more than 3,000 terms mainly with definitions with respect to the chemistry of water and steam in power plants along with the related types of water (untreated water, feedwater and boiler water, make-up water, waste water) and the water treatment processes (ion exchange, membrane process, etc.), water conditioning and chemical analysis, internal cleaning of steam generating plants (e.g. flushing, boiling-out, pre-operational and operational acid cleaning, steam blowing) as well as fundamentals of water chemistry. The technical knowledge of the authors, Heinz-Peter Schmitz, FDBR, with more than 25 years professional experience as translator/official in charge of documentation and Ulrich Teutenberg, Babcock/Hitachi with more than 30 years professional experience as senior consultant for water chemistry and commissioning is reflected in this dictionary. Part 1 contains the English-German version, Part 2 the German-English version. (orig.)

Recommendations for the Technical Infrastructure for Standardized International Rights Statements

OpenAIRE

Charles, Valentine; Cowles, Esmé; Estlund, Karen; Isaac, Antoine; Johnson, Tom; Matienzo, Mark A.; Peiffer, Patrick; Urban, Richard J.; Zeinstra, Maarten

2015-01-01

This white paper is the product of a joint Digital Public Library of America (DPLA)-Europeana working group organized to develop minimum rights statement metadata standards for organizations that contribute to DPLA and Europeana. This white paper deals specifically with the technical infrastructure of a common namespace (rightsstatements.org) that hosts the rights statements to be used by (at minimum) the DPLA and Europeana. These recommendations for a common technical infrastructure for righ...

A technical basis to relax the dew point specification for the environment in the vapor space in DWPF canisters

International Nuclear Information System (INIS)

Louthan, M.R. Jr.

1995-05-01

This memorandum establishes the technical basis to conclude that relaxing, from 0 C to 20 C, the dew point specification for the atmosphere in the vapor space (free volume) of a DWPF canister will not provide an environment that will cause significant amounts of corrosion induced degradation of the canister wall. The conclusion is based on engineering analysis, experience and review of the corrosion literature. The basic assumptions underlying the conclusion are: (1) the canister was fabricated from Type 304L stainless steel; (2) the corrosion behavior of the canister material, including base metal, fusion zones and heat effected zones, is typified by literature data for, and industrial experience with, 300 series austenitic stainless steels; and (3) the glass-metal crevices created during the pouring operation will not alter the basic corrosion resistance of the steel although such crevices might serve as sites for the initiation of minor amounts of corrosion on the canister wall

Globalizing Technical Communication Programs: Visions, Challenges, and Emerging Directions

DEFF Research Database (Denmark)

Maylath, Bruce; Mousten, Birthe; Vandepitte, Sonia

Speakers Maylath, Mousten and Vandepitte, co-authors of two chapters on what they call the Trans-Atlantic Project, will describe the programmatic framework for establishing the collaborative partnerships in which students studying technical writing in the U.S. work with students studying...... help achieve common program objectives, particularly in regard to intercultural negotiation and mediation processes. In addition, they will describe how they met course-specific objectives. For the technical writing course, such objectives included broadening students' awareness of the needs of readers...... translation in Europe to create procedural documents in Danish, Dutch, English, French, German and/or Italian. They will provide guidelines for  how international partnerships of this kind can be established between technical communication programs and translation programs anywhere, even in the abscence...

Technical Training on High-Order Spectral Analysis and Thermal Anemometry Applications

Science.gov (United States)

Maslov, A. A.; Shiplyuk, A. N.; Sidirenko, A. A.; Bountin, D. A.

2003-01-01

The topics of thermal anemometry and high-order spectral analyses were the subject of the technical training. Specifically, the objective of the technical training was to study: (i) the recently introduced constant voltage anemometer (CVA) for high-speed boundary layer; and (ii) newly developed high-order spectral analysis techniques (HOSA). Both CVA and HOSA are relevant tools for studies of boundary layer transition and stability.

LEU fuel powder technology at Babcock and Wilcox (USA)

International Nuclear Information System (INIS)

Bogacik, K.E.

1984-01-01

This paper traces BandW involvement in HEU fuel manufacturing to the current work directed at LEU reactor technology. Past work at BandW in areas such as alloying, fuel handling and core manufacturing has been of significant benefit to the current LEU fuel processing requirements. Recent investigations and process developments for production of LEU aluminide and silicide fuels are discussed. Techniques for alloying by vacuum are melting, followed by comminution methods after alloying, are presented for both the LEU aluminide and silicide fuel powders. Powder processing discussions include compacting techniques used by BandW for these alloys. This overview of BandW's LEU i nvolvement provides details of specific modifications and process developments in powdered fuels. Product attributes such as powder chemistry, size, and other physical properties of each LEU fuel are presented. (author)

Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-09-01

The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations

Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

International Nuclear Information System (INIS)

Little, C.A.

1995-01-01

The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author's responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A

[Evaluation of technical skills in surgical training].

