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Sample records for proposed technical specification

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. Technical specification use and application

    International Nuclear Information System (INIS)

    Williamson, D.; Hoffman, D.R.

    1991-01-01

    Since early 1988 intensive efforts have been under way to produce a new and improved Standard Technical Specification. The program involves a coordinated effort between utility personnel representing each of the four nuclear steam supply system (NSSS) product lines, the NSSS vendors, and the US Nuclear Regulatory Commission (NRC). This intensive work period is actually the culmination of a decade of rhetoric about shortcomings of the existing technical specifications. Work on the improved technical specifications provided a unique forum for intense philosophical discussions between the users and enforcers of technical specifications, the outcome of which could have an impact on all licensees. Some of the more intriguing difficulties in the use and application of existing technical specifications, as well as discussions of the resolutions being applied in the improved technical specifications and the dilemmas remaining to be resolved are discussed in the paper

  16. 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.

  17. 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

  18. 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

  19. 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

  20. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants 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 unproved 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 proved 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

  1. 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

  2. Technical evaluation of the proposed design modifications and technical specification changes for the R.E. Ginna Nuclear Power Plant, Unit 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1980-01-01

    The present design uses undervoltage relays to sense the loss of offsite power. There are no Class 1E loads on the 4160-volt buses. This design consists of two relays per 480-volt Class 1E bus (two Class 1E buses per redundant load group) for the first level of undervoltage protection. An undervoltage condition (loss-of-voltage) will result in isolating the Class 1E buses from all offsite sources, initiating emergency diesel generator start and load shedding on the Class 1E buses, permitting closure of the diesel generator supply breakers, and lastly, the loads will be automatically time-sequenced onto the buses. Actuation begins with loss of voltage to 368 volts (77% of 480 volts). The existing system does not bypass the load-shedding feature once the emergency diesel generators are energizing the Class 1E buses. The licensee has proposed a design change which includes automatic degraded voltage protection. This modification consists of the addition of two time-delayed, undervoltage relays on each 480-volt Class 1E bus, to provide the second level of undervoltage protection

  3. Standard Technical Specifications, Babcock and Wilcox Plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) 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. 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 developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

  4. Standard Technical Specifications, Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. Public safety around dams : proposed technical bulletins

    Energy Technology Data Exchange (ETDEWEB)

    Raska, C [BC Hydro, Burnaby, BC (Canada); Rowat, L [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

    2009-07-01

    This presentation provided an introduction to the Canadian Dam Association (CDA) public safety guideline and proposed technical bulletins for exterior danger and warning signs; waterway booms and buoys; and audible and visual alerts for water conveyance structures. The presentation outlined the hierarchy of documents for principles, guidelines and technical bulletins. Effective signage includes signs in which the text is sized according to the viewing distance; the message identifies the hazard and the actions to take; and the wording is understood by the public. The criteria for effective booms and buoys were discussed in terms of visibility of booms; types of buoys to use; distance between booms floats; design issues for headpond application versus tailrace application; angling to facilitate self-rescue; and distance from structure. Proposed criteria for audible and visual alerts were also discussed. The audible and visual danger signal should have a designated signal reception area where people can recognize and react to the signal. If a visual signalling device is used, it should be red to indicate danger. Maintenance and inspection tests should be performed regularly on audible and visual signalling devices. 1 ref., 2 figs.

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  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/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

  2. 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

  3. 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.

  4. 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)

  5. 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)

  6. 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

  7. 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.

  8. 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

  9. 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

  10. 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

  11. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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.

  17. 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

  18. Standard technical specifications for Babcock and Wilcox pressurized water reactors. Revision 4. Technical report

    International Nuclear Information System (INIS)

    Virgilio, M.J.

    1980-10-01

    The Standard Technical Specifications for Babcock and Wilcox Pressurized Water Reactors (BandW-STS) is a generic document prepared by the U.S. NRC for use in the licensing process. The BandW-STS provide applicants with model specifications to be used in formulation plant-specific technical specifications required by 10 CFR Part 50, Section 50.36, which set forth the specific characteristics of the facility and the conditions for its operation that are required to provide adequate protection to the health and safety of the public. This document is revised periodically to reflect current licensing requirements

  19. 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.

  20. Standard technical specifications: Babcock and Wilcox Plants. 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 Babcock ampersand Wilcox 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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.)

  6. 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.

  7. Torus II. Technical description of the design proposal

    International Nuclear Information System (INIS)

    Aymar, R.; Deck, C.; Deschamps, P.; Lafon, D.; Leloup, C.; Pariente, M.; Renaud, C.; Sledziewski, Z.; Torossian, A.

    1976-06-01

    A new Tokamak device, called TORUS II, is proposed to be built inside the EURATOM-CEA Association. This is a large machine: I=1.7MA; B=30kGs; R=1.8m; a=75cm, designed to be a successor to TFR and to follow the lines of research already initiated in the present TFR programme, i.e. on plasma heating, on impurities, on energy confinement and scaling laws, providing to JET a very efficient backing. This part of the report provides a technical description of the main components of the basic machine, according to the state of design reached in June 1976. Every subsystem whose assembly forms the basic machine is the subject of one section: vacuum vessel, toroidal field coils, poloidal field system, mechanical structures, monitoring, control and data acquisition, and power supplies. The first part in each section attempts to summarize the solution that was retained, pointing out the problems to be solved and the choice made. No contribution takes into account the problems of installation and buildings and the time schedule which is given is only concerned with the simplest solution. By way, contributions are given which show the state of development of the peripheral systems envisaged for TORUS II, mainly: additional heating, control of impurities and plasma diagnostics [fr

  8. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

  9. 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

  10. 77 FR 9216 - Native American Career and Technical Education Program; Proposed Waivers and Extension of the...

    Science.gov (United States)

    2012-02-16

    ... DEPARTMENT OF EDUCATION Native American Career and Technical Education Program; Proposed Waivers...) 2007 under the Native American Career and Technical Education Program (NACTEP), the Secretary proposes... secondary school career and technical education programs. \\1\\ Section 116(a)(2) of the Carl D. Perkins...

  11. 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

  12. 75 FR 6683 - Notice of Proposed Information Collection: Comment Request; Technical Processing Requirements for...

    Science.gov (United States)

    2010-02-10

    ... Information Collection: Comment Request; Technical Processing Requirements for Multifamily Project Mortgage... information: Title of Proposal: Technical Processing Requirements for Multifamily Project Mortgage Insurance... information collection requirement described below will be submitted to the Office of Management and Budget...

  13. 78 FR 64146 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-10-25

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY: HUD has submitted the proposed... Information Collection Title of Information Collection: Technical Processing Requirements for Multifamily...

  14. 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)

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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.

  20. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    Virgilio, M.

    1979-07-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS 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

  1. Standard technical specifications for Babcock and Wilcox pressurized water reactors

    International Nuclear Information System (INIS)

    1978-06-01

    The Standard Technical Specification (STS) has been structured for the broadest possible use on B and W NSSS 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. 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

  2. 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

  3. 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

  4. 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

  5. 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.

  6. 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.)

  7. Postclosure risks at the proposed Yucca Mountain repository: A review of methodological and technical issues

    International Nuclear Information System (INIS)

    Emel, J.; Kasperson, R.E.; Goble, R.; Renn, O.

    1988-06-01

    Accordingly, the first section of the report provides an overview and critique of the risk analysis methodology proposed by the US Department of Energy (DOE 1988) in the Draft Site Characterization Plan (SCP) and related documents. The second section addresses specific technical problems associated with the site. Each section considers the significance or implications of the issues for the successful long-term isolation of radioactive wastes from the biosphere. We conclude with overall observations on the adequacy of current understandings and approaches in the waste disposal program and implications for the State of Nevada

  8. 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

  9. 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

  10. A Proposal for a Flexible Trend Specification in DSGE Models

    Directory of Open Access Journals (Sweden)

    Slanicay Martin

    2016-06-01

    Full Text Available In this paper I propose a flexible trend specification for estimating DSGE models on log differences. I demonstrate this flexible trend specification on a New Keynesian DSGE model of two economies, which I consequently estimate on data from the Czech economy and the euro area, using Bayesian techniques. The advantage of the trend specification proposed is that the trend component and the cyclical component are modelled jointly in a single model. The proposed trend specification is flexible in the sense that smoothness of the trend can be easily modified by different calibration of some of the trend parameters. The results suggest that this method is capable of finding a very reasonable trend in the data. Moreover, comparison of forecast performance reveals that the proposed specification offers more reliable forecasts than the original variant of the model.

  11. 48 CFR 27.407 - Rights to technical data in successful proposals.

    Science.gov (United States)

    2010-10-01

    ... Copyrights 27.407 Rights to technical data in successful proposals. The clause at 52.227-23, Rights to... successful proposals. Pursuant to the clause, the prospective contractor is afforded the opportunity to... exclusion is not dispositive of the protective status of the data, but any excluded technical data, as well...

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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

  17. Technical Notes: Notes and Proposed Guidelines on Updated ...

    African Journals Online (AJOL)

    In light of recent expansion in the planning and construction of major building structures as well as other infrastructures such as railways, masshousing, dams, bridges, etc, this paper reviews the extent of seismic hazard in Ethiopia and proposes a review and update of the current out-dated and - in most cases ...

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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...

  5. 77 FR 46658 - Proposed Priority; Technical Assistance To Improve State Data Capacity-National Technical...

    Science.gov (United States)

    2012-08-06

    ... Assistance To Improve State Data Capacity--National Technical Assistance Center To Improve State Capacity To... and later years. We take this action to focus attention on an identified national need to provide TA to improve the capacity of States to meet the data collection requirements of the Individuals with...

  6. 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)

  7. 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)

  8. 48 CFR 452.215-71 - Instructions for the Preparation of Technical and Business Proposals.

    Science.gov (United States)

    2010-10-01

    ... contained in the technical proposal so that the contractor's understanding of the statement of work may be... required if appropriate.) (2) Business Proposal. (a) Furnish financial statements for the last two years... specified in the statement of work. Any “alternate” proposal may be considered if overall performance would...

  9. Complementary Safety Assessments: technical and organisational proposals from Areva

    International Nuclear Information System (INIS)

    Anon.

    2012-01-01

    The safety experts of the Areva group have worked on the definition of a hard core of safety measures necessary to assure the vital functions in any situation (event the most unlikely) of the following nuclear facilities: La Hague, Tricastin, Melox, and FBFC Romans. Areva proposes to reinforce its crisis management by deploying new equipment for the intervention and communication (pumps, robots, diesel sets, measuring devices, satellite phone...). More than 1500 people with training and skills related to nuclear crisis will be able to help local teams on nuclear facilities if necessary. Areva has announced that it will invest more than 2 billion euros for upgrading the industrial plants, the implementation of new technologies and the improvement of safety. (A.C.)

  10. Small reactor technical and design characteristics proposed for Indonesia

    International Nuclear Information System (INIS)

    Nurdin, M.

    1992-01-01

    A Team for Small Nuclear Electricity Reactor has been formed in Indonesia since June 1990. It is responsible for assessment and design of a small reactor for electricity and/or sea-water desalination. This concept may become a good alternative for power-plants for small islands and for isolated areas in Indonesia, the system should function economically and environmentally sound. In addition to existing concepts, this presentation deals with modifications proposed in improving reliability and safety of reactor operation. For the size of 200 MWth or more (80 MWe or more), the possibility of designing an internal auxiliary heat removal system is discussed, hence there are two separate heat sinks for the core. Future development works for this concept should be directed in expanding their spectrum of utilization and their contribution to the national energy needs. (author). 7 refs., 4 tabs

  11. Innovative and practical technical development of nuclear energy. Efforts on proposal and recruitment type technical development of nuclear energy

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Shioiri, Akio; Hamada, Jun; Kanagawa, Takashi; Mori, Yukihide; Kouno, Koji

    2003-01-01

    In technical development of nuclear energy conceiving a view on energy environment problem at the 21st Century, technical development on innovative nuclear energy system as well as next generation LWR is an important subject. Even in Japan, on the 'Long-term program for research, development and utilization of nuclear energy (LPRNE)' summarized by the Atomic Energy Commission, investigation on R and Ds of innovative reactors under cooperation of government, industrial field, and universities is required. In the Energy Generalized Engineering Institute, by receiving a subsidy from the Ministry of Economy and Industry since 2000, a proposal recruitment business on innovative and practical technical development of nuclear energy has been carried out. Here were introduced hopeful and unique five themes out of them applied to the recruitment, such as a super-critical pressure water cooling reactor (SCPR), an integrated modular LWR (IMR): technical development for practice, technical development on general purpose boiling transitional analysis method, technical development on direct extraction of U and Pu from consumed fuels based on super-DIREX reprocessing method, and material transfer forecasting in natural barriers at landfill disposal of radioactive wastes. (G.K.)

  12. 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

  13. 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.

  14. 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...

  15. Proposal for outline of training and evaluation method for non-technical skills

    International Nuclear Information System (INIS)

    Nagasaka, Akihiko; Shibue, Hisao

    2015-01-01

    The purpose of this study is to systematize measures for improvement of emergency response capability focused on non-technical skills. As the results of investigation of some emergency training in nuclear power plant and referring to CRM training, following two issues were picked up. 1) Lack of practical training method for improvement of non-technical skills. 2) Lack of evaluation method of non-technical skills. Then, based on these 7 non-technical skills 'situational awareness' 'decision making' 'communication' 'teamworking' 'leadership' 'managing stress' 'coping with fatigue' are promotion factors to improve emergency response capability, we propose practical training method for each non-technical skill. Also we give example of behavioral markers as evaluation factor, and indicate approaches to introduce the evaluation method of non-technical skills. (author)

  16. Methodological proposal for environmental impact evaluation since different specific methods

    International Nuclear Information System (INIS)

    Leon Pelaez, Juan Diego; Lopera Arango Gabriel Jaime

    1999-01-01

    Some conceptual and practical elements related to environmental impact evaluation are described and related to the preparation of technical reports (environmental impact studies and environmental management plans) to be presented to environmental authorities for obtaining the environmental permits for development projects. In the first part of the document a summary of the main aspects of normative type is made that support the studies of environmental impact in Colombia. We propose a diagram for boarding and elaboration of the evaluation of environmental impact, which begins with the description of the project and of the environmental conditions in the area of the same. Passing then to identify the impacts through a method matricial and continuing with the quantitative evaluation of the same. For which we propose the use of the method developed by Arboleda (1994). Also we propose to qualify the activities of the project and the components of the environment in their relative importance, by means of a method here denominated agglomerate evaluation. Which allows finding those activities more impacting and the mostly impacted components. Lastly it is presented some models for the elaboration and presentation of the environmental management plans. The pursuit programs and those of environmental supervision

  17. 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

  18. 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

  19. 48 CFR 52.214-23 - Late submissions, modifications, revisions, and withdrawals of technical proposals under two-step...

    Science.gov (United States)

    2010-10-01

    ..., modifications, revisions, and withdrawals of technical proposals under two-step sealed bidding. 52.214-23... Late submissions, modifications, revisions, and withdrawals of technical proposals under two-step..., Modifications, Revisions, and Withdrawals of Technical Proposals Under Two-Step Sealed Bidding (NOV 1999) (a...

  20. 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...

  1. Cultivating Advanced Technical Writing Skills through a Graduate-Level Course on Writing Research Proposals

    Science.gov (United States)

    McCarthy, Brian D.; Dempsey, Jillian L.

    2017-01-01

    A graduate-level course focused on original research proposals is introduced to address the uneven preparation in technical writing of new chemistry graduate students. This course focuses on writing original research proposals. The general course structure features extensive group discussions, small-group activities, and regular in-class…

  2. 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.

  3. 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

  4. 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

  5. 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.

  6. 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)

  7. 78 FR 52963 - 60-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-08-27

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY...: HUD is seeking approval from the Office of Management and Budget (OMB) for the information collection... interested parties on the proposed collection of information. The purpose of this notice is to allow for 60...

  8. 75 FR 75186 - Interview Room Video System Standard Special Technical Committee Request for Proposals for...

    Science.gov (United States)

    2010-12-02

    ... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1534] Interview Room Video System Standard Special Technical Committee Request for Proposals for Certification and Testing Expertise... Interview Room Video System Standard and corresponding certification program requirements. This work is...

  9. 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

  10. 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…

  11. 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...

  12. 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

  13. 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)

  14. 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...

  15. 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

  16. 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)

  17. [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

  18. 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

  19. Upper Caraş River (Danube watershed fish populations fragmentation – technical rehabilitation proposal

    Directory of Open Access Journals (Sweden)

    Voicu Răzvan

    2018-01-01

    Full Text Available We propose a technical solution for fish movement based on the flow of water over a spill threshold. Such barriers are common in the Danube system. The proposed system has a range of operating components which are easily detachable from the spill threshold, are resistant to corrosion and will not harm the fish. In fact, if designed to complement swimming abilities of target fish, it should provide adequate passage for both adults and juveniles. If implemented correctly, the design may offer a solution to help displaced fish recolonize upstream habitats.

  20. 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

  1. 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

  2. 76 FR 10530 - Supplemental Proposed Rule of Source Specific Federal Implementation Plan for Implementing Best...

    Science.gov (United States)

    2011-02-25

    ... sufficient ammonia to maximize the reduction of the NO X no matter what the age of the catalyst.\\7\\ \\5\\ The... BART proposal with our technical evaluation of APS' alternative proposal. We are proposing to find that... docket are listed in the index, some information may be publicly available only at the hard copy location...

  3. Technical specification for a 25 MV tandem electrostatic accelerator

    International Nuclear Information System (INIS)

    Jones, C.M.; Biggerstaff, J.A.; Blair, J.K.; Ball, J.B.; Larson, J.D.; Martin, J.A.; McConnell, J.W.; Milner, W.T.; Murray, J.A.; Ziegler, N.F.

    1975-08-01

    Specifications are given for an accelerator system to consist of a 25 MV tandem electrostatic accelerator and specified ancillary equipment, including an injector, a beam transport system, a vacuum system, a control system, and a system for storage of the insulating gas and transport of the gas to and from the accelerator. The insulating gas shall be SF 6 . The tandem electrostatic accelerator shall be vertical in orientation and of folded construction, and shall be installed in a new structure adjacent to the Oak Ridge Isochronous Cyclotron. (auth)

  4. Place of the adoption of technical proposals from research in farmers’ adaptation strategies

    Directory of Open Access Journals (Sweden)

    P. Pedelahore

    2011-01-01

    Full Text Available Technical innovation is often presented as the main lever to improve economical performances and livelihoods of family farmers. It is thus a way to face the variability of the socio-economical environment. The aim of this study was to analyze the role of the adoption of technical proposals from research within the range of the adaptation strategies used by farmers to maintain or even improve their livelihoods and that of their descendants. Semi-structured and structured interviews carried out on a sample of representative family farmers of South Cameroon showed that migrations, off farm activities, increase of cultivated areas, and cash crop diversification were adaptation strategies more often used by farmers than the adoption of technical proposals. The study highlighted that improving crop management sequences and performances of family farming systems could not be the sole orientation of research and development policies. The increase of farmers spatial and professional mobility points the need to develop research and development policies that focus more closely on territorial and farmers’ management and on interactions between the different sectors of the national economy.

  5. 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

  6. 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

  7. 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

  8. Magnetic field calculations for the technical proposal of the TESLA spectrometer magnet

    International Nuclear Information System (INIS)

    Morozov, N.A.; Schreiber, H.J.

    2003-01-01

    The TESLA electron-positron linear collider is under consideration at DESY (Hamburg). The realization of the physical program at this collider requires the knowledge of the beam energy of both beams (e + and e - ) with a precision of ΔE/E ≤ 10 -4 . The magnetic spectrometer was proposed as an energy measuring device. The report describes calculations for the preliminary conceptual design of this type of the spectrometer. The 2D calculations of the magnetic field for the spectrometer magnet have been performed by POISSON SUPERFISH computer code. The basic technical parameters of the magnet have been determined. These data will serve as a basis for the technical design of the spectrometer magnet and discuss its integration in the spectrometer

  9. Final technical evaluation report for the proposed revised reclamation plan for the Atlas Corporation Moab Mill

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This final Technical Evaluation Report (TER) summarizes the US Nuclear Regulatory Commission staff`s review of Atlas Corporation`s proposed reclamation plan for its uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tailings pile for permanent disposal and long-term custodial care by a government agency in its current location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC license terminated. The NRC staff concludes that, subject to license conditions identified in the TER, the proposed reclamation plan meets the requirements identified in NRC regulations, which appear primarily in 10 CFR Part 40. 112 refs., 6 figs., 16 tabs.

  10. Final technical evaluation report for the proposed revised reclamation plan for the Atlas Corporation Moab Mill

    International Nuclear Information System (INIS)

    1997-03-01

    This final Technical Evaluation Report (TER) summarizes the US Nuclear Regulatory Commission staff's review of Atlas Corporation's proposed reclamation plan for its uranium mill tailings pile near Moab, Utah. The proposed reclamation would allow Atlas to (1) reclaim the tailings pile for permanent disposal and long-term custodial care by a government agency in its current location on the Moab site, (2) prepare the site for closure, and (3) relinquish responsibility of the site after having its NRC license terminated. The NRC staff concludes that, subject to license conditions identified in the TER, the proposed reclamation plan meets the requirements identified in NRC regulations, which appear primarily in 10 CFR Part 40. 112 refs., 6 figs., 16 tabs

  11. 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

  12. 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

  13. Revision of the European Ecolabel Criteria for Personal, Notebook and Tablet Computers TECHNICAL REPORT Summary of the final criteria proposals

    OpenAIRE

    DODD NICHOLAS; VIDAL ABARCA GARRIDO CANDELA; WOLF Oliver; GRAULICH Kathrin; BUNKE Dirk; GROSS Rita; LIU Ran; MANHART Andreas; PRAKASH Siddharth

    2015-01-01

    This technical report provide the background information for the revision of the EU Ecolabel criteria for Personal and Notebook Computers. The study has been carried out by the Joint Research Centre with technical support from the Oeko-Institut. The work has been developed for the European Commission's Directorate General for the Environment. The main purpose of this report is to provide a summary of the technical background and rationale for each criterion proposal. This document is compl...

  14. Proposed changes to Incoloy Alloy 800 and 800H specifications

    International Nuclear Information System (INIS)

    Bassford, T.H.; Rahoi, D.W.

    1978-01-01

    Preliminary results from an extensive investigation of Alloy 800 and 800H have led the authors to recommend changes to the specifications covering these alloys usage under Code Case 1592-10 and Sec. VIII, Div. 7. The compositional changes recommended would result in changes in rupture ductility and design stress. (Auth.)

  15. Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

    Science.gov (United States)

    Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

    2006-07-01

    Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

  16. 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

  17. Abbreviations for device names: a proposed methodology with specific examples.

    Science.gov (United States)

    Alam, Murad; Dover, Jeffrey S; Alam, Murad; Goldman, Mitchel P; Kaminer, Michael S; Orringer, Jeffrey; Waldorf, Heidi; Alam, Murad; Avram, Mathew; Cohen, Joel L; Draelos, Zoe Diana; Dover, Jeffrey S; Hruza, George; Kilmer, Suzanne; Lawrence, Naomi; Lupo, Mary; Metelitsa, Andrei; Nestor, Mark; Ross, E Victor

    2013-04-01

    Many devices used in dermatology lack generic names. If investigators use commercial device names, they risk the appearance of bias. Alternatively, reliance on ad-hoc names and abbreviations may confuse readers who do not recognize these. To develop a system for assigning abbreviations to denote devices commonly used in dermatology. Secondarily, to use this system to create abbreviations for FDA-approved neurotoxins and prepackaged injectable soft-tissue augmentation materials. The American Society for Dermatologic Surgery convened a Lexicon Task Force in March 2012. One charge of this Task Force was to develop criteria for assigning abbreviations to medical devices. A modified consensus process was used. Abbreviations to denote devices were to be: based on a standardized approach; transparent to the casual reader; markedly brief; and in all cases, different than the commercial names. Three-letter all caps abbreviations, some with subscripts, were assigned to denote each of the approved neurotoxins and fillers. A common system of abbreviations for medical devices in dermatology may avoid the appearance of bias while ensuring effective communication. The proposed system may be expanded to name other devices, and the ensuing abbreviations may be suitable for journal articles, continuing medical education lectures, or other academic or clinical purposes. © 2013 by the American Society for Dermatologic Surgery, Inc. Published by Wiley Periodicals, Inc.

  18. 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

  19. 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

  20. 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

  1. 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.)

  2. 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

  3. 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

  4. 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...

  5. 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

  6. 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

  7. 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...

  8. 78 FR 65695 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-11-01

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Correction, notice. SUMMARY: On October 25, 2013 at... Collection Title of Information Collection: Technical Processing Requirements for Multifamily Project...

  9. 75 FR 75453 - Proposed Information Collection; Comment Request; Technical Data Letter of Explanation

    Science.gov (United States)

    2010-12-03

    ... Request; Technical Data Letter of Explanation AGENCY: Bureau of Industry and Security. ACTION: Notice....gov . SUPPLEMENTARY INFORMATION: I. Abstract These technical data letters of explanation will assure the Bureau of Industry and Security that U.S.-origin technical data will be exported only for...