Science.gov (United States)

Kasparian, Andres C; Martinez, A C; JoverClos, R J; Chércoles, R A

2014-01-01

technical skills acquisition is considered to be of paramount importance in surgical training. Yet, formal assessment of technical skills is the weakest and less developed area. Currently available resources to evaluate technical skills are largely subjective, and lack of validity and reliability. Direct observation, one of the most frequently used methods, is largely biased by interpersonal subjectivity and personality traits. We propose the creation and use of a new procedure-specific tool for objective assessment of technical skills in surgery to evaluate validity and reliability. laparoscopic cholecystectomy and Lichstenstein's inguinal hernia repair were the chosen procedures. Three groups of comparison were defined according to surgical expertise: initial, intermediate, and experts. Surgeries were videorecorded in real time without identification of the patient or the surgeon. Tapes without any posterior edition were assigned to two expert surgeons in a blind and randomized sequence. A newly proposed procedure-specific rating scale was used for evaluation, as well as Reznick's OSATS global scale. Kruskal-Wallis non-parametric test was used to assess validity. p 0.8 granted reliability. from April 2010 to December 2012 36 laparoscopic cholecystectomies and 31 inguinal hernia repairs were recorded. Significant difference was found among groups of comparison for every item (ptechnical skills in surgery is feasible and useful. The tool we proposed showed construct validity and reliability. Video recording of surgical procedures grants durability over time to an ephemeral phenomenon. The objectivity is based on the explicit statements and quantification of every step to be evaluated, and the blind randomization and anonymous treatment of the sample. Sharing the same quality criteria between evaluators is of paramount importance to reach satisfactory results. The process of evaluation always implies a shortened view of the reality.

Career and Technical Education. 2016 Annual Report

Science.gov (United States)

Utah System of Higher Education, 2016

2016-01-01

Career and Technical Education (CTE) is a key ingredient to meet the needs of Utah's economy. Utah System of Higher Education (USHE) institutions offer CTE programs in all regions of the state, working closely with local business and industry leaders to develop and deliver programs specifically tailored to local workforce development needs. This…

Career and Technical Education. 2015 Annual Report

Science.gov (United States)

Utah System of Higher Education, 2015

2015-01-01

Career and Technical Education (CTE) is a key ingredient to meet the needs of Utah's economy. Utah System of Higher Education (USHE) institutions offer CTE programs in all regions of the state, working closely with local business and industry leaders to develop and deliver programs specifically tailored to local workforce development needs. This…

Technical description of other types of reactors

International Nuclear Information System (INIS)

Vollmer, H.

1977-01-01

The paper reviews the development of reactor systems other than LWR, i. e. gas cooled reactors, heavy water reactors and fast breeders. The specific features of these reactors are discussed. Technical details on plant design of the various systems will be given as well as the present status-of-the-art. (orig.) [de

Design Specifications for Adaptive Real-Time Systems

Science.gov (United States)

1991-12-01

TICfl \\ E CT E Design Specifications for JAN’\\ 1992 Adaptive Real - Time Systems fl Randall W. Lichota U, Alice H. Muntz - December 1991 \\ \\\\/ 0 / r...268-2056 Technical Report CMU/SEI-91-TR-20 ESD-91-TR-20 December 1991 Design Specifications for Adaptive Real - Time Systems Randall W. Lichota Hughes...Design Specifications for Adaptive Real - Time Systems Abstract: The design specification method described in this report treats a software

Objectives, specification and elaboration of technical scenarios for emergency drills involving a French PWR

International Nuclear Information System (INIS)

Duco, J.

1989-08-01

All safety measures taken during the design, the construction and the operation of a nuclear power plant decrease to an extremely low level the probability of an accident with unacceptable consequences for the public. Nevertheless, for the case such an accident should be initiated, emergency plans have been elaborated: the on-site emergency plan to protect the plant personnel, terminate the accident and mitigate the consequences; the short-term and longer-term off-side emergency plans to protect the public and organise the return to acceptable living conditions. The appropriateness and preparedness of such plans have to be checked regularly by means of drills, which may be restricted to technical aspects concerning the nuclear units, or involve all actors, i.e. the utility, all the branches of the administration concerned and a media simulation. Some aspects of the choice of goals and preparation of drills are presented and illustrated by the national EPAULE exercice in 1987. Technically speaking, the drills have proved the validity of the current organization and evidenced its operability: uncertainties remain as regards the actual vs expected behavior of the population, due to emotional aspects linked to the lack of direct perception of the degree of danger and to the information received in an actual nuclear emergency

Bottomland Hardwood Planting: Example Contract Specifications

National Research Council Canada - National Science Library

Humprey, Monica

2002-01-01

This technical note provides an example of contract specifications that can be used as a template by USACE biologists, engineers, or contracting officers for contracting the planting of bottomland hardwood (BLH) seedlings...

Technical Support Essentials Advice to Succeed in Technical Support

CERN Document Server

Sanchez, Andrew

2010-01-01

Technical Support Essentials is a book about the many facets of technical support. It attempts to provide a wide array of topics to serve as points of improvement, discussion, or simply topics that you might want to learn. The topics range from good work habits to the way technical supportgroups establish their own style of work. This book applies theories, models, and concepts synthesized from existing research in other fields-such as management, economics, leadership, and psychology-and connects them to technical support. The goal is to build on the work of others and allow their success to

Relationship between intraoperative non-technical performance and technical events in bariatric surgery.