  10. 76 FR 23641 - Proposed Information Collection: Export Declaration of Defense Technical Data or Services

    Science.gov (United States)

    2011-04-27

    ... Defense Technical Data or Services AGENCY: Department of State. ACTION: Notice of request for public... Declaration of Defense Technical Data or Services. OMB Control Number: 1405-0157. Type of Request: Extension... of defense technical data and defense services will be electronically reported directly to the...

  11. 75 FR 33761 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-06-15

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  12. 75 FR 34974 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-06-21

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  13. 75 FR 62759 - Notice of Proposed Change to Section IV of the Virginia State Technical Guide

    Science.gov (United States)

    2010-10-13

    ... revisions made after enactment of the law to NRCS State technical guides used to carry out highly erodible... Section IV of the Virginia State Technical Guide AGENCY: Natural Resources Conservation Service (NRCS), U... NRCS State Technical Guide for review and comment. SUMMARY: It has been determined by the NRCS State...

  14. Addendum to Technical Proposal: A Facility to Search for Hidden Particles (SHiP) at the CERN SPS

    CERN Document Server

    SHiP Collaboration

    2015-01-01

    With the Technical Proposal submitted to the SPSC committee in April 2015, the SHiP collaboration declared its interest in proceeding towards a Comprehensive Design Study phase with the aim of preparing for the Technical Design Reports pending an approval by the CERN committees. Following the recommendation by the SPSC, it has been decided to complement the TP with this addendum that provides an update of the key aspects for the review of the SHiP project.

  15. 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)

  16. 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)

  17. Technical support for a proposed decay heat guide using SAS2H/ORIGEN-S data

    International Nuclear Information System (INIS)

    Hermann, O.W.; Parks, C.V.; Renier, J.P.

    1994-09-01

    Major revisions are proposed to the current US Nuclear Regulatory Commission decay heat rate guide entitled ''Regulatory Guide 3.54, Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation,'' using a new data base produced by the SAS2H analysis sequence of the SCALE-4 system. The data base for the proposed guide revision has been significantly improved by increasing the number and range of parameters that generally characterize pressurized-water-reactor (PWR) and boiling-water-reactor (BWR) spent fuel assemblies. Using generic PWR and BWR assembly models, calculations were performed with each model for six different burnups at each of three separate specific powers to produce heat rates at 20 cooling times in the range of 1 to 110 y. The proposed procedure specifies proper interpolation formulae for the tabulated heat generation rates. Adjustment formulae for the interpolated values are provided to account for differences in initial 235 U enrichment and changes in the specific power of a cycle from the average value. Finally, safety factor formulae were derived as a function of burnup, cooling time, and type of reactor. The proposed guide revision was designed to be easier to use. Also, the complete data base and guide procedure is incorporated into an interactive code called LWRARC which can be executed on a personal computer. The report shows adequate comparisons of heat rates computed by SAS2H/ORIGEN-S and measurements for 10 BWR and 10 PWR fuel assemblies. The average differences of the computed minus the measured heat rates of fuel assemblies were -07 ± 2.6% for the BWR and 1.5 ± 1.3% for the PWR. In addition, a detailed analysis of the proposed procedure indicated the method and equations to be valid

  18. Technical Issues and Proposes on the Legislation of Probabilistic Safety Assessment in Periodic Safety Review

    International Nuclear Information System (INIS)

    Hwang, Seok-Won; Jeon, Ho-Jun; Na, Jang-Hwan

    2015-01-01

    Korean Nuclear Power Plants have performed a comprehensive safety assessment reflecting design and procedure changes and using the latest technology every 10 years. In Korea, safety factors of PSR are revised to 14 by revision of IAEA Safety Guidelines in 2003. In the revised safety guidelines, safety analysis field was subdivided into deterministic safety analysis, PSA (Probabilistic safety analysis), and hazard analysis. The purpose to examine PSA as a safety factor on PSR is to make sure that PSA results and assumptions reflect the latest state of NPPs, validate the level of computer codes and analytical models, and evaluate the adequacy of PSA instructions. In addition, its purpose is to derive the plant design change, operating experience of other plants and safety enhancement items as well. In Korea, PSA is introduced as a new factor. Thus, the overall guideline development and long-term implementation strategy are needed. Today in Korea, full-power PSA model revision and low-power and shutdown (LPSD) PSA model development is being performed as a part of the post Fukushima action items for operating plants. The scope of the full-power PSA is internal/external level 1, 2 PSA. But in case of fire PSA, the scope is level 1 PSA using new method, NUREG/CR-6850. In case of LPSD PSA, level 1 PSA for all operating plants, and level 2 PSA for 2 demonstration plants are under development. The result of the LPSD PSA will be used as major input data for plant specific SAMG (Severe Accident Management Guideline). The scope of PSA currently being developed in Korea cannot fulfill 'All Mode, All Scope' requirements recommended in the IAEA Safety Guidelines. Besides the legislation of PSA, step-by-step development strategy for non-performed scopes such as level 3 PSA and new fire PSA is one of the urgent issues in Korea. This paper suggests technical issues and development strategies for each PSA technical elements.

  19. 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.

  20. 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

  1. 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)

  2. 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)

  3. Concept of the Cooling System of the ITS for ALICE: Technical Proposals, Theoretical Estimates, Experimental Results

    CERN Document Server

    Godisov, O N; Yudkin, M I; Gerasimov, S F; Feofilov, G A

    1994-01-01

    Contradictory demands raised by the application of different types of sensitive detectors in 5 layers of the Inner Tracking System (ITS) for ALICE stipulate the simultaneous use of different schemes of heat drain: gaseous cooling of the 1st layer (uniform heat production over the sensitive surface) and evaporative cooling for the 2nd-5th layers (localised heat production). The last system is also a must for the thermostabilization of Si-drift detectors within 0.1 degree C. Theoretical estimates of gaseous, evaporative and liquid cooling systems are done for all ITS layers. The results of the experiments done for evaporative and liquid heat drain systems are presented and discussed. The major technical problems of the evaporative systems' design are being considered: i) control of liquid supply; ii) vapour pressure control. Two concepts of the evaporative systems are proposed: 1) One channel system for joint transfer of two phases (liquid + gas); 2) Two channels system with separate transfer of phases. Both sy...

  4. Technical Proposal for the Phase-II Upgrade of the CMS Detector

    CERN Document Server

    CMS Collaboration; Contardo, D; Klute, M; Mans, J; Silvestris, L; Butler, J; CERN. Geneva. The LHC experiments Committee; LHCC

    2015-01-01

    This Technical Proposal presents the upgrades foreseen to prepare the CMS experiment for the High Luminosity LHC. In this second phase of the LHC physics program, the accelerator will provide to CMS an additional integrated luminosity of about 2500 fb-1 over 10 years of operation, starting in 2025. This will substantially enlarge the mass reach in the search for new particles and will also greatly extend the potential to study the properties of the Higgs boson discovered at the LHC in 2012. In order to meet the experimental challenges of unprecedented p-p luminosity, the CMS collaboration will need to address the aging of the present detector and to improve the ability of the apparatus to isolate and precisely measure the products of the most interesting collisions. This document describes the conceptual designs and the expected performance of the upgrades, along with the plans to develop the appropriate experimental techniques. The infrastructure upgrades and the logistics of the installation in the experim...

  5. A Proposal to Build an Education Research and Development Program: The Kamehameha Early Education Project Proposal. Technical Report #3.

    Science.gov (United States)

    Gallimore, Ronald; And Others

    This report summarizes the programmatic features of a proposal for the Kamehameha Early Education Project (KEEP), a program aimed at the development, demonstration, and dissemination of methods for improving the education of Hawaiian and part-Hawaiian children. A brief description of the proposed project goals, structure, organization, and…

  6. 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)

  7. 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

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 76 FR 41293 - Solicitation of Proposals for Technical Assistance Funding From the Native American Business...

    Science.gov (United States)

    2011-07-13

    ... for NABDI Technical Assistance Funding D. Submission of Application in Digital Format E. Application.... The IEED has spent considerable time and expense in collecting digital land grids, geographic...: Marketing studies. 9. What the NABDI Technical Assistance Funding Cannot Fund As stated above, these funds...

  13. Feasibility study and technical proposal for seismic monitoring of tunnel boring machine in Olkiluoto

    Energy Technology Data Exchange (ETDEWEB)

    Saari, J.; Lakio, A. (AF-Consult Ltd, Vantaa (Finland))

    2009-01-15

    In Olkiluoto, Posiva Oy has operated a local seismic network since February 2002. The purpose of the microearthquake measurements at Olkiluoto is to improve understanding of the structure, behaviour and long term stability of the bedrock. The studies include both tectonic and excavation-induced microearthquakes. An additional task of monitoring is related to safeguarding of the ONKALO. The possibility to excavate an illegal access to the ONKALO, have been concerned when the safeguards are discussed. Therefore all recorded explosions in the Olkiluoto area and in the ONKALO are located. If a concentration of explosions is observed, the origin of that is found out. Also a concept of hidden illegal explosions, detonated at the same time as the real excavation blasts, has been examined. According to the experience gained in Olkiluoto, it can be concluded that, as long the seismic network is in operation and the results are analysed by a skilled person, it is practically impossible to do illegal excavation by blasts. In this report a possibility of seismic monitoring of illegal excavation done by tunnel boring machine (TBM) has been investigated. Characteristics of the seismic signal generated by the raise boring machine are described. According to this study, it can be concluded that the generated seismic signal can be detected and the source of the signal can be located. However, this task calls for different kind of monitoring system than that, which is currently used for monitoring microearthquakes and explosions. The presented technical proposal for seismic monitoring of TBM in Olkiluoto is capable to detect and locate TBM coming outside the ONKALO area about two months before it would reach the ONKALO. (orig.)

  14. Feasibility study and technical proposal for seismic monitoring of tunnel boring machine in Olkiluoto

    International Nuclear Information System (INIS)

    Saari, J.; Lakio, A.

    2009-01-01

    In Olkiluoto, Posiva Oy has operated a local seismic network since February 2002. The purpose of the microearthquake measurements at Olkiluoto is to improve understanding of the structure, behaviour and long term stability of the bedrock. The studies include both tectonic and excavation-induced microearthquakes. An additional task of monitoring is related to safeguarding of the ONKALO. The possibility to excavate an illegal access to the ONKALO, have been concerned when the safeguards are discussed. Therefore all recorded explosions in the Olkiluoto area and in the ONKALO are located. If a concentration of explosions is observed, the origin of that is found out. Also a concept of hidden illegal explosions, detonated at the same time as the real excavation blasts, has been examined. According to the experience gained in Olkiluoto, it can be concluded that, as long the seismic network is in operation and the results are analysed by a skilled person, it is practically impossible to do illegal excavation by blasts. In this report a possibility of seismic monitoring of illegal excavation done by tunnel boring machine (TBM) has been investigated. Characteristics of the seismic signal generated by the raise boring machine are described. According to this study, it can be concluded that the generated seismic signal can be detected and the source of the signal can be located. However, this task calls for different kind of monitoring system than that, which is currently used for monitoring microearthquakes and explosions. The presented technical proposal for seismic monitoring of TBM in Olkiluoto is capable to detect and locate TBM coming outside the ONKALO area about two months before it would reach the ONKALO. (orig.)

  15. 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

  16. Preliminary draft industrial siting administration permit application: Socioeconomic factors technical report. Final technical report, November 1980-May 1982. [Proposed WyCoalGas project in Converse County, Wyoming

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    Under the with-project scenario, WyCoalGas is projected to make a difference in the long-range future of Converse County. Because of the size of the proposed construction and operations work forces, the projected changes in employment, income, labor force, and population will alter Converse County's economic role in the region. Specifically, as growth occurs, Converse County will begin to satisfy a larger portion of its own higher-ordered demands, those that are currently being satisfied by the economy of Casper. Business-serving and household-serving activities, currently absent, will find the larger income and population base forecast to occur with the WyCoalGas project desirable. Converse County's economy will begin to mature, moving away from strict dependence on extractive industries to a more sophisticated structure that could eventually appeal to national, and certainly, regional markets. The technical demand of the WyCoalGas plant will mean a significant influx of varying occupations and skills. The creation of basic manufacturing, advanced trade and service sectors, and concomitant finance and transportation firms will make Converse County more economically autonomous. The county will also begin to serve market center functions for the smaller counties of eastern Wyoming that currently rely on Casper, Cheyenne or other distant market centers. The projected conditions expected to exist in the absence of the WyCoalGas project, the socioeconomic conditions that would accompany the project, and the differences between the two scenarios are considered. The analysis is keyed to the linkages between Converse County and Natrona County.

  17. 76 FR 45589 - Notice of Submission of Proposed Information Collection to OMB; Application for Technical...

    Science.gov (United States)

    2011-07-29

    ... grantees will engage providers to supply expertise to shape their resources into effective, coordinated...: Application for technical assistance funds with which CPD grantees will engage providers to supply expertise to shape their resources into effective, coordinated, neighborhood and community development...

  18. 76 FR 35864 - Proposed Priority; Special Demonstration Programs-National Technical Assistance Projects To...

    Science.gov (United States)

    2011-06-20

    ... have national significance and improve the performance of State vocational rehabilitation (VR) agencies... Centers, the American Indian Vocational Rehabilitation Technical Assistance Center, and the Independent... of each priority as absolute, competitive preference, or invitational through a notice in the Federal...

  19. 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

  20. 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

  1. A proposal of ITER vacuum vessel fabrication specification and results of the full-scale partial mock-up test

    International Nuclear Information System (INIS)

    Nakahira, M.; Takeda, N.; Kakudate, S.; Onozuka, M.

    2008-01-01

    The structure and fabrication methods of the ITER vacuum vessel (VV) have been investigated and defined by the ITER International Team (IT). However, some of the current technical specifications are difficult to be achieved from the manufacturing point of view. To solve such an issue, this paper proposes an alternative specification of the VV to the IT's design. A series of the fabrication and assembly procedures for the mock-up are presented, together with candidates of welding configurations. Finally, the paper summarizes the results of mock-up fabrication, such as non-destructive examination of weld lines, obtained welding deformation and issues revealed from the fabrication experience. Based on the results, it is suggested that several issues such as clarification of conditions of repair welding, demonstration of welding distortion control and detectability/localization of internal defects should be solved before manufacturing the ITER VV

  2. A proposal of ITER vacuum vessel fabrication specification and results of the full-scale partial mock-up test

    Energy Technology Data Exchange (ETDEWEB)

    Nakahira, M. [Japan Atomic Energy Agency, Mukouyama 801-1, Naka-machi, Naka-gun, Ibaraki 311-0193 (Japan)], E-mail: nakahira.masataka@jaea.go.jp; Takeda, N.; Kakudate, S. [Japan Atomic Energy Agency, Mukouyama 801-1, Naka-machi, Naka-gun, Ibaraki 311-0193 (Japan); Onozuka, M. [Mitsubishi Nuclear Energy Systems, Inc., 1700K Street NW, Suite 440, Washington, DC 20006 (United States)

    2008-12-15

    The structure and fabrication methods of the ITER vacuum vessel (VV) have been investigated and defined by the ITER International Team (IT). However, some of the current technical specifications are difficult to be achieved from the manufacturing point of view. To solve such an issue, this paper proposes an alternative specification of the VV to the IT's design. A series of the fabrication and assembly procedures for the mock-up are presented, together with candidates of welding configurations. Finally, the paper summarizes the results of mock-up fabrication, such as non-destructive examination of weld lines, obtained welding deformation and issues revealed from the fabrication experience. Based on the results, it is suggested that several issues such as clarification of conditions of repair welding, demonstration of welding distortion control and detectability/localization of internal defects should be solved before manufacturing the ITER VV.

  3. Proposing buffer zones and simple technical solutions for safeguarding river water quality and public health

    Science.gov (United States)

    Podimata, M. V.; Bekri, E. S.; Yannopoulos, P. C.

    2012-04-01

    Framework Directive (WFD) 2000/60, but a practical necessity for the safeguarding of public health and ecosystem health, in general. The present study aims at developing a simple methodology for assessing spatial distribution characteristics of pollution in Erymanthos catchment. Pollution loads at various sites in Erymanthos watershed were illustrated with Geographical Information System (GIS). Flow rates of Erymanthos River were also taken into consideration. Based on previous studies, in situ river discharges have been compared to simulated discharges in order to calibrate the rainfall-runoff model ENNS which can then predict future scenarios regarding the river flow rates with consideration of climate change effects. The goal of this study is to detect the pertinent points and suggest a) suitable buffer zones in areas with high pollution risk and b) simple technical works in order to prevent the main channel of Erymanthos River from direct polluting discharges. The above systems could also act supportively in groundwater enrichment, forest protection and soil erosion prevention. Authors believe that the results of the study could assist authorities and engineers to design and develop strategies of improving river water quality and safeguarding public health. The proposed measures may be applicable to other catchments as well.

  4. 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

  5. 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

  6. 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

  7. Lowest Price, Technically Acceptable Evaluation Criteria Used in the November 2014 Request for Proposal for the Program Executive Office Soldier Systems Engineering and Technical Assistance (SETA) Contract

    Science.gov (United States)

    2017-09-01

    GS-0895-09 Industrial Engineering Technician 23.04 7.56 GS-0810-09 Civil Engineering Developmental (Programming) 23.04 7.56 GS-0810-11 Civil ... Engineering –Programming 27.88 9.14 GS-0810-12 Civil Engineering –Design 33.41 10.96 GS-2210-09 Info Tech Spec (Network Systems/Customer Support) 23.04...USED IN THE NOVEMBER 2014 REQUEST FOR PROPOSAL FOR THE PROGRAM EXECUTIVE OFFICE SOLDIER SYSTEMS ENGINEERING AND TECHNICAL ASSISTANCE (SETA) CONTRACT

  8. Proposal of a Technical Design of the ATLAS Forward Region Shielding

    CERN Document Server

    Leroy, C; Palla, J; Pospísil, S; Puchmajer, P; Sodomka, J; Stekl, I

    2002-01-01

    The aim of this note is to present a technical design of the ATLAS forward region. The concept is based on segmented shielding supported by the results of an experiment performed at CERN - PS and Monte Carlo simulations extending these results to ATLAS situation. This concept is translated into a practical engineering design.

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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, ...

  15. 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...

  16. Program of scientific investigations and development of solid-oxide fuel cells (SOFC) in VNIITF. Proposals on scientific and technical collaboration and SOFC commercialization

    Energy Technology Data Exchange (ETDEWEB)

    Kleschev, Yu.N.; Chukharev, V.F.

    1996-04-01

    This paper describes proposals on scientific and technical collaborations pertaining to solid oxide fuel cell commercialization. Topics included for discussion are: materials research and manufacture; market estimation and cost; directions of collaboration; and project of proposals on joint enterprise creation.

  17. 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

  18. Nagra technical report 14-02, Geological basics - Dossier VI - Barrier properties of proposed host rock sediments and neighbouring rock

    International Nuclear Information System (INIS)

    Gautschi, A.; Deplazes, G.; Traber, D.; Marschall, P.; Mazurek, M.; Gimmi, T.; Maeder, U.

    2014-01-01

    This dossier is the sixth of a series of eight reports concerning the safety and technical aspects of locations for the disposal of radioactive wastes in Switzerland. It discusses the barrier properties of the proposed host rock sediments and neighbouring rock layers. The mineralogical composition of the host rocks are discussed as are their pore densities and hydrological properties. Diffusion aspects are discussed. The aquifer systems in the proposed depository areas and their classification are looked at. The barrier properties of the host rocks and those of neighbouring sediments are discussed. Finally, modelling concepts and parameters for the transport of radionuclides in the rocks are discussed

  19. 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

  20. 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

  1. Standard technical specifications - Babcock and Wilcox 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 Babcock and Wilcox (B ampersand W) 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 B ampersand W Owners Group (BWOG), 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

  2. 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.

  3. 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

  4. 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

  5. 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.)

  6. Ecological compensation: From general guidance and expertise to specific proposals for road developments

    International Nuclear Information System (INIS)

    Villarroya, Ana; Persson, Jesper; Puig, Jordi

    2014-01-01

    The main scientific bibliography addressing the rationale behind ecological compensation is reviewed in order to examine general guidelines. This contains interesting general guidance on how to implement compensation, and provides the basis for future developments in compensation practice. On this basis, we propose a further step in compensation practice, advancing compensation proposals or rules for specific kinds of projects and contexts, focusing on road projects in the Spanish Environmental Impact Assessment (EIA). Three main residual impacts of roads are identified which usually remain uncompensated for: the loss of natural and semi-natural land use, the increase in emissions resulting from any new road, and the fragmentation, severance or barrier effect on the landscape and its wildlife. To counteract these, four proposals, or “rules”, are advanced: conservation of natural and semi-natural land use area, conservation of dominant plant species physiognomy, compensation for emissions, and the rule of positive defragmentation. -- Highlights: • Ecological compensation theory does not specify guidelines for types of projects. • EIA practitioners lack valuable specific guidance on how to implement compensation. • Specific guidance for road project ecological compensation is proposed. • Compensation proposals should have in mind present-day compensation practice level. • Specific ways to compensate for habitat loss, emissions, and fragmentation are shown

  7. Ecological compensation: From general guidance and expertise to specific proposals for road developments

    Energy Technology Data Exchange (ETDEWEB)

    Villarroya, Ana, E-mail: avillarroya@alumni.unav.es [Department of Zoology and Ecology, University of Navarra, c/Irunlarrea s/n, 31008 Pamplona, Navarra (Spain); Persson, Jesper, E-mail: jesper.persson@slu.se [Department of Landscape Management, Design and Construction, Swedish University of Agricultural Sciences (SLU), P.O. Box 66, SE-230 53 Alnarp (Sweden); Puig, Jordi, E-mail: jpbaguer@unav.es [Department of Zoology and Ecology, University of Navarra, c/Irunlarrea s/n, 31008 Pamplona, Navarra (Spain)

    2014-02-15

    The main scientific bibliography addressing the rationale behind ecological compensation is reviewed in order to examine general guidelines. This contains interesting general guidance on how to implement compensation, and provides the basis for future developments in compensation practice. On this basis, we propose a further step in compensation practice, advancing compensation proposals or rules for specific kinds of projects and contexts, focusing on road projects in the Spanish Environmental Impact Assessment (EIA). Three main residual impacts of roads are identified which usually remain uncompensated for: the loss of natural and semi-natural land use, the increase in emissions resulting from any new road, and the fragmentation, severance or barrier effect on the landscape and its wildlife. To counteract these, four proposals, or “rules”, are advanced: conservation of natural and semi-natural land use area, conservation of dominant plant species physiognomy, compensation for emissions, and the rule of positive defragmentation. -- Highlights: • Ecological compensation theory does not specify guidelines for types of projects. • EIA practitioners lack valuable specific guidance on how to implement compensation. • Specific guidance for road project ecological compensation is proposed. • Compensation proposals should have in mind present-day compensation practice level. • Specific ways to compensate for habitat loss, emissions, and fragmentation are shown.

  8. 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

  9. 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

  10. 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

  11. Standard technical specifications: Babcock and Wilcox 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 Babcock and Wilcox 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

  12. 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

  13. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” was threefold: 1) presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; 2) allow creating a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; 3) once a clear picture of the existing experimental infrastructures is defined, new experimental facilities are discussed and proposed, on the basis of the identified R&D needs

  14. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” is threefold: first, it is intended for presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; second, it will allow to create a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; third, once a clear picture of the existing experimental infrastructures is defined, new experimental facilities will be discussed and proposed, on the basis of the identified R&D needs

  15. 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.

  16. 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

  17. 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

  18. 76 FR 32967 - Proposed Extensions and Waivers: National Early Childhood Technical Assistance Center

    Science.gov (United States)

    2011-06-07

    ... under Parts B and C of the IDEA that ultimately improve their developmental and early learning outcomes... strengthen State and local early childhood systems and improve outcomes for infants, toddlers, and children... DEPARTMENT OF EDUCATION [CFDA No. 84.326H] Proposed Extensions and Waivers: National Early...

  19. 77 FR 16869 - Proposed Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF...

    Science.gov (United States)

    2012-03-22

    ... system. This TS improvement is part of the consolidated line item improvement process (CLIIP). Additional... NRC-2012-0071. NRC's Agencywide Documents Access and Management System (ADAMS): You may access... continuous hours every 31 days, would be changed to require at least 15 continuous minutes of heater...

  20. Technical support document for proposed 1994 revision of the MEC thermal envelope requirements

    Energy Technology Data Exchange (ETDEWEB)

    Conner, C.C.; Lucas, R.G.

    1994-03-01

    This report documents the development of the proposed revision of the Council of American Building Officials` (CABO) 1994 supplement to the 1993 Model Energy Code (MEC) building thermal envelope requirements for maximum component U{sub 0}-value. The 1994 amendments to the 1993 MEC were established in last year`s code change cycle and did not change the envelope requirements. The research underlying the proposed MEC revision was conducted by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Building Energy Standards program. The goal of this research was to develop revised guidelines based on an objective methodology that determines the most cost-effective (least total cost) combination of energy conservation measures (ECMs) (insulation levels and window types) for residential buildings. This least-cost set of ECMs was used as a basis for proposing revised MEC maximum U{sub 0}-values (thermal transmittances). ECMs include window types (for example, double-pane vinyl) and insulation levels (for example, R-19) for ceilings, walls, and floors.

  1. 77 FR 74002 - Proposed Information Collection Request; Comment Request; Technical Assistance Needs Assessments...

    Science.gov (United States)

    2012-12-12

    ... in the remedial/ removal process as possible and enable meaningful community involvement in the Superfund decision-making process. Additionally, the TANA process produces a blueprint for designing a... services to the affected community. Given the specific nature of the TANA, 8 to 10 persons will be...

  2. 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

  3. Analysis of the prevailing standard and technical documents for their applicability under conditions of the 'Ukrytie' operation and technical proposals relating to the elaboration of new ones concerning fire safety

    International Nuclear Information System (INIS)

    Nazarenko, B.S.; Emets, V.G.

    1998-01-01

    An analysis of the prevailing laws and standards and technical documents (STD) to ensure safe operation of nuclear power installations, with requirements of nuclear, radiation and fire safety taken into account, has been performed. Proposals on application of some items of prevailing STD under conditions of the 'Ukrytie' operation are presented. Also given are technical proposals on correction of the prevailing operational standard documents and elaboration of special STD

  4. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The discussion which followed the different presentations highlighted the following points: • All the Member States representatives participating in the technical meeting welcomed this IAEA initiative and expressed their potential interest in contributing to the catalogue; • Not all the countries with a fast reactor programme were represented at the meeting. In particular, it was noted that there was no participation from China, the Russian Federation and the USA. Even contribution from Sweden and Spain would be beneficial. It will be a task of the IAEA Secretariat to try involving also these countries in the preparation of the catalogue; • The catalogue will focus only on experimental facilities supporting development of liquid metal cooled fast reactors (Sodium, Lead and Lead-Bismuth). For the time being, facilities in support of GFR and MSR research will not be included; • As for countries involved in HLM technology research, only European countries were participating at the meeting, i.e. Belgium, France, Italy and Germany. In order to avoid duplication of the work performed within the European project ADRIANA, representatives from these countries underlined that a condition for their contribution to the IAEA catalogue is the involvement of non-European countries with HLM research programmes; • The advice from the Member States is fundamental to clearly define scope, objectives and content of the catalogue. The plan for its drafting has also to be further discussed with Member States representatives; • The catalogue is also intended to identify gaps and future needs that require further R&D initiatives; • The catalogue will be a useful tool to set up international collaboration

  5. End-of-waste criteria for waste plastic for conversion. Technical proposals.

    OpenAIRE

    VILLANUEVA KRZYZANIAK Alejandro; EDER Peter

    2014-01-01

    This report is the JRC-IPTS contribution to the development of the end-of-waste criteria for waste plastic in accordance with Article 6 of Directive 2008/98/EC of the European Parliament and of the Council on waste (the Waste Framework Directive). This report includes a possible set of end-of-waste criteria and shows how the proposals were developed based on a comprehensive techno-economic analysis of the waste plastic production chain and an analysis of the economic, environmental and le...

  6. 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

  7. 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

  8. 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.

  9. Early assessment of feasibility and technical specificities of transoral robotic surgery using the da Vinci Xi.

    Science.gov (United States)

    Gorphe, Philippe; Von Tan, Jean; El Bedoui, Sophie; Hartl, Dana M; Auperin, Anne; Qassemyar, Quentin; Moya-Plana, Antoine; Janot, François; Julieron, Morbize; Temam, Stephane

    2017-12-01

    The latest generation Da Vinci ® Xi™ Surgical System Robot released has not been evaluated to date in transoral surgery for head and neck cancers. We report here the 1-year results of a non-randomized phase II multicentric prospective trial aimed at assessing its feasibility and technical specificities. Our primary objective was to evaluate the feasibility of transoral robotic surgery using the da Vinci ® Xi™ Surgical System Robot. The secondary objective was to assess peroperative outcomes. Twenty-seven patients, mean age 62.7 years, were included between May 2015 and June 2016 with tumors affecting the following sites: oropharynx (n = 21), larynx (n = 4), hypopharynx (n = 1), parapharyngeal space (n = 1). Eighteen patients were included for primary treatment, three for a local recurrence, and six for cancer in a previously irradiated field. Three were reconstructed with a FAMM flap and 6 with a free ALT flap. The mean docking time was 12 min. "Chopsticking" of surgical instruments was very rare. During hospitalization following surgery, 3 patients experienced significant bleeding between day 8 and 9 that required surgical transoral hemostasis (n = 1) or endovascular embolization (n = 2). Transoral robotic surgery using the da Vinci ® Xi™ Surgical System Robot proved feasible with technological improvements compared to previous generation surgical system robots and with a similar postoperative course. Further technological progress is expected to be of significant benefit to the patients.

  10. 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

  11. 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

  12. Feasibility study and technical proposal for long-term observations of bedrock stability with gps

    International Nuclear Information System (INIS)

    Ruizhi Chen; Kakkuri, J.

    1994-01-01

    In order to study the regional crustal deformation pattern in the territory of Finland, the Finnish Geodetic Institute is establishing the Finnish Permanent GPS Network, which is part of the Fennoscandian Permanent GPS Network. The Finnish GPS Network consists of a 12 stations located in different geological structures. The operation procedure of the network is described in the report. Feasibility study for monitoring the bedrock stability at local scale was performed. The study was carried out on the basis of an experiment on a baseline of 1041 metres. Twelve artificial movements ranging from 1 mm to 22 mm were generated with a precision-manufactured screw drive (with an accuracy of better than +-0.05 mm). The artificial movements were then detected with the GPS measurements. A preliminary analysis of the GPS data shows that the maximum difference between the GPS detected movements and the artificial movements is 0.9 mm with a standard deviation of +-0.46 mm. The observation time for reaching such accuracy is about 55 minutes. Three GPS networks were preliminarily designed for the radioactive waste disposal investigation sites of Olkiluoto, Kivetty and Romuvaara. Detailed research plan for achieving the best possible result from GPS measurements was proposed. (58 refs., 25 figs., 1 tab.)

  13. 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)

  14. 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

  15. 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

  16. 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.

  17. 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

  18. 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

  19. 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

  20. 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)

  1. 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.

  2. Sensitivity and specificity of proposed DSM-5 diagnostic criteria for autism spectrum disorder.

    Science.gov (United States)

    McPartland, James C; Reichow, Brian; Volkmar, Fred R

    2012-04-01

    This study evaluated the potential impact of proposed DSM-5 diagnostic criteria for autism spectrum disorder (ASD). The study focused on a sample of 933 participants evaluated during the DSM-IV field trial; 657 carried a clinical diagnosis of an ASD, and 276 were diagnosed with a non-autistic disorder. Sensitivity and specificity for proposed DSM-5 diagnostic criteria were evaluated using field trial symptom checklists as follows: individual field trial checklist items (e.g., nonverbal communication); checklist items grouped together as described by a single DSM-5 symptom (e.g., nonverbal and verbal communication); individual DSM-5 criterion (e.g., social-communicative impairment); and overall diagnostic criteria. When applying proposed DSM-5 diagnostic criteria for ASD, 60.6% (95% confidence interval: 57%-64%) of cases with a clinical diagnosis of an ASD met revised DSM-5 diagnostic criteria for ASD. Overall specificity was high, with 94.9% (95% confidence interval: 92%-97%) of individuals accurately excluded from the spectrum. Sensitivity varied by diagnostic subgroup (autistic disorder = 0.76; Asperger's disorder = 0.25; pervasive developmental disorder-not otherwise specified = 0.28) and cognitive ability (IQ criteria could substantially alter the composition of the autism spectrum. Revised criteria improve specificity but exclude a substantial portion of cognitively able individuals and those with ASDs other than autistic disorder. A more stringent diagnostic rubric holds significant public health ramifications regarding service eligibility and compatibility of historical and future research. Copyright © 2012 American Academy of Child and Adolescent Psychiatry. Published by Elsevier Inc. All rights reserved.

  3. Towards sensible toxicity testing for nanomaterials: proposal for the specification of test design

    International Nuclear Information System (INIS)

    Potthoff, Annegret; Meißner, Tobias; Weil, Mirco; Kühnel, Dana

    2015-01-01

    During the last decade, nanomaterials (NM) were extensively tested for potential harmful effects towards humans and environmental organisms. However, a sound hazard assessment was so far hampered by uncertainties and a low comparability of test results. The reason for the low comparability is a high variation in the (1) type of NM tested with regard to raw material, size and shape and (2) procedures before and during the toxicity testing. This calls for tailored, nanomaterial-specific protocols. Here, a structured approach is proposed, intended to lead to test protocols not only tailored to specific types of nanomaterials, but also to respective test system for toxicity testing. There are existing standards on single procedures involving nanomaterials, however, not all relevant procedures are covered by standards. Hence, our approach offers a detailed way of weighting several plausible alternatives for e.g. sample preparation, in order to decide on the procedure most meaningful for a specific nanomaterial and toxicity test. A framework of several decision trees (DT) and flow charts to support testing of NM is proposed as a basis for further refinement and in-depth elaboration. DT and flow charts were drafted for (1) general procedure—physicochemical characterisation, (2) choice of test media, (3) decision on test scenario and application of NM to liquid media, (4) application of NM to the gas phase, (5) application of NM to soil and sediments, (6) dose metrics, (S1) definition of a nanomaterial, and (S2) dissolution. The applicability of the proposed approach was surveyed by using experimental data retrieved from studies on nanoscale CuO. This survey demonstrated the DT and flow charts to be a convenient tool to systematically decide upon test procedures and processes, and hence pose an important step towards harmonisation of NM testing. (paper)

  4. Ataques de nervios: proposed diagnostic criteria for a culture specific syndrome.

    Science.gov (United States)

    Oquendo, M; Horwath, E; Martinez, A

    1992-09-01

    The authors propose a set of diagnostic criteria and report two cases of ataque de nervios, a syndrome of brief duration seen primarily in Spanish-speaking people of the Caribbean. Following a psychosocial stressor, the afflicted person demonstrates impulsivity, dissociation and communication and perceptual disturbances. The symptoms often begin in the presence of the family, allow a temporary relinquishing of social roles, and result in the mobilization of the social network in support of the person. Further research is needed to improve our understanding of this culture specific syndrome and its relationship to psychiatric disorder.

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. Technical comments on EPA`s proposed revisions to the National Ambient Air Quality Standard for particulate matter

    Energy Technology Data Exchange (ETDEWEB)

    Lipfert, F.W.

    1997-03-01

    The US Environmental Protection Agency (EPA) has proposed new ambient air quality standards specifically for fine particulate matter, regulating concentrations of particles with median aerodynamic diameters less than 2.5 {mu}m (PM{sub 2.5}). Two new standards have been proposed: a maximum 24-hr concentration that is intended to protect against acute health effects, and an annual concentration limit that is intended to protect against longer-term health effects. EPA has also proposed a slight relaxation of the 24-hr standard for inhalable particles (PM{sub 10}), by allowing additional exceedances each year. Fine particles are currently being indirectly controlled by means of regulations for PM{sub 10} and TSP, under the Clean Air Act of 1970 and subsequent amendments. Although routine monitoring of PM{sub 2.5} is rare and data are sparse, the available data indicate that ambient concentrations have been declining at about 6% per year under existing regulations.

  12. 75 FR 75705 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2010-12-06

    ..., Rockville, Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available electronically at the NRC's Electronic Reading Room... and Management System (ADAMS) under Accession Number ML093570241. The proposed changes revise the...

  13. 78 FR 36012 - 30-Day Notice of Proposed Information Collection: Export Declaration of Defense Technical Data or...

    Science.gov (United States)

    2013-06-14

    ... Collection: Export Declaration of Defense Technical Data or Services. OMB Control Number: 1405-0157. Type of... Declaration of Defense Technical Data or Services ACTION: Notice of request for public comment and submission... and brokering of defense articles, defense services and related technical data are licensed by the...

  14. Technical and economic proposal for the extension of the Laguna Verde Nuclear Power plant with an additional nuclear reactor

    International Nuclear Information System (INIS)

    Leal C, C.D.; Francois L, J.L.

    2006-01-01

    The increment of the human activities in the industrial environments and of generation of electric power, through it burns it of fossil fuels, has brought as consequence an increase in the atmospheric concentrations of the calls greenhouse effect gases and, these in turn, serious repercussions about the environment and the quality of the alive beings life. The recent concern for the environment has provoked that industrialized countries and not industrialized carry out international agreements to mitigate the emission from these gases to the atmosphere. Our country, like part of the international community, not is exempt of this problem for what is necessary that programs begin guided toward the preservation of the environment. As for the electric power generation, it is indispensable to diversify the sources of primary energy; first, to knock down the dependence of the hydrocarbons and, second, to reduce the emission of polluting gases to the atmosphere. In this item, the nucleo electric energy not only has proven to be safe and competitive technical and economically, able to generate big quantities of electric power with a high plant factor and a considerable cost, but rather also, it is one of the energy sources that less pollutants it emits to the atmosphere. The main object of this work is to carry out a technical and economic proposal of the extension of the Laguna Verde Nuclear power plant (CNLV) with a new nuclear reactor of type A BWR (Advanced Boiling Water Reactor), evolutionary design of the BWR technology to which belong the two reactors installed at the moment in the plant, with the purpose of increasing the installed capacity of generation of the CNLV and of the Federal Commission of Electricity (CFE) with foundation in the sustainable development and guaranteeing the protection of the environment by means of the exploitation of a clean and sure technology that counts at the moment with around 12,000 year-reactor of operational experience in more of

  15. 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...

  16. 76 FR 189 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2011-01-03

    ... [pressurized water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  17. 75 FR 79048 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2010-12-17

    ... [boiling water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  18. 76 FR 66763 - Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-510...

    Science.gov (United States)

    2011-10-27

    ....'' TSTF-510, Revision 2, is available in the Agencywide Documents Access and Management System (ADAMS... SG Tube Integrity specification (Limiting Condition for Operation (LCO) 3.4.17, LCO 3.4.20, and LCO 3... address implementation issues associated with the inspection periods, and address other administrative...

  19. [Need of specific criteria for psychotherapy referral in the public health system: A proposal].

    Science.gov (United States)

    García-Haro, J; Fernández-Briz, N

    2015-01-01

    This study discusses the need of specific criteria for psychotherapy referral in the public services. the use of psychotherapy as a supplement to traditional medication, and its comparison with informal methods of support, has been questioned. This study proposes the establishment of basic criteria for the integration of psychotherapy, based on an analysis of the conditions that allow it to function. It thus aims to contribute to improving the reputation and the practice conditions of psychotherapy in the public health system. Copyright © 2013 Sociedad Española de Médicos de Atención Primaria (SEMERGEN). Publicado por Elsevier España, S.L.U. All rights reserved.

  20. 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.

  1. 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.

  2. 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

  3. 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.)

  4. 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.

  5. 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

  6. 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

    2002-01-01

    Hot cells are the facilities for handling the high radioactive materials and various R and D activities are performed using hot cells. Therefore the control of air flow in hot cell area is very important technology and it is started with the variable speed motor(VSM) controlling the air handling system in that area. This report describes various technical aspects of VS motors and will be useful for understanding the practical technologies of VS motors and also for optimization of the negative pressure controls in hot cell area.

  7. 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

  8. 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

  9. Validity of multiple stress creep recovery (MSCR) test for DOTD asphalt binder specification : technical summary.

    Science.gov (United States)

    2017-09-01

    Higher traffic coupled with heavier loads led the asphalt industry to introduce polymer-modified binders to enhance the durability and strength of hot mix asphalt (HMA) pavements. When the Superpave Performance Graded (PG) binder specification (AASHT...

  10. Technical specifications (Docket No. 50-400): Appendix ''A'' to License No. NPF-63

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents specifications concerning the Shearon Harris Nuclear Power Plant in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  11. Generic Community System Specification: A Proposed Format for Reporting the Results of Microgrid Optimization Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, Antonio [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-03-14

    This document provides a proposed format for reporting the results of microgrid optimization analysis. While the proposed format assumes that the modeling is conducted as part of a renewable energy retrofit of an existing diesel micro-grid, the format can certainly be adopted for other situations.

  12. 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

  13. 75 FR 16817 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2010-04-02

    ... and electronically comparable. This meeting is designed as an interactive forum where PSOs and... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability... specifications. Throughout the meeting there will be interactive discussion to allow meeting participants not...

  14. 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.

  15. 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.

  16. 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....

  17. RAMS+C informed decision-making with application to multi-objective optimization of technical specifications and maintenance using genetic algorithms

    International Nuclear Information System (INIS)

    Martorell, S.; Villanueva, J.F.; Carlos, S.; Nebot, Y.; Sanchez, A.; Pitarch, J.L.; Serradell, V.

    2005-01-01

    The role of technical specifications and maintenance (TSM) activities at nuclear power plants (NPP) aims to increase reliability, availability and maintainability (RAM) of Safety-Related Equipment, which, in turn, must yield to an improved level of plant safety. However, more resources (e.g. costs, task force, etc.) have to be assigned in above areas to achieve better scores in reliability, availability, maintainability and safety (RAMS). Current situation at NPP shows different programs implemented at the plant that aim to the improvement of particular TSM-related parameters where the decision-making process is based on the assessment of the impact of the change proposed on a subgroup of RAMS+C attributes. This paper briefly reviews the role of TSM and two main groups of improvement programs at NPP, which suggest the convenience of considering the approach proposed in this paper for the Integrated Multi-Criteria Decision-Making on changes to TSM-related parameters based on RAMS+C criteria as a whole, as it can be seem as a decision-making process more consistent with the role and synergic effects of TSM and the objectives and goals of current improvement programs at NPP. The case of application to the Emergency Diesel Generator system demonstrates the viability and significance of the proposed approach for the Multi-objective Optimization of TSM-related parameters using a Genetic Algorithm

  18. 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

  19. 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

  20. Specifications for conductors and proposed conductor configurations: Milestone M5.3

    CERN Document Server

    Bordini, Bernardo; Dhallé, Marc

    2018-01-01

    This document summarises the specifications of a superconductor suitable to be used in a particle accelerator dipole magnet that can reach a field of 16 Tesla during regular operation. The document reports also on the conductor configuration. These specifications set the performance targets for industrial production requirements at large scale. The document motivates the specifications on one hand by taking a particular magnet baseline design as starting point and by considering the results of various conductor test campaigns carried out at partner institutes.

  1. 77 FR 5616 - Proposed Technical Standard Order (TSO)-C151c, Terrain Awareness and Warning System (TAWS)

    Science.gov (United States)

    2012-02-03

    ... (TSO)-C151c, Terrain Awareness and Warning System (TAWS) ACTION: Notice of availability and request for... second draft of Technical Standard Order (TSO)- C151c, Terrain Awareness and Warning System. Comments.... b. Addition of Localizer Performance with Vertical guidance (LPV) and Global Navigation Satellite...

  2. Technical evaluation of the proposed deletion of a reactor trip on a turbine trip below 50-percent power for the Beaver Valley nuclear power plant, Unit 1

    International Nuclear Information System (INIS)

    Reeves, W.E.

    1979-12-01

    This report documents the technical evaluation of the Duquesne Light Company's proposed license amendment for the deletion of a reactor trip on a turbine trip below 50% power for the Beaver Valley nuclear power plant, Unit 1. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  3. Sensitivity and Specificity of Proposed "DSM-5" Diagnostic Criteria for Autism Spectrum Disorder

    Science.gov (United States)

    McPartland, James C.; Reichow, Brian; Volkmar, Fred R.

    2012-01-01

    Objective: This study evaluated the potential impact of proposed "DSM-5" diagnostic criteria for autism spectrum disorder (ASD). Method: The study focused on a sample of 933 participants evaluated during the "DSM-IV" field trial; 657 carried a clinical diagnosis of an ASD, and 276 were diagnosed with a non-autistic disorder. Sensitivity and…

  4. 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.

  5. 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.

  6. Technical Note: Harmonic analysis applied to MR image distortion fields specific to arbitrarily shaped volumes.

    Science.gov (United States)

    Stanescu, T; Jaffray, D

    2018-05-25

    Magnetic resonance imaging is expected to play a more important role in radiation therapy given the recent developments in MR-guided technologies. MR images need to consistently show high spatial accuracy to facilitate RT specific tasks such as treatment planning and in-room guidance. The present study investigates a new harmonic analysis method for the characterization of complex 3D fields derived from MR images affected by system-related distortions. An interior Dirichlet problem based on solving the Laplace equation with boundary conditions (BCs) was formulated for the case of a 3D distortion field. The second-order boundary value problem (BVP) was solved using a finite elements method (FEM) for several quadratic geometries - i.e., sphere, cylinder, cuboid, D-shaped, and ellipsoid. To stress-test the method and generalize it, the BVP was also solved for more complex surfaces such as a Reuleaux 9-gon and the MR imaging volume of a scanner featuring a high degree of surface irregularities. The BCs were formatted from reference experimental data collected with a linearity phantom featuring a volumetric grid structure. The method was validated by comparing the harmonic analysis results with the corresponding experimental reference fields. The harmonic fields were found to be in good agreement with the baseline experimental data for all geometries investigated. In the case of quadratic domains, the percentage of sampling points with residual values larger than 1 mm were 0.5% and 0.2% for the axial components and vector magnitude, respectively. For the general case of a domain defined by the available MR imaging field of view, the reference data showed a peak distortion of about 12 mm and 79% of the sampling points carried a distortion magnitude larger than 1 mm (tolerance intrinsic to the experimental data). The upper limits of the residual values after comparison with the harmonic fields showed max and mean of 1.4 mm and 0.25 mm, respectively, with only 1.5% of

  7. 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.

  8. 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

  9. 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.

  10. [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.

  11. 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

  12. 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

  13. Technical Proposal on the Treatment of the Influent of the José Antonio Alzate dam Using Aerobic Pond System

    Directory of Open Access Journals (Sweden)

    E. López–Galván

    2010-01-01

    Full Text Available In México, discharge of waste water not treated is a common problem; this is the case of the Lerma River, where the original clean water contribution of the Almoloya–Lerma–San Bartolo timber–roof system, located in the valley of Toluca, State of México, was replaced by the wastewater of the valley. The attempts to clean the water before their spill have been unfruitful and this has caused the present anaerobic conditions of the river in its entire route including the first receiving stage that is the José Antonio Alzate Dam (PJAA, becoming a potential source of diseases and a useless water body. In this work we evaluate the treatment efficiency of experimental waste water pond system. The treatment system was constructed with 5 screens which formed 6 internal channels and it had an operation in continuous form by 26 weeks, providing it with continuously polluted water of the Lerma River. We found that the efficiency of reduction of the organic matter reported as BOD5 was 83% and it is carried out in the first channel after 7 days of hydraulic retention verifying that the channels do not work like lagoons in series. With the collected data we calculated, through the application of design equations, the factor of decay of organic matter "k" and the number of dispersion "d", specific for the type of treatment and environmental conditions of the site. The required surface of treatment calculated to reach the efficiency of reduction of the BOD5 obtained experimentally. Thus, a surface of: 1 281.6 hectares distributed in 13 lagoons that can deal with a volume 8 646, 70 m3/h was determined. Since this was a bigger surfaces than that of the dam, the available area was evaluated to make a proposal closer to reallity.

  14. 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

  15. 77 FR 38779 - Notice of Availability of Draft Environmental Impact Statement for the Proposed Mather Specific...

    Science.gov (United States)

    2012-06-29

    ... Action alternative and three large-scale, mixed-use development alternatives in the approximately 5,749... Development and Marketing (applicant) is seeking authorization from USACE for the placement of dredged or fill... portions of the Mather Specific Plan area. The overall project purpose is a large scale, mixed use...

  16. Sensitivity and Specificity of Proposed DSM-5 Criteria for Autism Spectrum Disorder in Toddlers

    Science.gov (United States)

    Barton, Marianne L.; Robins, Diana L.; Jashar, Dasal; Brennan, Laura; Fein, Deborah

    2013-01-01

    Autism spectrum disorder (ASD) diagnosis is based on behavioral presentation; changes in conceptual models or defining behaviors may significantly impact diagnosis and uptake of ASD-specific interventions. The literature examining impact of DSM-5 criteria is equivocal. Toddlers may be especially vulnerable to the stringent requirements of…

  17. 76 FR 32969 - National Technical Assistance and Dissemination Center for Children Who Are Deaf-Blind; Proposed...

    Science.gov (United States)

    2011-06-07

    ... result in appropriate assessment, planning, placement, and services for individuals who are deaf-blind... for Children Who Are Deaf-Blind; Proposed Extension of Project Period and Waiver AGENCY: Office of... Assistance and Dissemination Center for Children Who Are Deaf-Blind. SUMMARY: The Secretary proposes to waive...