Science.gov (United States)

Fecso, A B; Kuzulugil, S S; Babaoglu, C; Bener, A B; Grantcharov, T P

2018-03-30

The operating theatre is a unique environment with complex team interactions, where technical and non-technical performance affect patient outcomes. The correlation between technical and non-technical performance, however, remains underinvestigated. The purpose of this study was to explore these interactions in the operating theatre. A prospective single-centre observational study was conducted at a tertiary academic medical centre. One surgeon and three fellows participated as main operators. All patients who underwent a laparoscopic Roux-en-Y gastric bypass and had the procedures captured using the Operating Room Black Box ® platform were included. Technical assessment was performed using the Objective Structured Assessment of Technical Skills and Generic Error Rating Tool instruments. For non-technical assessment, the Non-Technical Skills for Surgeons (NOTSS) and Scrub Practitioners' List of Intraoperative Non-Technical Skills (SPLINTS) tools were used. Spearman rank-order correlation and N-gram statistics were conducted. Fifty-six patients were included in the study and 90 procedural steps (gastrojejunostomy and jejunojejunostomy) were analysed. There was a moderate to strong correlation between technical adverse events (r s  = 0·417-0·687), rectifications (r s  = 0·380-0·768) and non-technical performance of the surgical and nursing teams (NOTSS and SPLINTS). N-gram statistics showed that after technical errors, events and prior rectifications, the staff surgeon and the scrub nurse exhibited the most positive non-technical behaviours, irrespective of operator (staff surgeon or fellow). This study demonstrated that technical and non-technical performances are related, on both an individual and a team level. Valuable data can be obtained around intraoperative errors, events and rectifications. © 2018 BJS Society Ltd Published by John Wiley & Sons Ltd.

Performance specifications for proton medical facility

Energy Technology Data Exchange (ETDEWEB)

Chu, W.T.; Staples, J.W.; Ludewigt, B.A.; Renner, T.R.; Singh, R.P.; Nyman, M.A.; Collier, J.M.; Daftari, I.K.; Petti, P.L.; Alonso, J.R. [Lawrence Berkeley Lab., CA (United States); Kubo, H.; Verhey, L.J. [University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine; Castro, J.R. [Lawrence Berkeley Lab., CA (United States)]|[University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine

1993-03-01

Performance specifications of technical components of a modern proton radiotherapy facility are presented. The technical items specified include: the accelerator; the beam transport system including rotating gantry; the treatment beamline systems including beam scattering, beam scanning, and dosimetric instrumentation; and an integrated treatment and accelerator control system. Also included are treatment ancillary facilities such as diagnostic tools, patient positioning and alignment devices, and treatment planning systems. The facility specified will accommodate beam scanning enabling the three-dimensional conformal therapy deliver .

A process for integrating public involvement into technical/social programs

International Nuclear Information System (INIS)

Wiltshire, S.; Williams, C.

1994-01-01

Good technical/social decisions--those that are technically sound and publicly acceptable--result from a planning process that considers consulting the public a basic part of the technical program, as basic as hiring a technical consultant to advise about new ideas in computer modeling. This paper describes a specific process for making public involvement an integral part of decision-making about high-level radioactive waste management, so that important technical, social, environmental, economic, and cultural information and values can be incorporated in a meaningful way in planning and carrying out a high-level waste management program or project. The process for integration must consider: (a) the decision or task for which public interaction is needed; (b) the people who should or will want to participate in the decision or task; (c) the goals or purposes of the communication or interaction--the agency's and the public's; (d) the kinds of information the public needs and that the agency needs in order to understand the relevant technical and social issues; and (e) the types of communication or involvement that best serve to meet the agency's and the public's goals

Imagining Technicities

DEFF Research Database (Denmark)

Liboriussen, Bjarke; Plesner, Ursula

2011-01-01

to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

Assessment of technical risks and R and D requirements for a magnetic confinement fusion fuel system. Final report

International Nuclear Information System (INIS)

DeFreece, D.A.

1983-11-01

This report documents a specific use and results of a novel technique for assessing the technical risks associated with the hardware development of a possible future commercial fusion power plant fuel system. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications. A technical risk assessment is the quantification of this risk. This Technical Risk Assessment (TRA) methodology was applied to a deuterium-tritium fuel system for a magnetic-confinement fusion power plant. The fuel system is defined to support a generic commercial reactor with at least two viable options for each critical subsystem. Each subsystem option is defined in detail including nominal performance requirements and subsystem interfaces. Subsystem experts were canvassed to obtain values for past, present and future technical performance parameters for each of the subsystem options. These forecasts are presented as probabilities of achieving given levels of performance in specific time periods for assumed funding scenarios. Several funding scenarios were examined to discern whether performance limitations are caused by funding or technology. A computerized Fuel System simulation is described which uses these subsystem performance parameter forecasts as inputs

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Switzerland (please sp...

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Swi...

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Monday 9 February 2004 From 10:00 to 12:00 - IT Auditorium - bldg. 31, 3rd floor ANSOFT High-Frequency Seminar David Prestaux, Application Engineer, ANSOFT F-78535 BUC, France This Technical Training seminar will present two Ansoft application products: Ansoft HFSS and Ansoft Designer. Ansoft HFSS makes use of the Finite Element Method (FEM) to calculate field solutions from first principles. It can accurately predict all high-frequency behaviours such as dispersion, mode conversion, and losses due to materials and radiation. Ansoft Designer is a suite of design tools to fully integrate high-frequency, physics-based electromagnetic simulations into a seamless system-level simulation environment. Ansoft Designer uses a simple interface to give complete control over every design task, by a method allowing multiple solvers, Solver on Demand. • Introduction • Overview of the Ansoft Total solution • Ansoft HFSS 9...

A Technical Analysis Information Fusion Approach for Stock Price Analysis and Modeling

Science.gov (United States)

Lahmiri, Salim

In this paper, we address the problem of technical analysis information fusion in improving stock market index-level prediction. We present an approach for analyzing stock market price behavior based on different categories of technical analysis metrics and a multiple predictive system. Each category of technical analysis measures is used to characterize stock market price movements. The presented predictive system is based on an ensemble of neural networks (NN) coupled with particle swarm intelligence for parameter optimization where each single neural network is trained with a specific category of technical analysis measures. The experimental evaluation on three international stock market indices and three individual stocks show that the presented ensemble-based technical indicators fusion system significantly improves forecasting accuracy in comparison with single NN. Also, it outperforms the classical neural network trained with index-level lagged values and NN trained with stationary wavelet transform details and approximation coefficients. As a result, technical information fusion in NN ensemble architecture helps improving prediction accuracy.

[Flexible ENT endoscopy--video technic].

Science.gov (United States)

Rasinger, G A; Horak, F

1985-02-01

This study discusses the solutions to the problem of documenting moving processes in the field of otolaryngology. A flexible bronchoscope and video equipment connected to it are presented as a specific solution of the problem, with ample of observations. A technical comparison is used as the basis for a discussion of the pros and cons of the video and film techniques. A successful arrangement of examination facilities illustrates the future of flexible-endoscope techniques in the field of otolaryngology.

Technical indicators of financial performance in the dairy herd

DEFF Research Database (Denmark)

Kristensen, Erling Lundager; Østergaard, Søren; Krogh, Mogens Agerbo

2008-01-01

Monte Carlo simulation was used to predict the long-term financial performance related to the technical performance of dairy herds. The indicators addressed were derived from data collected routinely in the herd. They indicated technical performance that can be affected by the farmer...... or the consultant, and they were derived from expected cause-effect relations between technical performance and financial performance at the herd level. The study included the indicators shape of lactation curve, reproduction efficiency, heifer management, variation between cows in lactation curve persistency...... cow was analyzed as the measure of financial performance. The potential effects of the selected indicators on the gross margin were estimated by means of an ANOVA. The final model allowed estimation of the financial value of specific changes within the key performance indicators. This study indicated...

Technical discussions on Emissions and Atmospheric Modeling (TEAM)

Science.gov (United States)

Frost, G. J.; Henderson, B.; Lefer, B. L.

2017-12-01

A new informal activity, Technical discussions on Emissions and Atmospheric Modeling (TEAM), aims to improve the scientific understanding of emissions and atmospheric processes by leveraging resources through coordination, communication and collaboration between scientists in the Nation's environmental agencies. TEAM seeks to close information gaps that may be limiting emission inventory development and atmospheric modeling and to help identify related research areas that could benefit from additional coordinated efforts. TEAM is designed around webinars and in-person meetings on particular topics that are intended to facilitate active and sustained informal communications between technical staff at different agencies. The first series of TEAM webinars focuses on emissions of nitrogen oxides, a criteria pollutant impacting human and ecosystem health and a key precursor of ozone and particulate matter. Technical staff at Federal agencies with specific interests in emissions and atmospheric modeling are welcome to participate in TEAM.

CERN Technical Training Programme: Learning for the LHC !

CERN Multimedia

2003-01-01

CLEAN-2002: Working in a Cleanroom CLEAN-2002 is a free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific problems put forward beforehand by attendees will also be addressed. If you are interested in CLEAN-2002, please discuss with your supervisor or your DTO. More information and online registration by EDH are available from the Technical Training pages: http://www.cern.ch/TechnicalTraining/ The next session, in English, will be on Friday, 11 April 2003 (afternoon). Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

Competition and safety as reflected in the legislation concerning technical supervision - are they incompatible

International Nuclear Information System (INIS)

Roth, H.A.

1986-01-01

The author discusses the conflicts between competition and safety in the legislation on technical supervision, the requirements on specific sectors, and the consequences of the concentration of the functions of technical supervision in the hands of the Technical Supervisory Board (TUEV). The demand to give more room for competition is found to have no legal basis in fundamental law. It therefore rests with the legislator to concert the one with the other. (orig./HP) [de

Innovation and Diffusion of Site-specific Crop Management

DEFF Research Database (Denmark)

Pedersen, Søren Marcus; Pedersen, Jørgen Lindgaard

2006-01-01

Site-specific crop management or precision farming is a highly complex managementsystem for site-specific input application of lime, fertilizers and pesticides in arable farming. The Global Positioning System (GPS)is the backbone of the system. To conduct precision farming several technical systems...

Aspects of the role of scientific-technical expert knowledge in administrative court procedures on licensing of large technical projects

International Nuclear Information System (INIS)

Wagner, H.