  18. Proposing a Central AEC Ontology That Allows for Domain Specific Extensions

    DEFF Research Database (Denmark)

    Rasmussen, Mads Holten; Pauwels, Pieter; Hviid, Christian Anker

    2017-01-01

    ontology version of the ISO standardised Industry Foundation Classes (IFC) schema, thereby violating the W3C best practice rule of minimum redundancy. The voluminous IFC schema with origins in a closed world assumption is likewise violating this rule by redefining concepts about time, location, units etc....... already available from other sources, and it is furthermore violating the rule of keeping ontologies simple for easy maintenance. Based on all the available ontologies, we propose a simple Building Topology Ontology (BOT) only covering the core concepts of a building, and three methods for extending...

  19. Proposed Site-Specific Response Spectra for Surabaya-Madura Bridge

    Directory of Open Access Journals (Sweden)

    Dyah Kusumastuti

    2008-01-01

    Full Text Available This paper presents a site-specific seismic hazard study to determine the recommended seismic design criteria for Suramadu Bridge. The study is performed using probabilistic seismic hazard approach to determine maximum acceleration and response spectra at bedrock and followed by local site effect analysis to determine maximum acceleration and response spectra at ground surface. The probabilistic seismic hazard analysis (PSHA is carried out using 3-dimension (3-D seismic source models (fault source model. Two hazard levels are analysed to represent 150 and 3,300 years return period of ground motion around site location. The local site effect analysis is performed using 1-dimension (1-D shear wave propagation theory to obtain peak ground acceleration and response spectra at ground surface. Finally, the site-specific surface response spectra with 5 percent damping are developed based on the mean plus one standard deviation concept from the result of local site effect analysis.

  20. 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

  1. Proposing a Technical Solution for Restoring Longitudinal Connectivity in the Brădeni/Retiş Accumulation Area on Hârtibaciu River

    Directory of Open Access Journals (Sweden)

    Voicu Răzvan

    2016-04-01

    Full Text Available The fish fauna of the Hârtibaciu River has experienced a disrupted connectivity due to the hydrotechnical works and the Brădeni/Retiş Dam located across the Hârtibaciu watercourse being one of this significant obstacles. The newly proposed constructed wetlands can improve the habitat quality for the fish species of conservative interest sampled in the Brădeni/Retiş Dam proximity Rhodeus amarus, and can increase the individuals’ number of this population. Also can benefit the local populations of Phoxinus phoxinus and Gobio obtusirostris. Using gravitational force and also the underground layout, a proposed technical solution gives maximum safety regarding the water supply for the newly proposed to be created wetlands.

  2. Technical evaluation of the electrical, instrumentation, and control design aspects of the proposed license amendment Revision 1 for single-loop operation of Browns Ferry Nuclear Plants (Docket No. 50-259, Unit 1; Docket No. 50-260, Unit 2; Docket No. 50-296, Unit 3)

    International Nuclear Information System (INIS)

    Donich, T.R.

    1983-01-01

    This report documents the technical evaluation of the proposed changes to the plant reactor protection system by the licensee of Browns Ferry Nuclear Power Station, Units 1, 2, and 3, to account for single-loop plant operation. This evaluation is restricted to only the electrical, instrumentation and control design aspects of proposed changes to the plant technical specifications for single-loop operation beyond 24 hours. Conclusion is that the license amendment for single-loop operation has met the review criteria provided sufficient administrative controls are in effect, and any anomalous control room indicators are corrected or warning-tagged for the duration of single-loop operation

  3. Carbohydrate/glycan-binding specificity of legume lectins in respect to their proposed biological functions

    Directory of Open Access Journals (Sweden)

    Márcio Viana Ramos

    2000-01-01

    Full Text Available The lectins, proteins which specifically recognize carbohydrate moieties, have been extensively studied in many biochemical and structural aspects in order to establish the molecular basis of this non-catalytic event. On the other hand, their clinical and agricultural potentials have been growing fast. Although lectins, mainly those from legume plants, had been investigated for biological properties, studies about the physiological functions of lectins are scarce in literature. Therefore, despite the accumulated data on lectins (as proteins, the role played by these signalizing molecules is poorly discussed. In the light of our accumulated results on legume lectins, specially those obtained from plants belonging to the Diocleinae sub-tribe and available data in literature, we discuss here the main hypothesis of their functions according to their carbohydrate/glycan-binding specificity.As lectinas, proteinas que especificamente reconhecem estruturas que contém carboidratos, têm sido extensivamente estudadas em muitos aspectos bioquímicos e estruturais, objetivando estabelecer as bases moleculares deste evento não-catalítico. Por outro lado, os potenciais clínicos e agriculturais destas proteínas têm crescido rapidamente. Embora as lectinas, principalmente aquelas de legumes tenham sido bastante investigadas em suas propriedades biológicas, estudos sobre as funcões fisiológicas de lectinas são escassos na literatura. Além disto, a despeito da quantidade de dados acumulados sobre lectinas (como proteínas, o papel desempenhado por estas moléculas de sinalização é pobremente discutido. Valendo-se de nossos estudos sobre lectinas de leguminosas, principalmente da sub-tribo Diocleinae, e outros dados presentes na literatura, discutimos aqui, as principais hipóteses de suas funções com base na especificidade por carboidratos e glicanos complexos.

  4. Discoveries and application of prostate-specific antigen, and some proposals to optimize prostate cancer screening

    Directory of Open Access Journals (Sweden)

    Tokudome S

    2016-05-01

    Full Text Available Shinkan Tokudome,1 Ryosuke Ando,2 Yoshiro Koda,3 1Department of Nutritional Epidemiology, National Institute of Health and Nutrition, Shinjuku-ku, Tokyo, 2Department of Nephro-urology, Nagoya City University Graduate School of Medical Sciences, Mizuho-ku, Nagoya, 3Department of Forensic Medicine and Human Genetics, Kurume University School of Medicine, Kurume, Japan Abstract: The discoveries and application of prostate-specific antigen (PSA have been much appreciated because PSA-based screening has saved millions of lives of prostate cancer (PCa patients. Historically speaking, Flocks et al first identified antigenic properties in prostate tissue in 1960. Then, Barnes et al detected immunologic characteristics in prostatic fluid in 1963. Hara et al characterized γ-semino-protein in semen in 1966, and it has been proven to be identical to PSA. Subsequently, Ablin et al independently reported the presence of precipitation antigens in the prostate in 1970. Wang et al purified the PSA in 1979, and Kuriyama et al first applied an enzyme-linked immunosorbent assay for PSA in 1980. However, the positive predictive value with a cutoff figure of 4.0 ng/mL appeared substantially low (~30%. There are overdiagnoses and overtreatments for latent/low-risk PCa. Controversies exist in the PCa mortality-reducing effects of PSA screening between the European Randomized Study of Screening for Prostate Cancer (ERSPC and the US Prostate, Lung, Colorectal, and Ovarian (PLCO Cancer Screening Trial. For optimizing PCa screening, PSA-related items may require the following: 1 adjustment of the cutoff values according to age, as well as setting limits to age and screening intervals; 2 improving test performance using doubling time, density, and ratio of free: total PSA; and 3 fostering active surveillance for low-risk PCa with monitoring by PSA value. Other items needing consideration may include the following: 1 examinations of cell proliferation and cell cycle markers

  5. Proposed Tenaska Washington II Generation Project : Final Environmental Impact Statement. Volume 1: Environmental Analysis and Technical Appendices.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1994-01-01

    BPA is considering whether to purchase electrical power from a proposed privately-owned combustion-turbine electrical generation plant in Washington. The plant would be fired by natural gas and would use combined-cycle technology to generate 240 average megawatts (aMW) of energy. The plant would be developed, owned, and operated by Tenaska Washington Partners II, L.P. The project would be located about 19 kilometers (12 miles) southeast of downtown Tacoma in the Frederickson Industrial Area, Pierce County. The proposed plant would occupy about half of a 6.4-hectare (16-acre) parcel and would be consistent with the industrial character of its surroundings. The proposed site is currently undeveloped and zoned for industrial use by the county. Main environmental concerns identified in the scoping process and in comments on the Draft Environmental Impact Statement (EIS) include: (1) potential air quality impacts, such as emissions and their contribution to the {open_quotes}greenhouse{close_quotes} effect; (2) potential health and safety impacts, such as nuisance odors, plant safety, visibility and heat-emission systems which may affect low-flying planes and potential health effects of electric and magnetic fields; and (3) potential water quality and quantity impacts, such as the amount of wastewater to be discharged, the source and amount of water required for plant operation. These and other issues are discussed in detail in the EIS. The proposed project already includes many features designed to reduce environmental impacts. Based on investigations performed for the EIS, no significant unavoidable adverse environmental impacts associated with the proposed project were identified, and no evidence emerged to suggest that the proposed action is controversial. The EIS is being mailed to numerous agencies, groups, and individuals (see Section 8.0). There will be a 30-day no-action period before any decisions are made and the Record of Decision is signed.

  6. Proposal for the development of IRMA kits for prostate specific antigen, PSA

    International Nuclear Information System (INIS)

    Abdul, A.B.

    1997-01-01

    The following are the major objectives of this research proposal: (1) To establish a protocol for biotinylation of monoclonal antibody, mabs or polyclonal antibody against the antigen, PSA. This shall include the purifying procedure using size exclusion chromatography on HPLC for use in binding assays to determine its binding capacity with PSA. (2) To establish an immunoassay protocol for IRMAs, using the technique of immobilizing the capture mabs on solid phase (surfaces of polystyrene) and the radioiodine labeled streptavidin-biotinylated bridge system. This will include optimization of the assay design and a Quality Control Assessment with the inclusion of standards derived from the Agency and subsequent work to determine its sensitivity (Minimum Detection Limit) and working range (the phenomenon of Hooke's Effect). An in-house quality control would also be useful to determine the assay's suitability for screening the tumour marker from patient samples obtained from neighboring hospitals (such as the Science University of Malaysia Hospital and the National University Hospital) and private clinical pathology laboratory (such as the Pantai Medical Centre) which compare concurrently the results with existing commercial immunoassay kits (RIA/IRMA). These work and that described earlier in (1) shall be done entirely at MINT. (3) To perform an external coordinated external Quality Control Assurance Programme with other research institutes (such as the Department of Immunology, Medical faculty, Science University of Malaysia and government hospitals) in Malaysia on several batches of the IRMA kits (produced at MINT and proven to be suitable for screening PSA in human serum from in-house Quality Control data, as mentioned earlier in (2)). This coordinated work shall include analyzing and documenting all values obtained from a group of patient's sample in clinical conditions such as batch to batch variation, inter and intra-assay variations and mean values for negative

  7. Implicit Treatment of Technical Specification and Thermal Hydraulic Parameter Uncertainties in Gaussian Process Model to Estimate Safety Margin

    Directory of Open Access Journals (Sweden)

    Douglas A. Fynan

    2016-06-01

    Full Text Available The Gaussian process model (GPM is a flexible surrogate model that can be used for nonparametric regression for multivariate problems. A unique feature of the GPM is that a prediction variance is automatically provided with the regression function. In this paper, we estimate the safety margin of a nuclear power plant by performing regression on the output of best-estimate simulations of a large-break loss-of-coolant accident with sampling of safety system configuration, sequence timing, technical specifications, and thermal hydraulic parameter uncertainties. The key aspect of our approach is that the GPM regression is only performed on the dominant input variables, the safety injection flow rate and the delay time for AC powered pumps to start representing sequence timing uncertainty, providing a predictive model for the peak clad temperature during a reflood phase. Other uncertainties are interpreted as contributors to the measurement noise of the code output and are implicitly treated in the GPM in the noise variance term, providing local uncertainty bounds for the peak clad temperature. We discuss the applicability of the foregoing method to reduce the use of conservative assumptions in best estimate plus uncertainty (BEPU and Level 1 probabilistic safety assessment (PSA success criteria definitions while dealing with a large number of uncertainties.

  8. 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)

  9. Comments on new technical and economic data available for EPA's proposed offshore oil and gas discharge guidelines and standards

    International Nuclear Information System (INIS)

    1989-01-01

    The purpose of this paper is to provide comments on the Environmental Protection Agency (EPA) Notice in the Federal Register entitled, ''Oil and Gas Extraction Point Source Category, Offshore Subcategory; Effluent Limitations Guidelines and New Source Performance Standards; New Information and Request or Comments'' (53 FR 41356; October 21, 1988). This Notice announces the availability of new technical, economic and environmental assessment information relating to the development of Best Available Technology economically achievable (BAT and New Source Performance Standards (NSPS) regulations under the Clean Water Act governing the discharge of drilling fluids (muds) and drill cuttings from offshore oil and gas facilities. The Notice is part of a rulemaking process which formally began with the initial release of rules in August 1985 and which incorporates numerous comments and additional data received subsequent to the release of the 1985 rules. The comments in this paper will concentrate on the following five issues: Estimated project impacts are misrepresented by assuming weighted-average incremental costs of regulation. Economic impacts are inaccurate, since annual compliance costs will likely affect the number of wells drilled, by the effect of compliance costs on project economics and the reduction in industry cash flows on capital available for drilling. Initial well productivity assumptions for various scenarios do not vary with field size. The assumed lease costs, which are based on historical data, do not accurately reflect the future value of leases. The experimental decline rates assumed for the Pacific are too high

  10. High sensitivity and specificity in proposed clinical diagnostic criteria for anti-N-methyl-D-aspartate receptor encephalitis.

    Science.gov (United States)

    Ho, Alvin C C; Mohammad, Shekeeb S; Pillai, Sekhar C; Tantsis, Esther; Jones, Hannah; Ho, Reena; Lim, Ming; Hacohen, Yael; Vincent, Angela; Dale, Russell C

    2017-12-01

    To determine the validity of the proposed clinical diagnostic criteria for anti-N-methyl-d-aspartate receptor (NMDAR) encephalitis in paediatric patients. The diagnostic criteria for anti-NMDAR encephalitis proposed by Graus et al. (2016) use clinical features and conventional investigations to facilitate early immunotherapy before antibody status is available. The criteria are satisfied if patients develop four out of six symptom groups within 3 months, together with at least one abnormal investigation (electroencephalography/cerebrospinal fluid) and reasonable exclusion of other disorders. We evaluated the validity of the criteria using a retrospective cohort of paediatric patients with encephalitis. Twenty-nine patients with anti-NMDAR encephalitis and 74 comparison children with encephalitis were included. As expected, the percentage of patients with anti-NMDAR encephalitis who fulfilled the clinical criteria increased over time. During the hospital inpatient admission, most patients (26/29, 90%) with anti-NMDAR encephalitis fulfilled the criteria, significantly more than the comparison group (3/74, 4%) (panti-NMDAR encephalitis was 2 weeks from first symptom onset (range 1-6). The sensitivity of the criteria was 90% (95% confidence interval 73-98) and the specificity was 96% (95% confidence interval 89-99). The proposed diagnostic criteria for anti-NMDAR encephalitis have good sensitivity and specificity. Incomplete criteria do not exclude the diagnosis. The proposed clinical diagnostic criteria for anti-N-methyl-d-aspartate receptor (NMDAR) encephalitis by Graus et al. (2016) have high sensitivity and specificity in paediatric patients. The median time of fulfilling the criteria in patients with anti-NMDAR was 2 weeks from first symptom onset. © 2017 Mac Keith Press.

  11. A proposal of ITER vacuum vessel fabrication specification and results of the full-scale partial mock-up test

    Energy Technology Data Exchange (ETDEWEB)

    Nakahira, Masataka; Takeda, Nobukazu; Onozuka, Masanori [Japan Atomic Energy Agency (Japan); Kakudate, Satoshi [Mitsubishi Heavy Industries, Ltd. (Japan)

    2007-07-01

    The structure and fabrication methods of the ITER vacuum vessel have been investigated and defined by the ITER international team. However, some of the current specifications are very difficult to be achieved from the manufacturing point of view and will lead to cost increase. In the mock-up fabrication, it is planned to conduct the following items: 1. Feasibility of the Japanese proposed VV structure and fabrication methods and the applicability to the ITER are to be confirmed; 2. Assembly procedure and inspection procedure are to be confirmed; 3. Manufacturing tolerances are to be assessed; 4. Manufacturing schedule is to be assessed. This report summarizes the Japanese proposed specification of the VV mock-up describing differences between the ITER supplied design. General scope of the mock-up fabrication and the detailed dimensions are also shown. In the VV fabrication, several types of weld joint configuration will be used. This report shows the joint configurations proposed by Japan to be used for the inner shell connection, the rib-to-shell connection and outer shell connection, and the housing-to-shell connection, respectively. Non-destructive testing considered to be applied to each joint configuration is also presented. A series of the fabrication and assembly procedures for the mock-up are presented in this report, together with candidates of welding configurations. Finally, the report summarizes the results of mock-up fabrication, including results of nondestructive examination of weld lines, obtained welding deformation and issues revealed from the fabrication experience. (orig.)

  12. Proposal for a Co-operation Agreement between the European Organization for Nuclear Research (CERN) and the Vietnamese Academy of Science and Technology (VAST) concerning Scientific and Technical Co-o

    CERN Document Server

    2006-01-01

    Proposal for a Co-operation Agreement between the European Organization for Nuclear Research (CERN) and the Vietnamese Academy of Science and Technology (VAST) concerning Scientific and Technical Co-o

  13. Critical evaluation of the nonradiological environmental technical specifications. Volume 2. Surry Power Plants, Units 1 and 2

    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 Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 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 two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to monitor changes in the primary producers. Models based on operating data were constructed to determine whether changes were occurring at each trophic level. Analysis of the monitoring data suggests that the thermal discharges at Surry are having a negative effect on the phytoplankton and zooplankton but are enhancing the benthic and nekton populations in the discharge area

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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

  3. Management Plan for Experimental Reintroduction of Sockeye into Skaha Lake; Proposed Implementation, Monitoring, and Evaluation, 2004 Technical Report.

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Howie; Smith, Howard (Okanagan Nation Alliance, Fisheries Department, Westbank, BC, Canada)

    2004-01-01

    Okanagan River sockeye salmon, which spawn near the town of Oliver, B.C., have their farther upstream migration limited by several water control and diversion dams. Stock numbers have been declining for many years and the Okanagan Native Alliance Fisheries Department (ONAFD) has been the principal advocate of a program to restore their numbers and range by reintroducing them into upstream waters where they may once have occurred in substantial numbers Some investigators have warned that without effective intervention Okanagan sockeye are at considerable risk of extinction. Among a host of threats, the quality of water in the single nursery areas in Osoyoos Lake. is deteriorating and a sanctuary such as that afforded in larger lakes higher in the system could be essential. Because the proposed reintroduction upstream has implications for other fish species, (particularly kokanee, the so-called ''landlocked sockeye'' which reside in many Okanagan lakes), the proponents undertook a three-year investigation, with funding from the Bonneville Power Administration and the Confederated Tribes of the Colville Reservation, to identify possible problem areas, and they committed to an interim experimental reintroduction to Skaha Lake where any problems could be worked out before a more ambitious reintroduction, (e.g. to Okanagan Lake) could be formally considered. The three-year investigation was completed in the spring of 2003. It included an assessment of risks from disease or the possible introduction of unwanted exotic species. It also considered the present quality and quantity of sockeye habitat, and opportunities for expanding or improving it. Finally ecological complexity encouraged the development of a life history model to examine interactions of sockeye with other fishes and their food organisms. While some problem areas were exposed in the course of these studies, they appeared to be manageable and the concept of an experimental reintroduction

  4. High-level specification of a proposed information architecture for support of a bioterrorism early-warning system.

    Science.gov (United States)

    Berkowitz, Murray R

    2013-01-01

    Current information systems for use in detecting bioterrorist attacks lack a consistent, overarching information architecture. An overview of the use of biological agents as weapons during a bioterrorist attack is presented. Proposed are the design, development, and implementation of a medical informatics system to mine pertinent databases, retrieve relevant data, invoke appropriate biostatistical and epidemiological software packages, and automatically analyze these data. The top-level information architecture is presented. Systems requirements and functional specifications for this level are presented. Finally, future studies are identified.

  5. Feasibility study and technical proposal for the use of microseismic methods in the long-term observation of bedrock stability

    International Nuclear Information System (INIS)

    Saari, J.

    1995-04-01

    Recent geodetic and seismological studies have paid attention to the slow deformation occurring in the Fennoscandian Shield. On the basis of these studies, together with in-situ stress measurements, the idea has been put forth that horizontal movement can be even greater than vertical movement. Local seismotectonics has importance in relation to the predictions of the long-term stability of the bedrock at the final disposal site. Potential direct and - what in Finland is more likely - indirect effects on the vault are due to local earthquakes of creep. The direct effects on the repository include rock vibration and displacement on an increasing fault. The indirect effects are changes in the surrounding structure, in the stress field, in the groundwater table, pressure, flux and chemistry. The block movements are controlled mainly by the network of fracture zones. The report deals with the possibilities to monitor by seismic methods slow movements occurring in the bedrock at the local level. The report includes descriptions of instrumentation for recording microearthquakes, the seismic network and an interpretation of the observations. The potential sites for disposal (Kuhmo, Aeaenekoski, Eurajoki) are compared in relation to seismic monitoring. Also the experiences of other investigations and a proposal for microearthquake investigations as well as of prospective developments within monitoring are presented. (28 refs., 17 figs.)

  6. Avian use of proposed KENETECH and CARES wind farm sites in Klickitat County, Washington: Technical report. Appendix D

    International Nuclear Information System (INIS)

    1995-01-01

    The Columbia Hills area above (north of) the Columbia River in Klickitat County, in southcentral Washington, is being considered for development of two wind power generation projects that could include the eventual placement of up to 436 wind turbines. The KENETECH Windpower Washington Windplant trademark Number 1 project would include placing up to 345 KENETECH 33M-VS turbines, capable of producing up to 115 megawatts (MW), in 39 rows (strings) on a 5,110-hectare (12,630-acre) site. The Conservation and Renewable Energy Systems (CARES) Columbia Wind Farm number-sign 1 project would include placing 91 Flowind AWT-26 turbines, capable of generating 25 MW, in 11 rows on a 395-hectare (975-acre) site. During scoping for these proposed developments, concerns were raised regarding the potential for avian mortality associated with wind farm development. Collision with wind turbine blade, towers, guy wires, and transmission lines, and electrocution from power lines have been identified as sources of avian mortality, particularly raptors, at existing wind farm facilities. To address these concerns, an avian study was conducted at the site in accordance with an avian study plan and protocol developed, with input from a national avian task force, state agencies (Washington Department of Fish and Wildlife [WDFW]), and federal agencies (USFWS). The study included four elements: (1) a winter raptor and waterfowl study, (2) spring migration and fall migration studies, (3) a summer resident study, and (4) a raptor breeding study. The study involved extensive field studies conducted by biologists experienced in identifying raptors and other birds

  7. Committee on Atomic, Molecular, and Optical Sciences (CAMOS). Technical progress report ampersand continuation proposal, February 1, 1993--January 31, 1994

    International Nuclear Information System (INIS)

    Taylor, R.D.

    1997-01-01

    The Committee on Atomic, Molecular and Optical Sciences (CAMOS) of the National Research Council (NRC) is charged with monitoring the health of the field of atomic, molecular, and optical (AMO) science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special symposia are among the mechanisms used by the CAMOS to meet its charge. This progress report presents a review of CAMOS activities from February 1, 1993 to January 31, 1994. The details of prior activities are discussed in earlier progress reports. This report also includes the status of activities associated with the CAMOS study on the field that is being conducted by the Panel on the Future of Atomic, Molecular, and Optical Sciences (FAMOS). During the above period, CAMOS has continued to track and participate in, when requested, discussions on the health of the field. Much of the perspective of CAMOS has been presented in the recently-published report Research Briefing on Selected Opportunities in Atomic, Molecular, and Optical Sciences. That report has served as the basis for briefings to representatives of the federal government as well as the community-at-large. In keeping with its charge to monitor the health of the field, CAMOS launched a study designed to highlight future directions of the field

  8. Proposal of a new analytical procedure for the measurement of water absorption by stone. Preliminary study for an alternative to the Italian technical normative NORMAL 07-81

    Directory of Open Access Journals (Sweden)

    Plattner Susanne

    2012-06-01

    Full Text Available Abstract Background Italian technical normative in the field of cultural heritage is often considered insufficient or not suitable in practise, therefore efforts are necessary to design new and/or improve already existing ones. Results In this paper an alternative analytical procedure for the determination of water absorption (by full immersion by stone material, described in the NORMAL 07-81 document, is proposed. Improvements concern methods accuracy and reduction of sample size; further also density data is obtained. Conclusions The new procedure was applied on three different marble samples and outcomes are encouraging, but further testing is running to better understand to what extent sample size can be reduced without worsening accuracy of results, taking into account that stone is a very heterogeneous material.

  9. Influence analysis of design parameters of suspensions on the technical specifications of conveyor with suspended belt and distributed drive

    Directory of Open Access Journals (Sweden)

    Lagerev A.V.