1983-01-01

On the basis of atomic energy law, the author explains some specific problems associated with the respective roles of experts (or expert bodies) and courts of law. In legal theory, it is comparatively easy to draw the line between the two functions, but in practice this delimination meets with difficulties. Finally, the author proposes to improve the definitions of the respective functions of experts (expert bodies) and courts of law in procedures dealing with permits of large technical facilities as follows: A highly qualified, independent body of experts in a technically representative composition lays down, in a binding way, the main elements of the safety standard of a specific plant or type of plant. The responsible administrative authority, after having examined all other legal conditions, grants the permit for that plant. There are no objections to such a model in the light either of aspects of constitutional law or of legal policy or constitutional policy, not are there any practical reasons against this approach. The only doubtful aspect is the present political feasibility. (orig.) [de

Briefing Products - Tools for Communicating Technical Issues to a Non-Technical Audience

International Nuclear Information System (INIS)

Clark, Harvey; Foster, Kevin T.

2011-01-01

Briefing Products are a new NARAC/IMAAC product line designed to communicate the consequences of a radiological, nuclear, chemical or biological agent incident to non-technical decision makers and key leaders. Each Briefing Product addresses a single decision or issue focused on potential actions that should be considered when responding to a hazard, while avoiding the use of technical or regulatory jargon. Briefing Products do not make protective action recommendations, although they do concretely assist decision-makers with development of their own protective actions by quoting or paraphrasing the published guidance relevant to the decision at hand. Briefing Products are produced in sets tailored to specific types of incident which together depict the key decisions and characteristics of the incident. Each Briefing Product in the set consists of three elements: (1) Primary Effects, (2) Key Points and (3) Presenter Notes. Both the Primary Effects and Key Points are ready for direct presentation, while the Presenter Notes are designed to provide background information to the presenter and are not for direct presentation to the audience. The Briefing Products themselves are alternative presentations of results from the customary standard NARAC/IMAAC technical products. Currently, Briefing Products are available for detonation of both RDDs (Radiological Dispersal Devices) and INDs (Improvised Nuclear Devices). A new set of products tailored to nuclear power plant (NPP) accidents is currently under development. This paper describes the scope, structure and content of the Briefing Product sets. Examples from the two sets of Briefing Products now available are presented.

Re-Engineering Vocational and Technical Education for Sustainable ...

African Journals Online (AJOL)

Using the case of North Central Geo-Political Zone of Nigeria, this study interrogates the nexus between vocational and technical education (VTE) and sustainable development. Specific attention is put on provision and attainment of basic skills on one hand and job creation, self-employment, utilization of locally available ...

Determinants of technical inefficiency among maize-based farming ...

African Journals Online (AJOL)

Examining the level of farm-specific technical inefficiency of maize-based farming households in Niger state of Nigeria, this study fitted cross-sectional data into a Cobb- Douglass production frontier. Data used for this study were obtained using structured questionnaire administered to 108 randomly selected maize-based ...

IAEA technical co-operation with least developed Member States. Special evaluation

International Nuclear Information System (INIS)

1993-01-01

The main purposes of this evaluation were to: Review the overall situation with regard to IAEA technical co-operation with least developed Member States, including specific conditions in nuclear-related activities prevailing in these countries, approaches and practices used by the IAEA in providing assistance to LDCs, and the main results of the co-operation in question. Identify any adjustments to technical co-operation with LDC Member States that may strengthen this activity

Innovation and diffusion of site-specific crop management

DEFF Research Database (Denmark)

Pedersen, Søren Marcus; Pedersen, Jørgen Lindgaard

2004-01-01

Site-specific crop management or precision farming (PF) is a highly complex management system for site-specific input application of lime, fertilizers and pesticides in arable farming. The Global Positioning System (GPS) is the backbone of the system. To conduct PF several technical systems...

Technical Support Document for Version 3.4.0 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2007-09-14

COMcheck provides an optional way to demonstrate compliance with commercial and high-rise residential building energy codes. Commercial buildings include all use groups except single family and multifamily not over three stories in height. COMcheck was originally based on ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989) requirements and is intended for use with various codes based on Standard 90.1, including the Codification of ASHRAE/IES Standard 90.1-1989 (90.1-1989 Code) (ASHRAE 1989a, 1993b) and ASHRAE/IESNA Standard 90.1-1999 (Standard 90.1-1999). This includes jurisdictions that have adopted the 90.1-1989 Code, Standard 90.1-1989, Standard 90.1-1999, or their own code based on one of these. We view Standard 90.1-1989 and the 90.1-1989 Code as having equivalent technical content and have used both as source documents in developing COMcheck. This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards.

Endogenous induced technical change and the costs of Kyoto

International Nuclear Information System (INIS)

Buonanno, Paolo; Carraro, Carlo; Galeotti, M.

2001-09-01

Many predictions and conclusions in the climate change literature have been made and drawn on the basis of theoretical analyses and quantitative models that are either static or that allow for simple forms of changes in technology, often along exogenously given time paths. It is therefore not clear a priori whether those conclusions and policy recipes still hold in the more realistic case of endogenously evolving technologies. In this paper, a quantitative tool with the features of an endogenous growth model is presented, which also accounts for the possibility that technical change can be induced by environmental policy measures. Both the output production technology and the emission-output ratio depend upon the stock of knowledge, which accumulates through R and D activities. R and D is thus an additional policy variable that comes into play along with pollution abatement and capital investment. Two versions of this climate model are studied, one with endogenous technical change but exogenous environmental technical change (i.e. no induced technical change) and the other with both endogenous and induced technical change. Hence, in both models technical change evolves endogenously as far as the production technology is concerned, but endogenous environmental (or induced) technical change is only accounted for in the second version. Finally, a third version of the model also captures technological spillover effects. As an application, the three versions of the model are simulated allowing for trade of pollution permits as specified in the Kyoto Protocol and assessing the implications in terms of cost efficiency, economic growth and R and D efforts of the three different specifications of technical change

Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

International Nuclear Information System (INIS)

1999-09-01

This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

76 FR 16785 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

Science.gov (United States)

2011-03-25

... designed as an interactive forum where PSOs and software developers can provide input on these technical... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability.... Throughout the meeting there will be interactive discussion to allow meeting participants not only to provide...

PET/MRI: Technical challenges and recent advances

International Nuclear Information System (INIS)

Jung, Jin Ho; Choi, Yong; Im, Ki Chun

2016-01-01

Integrated positron emission tomography (PET)/magnetic resonance imaging (MRI), which can provide complementary functional and anatomical information about a specific organ or body system at the molecular level, has become a powerful imaging modality to understand the molecular biology details, disease mechanisms, and pharmacokinetics in animals and humans. Although the first experiment on the PET/MRI was performed in the early 1990s, its clinical application was accomplished in recent years because there were various technical challenges in integrating PET and MRI in a single system with minimum mutual interference between PET and MRI. This paper presents the technical challenges and recent advances in combining PET and MRI along with several approaches for improving PET image quality of the PET/MRI hybrid imaging system

Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants

International Nuclear Information System (INIS)

Norte Gomez, M.D.; Alcantud, F.; Hoyo, C. del

1993-01-01

Technical Specifications (TS) form one of the basic documents necessary for licensing nuclear power plants and are required by the Government in accordance with Article 26 of the Regulation for Nuclear and Radioactive Facilities. They contain specific plant characteristics and operating limits to provide adequate protection for the safety and health of operators and the general public. For operator actuation, TS include all the surveillance requirements and limiting operating conditions (operation at full power, startup, hot and cold shutdown, and refueling outage) of safety-related systems. They also include the conventional support systems which are necessary to keep the plant in a safe operating conditioner to bring it to safe shutdown in the event of incidents or hypothetical accidents. Because of the large volume of information contained in the TS, the NRC and American utility owners began to simplify and improve the initial standard TS, which has given way to the development of a TS Optimization Program in the USA under the auspices of the NRC. Empresarios Agrupados has been contracted by the BWR Spanish Owners' Group (GPE-BWR) to develop optimized TS for the Santa Maria de Garona and Cofrentes Nuclear Power Plants. The optimized and improved TS are simplified versions of the current ones and facilitate the work of plant operators. They help to prevent risks, and reduce the number of potential transients caused by the large number of tests required by current TS. Plant operational safety is enhanced and higher effective operation is achieved. The GPE-BWR has submitted the first part of the optimized TS with their corresponding Bases to the Spanish Nuclear Council (CSN), for comment and subsequent approval. Once the TS are approved by the Spanish Nuclear Council, the operators of the Santa Maria de Garona and Cofrentes Nuclear Power Plants will be given a training and adaptation course prior to their implementation. (author)

CERN Technical Training Programme: Learning for the LHC!

CERN Multimedia

CLEAN-2002: Working in a Cleanroom CLEAN-2002 is a free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific problems put forward beforehand by attendees will also be addressed. If you are interested in CLEAN-2002, please discuss with your supervisor or your DTO. More information and online registration by EDH are available from the Technical Training pages: http://www.cern.ch/TechnicalTraining/ The next session in French will be on Thursday, 4 September 2003 (afternoon), and in English on Thursday, 23 October 2003 (afternoon). Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

Sensitivity of Technical Efficiency Estimates to Estimation Methods: An Empirical Comparison of Parametric and Non-Parametric Approaches

OpenAIRE

de-Graft Acquah, Henry

2014-01-01

This paper highlights the sensitivity of technical efficiency estimates to estimation approaches using empirical data. Firm specific technical efficiency and mean technical efficiency are estimated using the non parametric Data Envelope Analysis (DEA) and the parametric Corrected Ordinary Least Squares (COLS) and Stochastic Frontier Analysis (SFA) approaches. Mean technical efficiency is found to be sensitive to the choice of estimation technique. Analysis of variance and Tukey’s test sugge...

Technical evaluation of RETS-required reports for Rancho Seco Nuclear Generating Station, Unit 1 for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Rancho Seco Nuclear Generating Station, Unit 1 were the Semiannual Effluent Release Report, January 1, 1983 to June 30, 1983 and the Radiation Exposure, Environmental Protection, Effluent and Waste Disposal Report. The principal review guidelines were the plant's specific RETS which were based on NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Technical innovation and management

Energy Technology Data Exchange (ETDEWEB)

Yoon, Yang Cheol

1982-08-15

This book gives explanations of the conception of technical innovation, development plan in Korea, connection between technology and a growth factor in national income, problem of technical innovation in developing country, analysis on cooperation between a developed country and a developing country, evaluation and strategy of technical development in Korea, technical innovation of industry, management of technical industry, analysis of special condition in Korea.