    2016-09-01

    Full Text Available Using the basic design of the conveyor with suspended belt and distributed drive, a series of numerical calculations was performed. As a result, the influence of friction and mass-dimensional design parameters of suspensions on the main technical parameters of the conveyor was established. Recommendations on the choice of rational parameters were formulated.

  10. [Medical surveillance in university: organizational difficulties, legal problems, scientific e technical specificities. Experience of University of Milan Bicocca].

    Science.gov (United States)

    D'Orso, M I; Giuliani, C; Assini, R; Riva, M A; Cesana, G

    2012-01-01

    Our research describes activities of Occupational Health carried out during last year in University of Milan Bicocca by Occupational Doctors. We describe results of medical surveillance in 1153 employees or students exposed to occupational risks for health and safety. We report results obtained, technical difficulties, organizational problems, and preventive actions decided to improve functionality of our activity. Students seem to be less protected and consequently seem to have higher professional safety and health risks.

  11. Development of a methodology for optimization of technical specifications using PSA based techniques. Development of methodology for evaluation of STI (Surveillance Test Interval) and AOT (Allowed Outage Time) in technical specifications using PSA techniques

    International Nuclear Information System (INIS)

    Jong In Lee; Dae Wook Chung; Sok Chul Kim

    1997-01-01

    In Korea, continued improvement of the safety of nuclear power plants has been set as national policy for the construction and operation of NPPs. Safety Related regulatory requirements under the Korea's Atomic Energy Laws are strictly observed in the design, fabrication, construction, and operation of NPPs. Safety regulation as regulatory concepts, efficient management of regulatory organizations, and rationalization will be improved further through the improvement of regulatory systems, introduction of to technical standards. The following improvements are considered: Periodical safety reevaluation of the operating plants; licensing system allowing certification for standard design and comprehensive site approval; and severe accident policies and criteria established for next generation reactors

  12. 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

  13. Technical aspects of typing for HLA-DP alleles using allele-specific DNA in vitro amplification and sequence-specific oligonucleotide probes. Detection of single base mismatches

    DEFF Research Database (Denmark)

    Fugger, L; Morling, N; Ryder, L P

    1990-01-01

    The polymerase chain reaction (PCR) is an effective method for in vitro DNA amplification which combined with probing with synthetic oligonucleotides can be used for, e.g., HLA-typing. We have studied the technical aspects of HLA-DP typing with the technique. DNA from mononuclear nucleated cells...... was extracted with either a simple salting out method or phenol/chloroform. Both DNAs could be readily used for PCR. The MgC2 concentration of the PCR buffer and the annealing temperature of the thermal cycle of the PCR were the two most important variables. The MgCl2 concentration and the temperature must...... be carefully titrated for each primer pair in the PCR. The influence of mismatches between the primer and the DNA template were studied and we found that, by using primers differing only from each other at the 3' end, cross-amplification of closely homologous alleles could be avoided. Thus, single base...

  14. A technical assessment of the porcine ejaculated spermatozoa for a sperm-specific RNA-seq analysis.

    Science.gov (United States)

    Gòdia, Marta; Mayer, Fabiana Quoos; Nafissi, Julieta; Castelló, Anna; Rodríguez-Gil, Joan Enric; Sánchez, Armand; Clop, Alex

    2018-04-26

    The study of the boar sperm transcriptome by RNA-seq can provide relevant information on sperm quality and fertility and might contribute to animal breeding strategies. However, the analysis of the spermatozoa RNA is challenging as these cells harbor very low amounts of highly fragmented RNA, and the ejaculates also contain other cell types with larger amounts of non-fragmented RNA. Here, we describe a strategy for a successful boar sperm purification, RNA extraction and RNA-seq library preparation. Using these approaches our objectives were: (i) to evaluate the sperm recovery rate (SRR) after boar spermatozoa purification by density centrifugation using the non-porcine-specific commercial reagent BoviPure TM ; (ii) to assess the correlation between SRR and sperm quality characteristics; (iii) to evaluate the relationship between sperm cell RNA load and sperm quality traits and (iv) to compare different library preparation kits for both total RNA-seq (SMARTer Universal Low Input RNA and TruSeq RNA Library Prep kit) and small RNA-seq (NEBNext Small RNA and TailorMix miRNA Sample Prep v2) for high-throughput sequencing. Our results show that pig SRR (~22%) is lower than in other mammalian species and that it is not significantly dependent of the sperm quality parameters analyzed in our study. Moreover, no relationship between the RNA yield per sperm cell and sperm phenotypes was found. We compared a RNA-seq library preparation kit optimized for low amounts of fragmented RNA with a standard kit designed for high amount and quality of input RNA and found that for sperm, a protocol designed to work on low-quality RNA is essential. We also compared two small RNA-seq kits and did not find substantial differences in their performance. We propose the methodological workflow described for the RNA-seq screening of the boar spermatozoa transcriptome. FPKM: fragments per kilobase of transcript per million mapped reads; KRT1: keratin 1; miRNA: micro-RNA; miscRNA: miscellaneous

  15. UK: Technical data for waste incineration background for modelling of product-specific emissions in a life cycle assessment context

    DEFF Research Database (Denmark)

    Hauschild, Michael Zwicky

    and possible recycling hereof. The assessment is based on an inventory of inputs and outputs (resource/material consumption and generation of energy and emissions) for all the processes that occur as part of the product life-cycle. A model is developed to estimate the inputs and outputs associated...... and output of emissions to the environment caused by the incineration. The work has been performed as part of the EUREKA project EUROENVIRON 1296: LCAGAPS, sponsored by the Danish Agency for Industry and Trade. This report presents a compilation of technical data on waste incineration that serve...

  16. Proposal for a technical-economic and environmental evaluation projects for distributed generation; Proposta de avaliacao tecnica-economica-ambiental para projetos de geracao distribuida

    Energy Technology Data Exchange (ETDEWEB)

    Fortes, Marcio Zamboti [Universidade Severino Sombra, Vassouras, RJ (Brazil); Gouvea, Marcos Roberto [Universidade de Sao Paulo (USP), SP (Brazil)

    2008-07-01

    The multi discipline effects in engineering projects, mainly in those of infrastructure, have extended the borders of research to not only evaluate them of the conventional point of view, economic and technical, but also environmental and social. On the other hand, the investor who traditionally searched alternatives only considering the economic and financial performance currently is taken to analyze also the social and environmental aspects. The model described in this paper is a solution proposal to evaluate the merit of an enterprise of distributed generation of thermal origin, considering the economic, social and environmental aspects, using merit indexes that quantify, directly, economic aspects as capital return tax and operating income eliminates, as well as social factors like the impact in the education, health, income and employment rates and still, it verifies the attendance of the environmental restrictions. The solution presented brings a simple and clear form to attribute a merit degree of aggregate to the alternatives to embed distributed generation, considering the intensity of the subjective social responsibility of the investor. The presented model is an important contribution to stimulate a form to evaluate and to prioritize the multi discipline implementation to a distributed generation enterprise, also being able, to be used as financial index or other incentives of the sort. (author)

  17. RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhanced safety and availability. IEC technical report of type 3. Working material

    International Nuclear Information System (INIS)

    1995-01-01

    The present material presents a CD+V draft report ''RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhance safety and availability'' prepared by the Joint IEC/IAEA team during 1993-1995. Experience has demonstrated the need to improve the safety instrumentation of the RBMK type reactors using well proven modern technology. The working group identified the upgrades and changes of the highest priority based on the evaluation of the RBMK systems and the events where the instrumentation was found to be inadequate for safe operation. The subjects discussed in this document were not selected on a systematic basis but were selected by the IEC and IAEA experts as considered to be appropriate to the activities of the IEC and for which technical experience was available. The items identified therefore do not reflect any ranking of the safety issues or any priority or impact on safety of any of the measures were they to be implemented. Many important safety issued and areas where physical measures are required to improve safety have been omitted and indeed not even acknowledged in this document. The recommendations presented in the document differ from those normally produced by the IEC in the form of standards as they are of a transitory nature and some have already been overtaken by the continuing process of improvements to plant safety. Figs and tabs

  18. 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.

  19. Technical specifications Limerick Generating Station, Unit No.1 (Docket No. 50-352). Appendix ''A'' to License No. NPF-39

    International Nuclear Information System (INIS)

    1985-06-01

    The specifications include: definitions, safety limits and limiting safety system settings, bases, limiting conditions for operation and surveillance requirements, design features, and administrative controls

  20. Technical specifications: Byron Station Unit No. 1 (Docket No. STN 50-454). Appendix A to License No. NPF-23

    International Nuclear Information System (INIS)

    1984-10-01

    Specifications are presented concerning safety limits; reactor control systems; instrumentation; coolant circuits; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; design features; and administrative controls

  1. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443). Appendix ''A'' to License No. NPF-56

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides specifications for the Seabrook Station Unit 1 reactor concerning: safety limits and limiting safety settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  2. Technical specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-71

    International Nuclear Information System (INIS)

    1987-08-01

    This report presents specifications for the South Texas Project, Unit No. 1 concerning: safety limits, and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  3. TECHNICAL ECONOMIC FEASIBILITY OF PADDY RICE FIELDS VARIETY OF APPROACH PTT SPECIFIC LOCATIONS IN PAPUA (Case Jayapura

    Directory of Open Access Journals (Sweden)

    Afrizal Malik

    2013-01-01

    Full Text Available Study aims to determine technical economically feasibility of irrigration rice in village of Sumbe, Namblong District, Jayapura on-farm research involving farmers with an area of 2.50 ha cooperators, July to November 2011. Technology introduced: PTT, 4:1 legowo systems, seed varieties Inpari labeled 1, 2, 4, 6, 7, 9, 10, and Sintanur. Fertilizer: urea 150 kg +100 kg +100 kg SP-36 Phonska KCl +50 kg per ha. Variables: height and number of tillers 35 and 65 dap, weight of 1000 seeds, productivity, input, and output. Data were analyzed descriptively. Highest productivity in varieties Inpari 7 (7.925 tonnes per ha Milled Rice (MR and lowest Sintanur varieties (4.625 tonnes per ha MR. Pest stand: rice leaffolder and stinky rice pest. Lowest expenditure on non-cooperators Ciherang farmers IDR 12.15 million per ha per Growing Season (GS and highest in varieties Inpari 7 (IDR 15,005,000 per ha per GS. Lowest Acceptance Ciherang farmers on non-cooperators, IDR 16.4 million per ha per GS and highest in varieties Inpari 7, IDR 27.7 million per ha per GS. If farmers apply recommendation technologies using Inpari 7 varieties, farmers receiving IDR 3,173,750 per month (greater than Regional Minimum Wage of Jayapura. Need government support in order to minimize dependence on outside

  4. Proposal for geological site selection for L/ILW and HLW repositories. Statement of requirements, procedure and results. Technical report 08-03

    International Nuclear Information System (INIS)

    2008-10-01

    Important steps in the process of managing radioactive wastes have already been implemented in Switzerland. These include the handing and packaging of the waste, waste characterisation and documentation of waste inventories and interim storage along with associated transport. In terms of preparing for deep geological disposal, the necessary scientific and technical work is well advanced and the feasibility of constructing geological repositories that provide the required long-term safety has been successfully demonstrated for all waste types arising in Switzerland. Sufficient knowledge is available to allow the next steps in the selection of repository sites to be defined. The legal framework is also in place and organisational measures have been provided that will allow the tasks to be performed in the coming years to be implemented efficiently. The selection of geological siting regions and sites for repositories in Switzerland will be conducted in three stages. Stage 1 ends with the definition of geological siting regions within which the repository projects will be elaborated in more detail in stages 2 and 3. This report documents and justifies the siting proposals prepared by Nagra for the repositories for low- and intermediate-level waste (L/ILW) and high-level waste (HLW). Formulation of these proposals is conducted in five steps: 1) The waste inventory, which includes reserves for future developments, is allocated to the L/ILW and HLW repositories; 2) Based on this waste allocation, the second step involves defining the barrier and safety concepts for the two repositories. With a view to evaluating the geological siting possibilities, quantitative and qualitative guidelines and requirements on the geology are derived on the basis of these concepts. These relate to the time period to be considered, the space requirements for the repository, the properties of the host rock (depth, thickness, lateral extent, hydraulic conductivity), long-term stability

  5. 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

  6. Specification of technical means for implementation of supervisory algorithms of the status of a nuclear reactor and of the main coolant pump of a NPP

    International Nuclear Information System (INIS)

    Jirsa, P.

    2000-11-01

    Inclusion into the programming of inputs of the supervisory algorithm (data collection from the monitoring system, transmission of diagnostic output fro other system and transmission of technological data), of the supervisory process proper based on the data obtained (data analysis) and of the output (presentation of the results to the operator, communication with the master and archiving systems, etc.) requires knowledge of the format of the data transmitted, their availability, communication network protocols, operating system, etc. Hence, the environment for which the algorithm will be developed should be specified, roughly at least. The following topics are addressed: Description of technical means of Czech nuclear power plants (Dukovany, Temelin, Mochovce), and Proposal for technical means to implement the monitoring algorithm (Requirements related to the monitoring systems, Identification of the reference system, Parameters of the selected system). Since no domestic manufacturer of HW for monitoring and diagnostic systems exists, a novel system of the Brueel and Kjaer company for on-line diagnosis and monitoring, COMPASS, was selected as a model model system for the implementation of the supervisory algorithms. (P.A.)

  7. Patient-specific reconstruction plates are the missing link in computer-assisted mandibular reconstruction: A showcase for technical description.

    Science.gov (United States)

    Cornelius, Carl-Peter; Smolka, Wenko; Giessler, Goetz A; Wilde, Frank; Probst, Florian A

    2015-06-01

    Preoperative planning of mandibular reconstruction has moved from mechanical simulation by dental model casts or stereolithographic models into an almost completely virtual environment. CAD/CAM applications allow a high level of accuracy by providing a custom template-assisted contouring approach for bone flaps. However, the clinical accuracy of CAD reconstruction is limited by the use of prebent reconstruction plates, an analogue step in an otherwise digital workstream. In this paper the integration of computerized, numerically-controlled (CNC) milled, patient-specific mandibular plates (PSMP) within the virtual workflow of computer-assisted mandibular free fibula flap reconstruction is illustrated in a clinical case. Intraoperatively, the bone segments as well as the plate arms showed a very good fit. Postoperative CT imaging demonstrated close approximation of the PSMP and fibular segments, and good alignment of native mandible and fibular segments and intersegmentally. Over a follow-up period of 12 months, there was an uneventful course of healing with good bony consolidation. The virtual design and automated fabrication of patient-specific mandibular reconstruction plates provide the missing link in the virtual workflow of computer-assisted mandibular free fibula flap reconstruction. Copyright © 2015 European Association for Cranio-Maxillo-Facial Surgery. Published by Elsevier Ltd. All rights reserved.

  8. Technical note: Protozoa-specific antibodies raised in sheep plasma bind to their target protozoa in the rumen.

    Science.gov (United States)

    Williams, Y J; Rea, S M; Popovski, S; Skillman, L C; Wright, A-D G

    2014-12-01

    Binding of IgG antibodies to Entodinium spp. in the rumen of sheep (Ovis aries) was investigated by adding IgG, purified from plasma, directly into the rumen. Plasma IgG was sourced from sheep that had or had not been immunized with a vaccine containing whole fixed Entodinium spp. cells. Ruminal fluid was sampled approximately 2 h after each antibody dosing. Binding of protozoa by a specific antibody was detected using an indirect fluorescent antibody test. An antibody titer in the ruminal fluid was determined by ELISA, and the concentration of ruminal fluid ammonia-N and ruminal pH were also determined. Entodinium spp. and total protozoa from IgG-infused sheep were enumerated by microscopic counts. Two-hourly additions of IgG maintained a low antibody titer in the rumen for 12 h and the binding of the antibody to the rumen protozoa was demonstrated. Increased ammonia-N concentrations and altered ruminal fluid pH patterns indicated that additional fermentation of protein was occurring in the rumen after addition of IgG. No reduction in numbers of Entodinium spp. was observed (P>0.05). Although binding of antibodies to protozoa has been demonstrated in the rumen, it is unclear how much cell death occurred. On the balance of probability, it would appear that the antibody was degraded or partially degraded, and the impact of this on protozoal populations and the measurement of a specific titer is also unclear.

  9. Assessment of Technical Skills in Young Soccer Goalkeepers: Reliability and Validity of Two Goalkeeper-Specific Tests

    Directory of Open Access Journals (Sweden)

    Ricardo Rebelo-Gonçalves, António J. Figueiredo, Manuel J. Coelho-e-Silva, Antonio Tessitore

    2016-09-01

    Full Text Available The purpose of this study was to evaluate the reproducibility and validity of two new tests designed to examine goalkeeper-specific technique. Twenty-six goalkeepers (14.49 ± 2.52 years old completed two trial sessions, each separated by one week, to evaluate the reproducibility of the Sprint-Keeper Test (S-Keeper and the Lateral Shuffle-Keeper Test (LS-Keeper. Construct validity was assessed among forty goalkeepers (14.49 ± 1.71 years old by competitive level (elite versus non-elite, after controlling for chronological age. All participants were examined in vertical jump (CMJ and CMJ-free arms, acceleration (5-m and 10-m sprint and goalkeeper-specific technique. The S-Keeper requires the goalkeeper to accelerate during 3 m and dive over a stationary ball after performing a change of direction in a total distance of 10 m. The LS-Keeper involves three changes of direction and a diving save over a stationary ball, in a total distance of 12.55 m. Performance was respectively measured as total time for the right and left sides in each protocol. Bivariate correlations between repeated measures were high and significant (r = 0.835 – 0.912. Test-retest results for the S-Keeper and LS-Keeper showed good reliability (reliability coefficients > 0.88, intra-class correlation coefficient > 0.908 and coefficients of variation < 4.37%, even though participants tended to improve performance when diving to their right side (p < 0.05. Both tests were able to detect significant differences between elite and non-elite goalkeepers, particularly to the left side (p < 0.05. These findings suggest that the S-Keeper and LS-Keeper are reliable and valid tests for assessing goalkeeper-specific technique. Both protocols can be used as a practical tool to provide relevant information about the influence of several components of performance in the overall execution of a diving save, particularly movement patterns, take-off movements and possible asymmetries.

  10. Technical documentation in support of the project-specific analysis for construction and operation of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lazaro, M.A.; Vinikour, W. [Argonne National Lab., IL (United States). Environmental Assessment Div.; Allison, T. [Argonne National Lab., IL (United States). Decision and Information Sciences Div.] [and others

    1996-09-01

    This document provides information that supports or supplements the data and impact analyses presented in the National Ignition Facility (NIF) Project-Specific Analysis (PSA). The purposes of NIF are to achieve fusion ignition in the laboratory for the first time with inertial confinement fusion (ICF) technology and to conduct high- energy-density experiments ins support of national security and civilian application. NIF is an important element in the DOE`s science-based SSM Program, a key mission of which is to ensure the reliability of the nation`s enduring stockpile of nuclear weapons. NIF would also advance the knowledge of basic and applied high-energy- density science and bring the nation a large step closer to developing fusion energy for civilian use. The NIF PSA includes evaluations of the potential environmental impacts of constructing and operating the facility at one of five candidate site and for two design options.

  11. Determination dimension and technical specification of the cylindrical pneumatics for the tote movement on multipurpose the gamma irradiator BATAN

    International Nuclear Information System (INIS)

    Muhammad Subhan; Ari Satmoko

    2016-01-01

    BATAN develops irradiator gamma category IV in cooperation with IZOTOP (Hungary). Transportation technology products that will be developed uses rail system to pool. Products that will be irradiated are put into tote then placed on the transportation rail, when tote has been in irradiated room tote enters into irradiated rack. The movement of the tote during on irradiated rack will be driven by the pneumatic system. Based on data from Isotop there are 14 cylindrical pneumatics that are in the irradiated room. Through the results analysis then used double acting cylinder type from the Festo pneumatics catalog. Through the results calculation that the force used on all types of cylinders for movement tote still much smaller than of force bent permitted. Beside that there are 4 group a pneumatic have common specifications they are group one cylindrical C1, C3, C12 and C14 they are group two cylindrical C2, C4, C11, and C13 they are group three cylindrical C7, C9, C15 and C17 they are group four cylindrical C10 and C17. (author)

  12. HIGHWAY INFRASTRUCTURE FOCUS AREA NEXT-GENERATION INFRASTRUCTURE MATERIALS VOLUME I - TECHNICAL PROPOSAL & MANAGEMENTENHANCEMENT OF TRANSPORTATION INFRASTRUCTURE WITH IRON-BASED AMORPHOUS-METAL AND CERAMIC COATINGS

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, J C

    2007-12-04

    . The high boron content of this particular amorphous metal made it an effective neutron absorber, and suitable for criticality control applications. These amorphous alloys appear to maintain their corrosion resistance up to the glass transition temperature. Visionary research is proposed to extend the application of corrosion-resistant iron-based amorphous metal coatings, and variants of these coatings, to protection of the Nation's transportation infrastructure. Specific objectives of the proposed work are: (1) fabrication of appropriate test samples for evaluation of concept; (2) collection of production and test data for coated steel reinforcement bars, enabling systematic comparison of various coating options, based upon performance and economic considerations; and (3) construction and testing of concrete structures with coated steel reinforcement bars, thereby demonstrating the value of amorphous-metal coatings. The benefits of ceramic coatings as thermal barriers will also be addressed.

  13. The Validation of Vapor Phase Hydrogen Peroxide Microbial Reduction for Planetary Protection and a Proposed Vacuum Process Specification

    Science.gov (United States)

    Chung, Shirley; Barengoltz, Jack; Kern, Roger; Koukol, Robert; Cash, Howard

    2006-01-01

    The Jet Propulsion Laboratory, in conjunction with the NASA Planetary Protection Officer, has selected the vapor phase hydrogen peroxide sterilization process for continued development as a NASA approved sterilization technique for spacecraft subsystems and systems. The goal is to include this technique, with an appropriate specification, in NPR 8020.12C as a low temperature complementary technique to the dry heat sterilization process.To meet microbial reduction requirements for all Mars in-situ life detection and sample return missions, various planetary spacecraft subsystems will have to be exposed to a qualified sterilization process. This process could be the elevated temperature dry heat sterilization process (115 C for 40 hours) which was used to sterilize the Viking lander spacecraft. However, with utilization of such elements as highly sophisticated electronics and sensors in modern spacecraft, this process presents significant materials challenges and is thus an undesirable bioburden reduction method to design engineers. The objective of this work is to introduce vapor hydrogen peroxide (VHP) as an alternative to dry heat microbial reduction to meet planetary protection requirements.The VHP process is widely used by the medical industry to sterilize surgical instruments and biomedical devices, but high doses of VHP may degrade the performance of flight hardware, or compromise material properties. Our goal for this study was to determine the minimum VHP process conditions to achieve microbial reduction levels acceptable for planetary protection.

  14. Complementarity of technical skills with art and culture: theoretical reflections, the Talent Show Project experiment at IFRJ – campus Realengo and a proposal for its expansion

    Directory of Open Access Journals (Sweden)

    Maria Célia Dantas Pollig

    2016-12-01

    Full Text Available This paper presents the theoretical basis I have used to better understand the dimension of the task I intend to accomplish. As Educational Advisor at the Federal Institute of Education, Science and Technology of Rio de Janeiro (IFRJ, campus Realengo, my plan is to develop and expand the so called Talent Show Project, by complementing technical training, and providing opportunities for artistic and cultural expression. The study also presents several reflections for achieving the expansion of the scope of the Project intervention, which can become an institutional program developed at IFRJ.

  15. Proposal for the Award of Two Contracts for the Technical Services for Work on Components of CERN Particle Accelerators and High Energy Physics Experiments

    CERN Document Server

    2003-01-01

    This document concerns the award of two contracts for the technical services for work on components of CERN particle accelerators and high energy physics experiments. Following a market survey carried out among 73 firms in fourteen Member States, a call for tenders (IT-3156/SPL) was sent on 4 November 2002 to three consortia in four Member States. By the closing date, CERN had received tenders from the three consortia. The Finance Committee is invited to agree to the negotiation of two contracts with: 1) the consortium SERCO FACILITIES MANAGEMENT (NL) - GERARD PERRIER INDUSTRIE (FR) - INEO ALPES (FR), the lowest bidder, for approximately 55% of the technical services for work on components of CERN particle accelerators and high energy physics experiments, for an initial period of five years and for a total amount not exceeding 37 435 270 euros (54 902 500 Swiss francs), subject to revision for inflation from 1 January 2005. The contract will include options for two one-year extensions beyond the initial five-...

  16. 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.

  17. Incorporation of gypsum waste in ceramic block production: Proposal for a minimal battery of tests to evaluate technical and environmental viability of this recycling process.

    Science.gov (United States)

    Godinho-Castro, Alcione P; Testolin, Renan C; Janke, Leandro; Corrêa, Albertina X R; Radetski, Claudemir M

    2012-01-01

    Civil engineering-related construction and demolition debris is an important source of waste disposed of in municipal solid waste landfills. After clay materials, gypsum waste is the second largest contributor to the residential construction waste stream. As demand for sustainable building practices grows, interest in recovering gypsum waste from construction and demolition debris is increasing, but there is a lack of standardized tests to evaluate the technical and environmental viability of this solid waste recycling process. By recycling gypsum waste, natural deposits of gypsum might be conserved and high amounts of the waste by-product could be reused in the civil construction industry. In this context, this paper investigates a physical property (i.e., resistance to axial compression), the chemical composition and the ecotoxicological potential of ceramic blocks constructed with different proportions of clay, cement and gypsum waste, and assesses the feasibility of using a minimal battery of tests to evaluate the viability of this recycling process. Consideration of the results for the resistance to axial compression tests together with production costs revealed that the best formulation was 35% of plastic clay, 35% of non-plastic clay, 10% of Portland cement and 20% of gypsum waste, which showed a mean resistance of 4.64MPa. Energy dispersive X-ray spectrometry showed calcium and sulfur to be the main elements, while quartz, gypsum, ettringite and nacrite were the main crystalline compounds found in this formulation. Ecotoxicity tests showed that leachate from this formulation is weakly toxic toward daphnids and bacteria (EC(20%)=69.0 and 75.0, respectively), while for algae and fish the leachate samples were not toxic at the EC(50%) level. Overall, these results show that the addition of 20% of gypsum waste to the ceramic blocks could provide a viable substitute for clay in the ceramics industry and the tests applied in this study proved to be a useful tool

  18. Development of the methodology on priority of element-specific biosphere parameters for geological disposal applicable to any proposed repository site

    International Nuclear Information System (INIS)

    Kato, Tomoko; Ohi, Takao; Suzuki, Yuji

    2009-01-01

    It is difficult to acquire all of biosphere parameters for geological disposal at the repository site because several hundreds of the parameters have to be dealt with in one calculation case of the biosphere assessment. Before site-specific activities, it is important to develop the data acquisition methodology of biosphere parameters applicable to any proposed repository site. The methodology for identification of the priority of the parameters was developed for the effective data acquisition of biosphere parameters at the site. First of all, flow diagram was constructed to evaluate the availability of the existing generic biosphere dataset. It was found to be effective for the data acquisition at the site to focus on the element-specific parameters with the existing dataset. Secondly, the priority of the data acquisition was identified for element-specific parameters at the site, with considering the variation of dose rate by combining the significant element-specific parameters. The availability of the existing generic biosphere dataset and the priority on data acquisition were identified for the element-specific parameters of key radionuclides in the safety assessment of geological disposal that should be acquired at the site. This priority list would be useful for effective data acquisition at the site. (author)

  19. 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.

  20. Technical review comments on the environmental impact statement for the proposed Lone Pine Resources Ltd. Great Sand Hills Natural Gas Development

    International Nuclear Information System (INIS)

    1992-01-01

    Lone Pine Resources is proposing to construct and operate a natural gas production and transportation system in the Freefight Lake area of the Great Sand Hills in Saskatchewan. The initial development proposal consists of 58 gas wells at 160-acre spacing, with associated infrastructure. After drilling, completion, and tie-ins, the wells would be operated for an estimated 25 y. Following completion of construction, disturbed well sites and some pipeline rights of way would be fenced off and necessary reclamation, erosion control, and revegetation measures would be implemented and continued until revegetation standards are met. The thin vegetation, poorly developed soils, and wind exposure renders the project area vulnerable to disturbance, and the area's terrain, plant communities, wildlife, and surface and ground water are subject to potential biophysical impacts. About 4.6% of the total project area is expected to be affected temporarily by construction of the project. Although the project area is formally designated as a critical wildlife habitat, it is believed that the proposed project can be constructed and operated with only minor impacts on wildlife. Groundwater contamination will be avoided by enforcing strict drilling regulations, including containment of all drilling fluids. If approved, the project would create economic benefits to the Fox Valley-Maple Creek area, mainly during construction. Potential impacts on the esthetic character of the area are considered to be minor

  1. Congener-specific analysis of polychlorinated naphthalenes (PCNs) in the major Chinese technical PCB formulation from a stored Chinese electrical capacitor.

    Science.gov (United States)

    Huang, Jun; Yu, Gang; Yamauchi, Makoto; Matsumura, Toru; Yamazaki, Norimasa; Weber, Roland

    2015-10-01

    Impurity of polychlorinated naphthalenes (PCNs) in commercial polychlorinated biphenyl (PCB) formulations has been recognized as a relevant source of PCNs in the environment. Congener-specific analysis of most main PCB formulations has been accomplished previously, excluding the Chinese product. The insulating oil in a stored Chinese electric capacitor containing the major Chinese technical formulation "PCB3" was sampled and tested by isotope dilution technology using high-resolution gas chromatography coupled to high-resolution mass spectrometry (HRGC/HRMS). The detected concentration of PCNs in the Chinese PCB oil sample was 1,307.5 μg/g and therefore significantly higher than that reported in PCB formulations from other countries, as well as that in the transformer oil (ASKAREL Nr 1740) additionally tested in the present study for comparison. Based on the measurement, the total amount of PCNs in Chinese PCB3 oil is estimated to be 7.8 t, which would mean only 0.005 % of global production of PCNs of 150,000 t. The homolog profile is similar to those of PCN in Aroclor 1262 and Clophen A40, where the contributions from hexa-CNs and hepta-CNs are predominant and accounted for similar proportions. The Toxic Equivalent Quantity (TEQ) concentration of dioxin-like PCN congeners is 0.47 μg TEQ/g, with the dominant contributors of CN-73 and CN-66/67. This TEQ content from PCN is higher than that in most other PCB formulations with the exemption of the Russian Sovol formulation. The total TEQ in the historic 6,000 t of the Chinese PCB3 formulation is estimated to be 2.8 kg TEQ.

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. Energy saving in the design and operation of fans; 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, Northern Ireland (United Kingdom)

    1995-12-01

    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)

  8. Design, construction, and technical implementation of a web-based interdisciplinary symptom evaluation (WISE) - a heuristic proposal for orofacial pain and temporomandibular disorders.

    Science.gov (United States)

    Ettlin, Dominik A; Sommer, Isabelle; Brönnimann, Ben; Maffioletti, Sergio; Scheidt, Jörg; Hou, Mei-Yin; Lukic, Nenad; Steiger, Beat

    2016-12-01

    Medical symptoms independent of body location burden individuals to varying degrees and may require care by more than one expert. Various paper and computer-based tools exist that aim to comprehensively capture data for optimal clinical management and research. A web-based interdisciplinary symptom evaluation (WISE) was newly designed, constructed, and technically implemented. For worldwide applicability and to avoid copyright infringements, open source software tools and free validated questionnaires available in multiple languages were used. Highly secure data storage limits access strictly to those who use the tool for collecting, storing, and evaluating their data. Concept and implementation is illustrated by a WISE sample tailored for the requirements of a single center in Switzerland providing interdisciplinary care to orofacial pain and temporomandibular disorder patients. By combining a symptom- burden checklist with in-depth questionnaires serving as case-finding instruments, an algorithm was developed that assists in clarifying case complexity and need for targeted expert evaluation. This novel modular approach provides a personalized, response-tailored instrument for the time- and cost-effective collection of symptom-burden focused quantitative data. The tool includes body drawing options and instructional videos. It is applicable for biopsychosocial evaluation in a variety of clinical settings and offers direct feedback by a case report summary. In clinical practice, the new instrument assists in clarifying case complexity and referral need, based on symptom burden and response -tailored case finding. It provides single-case summary reports from a biopsychosocial perspective and includes graphical symptom maps. Secure, centrally stored data collection of anonymous data is possible. The tool enables personalized medicine, facilitates interprofessional education and collaboration, and allows for multicenter patient-reported outcomes research.

  9. An alternative beam line at the U-400 M cyclotron for RIB separation and transport to the FOBOS spectrometer (The technical proposal)

    International Nuclear Information System (INIS)

    Majdikov, V.Z.; Bashevoj, V.V.

    1998-01-01

    The first order ion-optic calculations performed together with the graphical modeling permits us to propose a new variant of the beam-transport line from the backside of the U-400M cyclotron to the FOBOS spectrometer. This beam line could be built in a rather short time without large financial expenditures from available magnetic and vacuum elements. The new beam line could even be considered as an economic alternative to the existing beam line and as a RIB separator. This work is the result of the pre-design R and D aimed to develop the U-400M cyclotron facilities for the RIB experiments performance with the FOBOS spectrometer

  10. Proposals for a revision and amendment of the 'Guide for the examination of control room personnel of nuclear power plants, technical and expert knowledge required'

    International Nuclear Information System (INIS)

    Frisch, W.; Kersting, E.; Meissner, R.; Mester, W.; Richter, H.; Weber, J.P.

    1983-01-01

    a) Proposals are presented for amending the Guide in section 5 and 6 (Table I and II) and in the Annex (Examples of problems and answers), relating to three special subjects, namely: Thermohydraulics; Methods and procedures of analyzing the current operational state of a plant in case of incidents, malfunction failure indication; Plant operational performance and behaviour in cases exceeding design limits (especially analysis and counter-measures in case of reactor core damage, general behaviour in critical situations). b) Revision of all examples of problems to be put in examinations, and of the answers, as given in the Annex. Revision with regard to correctness and balanced distribution of difficulty of problems to be put in the various subject fields, and with regard to correctness of answers. This revision shall include an examination of the problems for their suitability to show the candidate's efficiency in diagnosis, prognosis and appropriate action. c) Proposals for amending and improving the Guide, resulting from an evaluation of the results and the experience gained in previous examinations. (orig.) [de

  11. Proposal of a technical guide for the evaluation and management of the solitary pulmonary nodule in function of the radiological characteristics obtained by computed tomography

    International Nuclear Information System (INIS)

    Clinton Hidalgo, Carolina

    2015-01-01

    A guide is proposed to guide clinical personnel in early diagnosis, assessment and management of the solitary pulmonary nodule, with high potential of to develop lung cancer, in function of the radiological characteristics obtained by computed tomography. The management of patients with diagnosis of solitary pulmonary nodule is standardized with the purpose of to unify diagnostic criteria in a multidisciplinary and institutional environment. Tomographic radiological characteristics are described to allow the suspicion of the solitary pulmonary nodule benignity or malignity. A flow diagram is developed to guide the physician to an adequate monitoring, control and eventual therapeutic treatment. A clear and structured perspective of the diagnostic and therapeutic process is provided to the treating physician and patient [es

  12. 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.

  13. 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.

  14. Recycled aggregate in road construction following the Spanish General Technical Specifications for Roads and Bridge Works (PG-3: a case study

    Directory of Open Access Journals (Sweden)

    Martín-Morales, M.

    2013-03-01

    Full Text Available This research characterizes four samples of recycled aggregate for their potential use in road construction projects in consonance with the Spanish General Technical Specifications for Roads and Bridge Works (PG-3. Although some fractions were of sufficient quality for the construction of embankments, backfills, and quarry-run fills, they were ultimately found to be unsuitable for the construction of underground drainage, granular structural layers, soil stabilization and concrete pavements. They were negatively evaluated because of their particle size distribution and sulfate content. Nevertheless, the quality of this recycled aggregate could be substantially improved by manually removing the gypsum before the crushing process at the plant or by selecting the material with greater care at the beginning of the process. Finally, we suggest that Construction and Demolition (C&D waste plant managers should modify the manufacturing process to obtain a suitable particle size distribution in accordance with PG-3 requirements and the projected use of the aggregate.

    En esta investigación se han caracterizado cuatro muestras de árido reciclado para su potencial uso en obras de carreteras en España siguiendo el Pliego de Prescripciones Técnicas Generales para Obras de Carreteras y Puentes (PG-3. Aunque algunas fracciones presentaron suficiente calidad para la construcción de terraplenes, rellenos localizados y rellenos todo en uno, resultaron inadecuadas para la construcción de drenes subterráneos, zahorras, suelos estabilizados y pavimentos de hormigón. Obtuvieron una evaluación negativa en cuanto a distribución granulométrica y contenido en sulfatos. No obstante, la calidad de este árido reciclado podría mejorar sustancialmente eliminando manualmente el yeso antes de la trituración en planta o seleccionando el material con un mayor cuidado al inicio del proceso. Finalmente, recomendamos que los empresarios de las plantas de residuos

  15. The technical basis for emergency planning and preparedness in EC countries. An examination of criteria, practices and recent developments and proposals for a harmonized approach

    International Nuclear Information System (INIS)

    Eckered, T.

    1985-01-01

    Many existing or planned EPP measures are based on assumptions concerning accident sequences, release of radioactivity and accident consequences which in many cases are far too pessimistic. A higher level of ambition for EPP measures based on these assumptions does therefore not seem to be justified. This study is based mainly on the experience gained from operation of Light Water Reactors. Consequently, many of the conclusions and recommendations drawn from the discussions refers to LWRs. Horwever, EPP consist of many elements which are independent of the kind of reactor chosen. So much of the content of this report is therefore valid for other reactor systems. In this report different elements of risk scenarios (accident sequences, source-term assumption and release behaviour, dose assessment, contamination, etc.) and different protective actions (taking shelter, evacuation, use of potassium iodine, etc.) are discussed with reference to present knowledge and ongoing studies. Proposals are given for what emergency preparedness measures to choose and what priority to give them in order to create an efficient and sufficient protection of health and safety of the public

  16. Avian use of proposed KENETECH and CARES wind farm sites in Klickitat County, Washington. Appendix C to Washington Windplant No. 1 EIS. Technical report

    International Nuclear Information System (INIS)

    1995-01-01

    The Columbia Hills area above (north of) the Columbia River in Klickitat County, in southcentral Washington, is being considered for development of two wind power generation projects that could include the eventual placement of up to 436 wind turbines. The KENETECH Windpower Washington Windplant TM Number 1 project would include placing up to 345 KENETECH 33M-VS turbines, capable of producing up to 115 megawatts (MW), in 39 rows (strings) on a 5,110-hectare (12,630-acre) site. During scoping for these proposed developments, concerns were raised regarding the potential for avian mortality associated with wind farm development. Collision with wind turbine blade, towers, guy wires, and transmission lines, and electrocution from power lines have been identified as sources of avian mortality, particularly raptors, at existing wind farm facilities. To address these concerns, an avian study was conducted at the site in accordance with an avian study plan and protocol developed, with input from a national avian task force, state agencies (Washington Department of Fish and Wildlife [WDFW]), and federal agencies (USFWS). The study included four elements: (1) a winter raptor and waterfowl study, (2) spring migration and fall migration studies, (3) a summer resident study, and (4) a raptor breeding study. The study involved extensive field studies conducted by biologists experienced in identifying raptors and other birds

  17. Biomass heating at East Surrey Hospital: technical evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Landen, R; Rippengal, R

    2000-07-01

    This report provides the results of a detailed evaluation of the proposed biomass heating installation at East Surrey Hospital. It is intended to allow the Trust to make a decision on whether to proceed further with the scheme and, if so, on what basis. Specific areas assessed and reported on include: existing services provision for heating and cooling; technical aspects of the proposed biomass scheme; commercial aspects of the proposed biomass scheme. (author)

  18. Technical Note: A proposal of air ventilation system design criteria for a clinical room in a heavy-ion medical facility.

    Science.gov (United States)

    Kum, Oyeon

    2018-04-16

    An optimized air ventilation system design for a treatment room in Heavy-ion Medical Facility is an important issue in the aspects of nuclear safety because the activated air produced in a treatment room can directly affect the medical staff and the general public in the radiation-free area. Optimized design criteria of air ventilation system for a clinical room in 430 MeV/u carbon ion beam medical accelerator facility was performed by using a combination of MCNPX2.7.0 and CINDER'90 codes. Effective dose rate and its accumulated effective dose by inhalation and residual gamma were calculated for a normal treatment scenario (2 min irradiation for one fraction) as a function of decay time. Natural doses around the site were measured before construction and used as reference data. With no air ventilation system, the maximum effective dose rate was about 3 μSv/h (total dose of 90 mSv/y) and minimum 0.2 μSv/h (total dose of 6 mSv/y), which are over the legal limits for medical staff and for the general public. Although inhalation dose contribution was relatively small, it was considered seriously because of its long-lasting effects in the body. The integrated dose per year was 1.8 mSv/y in the radiation-free area with the 20-min rate of air ventilation system. An optimal air ventilation rate of 20 min is proposed for a clinical room, which also agrees with the best mechanical design value. © 2018 American Association of Physicists in Medicine.

  19. Analysis of the influence of design parameters of vertically-closed track conveyor with suspended belt and distributed drive on the technical specifications

    Directory of Open Access Journals (Sweden)

    Tolkachev E.N.

    2016-12-01

    Full Text Available Using the basic design of the conveyor with suspended belt and distributed drive, a series of numerical calcu-lations was performed. As a result, the influence of design parameters of vertical loop route on the main tech-nical parameters of the conveyor was established. Recommendations on the choice of rational parameters were formulated.

  20. Benchmark Specification for an HTR Fuelled with Reactor-grade Plutonium (or Reactor-grade Pu/Th and U/Th). Proposal version 2

    International Nuclear Information System (INIS)

    Hosking, J.G.; Newton, T.D.; Morris, P.

    2007-01-01

    This benchmark proposal builds upon that specified in NEA/NSC/DOC(2003)22 report. In addition to the three phases described in that report, another two phases have now been defined. Additional items for calculation have also been added to the existing phases. It is intended that further items may be added to the benchmark after consultation with its participants. Although the benchmark is specifically designed to provide inter-comparisons for plutonium- and thorium-containing fuels, it is proposed that phases considering simple calculations for a uranium fuel cell and uranium core be included. The purpose of these is to identify any increased uncertainties, relative to uranium fuel, associated with the lesser-known fuels to be investigated in different phases of this benchmark. The first phase considers an infinite array of fuel pebbles fuelled with uranium fuel. Phase 2 considers a similar array of pebbles but for plutonium fuel. Phase 3 continues the plutonium fuel inter-comparisons within the context of whole core calculations. Calculations for Phase 4 are for a uranium-fuelled core. Phase 5 considers an infinite array of pebbles containing thorium. In setting the benchmark the requirements in the definition of the LEUPRO-12 PROTEUS benchmark have been considered. Participants were invited to submit both deterministic results as well as, where appropriate, results from Monte Carlo calculations. Fundamental nuclear data, Avogadro's number, natural abundance data and atomic weights have been taken from the references indicated in the document

  1. Towards a specific approach to education in dental ethics: a proposal for organising the topics of biomedical ethics for dental education.

    Science.gov (United States)

    Gorkey, Sefik; Guven, Tolga; Sert, Gurkan

    2012-01-01

    Understanding dental ethics as a field separate from its much better known counterpart, medical ethics, is a relatively new, but necessary approach in bioethics. This need is particularly felt in dental education and establishing a curriculum specifically for dental ethics is a challenging task. Although certain topics such as informed consent and patient rights can be considered to be of equal importance in both fields, a number of ethical issues in dental practice are only remotely-if at all-relevant for medical practice. Therefore, any sound approach to education in dental ethics has to recognise the unique aspects of dental practice in order to meet the needs of dental students and prepare them for the ethical challenges they may face during their professional practice. With this goal in mind, this paper examines the approach of the authors to dental ethics education and proposes a system to organise the topics of biomedical ethics for dental education. While the authors' perspective is based on their experience in Turkey, the proposed system of classification is not a rigid one; it is open to interpretation in other contexts with different social, cultural and professional expectations. Therefore, the paper also aims to inspire discussion on the development of an ideal dental ethics curriculum at an international level.

  2. 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....

  3. Towards technical interoperability in telemedicine.

    Energy Technology Data Exchange (ETDEWEB)

    Craft, Richard Layne, II

    2004-05-01

    For telemedicine to realize the vision of anywhere, anytime access to care, the question of how to create a fully interoperable technical infrastructure must be addressed. After briefly discussing how 'technical interoperability' compares with other types of interoperability being addressed in the telemedicine community today, this paper describes reasons for pursuing technical interoperability, presents a proposed framework for realizing technical interoperability, identifies key issues that will need to be addressed if technical interoperability is to be achieved, and suggests a course of action that the telemedicine community might follow to accomplish this goal.

  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.

  5. User's guide for the implementation of level one of the proposed American National Standard Specifications for an information interchange data descriptive file on control data 6000/7000 series computers

    CERN Document Server

    Wiley, R A

    1977-01-01

    User's guide for the implementation of level one of the proposed American National Standard Specifications for an information interchange data descriptive file on control data 6000/7000 series computers

  6. Ideal Based Cyber Security Technical Metrics for Control Systems

    Energy Technology Data Exchange (ETDEWEB)

    W. F. Boyer; M. A. McQueen

    2007-10-01

    Much of the world's critical infrastructure is at risk from attack through electronic networks connected to control systems. Security metrics are important because they provide the basis for management decisions that affect the protection of the infrastructure. A cyber security technical metric is the security relevant output from an explicit mathematical model that makes use of objective measurements of a technical object. A specific set of technical security metrics are proposed for use by the operators of control systems. Our proposed metrics are based on seven security ideals associated with seven corresponding abstract dimensions of security. We have defined at least one metric for each of the seven ideals. Each metric is a measure of how nearly the associated ideal has been achieved. These seven ideals provide a useful structure for further metrics development. A case study shows how the proposed metrics can be applied to an operational control system.

  7. Independent Technical Review Of The Focused Feasibility Study And Proposed Plan For Designated Solid Waste Management Units Contributing To The Southwest Groundwater Plume At The Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Looney, B.; Eddy-Dilek, C.; Amidon, M.; Rossabi, J.; Stewart, L.

    2011-01-01

    The U. S. Department of Energy (DOE) is currently developing a Proposed Plan (PP) for remediation of designated sources of chlorinated solvents that contribute contamination to the Southwest (SW) Groundwater Plume at the Paducah Gaseous Diffusion Plant (PGDP), in Paducah, KY. The principal contaminants in the SW Plume are trichloroethene (TCE) and other volatile organic compounds (VOCs); these industrial solvents were used and disposed in various facilities and locations at PGDP. In the SW plume area, residual TCE sources are primarily in the fine-grained sediments of the Upper Continental Recharge System (UCRS), a partially saturated zone that delivers contaminants downward into the coarse-grained Regional Gravel Aquifer (RGA). The RGA serves as the significant lateral groundwater transport pathway for the plume. In the SW Plume area, the four main contributing TCE source units are: (1) Solid Waste Management Unit (SWMU) 1 / Oil Landfarm; (2) C-720 Building TCE Northeast Spill Site (SWMU 211A); (3) C-720 Building TCE Southeast Spill Site (SWMU 211B); and (4) C-747 Contaminated Burial Yard (SWMU 4). The PP presents the Preferred Alternatives for remediation of VOCs in the UCRS at the Oil Landfarm and the C-720 Building spill sites. The basis for the PP is documented in a Focused Feasibility Study (FFS) (DOE, 2011) and a Site Investigation Report (SI) (DOE, 2007). The SW plume is currently within the boundaries of PGDP (i.e., does not extend off-site). Nonetheless, reasonable mitigation of the multiple contaminant sources contributing to the SW plume is one of the necessary components identified in the PGDP End State Vision (DOE, 2005). Because of the importance of the proposed actions DOE assembled an Independent Technical Review (ITR) team to provide input and assistance in finalizing the PP.

  8. INDEPENDENT TECHNICAL REVIEW OF THE FOCUSED FEASIBILITY STUDY AND PROPOSED PLAN FOR DESIGNATED SOLID WASTE MANAGEMENT UNITS CONTRIBUTING TO THE SOUTHWEST GROUNDWATER PLUME AT THE PADUCAH GASEOUS DIFFUSION PLANT

    Energy Technology Data Exchange (ETDEWEB)

    Looney, B.; Eddy-Dilek, C.; Amidon, M.; Rossabi, J.; Stewart, L.

    2011-05-31

    The U. S. Department of Energy (DOE) is currently developing a Proposed Plan (PP) for remediation of designated sources of chlorinated solvents that contribute contamination to the Southwest (SW) Groundwater Plume at the Paducah Gaseous Diffusion Plant (PGDP), in Paducah, KY. The principal contaminants in the SW Plume are trichloroethene (TCE) and other volatile organic compounds (VOCs); these industrial solvents were used and disposed in various facilities and locations at PGDP. In the SW plume area, residual TCE sources are primarily in the fine-grained sediments of the Upper Continental Recharge System (UCRS), a partially saturated zone that delivers contaminants downward into the coarse-grained Regional Gravel Aquifer (RGA). The RGA serves as the significant lateral groundwater transport pathway for the plume. In the SW Plume area, the four main contributing TCE source units are: (1) Solid Waste Management Unit (SWMU) 1 / Oil Landfarm; (2) C-720 Building TCE Northeast Spill Site (SWMU 211A); (3) C-720 Building TCE Southeast Spill Site (SWMU 211B); and (4) C-747 Contaminated Burial Yard (SWMU 4). The PP presents the Preferred Alternatives for remediation of VOCs in the UCRS at the Oil Landfarm and the C-720 Building spill sites. The basis for the PP is documented in a Focused Feasibility Study (FFS) (DOE, 2011) and a Site Investigation Report (SI) (DOE, 2007). The SW plume is currently within the boundaries of PGDP (i.e., does not extend off-site). Nonetheless, reasonable mitigation of the multiple contaminant sources contributing to the SW plume is one of the necessary components identified in the PGDP End State Vision (DOE, 2005). Because of the importance of the proposed actions DOE assembled an Independent Technical Review (ITR) team to provide input and assistance in finalizing the PP.