Technical innovation and management

International Nuclear Information System (INIS)

Yoon, Yang Cheol

1982-08-01

This book gives explanations of the conception of technical innovation, development plan in Korea, connection between technology and a growth factor in national income, problem of technical innovation in developing country, analysis on cooperation between a developed country and a developing country, evaluation and strategy of technical development in Korea, technical innovation of industry, management of technical industry, analysis of special condition in Korea.

Pedagogical characteristics of the systems for assessing the technical and tactical skills of qualified volleyball players

Directory of Open Access Journals (Sweden)

Мykhailo Oliinyk

2017-12-01

Full Text Available Purpose: on the basis of the analysis of the special literature and their own experimental studies, to determine the characteristics of the systems for assessing the technical and tactical skills of qualified volleyball players. Material & Methods: study was conducted on the basis of the material of the national team of Zaporozhye State Medical University on volleyball. Analysis and generalization of the data of scientific and methodical literature are used; registration, analysis and interpretation of indicators of technical and tactical actions of qualified volleyball players in training and competitive processes; pedagogical observations; algorithms for calculating the quantitative and qualitative indicators of technical and tactical skill in volleyball; methods of mathematical statistics. Results: data on the existence of a strong statistical relationship between the systems of assessment of technical and tactical skills of qualified volleyball players, taking into account the specificity of the game role. Conclusion: shows the specifics of the application of various systems for assessing the technical and tactical skills of qualified volleyball players, taking into account the factors of the game role, noted the methodological features of special analysis and interpretation of indicators of technical and tactical actions in the adversarial process.

LARGE-SCALE MECURY CONTROL TECHNOLOGY TESTING FOR LIGNITE-FIRED UTILITIES-OXIDATION SYSTEMS FOR WET FGD

Energy Technology Data Exchange (ETDEWEB)

Michael J. Holmes; Steven A. Benson; Jeffrey S. Thompson

2004-03-01

The Energy & Environmental Research Center (EERC) is conducting a consortium-based effort directed toward resolving the mercury (Hg) control issues facing the lignite industry. Specifically, the EERC team--the EERC, EPRI, URS, ADA-ES, Babcock & Wilcox, the North Dakota Industrial Commission, SaskPower, and the Mercury Task Force, which includes Basin Electric Power Cooperative, Otter Tail Power Company, Great River Energy, Texas Utilities (TXU), Montana-Dakota Utilities Co., Minnkota Power Cooperative, BNI Coal Ltd., Dakota Westmoreland Corporation, and the North American Coal Company--has undertaken a project to significantly and cost-effectively oxidize elemental mercury in lignite combustion gases, followed by capture in a wet scrubber. This approach will be applicable to virtually every lignite utility in the United States and Canada and potentially impact subbituminous utilities. The oxidation process is proven at the pilot-scale and in short-term full-scale tests. Additional optimization is continuing on oxidation technologies, and this project focuses on longer-term full-scale testing. The lignite industry has been proactive in advancing the understanding of and identifying control options for Hg in lignite combustion flue gases. Approximately 1 year ago, the EERC and EPRI began a series of Hg-related discussions with the Mercury Task Force as well as utilities firing Texas and Saskatchewan lignites. This project is one of three being undertaken by the consortium to perform large-scale Hg control technology testing to address the specific needs and challenges to be met in controlling Hg from lignite-fired power plants. This project involves Hg oxidation upstream of a system equipped with an electrostatic precipitator (ESP) followed by wet flue gas desulfurization (FGD). The team involved in conducting the technical aspects of the project includes the EERC, Babcock & Wilcox, URS, and ADA-ES. The host sites include Minnkota Power Cooperative Milton R. Young

Development of knowledge models by linguistic analysis of lexical relationships in technical documents

International Nuclear Information System (INIS)

Seguela, Patrick

2001-01-01

This research thesis addresses the problem of knowledge acquisition and structuring from technical texts, and the use of this knowledge in the development of models. The author presents the Cameleon method which aims at extracting binary lexical relationships from technical texts by identifying linguistic markers. The relevance of this method is assessed in the case of four different corpuses: a written technical corpus, an oral technical corpus, a corpus of texts of instructions, and a corpus of academic texts. The author reports the development of a model of representation of knowledge of a specific field by using lexical relationships. The method is then applied to develop a model used in document search within a knowledge management system [fr

Technical/economical analysis of bioenergy systems

International Nuclear Information System (INIS)

Solantausta, Y.

1998-01-01

The objectives of the IEA Bioenergy Technoeconomic Analysis Activity are: (1) To promote development of thermochemical biomass conversion methods by carrying out selected site specific feasibility studies in participating countries. Both agricultural and woody biomasses will be converted either into electricity or boiler fuels; (2) To compare advanced technologies to commercial alternatives based on technoeconomic basis to establish future development needs, and (3) To facilitate information exchange between participants on relevant basic process issues. Five countries (Finland, Canada, USA, Norway, Austria) are participating to the Activity. Initially two feasibility studies are planned for each country. Each study has three common elements: site specific, technical, and economic data. The site specific cases are described below in short. Products in the cases are electricity, heat and fuel oil. Total of two cases per country are planned. (orig.)

Technical evaluation of RETS-required reports for Zion Nuclear Power Station, Units 1 and 2 for 1983

International Nuclear Information System (INIS)

Young, T.E.; Magleby, E.H.