  9. Technical specifications, Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Appendix ''A'' to License No. NPF-49

    International Nuclear Information System (INIS)

    1986-01-01

    Information is presented concerning specifications on the following aspects of the Millstone Nuclear Power Station, Unit No. 3: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  10. Technical specifications: Callaway Plant, Unit No. 1 (Docket No. STN 50-483). Appendix A to License No. NPF-30. Revision 1

    International Nuclear Information System (INIS)

    1984-10-01

    Revised specifications are presented concerning limiting safety system settings for control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical systems, refueling operations, radioactive effluents, and radiation environmental monitoring

  11. Technical Specifications, Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. 50-400). Appendix ''A'' to License No. NPF-53

    International Nuclear Information System (INIS)

    1986-10-01

    This report presents specifications for the Shearon Harris Nuclear Power Plant Unit No. 1 concerning: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  12. 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

  13. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the 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 e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  14. 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

  15. Technical specifications, La Salle County Station, Unit No. 1. Appendix A to License No. NPF-11, Docket No. 50-373

    International Nuclear Information System (INIS)

    1982-04-01

    Specifications are presented concerning safety limits; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; radiological environmental monitoring; reactor site; fuel storage; and plant operations

  16. Technical specifications for waste packages conditioned in a durable confining shell, with an hydraulic binder basis, intended to a ground disposal site

    International Nuclear Information System (INIS)

    1995-06-01

    The aim of this document is to precise the general and particular conditions for the acceptance on a ground disposal site of a low- and middle-level radioactive waste package conditioned in a durable confining shell. This specification concerns the wastes that contain beta and gamma decay radionuclides and/or long life alpha decay radionuclides in higher quantities than accepted for the protective coatings. Physico-chemical and mechanical specifications are given for the wastes, the fixing material, the confining shell and the container. Accepted limits for degassing and dose rates, surface contamination, dimensions and weight are given. The agreement is delivered by the ANDRA after the package has satisfied the different mechanical, chemical, fire, moisture and radiation resistance tests. (J.S.). 1 fig., 3 tabs., 1 glossary

  17. Technical review of the environmental study and report referent to the proposal of construction of a 1200 MW thermoelectric power plant (Carioba II) in the Americana district, SP, Brazil; Parecer tecnico parcial do estudo e relatorio de impacto ambiental (EIA/RIMA) referentes a proposta de implantacao de uma usina termeletrica de 1200 Mw (Carioba II) no municipio de Americana, SP

    Energy Technology Data Exchange (ETDEWEB)

    Figueiredo, Paulo Jorge Moraes; Martins, Gilberto [Universidade Metodista de Piracicaba (UNIMEP), SP (Brazil)]. E-mails: pfigueir@unimep.br; gmartins@unimep.br

    2001-06-01

    This document represents a partial analysis and a technical review about the environmental study and report of a 1200 MW thermoelectric power plant, proposed for the Americana district, SP, Brazil. Published on June, 4th 2001, this article points out many problems and mistakes of the referred studies, with the objective of providing support to the Federal attorney office and the general public. (author)

  18. Specific PVMaT R and D in CdTe Product Manufacturing; Phase II Annual Subcontract Technical Report; May 1999--September 2000

    Energy Technology Data Exchange (ETDEWEB)

    McMaster, A. (First Solar, LLC)

    2001-01-22

    Just prior to the beginning of Phase II of the PVMaT project Solar Cells, Inc, (SCI) and True North Partners of Scottsdale, AZ, formed a joint venture partnership name First Solar, LLC. By the end of 1999, this event resulted in the construction of a new major manufacturing plant for photovoltaic modules, based on cadmium telluride, located in Perrysburg, a suburb of Toledo, Ohio. This plant was designed to be capable of producing PV modules at a rate of 100 MW per year within about three years. Significantly, a new semiconductor coating system, the heat of the production line, has already shown the capability of the 100 MW per year rate. These events have led to the expansion of the effort on the PVMaT project that included the former SCI team in Toledo, Ohio, a new team of engineering subcontractor, Product Search, Inc., and, later, a new laser team from First Solar, both from Scottsdale, Arizona. These three teams joined in a collaborative effort on Tasks 4: Manufacturing Line Improvements, on Task 5: Product Readiness, and on Task Environmental, Health, and Safety Issues. One Task 4 goal was to address the technical issues of the failed UL 1703 qualification testing in Phase I. Completing this goal, along with module lamination improvement done in Task 5, was instrumental in the design, fabrication, and installation of a high-throughput solar finishing line. The main components of this line, also a Task 4 project, were successfully tested in module finalization on the production line. Developing a novel, single-laser scribing system was another major accomplishment. In Task 5, the major activity was improved module lamination. Progress in Tasks 4 and 5 resulted in improved modules that were submitted for UL 1703 qualification testing. In March 2000, a new encapsulation process came under development, in which the back glass cover plate is substituted by a combination of a polymer layer as a dielectric and aluminum foil as a moisture barrier. The go al of the

  19. The logic of Technical Standardisation

    DEFF Research Database (Denmark)

    Nedergaard, Peter

    In this paper technical standardisation is understood and explained in a model where economic analysis is coupled with an analysis of the political system as proposed in rational choice theory. The aim is to answer both the question why various countries (e.g. the United States versus European...... countries) let either the market or public intervention determine the mode of technical standardisation and the possible implications of these two ways of organizing technical standardisation from an economic and a political point of view. Based upon the analysis of the paper a couple of general policy...... recommendations are made concerning the mode of technical standardisation....

  20. [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.

  1. 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

  2. Proposal for novel curcumin derivatives as potent inhibitors against Alzheimer's disease: Ab initio molecular simulations on the specific interactions between amyloid-beta peptide and curcumin

    Science.gov (United States)

    Ota, Shintaro; Fujimori, Mitsuki; Ishimura, Hiromi; Shulga, Sergiy; Kurita, Noriyuki

    2017-10-01

    Accumulation of amyloid-β (Aβ) peptides in a brain is closely related with the pathogenesis of Alzheimer's disease. To suppress the production of Aβ peptides, we propose novel curcumin derivatives and investigate their binding properties with the amyloid precursor protein (APP), using protein-ligand docking as well as ab initio molecular simulations. Our proposed derivative (curcumin XIV) is found to have a large binding energy with APP and interacts strongly with the cleavage site Ala19 by secretase. It is thus expected that curcumin XIV can protect APP from the secretase attack and be a potent inhibitor against the production of Aβ peptides.

  3. Specification ''I'' of the CEFRI concerning the interim job enterprises proposing personnel of A or B category to work in nuclear facilities

    CERN Document Server

    Int. At. Energy Agency Wien

    2002-01-01

    This document aims to specify the organization dispositions which have to bee taken by the interim job enterprises proposing personnel of A or B category to work in nuclear facilities. These dispositions should allow to respect the demands of the CEFRI in matter of formation, medical control and personnel dosimetry. (A.L.B.)

  4. Technical Note

    African Journals Online (AJOL)

    Administratör

    In this report on four patients, we did not use any of these techniques. The existence and the site of the fistulas was clearly demonstrated using basic but important preoperative detailed assessment and two intraoperative findings. The preoperative referral note that indicated the site of technical difficulty during the previous ...

  5. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience At the end of the first full-year running period of LHC, CMS is established as a reliable, robust and mature experiment. In particular common systems and infrastructure faults accounted for <0.6 % CMS downtime during LHC pp physics. Technical operation throughout the entire year was rather smooth, the main faults requiring UXC access being sub-detector power systems and rack-cooling turbines. All such problems were corrected during scheduled technical stops, in the shadow of tunnel access needed by the LHC, or in negotiated accesses or access extensions. Nevertheless, the number of necessary accesses to the UXC averaged more than one per week and the technical stops were inevitably packed with work packages, typically 30 being executed within a few days, placing a high load on the coordination and area management teams. It is an appropriate moment for CMS Technical Coordination to thank all those in many CERN departments and in the Collaboration, who were involved in CMS techni...

  6. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    2010-01-01

    Operational Experience Since the closure of the detector in February, the technical operation of CMS has been quite smooth and reliable. Some minor interventions in UXC were required to cure failures of power supplies, fans, readout boards and rack cooling connections, but all these failures were repaired in scheduled technical stops or parasitically during access dedicated to fixing LHC technical problems. The only occasion when CMS had to request an access between fills was to search for the source of an alarm from the leak-detection cables mounted in the DT racks. After a few minutes of diagnostic search, a leaking air-purge was found. Replacement was complete within 2 hours. This incident demonstrated once more the value of these leak detection cables; the system will be further extended (during the end of year technical stop) to cover more racks in UXC and the floor beneath the detector. The magnet has also been operating reliably and reacted correctly to the 14s power cut on 29 May (see below). In or...

  7. Technical endoscopy

    International Nuclear Information System (INIS)

    Cavalar, K.O.

    1988-01-01

    A survey is provided on different versions of endoscopes, taking into account the new developments of video endoscopy. With a variety of practical examples it is shown that technical tests using endoscopy are a demanding task for nondestructive testing, whose requirements can only be met on a customized basis. (orig./HP) [de

  8. 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...

  9. The role of reported tobacco-specific media exposure on adult attitudes towards proposed policies to limit the portrayal of smoking in movies.

    Science.gov (United States)

    Blake, Kelly D; Viswanath, K; Blendon, Robert J; Vallone, Donna

    2010-06-01

    To assess the relative, independent contribution of reported tobacco-specific media exposure (pro-tobacco advertising, anti-tobacco advertising, and news coverage of tobacco issues) to US adults' support for policy efforts that aim to regulate the portrayal of smoking in movies. Using the American Legacy Foundation's 2003 American Smoking and Health Survey (ASHES-2), multivariable logistic regression was used to model the predicted probability that US adults support movie-specific tobacco control policies, by reported exposure to tobacco-specific media messages, controlling for smoking status, education, income, race/ethnicity, age, sex, knowledge of the negative effects of tobacco and state. Across most outcome variables under study, findings reveal that reported exposure to tobacco-specific media messages is associated with adult attitudes towards movie-specific policy measures. Most exposure to tobacco information in the media (with the exception of pro-tobacco advertising on the internet) contributes independently to the prediction of adult support for movie-specific policies. The direction of effect follows an expected pattern, with reported exposure to anti-tobacco advertising and news coverage of tobacco predicting supportive attitudes towards movie policies, and reported exposure to pro-tobacco advertising lessening support for some movie policies, though the medium of delivery makes a difference. Media campaigns to prevent tobacco use and exposure to secondhand smoke have had value beyond the intended impact of single-issue campaigns; exposure to anti-tobacco campaigns and public dialogue about the dangers of tobacco seem also to be associated with shaping perceptions of the social world related to norms about tobacco, and ideas about regulating the portrayal of smoking in movies.

  10. 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

  11. Technical expertise on the safety of the proposed geological repository sites. Planning for geological deep repositories, step 1; Sicherheitstechnisches Gutachten zum Vorschlag geologischer Standortgebiete. Sachplan geologische Tiefenlager, Etappe 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-01-15

    On October 17, 2010, on request of those Swiss government institutions responsible for the disposal of radioactive wastes, the National Co-operative for the Disposal of Radioactive Waste (NAGRA) presented its project concerning geological sites for the foreseen disposal of radioactive wastes to the Federal Authorities. According to the present disposal concept, two types of repository are foreseen: one for highly radioactive wastes (HAA) and the other for low radioactive and intermediate-level radioactive wastes (SMA). If a site fulfils the necessary conditions for both HAA as well as for SMA, a combined site for both types of waste may be chosen. As a qualified control authority in Switzerland, the Federal Nuclear Safety Inspectorate (ENSI) has to examine the quality of the NAGRA proposals from the point of view of the nuclear safety of the sites. The project for deep underground waste disposal first defines the process and the criteria according to which sites for the geological storage of all types of radioactive wastes in Switzerland have to be chosen. The choice is based on the actual knowledge of Swiss geology. After dividing the wastes into SMA and HAA, some large-scale areas are to be identified according to their suitability from the geological and tectonic points of view. NAGRA's division of waste into SMA and HAA is based on calculations of the long-term safety for a broad range of different rock types and geological situations and takes the different properties of all waste types into account. As a conclusion, a small portion of SMA has to be stored with {alpha}-toxic wastes in the HAA repository. The estimation of the total volume of wastes to be stored is based on 60 years of operation of the actual nuclear power plants, augmented with the wastes from possible replacement plants with a total power of 5 GW{sub e} during a further 60 years. The safety concept of the repository is based on passive systems using technical and natural barriers. The

  12. A generation proposal of management signals from the distribution technical service quality control; Una propuesta de generacion de senales de gestion a partir del control de calidad del servicio tecnico de distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Vidal, Pedro [Energia San Juan S.A. (Argentina). E-mail: pfpvidal@hotmail.com; Andreoni, Alberto M. [ASINELSA S.A., San Juan (Argentina). E-mail: info@asinelsa.com.ar

    1998-07-01

    A set of management signals are presented which help to make the best decision of Operation and Maintenance actions (O and M) and/or investments within the period of technical service quality control so that, at the end of it, the total cost, included compensations to customers related to energy received with bad quality technical service, can be minimized. First, the normative in force is put forward for the measurement and quality control of the technical service according to the Concession Agreement of the distribution service of electric system of San Juan Province - Argentina managed by Energia San Juan S.A. and later, a calculation methodology for some of the signals used during the management period are introduced. These signals are the result of the analysis of interruptions and relations between indicators of the same utility resulting from the first three management periods of the electric distribution system of the province. (author)

  13. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball

    Overview From a technical perspective, CMS has been in “beam operation” state since 6th November. The detector is fully closed with all components operational and the magnetic field is normally at the nominal 3.8T. The UXC cavern is normally closed with the radiation veto set. Access to UXC is now only possible during downtimes of LHC. Such accesses must be carefully planned, documented and carried out in agreement with CMS Technical Coordination, Experimental Area Management, LHC programme coordination and the CCC. Material flow in and out of UXC is now strictly controlled. Access to USC remains possible at any time, although, for safety reasons, it is necessary to register with the shift crew in the control room before going down.It is obligatory for all material leaving UXC to pass through the underground buffer zone for RP scanning, database entry and appropriate labeling for traceability. Technical coordination (notably Stephane Bally and Christoph Schaefer), the shift crew and run ...

  14. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

    In this report we will review the main achievements of the Technical Stop and the progress of several centrally-managed projects to support CMS operation and maintenance and prepare the way for upgrades. Overview of the extended Technical Stop  The principal objectives of the extended Technical Stop affecting the detector itself were the installation of the TOTEM T1 telescopes on both ends, the readjustment of the alignment link-disk in YE-2, the replacement of the light-guide sleeves for all PMs of both HFs, and some repairs on TOTEM T2 and CASTOR. The most significant tasks were, however, concentrated on the supporting infrastructure. A detailed line-by-line leak search was performed in the C6F14 cooling system of the Tracker, followed by the installation of variable-frequency drives on the pump motors of the SS1 and SS2 tracker cooling plants to reduce pressure transients during start-up. In the electrical system, larger harmonic filters were installed in ...

  15. Proposed reliability cost model

    Science.gov (United States)

    Delionback, L. M.

    1973-01-01

    The research investigations which were involved in the study include: cost analysis/allocation, reliability and product assurance, forecasting methodology, systems analysis, and model-building. This is a classic example of an interdisciplinary problem, since the model-building requirements include the need for understanding and communication between technical disciplines on one hand, and the financial/accounting skill categories on the other. The systems approach is utilized within this context to establish a clearer and more objective relationship between reliability assurance and the subcategories (or subelements) that provide, or reenforce, the reliability assurance for a system. Subcategories are further subdivided as illustrated by a tree diagram. The reliability assurance elements can be seen to be potential alternative strategies, or approaches, depending on the specific goals/objectives of the trade studies. The scope was limited to the establishment of a proposed reliability cost-model format. The model format/approach is dependent upon the use of a series of subsystem-oriented CER's and sometimes possible CTR's, in devising a suitable cost-effective policy.

  16. 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...

  17. Technical and economic guidelines

    International Nuclear Information System (INIS)

    1978-01-01

    This paper proposes technical and economic data and analysis for use in comparing the nuclear systems considered in INFCE. It suggests that a relatively detailed set of characteristics be developed for each system. An alternative to this approach is to concentrate on comparing the characteristic of most interest to INFCE, using a differential comparison to established systems (such as the LWR and HWR) where possible. This would avoid the repetitive analysis of design characteristics that are common to many systems. In making the INFCE comparisons it would still be appropriate that a selected set of information, pertinent to the primary assessment factors under consideration, be developed for each nuclear system. This selected set, much more limited than that set forth in the body of this paper, would include overall descriptions of the reactor and fuel cycle facilities, as well as specific information on resource utilization, flow of nuclear materials, and other areas to be determined by the Working Group. On the other hand, in areas such as costs, nuclear safety, and environmental impacts, it would not be intended that information be developed at a level of detail comparable to that resulting from a detailed design of each system being compared. Instead, the detailed set of data identified in this paper can serve as a check list to assure that all pertinent characteristics are considered, at least on a differential basis; more detailed assessments would be needed only where the differences have substantial impact. Thus this paper asks for more detail than will probably be appropriate for many contributed papers

  18. Proposed nomination of sites for site characterization and recommendation of issues for environmental assessments and site characterization plans. Technical report. Summary of issues and concerns expressed during the April-May 1983 US Department of Energy public hearings

    International Nuclear Information System (INIS)

    1983-09-01

    As required by Section 112(b)(2) of the Nuclear Waste Policy Act (Public Law 97-425), the US Department of Energy (DOE) conducted a series of nine formal public hearings during April and May 1983 in local communities in the vicinity of seven identified potentially acceptable salt sites and in the state capitals of the States of Louisiana, Mississippi, Texas, and Utah. The public hearings focused on the proposed nomination of the Vacherie Dome site in Louisiana; the Richton and Cypress Creek Salt Dome sites in Mississippi; the Deaf Smith County and Swisher County bedded salt sites in Texas; and the Davis and Lavender Canyon bedded salt sites in Utah. The issues expressed during area public hearings are summarized in this document, which serves as a digest of and as an index to the public hearing records of each of the four salt states. Specifically, almost 1100 paraphrased public hearing comments are identified and grouped into 62 subjects within the following nine general topical areas: NWTS Program Planning Process, Consultation and Cooperation, Engineering/Repository Design, Geology, Hydrology, Transportation, Public Health and Safety, Environmental Quality, and Socioeconomics

  19. Technical and economical studies on the modernization of small-scale hydroelectric power plants: difficulties and proposals; Estudo tecnico-economicos de mordernizacao de PCH`s: Dificuldades e propostas

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Antonio Tadeu Lyrio de; Beltrame, Eduardo; Santos, Afonso Henriques Moreira; Souza, Zulcy [Escola Federal de Engenharia de Itajuba, MG (Brazil)

    1989-12-31

    This work describes and analyses some technical alternatives to be used in re-designing or reforming small-scale hydroelectric power plants. In addition, some criteria are also presented in order to proceed a comparative evaluation based on economic feasibility 7 refs. 5 figs. 1 tab.

  20. Technical and economical studies on the modernization of small-scale hydroelectric power plants: difficulties and proposals; Estudo tecnico-economicos de mordernizacao de PCH`s: Dificuldades e propostas

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Antonio Tadeu Lyrio de; Beltrame, Eduardo; Santos, Afonso Henriques Moreira; Souza, Zulcy [Escola Federal de Engenharia de Itajuba, MG (Brazil)

    1990-12-31

    This work describes and analyses some technical alternatives to be used in re-designing or reforming small-scale hydroelectric power plants. In addition, some criteria are also presented in order to proceed a comparative evaluation based on economic feasibility 7 refs. 5 figs. 1 tab.

  1. 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...

  2. 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...

  3. Technical specification of HANARO fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y

    1998-03-01

    The design and installation of the irradiation test facility for verification test of the fuel performance are very important in connection with maximization of the utilization of HANARO. HANARO fuel test loop was designed in accordance with the same code and standards of nuclear power plant because HANARO FTL will be operated the high pressure and temperature same as nuclear power plant operation conditions. The objective of this study is to confirm the operation limit, safety limit, operation condition and checking points of HANARO fuel test loop. This results will become guidances for the planning of irradiation testing and operation of HANARO fuel test loop. (author). 13 refs., 13 tabs., 8 figs.

  4. High Flux Isotope Reactor technical specifications

    International Nuclear Information System (INIS)

    1977-03-01

    Included are sections covering safety limits and limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. An appendix deals with accidents and anticipated transients

  5. Quality assurance of technical specification approval process

    Science.gov (United States)

    Antsev, V. Yu; Antseva, N. V.; Chernecova, E. A.

    2018-03-01

    The paper reviews the issue of increasing the efficiency of contract analysis on machine-building plants in accordance with process approach principles and on the basis of better interaction between marketing, finance and accounting, and R&D departments.

  6. Knowledge based management of technical specifications

    International Nuclear Information System (INIS)

    Fiedler, U.; Schalm, S.; Pranckeviciute, K.

    1992-01-01

    TechSPEX is a knowledge based advisory system for checking the status of a nuclear plant on compliance with the safety limits and the limiting conditions of operation. These prescripts for safe reactor operation exist as textual information. For the purpose of its operational use an explicit representation formalism is introduced. On this basis, various approaches of text retrieval are realized, condition based surveillance and control is supported too. Knowledge editing and verification modules ease the adaption to changing requirements. TechSPEX has been implemented in PROLOG. (author). 6 refs, 3 figs

  7. 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, ...

  8. 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...

  9. Nagra technical report 14-02, Geological basics - Dossier VI - Barrier properties of proposed host rock sediments and neighbouring rock; SGT Etappe 2: Vorschlag weiter zu untersuchender geologischer Standortgebiete mit zugehörigen Standortarealen für die Oberflächenanlage -- Geologische Grundlagen -- Dossier VI -- Barriereneigenschaften der Wirt- und Rahmengesteine

    Energy Technology Data Exchange (ETDEWEB)

    Gautschi, A.; Deplazes, G.; Traber, D.; Marschall, P. [National Cooperative for the Disposal of Radioactive Waste (NAGRA), Wettingen (Switzerland); Mazurek, M.; Gimmi, T.; Maeder, U. [Institute of Geological Sciences, University of Berne, Berne (Switzerland)

    2014-12-15

    This dossier is the sixth of a series of eight reports concerning the safety and technical aspects of locations for the disposal of radioactive wastes in Switzerland. It discusses the barrier properties of the proposed host rock sediments and neighbouring rock layers. The mineralogical composition of the host rocks are discussed as are their pore densities and hydrological properties. Diffusion aspects are discussed. The aquifer systems in the proposed depository areas and their classification are looked at. The barrier properties of the host rocks and those of neighbouring sediments are discussed. Finally, modelling concepts and parameters for the transport of radionuclides in the rocks are discussed.

  10. TECHNICAL COORDINATION

    CERN Document Server

    A. Ball and W. Zeuner

    2013-01-01

    For the reporting period, the CMS common systems and infrastructure worked well, without failures that caused significant data losses. One more disconnection of the magnet cold box occurred in the shadow of interruptions in data taking, caused by a series of technical faults. The recognition during 2012 that re-connection can only safely be done at around 2 T implies a minimum magnet recovery time of 12 hours and raises serious concerns about the number of ramping cycles of the magnet these incidents cause. This has triggered studies of how to make the cryo-system of the magnet more robust against failures. The proton-proton run ended just before the end-of-year CERN closure, during which CASTOR was installed on the negative end of CMS and both ZDC calorimeters were installed in TAN absorbers the LHC tunnel, in preparation for the heavy-ion run. The installation of CASTOR was an excellent “engineering test” of procedures for working in an activated environment. Despite some technical pr...

  11. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    Summary of progress since last CMS week. Ten years of construction work have been completed. CMS is closed, in very close to the ideal low luminosity configuration, and performed well in the first tests with LHC beam. Behind this encouraging news is the story of a summer of intense commitment by many teams (from the collaboration and 3 CERN departments) working together, against the clock and despite many minor setbacks, to ensure that the experiment was ready to play a leading role in the excitement of September 10. Following beampipe bakeout and refill with pure neon, a magnificent effort by the ECAL group and the pt 5 technical crew made it possible to install and commission all 4 ECAL endcap Dees before the end of August. In the shadow of this activity, the barrel and forward pixel trackers and part of the beam monitoring were installed within the vac tank. The pt 5 technical teams then succeeded in safely removing the 20t installation tables and their support blocks from beneath the already installed ...

  12. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2011-01-01

      Operational experience 2011 CMS is approaching the end of a very successful year of operation. Proton- proton running ended in the late afternoon of 30th October with a stunning 5.73 fb–1 delivered by LHC, of which CMS recorded 5.22 fb–1. During heavy-ion operation, which continues until 7th December, both the accelerator and the CMS detector have also performed very well. Despite the encouraging overall reliability of technical operation, several infrastructure failures which occurred since the last Bulletin are worthy of mention, with one leading for the first time to significant data-loss. On 10th July, a CERN-wide power failure brought down essentially all services including the magnet, due to an MCS setting being left in “manual” after the recent technical stop, but there was no significant damage and the detector was operational before the LHC, despite a slow and tortuous recovery (one of several indications this year that there is room for improve...

  13. Technical presentation

    CERN Document Server

    FP Department

    2009-01-01

    07 April 2009 Technical presentation by Leuze Electronics: 14.00 – 15.00, Main Building, Room 61-1-017 (Room A) Photoelectric sensors, data identification and transmission systems, image processing systems. We at Leuze Electronics are "the sensor people": we have been specialising in optoelectronic sensors and safety technology for accident prevention for over 40 years. Our dedicated staff are all highly customer oriented. Customers of Leuze Electronics can always rely on one thing – on us! •\tFounded in 1963 •\t740 employees •\t115 MEUR turnover •\t20 subsidiaries •\t3 production facilities in southern Germany Product groups: •\tPhotoelectric sensors •\tIdentification and measurements •\tSafety devices

  14. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2010-01-01

    Overview Once again, the bulk of this article reviews the intense activity of a recently completed shutdown, which, although quite unforeseeable until a few weeks before it started, proved by its success that our often advertised capability to conduct major maintenance within a two month period is real. Although safely completed, on-time to remarkable precision, the activity was not without incident, and highlighted our dependence on many experienced, specialist teams and their precise choreography. Even after the yoke was safely closed, magnet re-commissioning and beampipe pumpdown showed new and thought-provoking behaviour. The struggle to maintain adequate technical resources will be a pre-occupation over the coming months, in parallel with the start of truly sustained operation, for which various procedures are still being put in place. Planning for future shutdowns must now become a high priority, with many working groups and task forces already in existence to prepare infrastructure improvements and to...

  15. Technical presentation

    CERN Document Server

    FI Department

    2008-01-01

    RADIOSPARES, the leading catalogue distributor of components (electronic, electrical, automation, etc.) and industrial supplies will be at CERN on Friday 3 October 2008 (Main Building, Room B, from 9.00 a.m. to 3.00 p.m.) to introduce its new 2008/2009 catalogue. This will be the opportunity for us to present our complete range of products in more detail: 400 000 part numbers available on our web site (Radiospares France, RS International, extended range of components from other manufacturers); our new services: quotations, search for products not included in the catalogue, SBP products (Small Batch Production: packaging in quantities adapted to customers’ requirements); partnership with our focus manufacturers; demonstration of the on-line purchasing tool implemented on our web site in conjunction with CERN. RADIOSPARES will be accompanied by representatives of FLUKE and TYCO ELECTRONICS, who will make presentations, demonstrate materials and answer any technical questio...

  16. 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

  17. ATF2 Proposal v. 2

    CERN Document Server

    Grishanov, B I; Alabau-Pons, M; Angal-Kalinin, Deepa; Appleby, R; Araki, S; Bailey, I; Bambade, P; Bane, Karl Leopold Freitag; Barlow, R; Blair, G A; Bolzon, B; Boorman, G; Bosco, A; Brachmann, A; Braun, Hans Heinrich; Burrows, P N; Carter, J; Choi, J; Christian, Glenn B; Clarke, C; Dabiri-Khah, A; Dadoun, O; Danagulyan, S; Delerue, N; Dixit, S; Driouichi, C; Elsen E; Gao, J; Geffroy, N; Gronberg, J; Hartin, Anthony F; Hayano, H; Higashi, Y; Himel, T; Honda, Y; Howell, D; Huang, J Y; Iwashita, Y; Jenner, L; Jones, J; Jones, R; Jérémie, A; Kalinin, A; Kanazawa, K; Kang, H S; Karyotakis, Yu; Kim, E S; Kim, S; Komamiya, S; Kourevlev, German Yu; Kubo, K; Kumada, M; Kume, T; Kuriki, M; Kuroda, S; Liu, W; Logatchev, P V; Lyapin, A; Malton, S; Markiewicz, T W; Masuzawa, M; Mihara, T; Miller, D J; Molloy, S; Mtingwa, S; Naito, T; Nan-Phinney, Y; Napoly, O; Nelson, J; Okugi, T; Payet, J; Pei, G X; Pivi, M T F; Podgorny, F; Price, M; Raubenheimer, T O; Reichold, A; Ross, M; Sanuki, T; Schulte, Daniel; Seryi, R A; Solyak, N; Soo Ko In; Spencer, C M; Suehara, T; Sugahara, R; Takahashi, T; Takashi-Boogert, S; Tauchi, T; Telnov, Valery I; Tenenbaum, P G; Terunuma, N; Toge, N; Torrence, E; Urakawa, J; Urner, D; Vogel, V; Walker, N; Wang, J Q; Wendt, M; White, G; Wing, M; Wolski, A; Woodley, M; Yamaoka, H; Yokoya, K; Zimmermann, Frank

    2006-01-01

    For achieving the high luminosity required at the International Linear Collider (ILC), it is critical to focus the beams to nanometer size with the ILC Beam Delivery System (BDS), and to maintain the beam collision with a nanometer-scale stability. To establish the technologies associated with this ultra-high precision beam handling, it has been proposed to implement an ILC-like final focus optics in an extension of the existing extraction beamline of ATF at KEK. The ATF is considered to be the best platform for this exercise, since it provides an adequate ultra-low emittance electron beam in a manner dedicated to the development of ILC. The two major goals for this facility, called ATF2, are : (A) Achievement of a 37 nm beam size, and (B) control of beam position down to 2 nm level. The scientific justification for the ATF2 project and its technical design have been described in Volume 1 of the ATF2 Proposal [1]. We present here Volume 2 of the ATF2 Proposal, in which we present specifics of the construction...

  18. Technical Training: Technical Training Seminar

    CERN Multimedia

    2004-01-01

    TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Tuesday 3 February 2004 From 09:00 to 13:30 - Training Centre Auditorium - bldg. 593, room 11 USB (Universal Serial Bus) CYPRESS Seminar Claudia Colombini, Field Application Engineer CYPRESS ActiveComp Electronic GmbH D-85077 MANCHING, Germany As a pioneer in USB, CYPRESS sets the standard for cost-effective solutions without sacrificing functionality, performance or reliability. Having shipped over 200 million USB devices, Cypress is the undisputed market leader and demonstrates unmatched USB expertise. With the industry's broadest selection of USB solutions, Cypress has the right silicon, software and support for every USB application, from Low-speed to High-Speed and USB On-The-Go (OTG). 9:00 - 10:30 Overview of USB systems. USB CYPRESS product overview. Peripherals: Low Speed, Full Speed, High Speed (1.1 and 2.0). Hub Solutions, Embedded Host Solutions, On-The-Go (OTG) and wireless USB. USB Development Tools (first part) 10:30 -...

  19. ESGE-ESGENA technical specification for process validation and routine testing of endoscope reprocessing in washer-disinfectors according to EN ISO 15883, parts 1, 4, and ISO/TS 15883-5.

    Science.gov (United States)

    Beilenhoff, Ulrike; Biering, Holger; Blum, Reinhard; Brljak, Jadranka; Cimbro, Monica; Dumonceau, Jean-Marc; Hassan, Cesare; Jung, Michael; Neumann, Christiane; Pietsch, Michael; Pineau, Lionel; Ponchon, Thierry; Rejchrt, Stanislav; Rey, Jean-François; Schmidt, Verona; Tillett, Jayne; van Hooft, Jeanin

    2017-12-01

    1 Prerequisites. The clinical service provider should obtain confirmation from the endoscope washer-disinfector (EWD) manufacturer that all endoscopes intended to be used can be reprocessed in the EWD. 2 Installation qualification. This can be performed by different parties but national guidelines should define who has the responsibilities, taking into account legal requirements. 3 Operational qualification. This should include parametric tests to verify that the EWD is working according to its specifications. 4 Performance qualification. Testing of cleaning performance, microbiological testing of routinely used endoscopes, and the quality of the final rinse water should be considered in all local guidelines. The extent of these tests depends on local requirements. According to the results of type testing performed during EWD development, other parameters can be tested if local regulatory authorities accept this. Chemical residues on endoscope surfaces should be searched for, if acceptable test methods are available. 5 Routine inspections. National guidelines should consider both technical and performance criteria. Individual risk analyses performed in the validation and requalification processes are helpful for defining appropriate test frequencies for routine inspections. © Georg Thieme Verlag KG Stuttgart · New York.

  20. Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants; Optimizacion y mejora de las especificaciones tecnicas de funcionamiento para las centrales de Santa Maria de Garona y Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Norte Gomez, M D [Empresarios Agrupados, A.I.E., Madrid (Spain); Alcantud, F [Iberdrola C.N., Cofrentes, (Spain); Hoyo, C del [Nuclenor C.N., Santa Maria de Garona (Spain)

    1993-12-15

    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)

  1. Wyoming coal-conversion project. Final technical report, November 1980-February 1982. [Proposed WyCoalGas project, Converse County, Wyoming; contains list of appendices with title and identification

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    This final technical report describes what WyCoalGas, Inc. and its subcontractors accomplished in resolving issues related to the resource, technology, economic, environmental, socioeconomic, and governmental requirements affecting a project located near Douglas, Wyoming for producing 150 Billion Btu per day by gasifying sub-bituminous coal. The report summarizes the results of the work on each task and includes the deliverables that WyCoalGas, Inc. and the subcontractors prepared. The co-venturers withdrew from the project for two reasons: federal financial assistance to the project was seen to be highly uncertain; and funds were being expended at an unacceptably high rate.

  2. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    2013-01-01

      Since the last report, much visible progress has been made, as the LS1 programme approaches the halfway point. From early October, technical and safety shift-crew have been present around the clock, allowing detectors to stay switched on overnight, ensuring that safety systems are operational and instructions for non-expert shift-crew are clear. LS1 progress Throughout the summer, whilst the solenoid vacuum tank and YB0 surfaces were accessible, an extensive installation programme took place to prepare for Tracker colder operation and the PLT installation, in 2014, the Phase 1 Pixel Tracker installation, in 2016–’17, and the HCAL Phase 1 upgrade completion, ending in LS2. This included pipework for N2 or dry air to flush the Tracker bulkhead region, many sensors to monitor temperature and dew point in the Tracker and its service channels, heating wires outside the Tracker cooling bundles, supports for the new vacuum-jacketed, concentric, CO2 Pixel cooling lines, the PLT cool...

  3. TECHNICAL COORDINATION

    CERN Multimedia

    A. Ball and W. Zeuner

    2012-01-01

      UXC + detectors As explained in detail in the November 2011 bulletin, the bellows unit at −18.5 m from the CMS interaction point was identified as a prime candidate for the regularly occurring pressure spikes which occasionally led to sustained severe background conditions in 2011, affecting dead time and data quality. Similar regions in LHC with vacuum instabilities were observed to be close to bellows, which radiography showed to have distorted RF-fingers — on removal, they proved to have been severely overheated. The plans for the Year-End Technical Stop were adapted to prioritise radiography of the bellows at 16 m to 18 m either end of CMS. Excellent work by the beam pipe, survey and heavy mechanical teams allowed the X-rays to be taken as planned on 20th December, showing that the bellow at −18.5m had an obvious non-conformity. The RF-fingers were found inside the end of the opposing flared pipe instead of outside. In addition, the overlap between fingers and...

  4. Innovative methods of popularizing technical education

    Science.gov (United States)

    Shkitsa, L. Y.; Panchuk, V. G.; Kornuta, V. A.

    2017-05-01

    There have been analyzed reasons of the loss of technical education’s popularity. Also, the analysis of known educational and production methods, oriented at the innovative model of development of society, was performed. It is stated that the acquisition of 21st century’s skills as a result of competition of technical education are natural for the DIY ideology, which was realized in the institutions like Fab Lab. The new educational strategy, based on project-based learning, is proposed to be implemented as a special laboratory with equipment, which would be a center of innovative development for students at the Technical University. Moreover, the list of projects planned for implementation, that includes not only projects, specific to a particular university, but also projects, demanded by society as a whole, is specified. It is worth to implement trendy projects in the laboratory, such as toy-like, ecological projects; projects of the energy dependence decrease or the energy efficiency increase, modern digital or innovative projects etc. The student should gain knowledge, skills and, possibly, equipment that are available for immediate usage on the labor market or for the realization of his own projects or the community’s projects in everyday life after the realization of the particular project at the laboratory

  5. Technical approach document

    International Nuclear Information System (INIS)

    1989-12-01

    The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law 95-604 (PL95-604), grants the Secretary of Energy the authority and responsibility to perform such actions as are necessary to minimize radiation health hazards and other environmental hazards caused by inactive uranium mill sites. This Technical Approach Document (TAD) describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement remedial action plans (RAPS) and final designs that comply with EPA standards. It does not address the technical approaches necessary for aquifer restoration at processing sites; a guidance document, currently in preparation, will describe aquifer restoration concerns and technical protocols. This document is a second revision to the original document issued in May 1986; the revision has been made in response to changes to the groundwater standards of 40 CFR 192, Subparts A--C, proposed by EPA as draft standards. New sections were added to define the design approaches and designs necessary to comply with the groundwater standards. These new sections are in addition to changes made throughout the document to reflect current procedures, especially in cover design, water resources protection, and alternate site selection; only minor revisions were made to some of the sections. Sections 3.0 is a new section defining the approach taken in the design of disposal cells; Section 4.0 has been revised to include design of vegetated covers; Section 8.0 discusses design approaches necessary for compliance with the groundwater standards; and Section 9.0 is a new section dealing with nonradiological hazardous constituents. 203 refs., 18 figs., 26 tabs

  6. 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.

  7. 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.

  8. Technical proposal on the treatment of the influent of the Jose Antonio Alzate dam using aerobic pond system; Propuesta tecnica sobre el tratamiento del influente de la presa Jose Antonio Alzate a traves un sistema lagunar aerobio

    Energy Technology Data Exchange (ETDEWEB)

    Rosas de Alba, S.G. [Instituto Tecnologico de Toluca, Metepec, Estado de Mexico (Mexico)]. E-mail: sergio.rosas01@cfe.gob.mx; Barcelo Quintal, I.D.; Bussy Beaurain, A.L.; lopez Galvan, E. [Universidad Autonoma Metropolitana, Unidad Azcapotzalco (Mexico)]. E-mail: idbq@correo.azc.uam.mx; leemp@correo.azc.uam.mx; loge@correo.azc.uam.mx

    2010-01-15

    In Mexico, discharge of waste water not treated is a common problem; this is the case of the Lerma river, where the original clean water contribution of the Almoloya-Lerma-San Bartolo timber-roof system, located in the valley of Toluca, State of Mexico, was replaced by the wastewater of the valley. The attempts to clean the water before their spill have been unfruitful and this has caused the present anaerobic conditions of the river in its entire route including the first receiving stage that is the Jose Antonio Alzate Dam (PJAA), becoming a potential source of diseases and a useless water body. In this work we evaluate the treatment efficiency of experimental waste water pond system. The treatment system was constructed with 5 screens which formed 6 internal channels and it had an operation in continuous form by 26 weeks, providing it with continuously polluted water of the Lerma river. We found that the efficiency of reduction of the organic matter reported as BOD, was 83% and it is carried out in the first channel after 7 days of hydraulic retention verifying that the channels do not work like lagoons in series. With the collected data we calculated, through the application of design equations, the factor of decay of organic matter k and the number of dispersion d, specific for the type of treatment and environmental conditions of the site. The required surface of treatment calculated to reach the efficiency of reduction of the DOD5 obtained experimentally. Thus, a surface of: 1 281.6 hectares distributed in 13 lagoons that can deal with a volume 8646.70 m{sup 3}/h was determined. Since this was a bigger surface than that of the dam, the available area was evaluated to make a proposal closer to reallity. [Spanish] La descarga de aguas residuales a los sistemas acuaticos, sin previo tratamiento, es un problema generalizado en Mexico; como es el caso del rio Lerma en donde se sustituyo el aporte de agua limpia proveniente del sistema lagunar Almoloya

  9. 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

  10. Fiscal 2000 survey report. High-efficiency energy system introduction promotion project for houses and structures - Houses (Technical classification tables prepared by analysis of proposed systems, and comments on the same); 2000 nendo jutaku kenchikubutsu kokoritsu energy system donyu sokushin jigyo (jutaku ni kakawaru mono) teian system no bunseki ni yoru gijutsu bunruihyo oyobi dokaisetsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    As an energy conservation promotion measure, a project is under development for introducing and subsidizing high-efficiency energy systems and for letting their effect known publicly and widely. The number of proposed energy systems has increased greatly and technical divisions to follow in classifying them have become vague, from which problems are now arising over the execution of follow-up checks and the maintenance of fair treatment. In the effort to solve this problem, 376 propositions are analyzed and classified, a technical classification method is proposed, and an instruction manual on the method is compiled. The classification involves (1) proposed classification, (2) variation, (3) energy reduction rate, and (4) tentatively calculated cost. Item (1) deals with the basic classification (air-conditioning, ventilation, and hot water supply, and, to be considered in combination with them, options which are cooking, illumination, and others) and, item (2) covers eight items such as new/old construction, structure, and structural frame. In Chapter 1 of the report, the 376 propositions are put in order according to common classification items and an original classification table is prepared. In Chapter 2, the goals are clarified and the classification principles are defined. In Chapter 3, the classification is checked for its validity and some realistic ways of grouping are described. In Chapter 4, a classification implementation flow chart is shown. (NEDO)

  11. 78 FR 16447 - Rehabilitation Continuing Education Program (RCEP) for the Technical Assistance and Continuing...

    Science.gov (United States)

    2013-03-15

    ... (RCEP) for the Technical Assistance and Continuing Education Centers (TACE Centers); Proposed Extension... (RCEP) for the Technical Assistance and Continuing Education Centers (TACE Centers), the Secretary... with disabilities through enhanced technical assistance (TA) and continuing education (CE) for State...

  12. Technical note

    International Nuclear Information System (INIS)

    Moshier, W.C.; Tack, W.T.; Phull, B.

    1992-01-01

    Lithium is a potent addition to Al alloys for increasing their specific strength and stiffness, which makes Li-containing Al alloys attractive materials for typical aerospace applications in which reduced weight and increased strength and stiffness can improve system performance. Weldalite 049 (AA X2094) [Al-(4.0-6.3) Cu-1.3 Li-0.4 Ag-0.4 Mg-0.14 Zr] was recently developed as an ultra-high strength, weldable alloy designed for use in launch vehicle structures. Standard SCC testing contains the inherent difficulty of test duration and unclear interpretation of results. Use of slow strain rate tests (SSRTs) on aluminum alloys has met with mixed results, and the purpose of this paper is to evaluate the feasibility of using SSRT to evaluate the SCC susceptibility of two Weldalite 049 variants

  13. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Howe, Gary [RTI International, Research Triangle Park, NC (United States); Albritton, John [RTI International, Research Triangle Park, NC (United States); Denton, David [RTI International, Research Triangle Park, NC (United States); Turk, Brian [RTI International, Research Triangle Park, NC (United States); Gupta, Raghubir [RTI International, Research Triangle Park, NC (United States)

    2018-01-31

    technology has great potential to provide clean syngas from coal and petcoke-based gasification at increased efficiency and at significantly lower capital and operating costs than conventional syngas cleanup technologies. However, before the technology can be deemed ready for scale-up to a full commercial-scale demonstration, additional R&D testing is needed at the site to address the following critical technical risks: WDP sorbent stability and performance; Impact of WDP on downstream cleanup and conversion steps; Metallurgy and refractory; Syngas cleanup performance and controllability; Carbon capture performance and additional syngas cleanup The proposed plan to acquire this additional R&D data involves: Operation of the units to achieve an additional 3,000 hours of operation of the system within the performance period, with a target of achieving 1,000 hours of those hours via continuous operation of the entire integrated pre-commercial demonstration system; Rapid turnaround of repairs and/or modifications required as necessary to return any specific unit to operating status with documentation and lessons learned to support technology maturation, and; Proactive performance of maintenance activities during any unplanned outages and if possible while operating.

  14. As especificidades na formação do educador de jovens e adultos: um estudo sobre propostas de eja The specificities in the formation of the teacher of the young and adult students: a study on the eja proposal

    Directory of Open Access Journals (Sweden)

    Leôncio Soares

    2011-08-01

    Full Text Available Este artigo traz resultados de uma pesquisa que vem sendo realizada sobre as especificidades da formação do educador de jovens e adultos em que buscamos selecionar propostas que nos auxiliassem a identificar suas singularidades. De acordo com o tempo de existência, histórico, tradição, impacto na área e a relevância para a comunidade envolvida, elegemos as quatro propostas a serem visitadas: o Projeto Escola Zé Peão, o Projeto Paranoá, o PROEF e o CMET Paulo Freire. Ao analisarmos como acontece a EJA e o que ressaltou quanto às suas especificidades, nas propostas pesquisadas, oito pontos se destacaram: a origem de cada um; a diversidade dos sujeitos; a preocupação com o espaço físico; as formas de conceber as propostas curriculares; a disponibilidade de recursos didáticos; as políticas complementares de alimentação e transporte; a formulação de uma política pública para a EJA; e as iniciativas de formação inicial e continuada.This article brings out the results of a research that has been realized about the specificities of the Young and Adults educators´ formation, in which we sought to select proposals to help us indentifying the singularities of those educators. We elected the four proposals to be visited according to their time of existence, their historic, their tradition, their impact on the area and their relevance for the community involved. They are: the Project "Escola Zé Peão", the Project "Paranoá", the "PROEF" and the "CMET Paulo Freire". By analyzing how EJA takes place in each proposal studied and what came out about their specificity, we can stress eight points: the origin of each project, the diversity of the subjects, the caution with the physical space, the way of conceiving the circular proposals; the availability of didactical resources; the complementary politics of food and transportation; the public policy formulation for EJA and the initiatives of initial and continued formation.

  15. The Effectiveness of Problem-based Learning Approach on Students’ Skills in Technical Vocational Education and Training (TVET) Specifically on Programming Course Using a Computerized Numerical Control (CNC) Simulator

    DEFF Research Database (Denmark)

    Mohamad, Hasim Bin; de Graaff, Erik

    2013-01-01

    Industry has a great need for highly skilled technicians that graduate from Technical Vocational Education and Training (TVET). In a study started at Aalborg University (AAU) the purpose is to evaluate the effectiveness of the (PBL) approach on students’ skills, in particular on programming course...... using a Computerized Numerical Control (CNC) simulator. The study will use data from the German-Malaysian Institute in Malaysia. The findings of this study will provide a general guideline for educators in Technical and Vocational Education and Training (TVET) institutions in implementing Problem...

  16. Strategy of technical innovation

    International Nuclear Information System (INIS)

    Lee, Ga Jong

    1990-12-01

    This book deals with policy of scientific technique and technical innovation such as research for development and types of technical innovation, historical development and process of technical innovation, economic growth, technology change and investment for research and development, structure and form of technical transfer with the meaning process, from, structure and theory, economic growth and investment of research and development with experiential analysis and case study on strategy of technical innovation in electron and fine chemical industry.

  17. Thesis Proposal

    DEFF Research Database (Denmark)

    Sloth, Erik

    2010-01-01

    Strukturen i Thesis proposal er følgende: Først præsenteres mine konkrete empiriske forskningsprojekter som skal munde ud i afhandlingens artikler. Jeg præsenterer herefter de teoretiske overvejelser omkring oplevelsesbegrebet og forbrugerkulturteori som danner baggrund for at jeg er nået frem til...

  18. 10 CFR 601.205 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ..., drafting of a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 10 Energy 4 2010-01-01 2010-01-01 false Professional and technical services. 601.205 Section 601... Activities by Own Employees § 601.205 Professional and technical services. (a) The prohibition on the use of...

  19. 32 CFR 28.205 - Professional and technical services.

    Science.gov (United States)

    2010-07-01

    ... or technical discipline. For example, drafting of a legal document accompanying a bid or proposal by... 32 National Defense 1 2010-07-01 2010-07-01 false Professional and technical services. 28.205... technical services. (a) The prohibition on the use of appropriated funds, in § 28.100 (a), does not apply in...

  20. 15 CFR 28.300 - Professional and technical services.

    Science.gov (United States)

    2010-01-01

    ..., drafting or a legal document accompanying a bid or proposal by a lawyer is allowable. Similarly, technical... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Professional and technical services... ON LOBBYING Activities by Other Than Own Employees § 28.300 Professional and technical services. (a...