1985-01-01

A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Commonwealth Edison's Zion Nuclear Power Station during 1983. The two periodic reports reviewed: (1) were the Effluent and Waste Disposal Semiannual Report, July-December 1983, and (2) the Radioactive Waste and Environmental Monitoring Annual Report - 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

A method for strategic technical life cycle management of real estates

OpenAIRE

Koskelo, Taina

2005-01-01

This research study focuses on the strategic technical life cycle management (TLCM) of real estate. In the early phases of the study it became clear that very often the performance of TLCM was not perceived as satisfactory: there were problems in the purchasing and provision of technical services, TLCM was not performed according to real estate specific needs and objective-setting for building characteristics did not serve cost-effective ownership. The study focuses on four research quest...

A technical approach to groundwater contamination problems

International Nuclear Information System (INIS)

Burton, J.C.; Leser, C.; Rose, C.M.

1993-01-01

Argonne National Laboratory has been performing technical investigations at sites in Nebraska and Kansas that have identified groundwater contamination by carbon tetrachloride. This comprehensive program will ultimately provide the affected communities with safe drinking water. The first step in the program is to evaluate the available data and identify sites that will require an Alternate Water Supply Study (AWSS). The objective of the AWSS is to identify options for providing a safe drinking water supply to all users, in compliance with the Safe Drinking Water Act. The AWSS consists of an engineering and cost evaluation followed by implementation of the selected alternative. For sites with contamination less than a specific concentration, the AWSS is regarded as a satisfactory long term solution, and no further action is taken. For those sites with concentrations above that specific limit, the AWSS implementation is regarded as only a stopgap measure, and the site is selected for additional remedial action. The first step of the remedial action is an Expedited Site Characterization (ESC). The ESC was developed at Argonne to decrease the cost and time of the remedial investigation and feasibility study while producing a high-quality technical investigation. The ESC is designed to characterize the contaminant plume configuration and movement, which requires an understanding of the geological and hydrogeologic controls on groundwater movement as well as the nature and extent of any remaining carbon tetrachloride source in the soils. The ESC program uses a multidisciplinary technical approach that incorporates geology, geochemistry, geohydrology, and geophysics. Field activities include sampling, chemical analysis, and borehole and surface geophysical surveys

Airway management by the general practitioner in trauma patients. Technical and non-technical skills

Directory of Open Access Journals (Sweden)

Juan David Dominguez-Sánchez

2016-07-01

Full Text Available General practitioners must constantly face challenges imposed by their profession when performing interventions that are necessary for their patients. Many of these interventions not only require proper use of theoretical knowledge, but also putting into practice non-technical and psychomotor skills developed through professional training. Given the specific characteristics of each patient, the clinical setting in the which procedure takes place and the limited skills of the professional, the management of the airway of a patient with trauma injuries in the emergency room represents a major challenge for physicians.

How to develop and write a case for technical writing

Science.gov (United States)

Couture, B.; Goldstein, J.

1981-01-01

Case of different sizes and shapes for teaching technical writing to engineers at Wayne State University have been developed. The case approach was adopted for some assignments because sophomores and juniors lacked technical expertise and professional knowledge of the engineering world. Cases were found to be good exercises, providing realistic practice in specific writing tasks or isolating particular skills in the composing process. A special kind of case which narrates the experiences of one technical person engaged in the problem-solving process in a professional rhetorical situation was developed. This type of long, realistic fiction is called a an "holistic" case. Rather than asking students to role-play a character, an holistic case realistically encompasses the whole of the technical writing process. It allows students to experience the total communication act in which the technical task and data are fully integrated into the rhetorical situation and gives an opportunity to perform in a realistic context, using skills and knowledge required in communication on the job. It is believed that the holistic case most fully exploits the advantages of the case method for students of professional communication.

Technical Network

CERN Multimedia

2007-01-01

In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Technical Exchange Meeting

Energy Technology Data Exchange (ETDEWEB)

Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-09-01

During FY13, the INL developed an advanced SMR PRA framework which has been described in the report Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Detailed Technical Framework Specification, INL/EXT-13-28974 (April 2013). In this framework, the various areas are considered: Probabilistic models to provide information specific to advanced SMRs Representation of specific SMR design issues such as having co-located modules and passive safety features Use of modern open-source and readily available analysis methods Internal and external events resulting in impacts to safety All-hazards considerations Methods to support the identification of design vulnerabilities Mechanistic and probabilistic data needs to support modeling and tools In order to describe this framework more fully and obtain feedback on the proposed approaches, the INL hosted a technical exchange meeting during August 2013. This report describes the outcomes of that meeting.

Compilation of Sandia Laboratories technical capabilities

International Nuclear Information System (INIS)

Lundergan, C.D.; Mead, P.L.

1975-11-01

This report is a compilation of 17 individual documents that together summarize the technical capabilities of Sandia Laboratories. Each document in this compilation contains details about a specific area of capability. Examples of application of the capability to research and development problems are provided. An eighteenth document summarizes the content of the other seventeen. Each of these documents was issued with a separate report number (SAND 74-0073A through SAND 74-0091, except -0078)

Restructuring of technical standards for regulation of nuclear power plants in Japan

International Nuclear Information System (INIS)

Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

2005-01-01

Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

Technical specifications of variable speed motors for negative pressure control in hot cell area

Energy Technology Data Exchange (ETDEWEB)

Kim, Seon Duk; Bang, H. S.; Cho, W. K