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Sample records for environmental technical specifications

  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. 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

  3. 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

  4. 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)

  5. 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

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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.

  12. ENVIRONMENTAL SPECIFICATION REQUIREMENTS

    International Nuclear Information System (INIS)

    TIFFT, S.R.

    2003-01-01

    Through regulations, permitting or binding negotiations, Regulators establish requirements, limits, permit conditions and Notice of Construction (NOC) conditions with which the Office of River Protection (ORP) and the Tank Farm Contractor (TFC) must comply. Operating Specifications are technical limits which are set on a process to prevent injury to personnel, or damage to the facility or environment. The main purpose of this document is to provide specification limits and recovery actions for the TFC Environmental Surveillance Program at the Hanford Site. Specification limits are given for monitoring frequencies and permissible variation of readings from an established baseline or previous reading. The requirements in this document are driven by environmental considerations and data analysis issues, rather than facility design or personnel safety issues. This document is applicable to all single-shell tank (SST) and double-shell tank (DST) waste tanks, and the associated catch tanks and receiver tanks, and transfer systems. This Tank Farm Environmental Specifications Document (ESD) implements environmental-regulatory limits on the configuration and operation of the Hanford Tank Farms facility that have been established by Regulators. This ESD contains specific field operational limits and recovery actions for compliance with airborne effluent regulations and agreements, liquid effluents regulations and agreements, and environmental tank system requirements. The scope of this ESD is limited to conditions that have direct impact on Operations Projects or that Operations/Projects have direct impact upon. This document does not supercede or replace any DOE Orders, regulatory permits, notices of construction, or Regulatory agency agreements binding on the ORP or the TFC. Refer to the appropriate regulation, permit, or NOC for an inclusive listing of requirements

  13. 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

  14. ENVIRONMENTAL SPECIFICATION REQUIREMENTS

    International Nuclear Information System (INIS)

    TIFFT, S.R.

    2003-01-01

    Through regulations, permitting or binding negotiations, Regulators establish requirements, limits, permit conditions and Notice of Construction (NOC) conditions with which the Office of River Protection (ORP) and the Tank Farm Contractor (TFC) must comply. Operating Specifications are technical limits which are set on a process to prevent injury to personnel, or damage to the facility or environment. The main purpose of this document is to provide specification limits and recovery actions for the TFC Environmental Surveillance Program at the Hanford Site. Specification limits are given for monitoring frequencies and permissible variation of readings from an established baseline or previous reading. The requirements in this document are driven by environmental considerations and data analysis issues, rather than facility design or personnel safety issues. This document is applicable to all SST and DST waste tanks, and the associated catch tanks and receiver tanks, and transfer systems. This Tank Farm ESD implements environmental-regulatory limits on the configuration and operation of the Hanford Tank Farms facility that have been established by Regulators. This ESD contains specific field operational limits and recovery actions for compliance with airborne effluent regulations and agreements, liquid effluents regulations and agreements, and environmental tank system requirements. The scope of this ESD is limited to conditions that have direct impact on Operations/Projects or that Operations/Projects have direct impact upon. This document does not supercede or replace any DOE Orders, regulatory permits, notices of construction, or Regulatory agency agreements binding on the ORP or the TFC. Refer to the appropriate regulation, permit, or NOC for an inclusive listing of requirements

  15. 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

  16. Environmental impacts on technical products

    International Nuclear Information System (INIS)

    1991-01-01

    The interaction between an object and its environment is examined by methods of environment simulation. With regard to possible synergisms, technical considerations and holistic thinking are essential. Environmental simulation is mainly concerned with questions of ability to function and the service life of technical products in their environment. The environmental simulation is used to discover cause/effect mechanisms in ageing and weathering processes. Questions of artificial ageing and speeded up time tests play a great part here. (orig.) [de

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. Hanford Site Environmental Management Specification

    International Nuclear Information System (INIS)

    DAILY, J.L.

    2001-01-01

    The US Department of Energy, Richland Operations Office (RL) has established a document hierarchy as part of its integrated management system. The Strategic Plan defines the vision, values, missions, strategic goals, high-level outcomes, and the basic strategies in achieving those outcomes. As shown in Figure 1-1, the Site Specification derives requirements from the Strategic Plan and documents the top-level mission technical requirements for the work involved in the RL Hanford Site cleanup and infrastructure activities under the responsibility of the U.S. Department of Energy, Office of Environmental Management (EM). It also provides the basis for all contract technical requirements. Since this is limited to the EM work, neither the Fast Flux Test Facility (FFTF) nor the Pacific Northwest National Laboratory (PNNL) non-EM science activities are included. Figure 1-1 also shows the relationship between this Site Specification and the other Site management and planning documents. Similarly, the documents, orders, and laws referenced in this document represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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)

  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. Transportation Technical Environmental Information Center index

    International Nuclear Information System (INIS)

    Davidson, C.A.; Foley, J.T.

    1979-01-01

    In an effort to determine the environmental intensities to which energy materials in transit may be exposed, a ''Data Center'' of technical environmental information has been established by Sandia Laboratories, Division 5522, for the DOE Division of Environmental Control Technology. An index is presented which can be used to request data of interest

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  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. 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

  8. 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

  9. 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

  10. 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

  11. Transportation Technical Environmental Information Center index

    Energy Technology Data Exchange (ETDEWEB)

    Davidson, C. A.; Foley, J. T.

    1980-10-01

    In an effort to determine the environmental intensities to which energy materials in transit may be exposed, a Data Center of technical environmental information has been established by Sandia National Laboratories, Division 5523, for the DOE Office of Transportation Fuel Storage. This document is an index which can be used to request data of interest. Access to the information held is not limited to Sandia personnel. The purpose of the Transportation Technical Environmental Information Center is to collect, analyze, store, and make available descriptions of the environment of transportation expressed in engineering terms. The data stored in the Center are expected to be useful in a variety of transportation related analyses. Formulations of environmental criteria for shipment of cargo, risk assessments, and detailed structural analyses of shipping containers are examples where these data have been applied. For purposes of indexing and data retrieval, the data are catalogued under two major headings: Normal and Abnormal Environments.

  12. Transportation Technical Environmental Information Center index

    International Nuclear Information System (INIS)

    Davidson, C.A.; Foley, J.T.

    1980-10-01

    In an effort to determine the environmental intensities to which energy materials in transit may be exposed, a Data Center of technical environmental information has been established by Sandia National Laboratories, Division 5523, for the DOE Office of Transportation Fuel Storage. This document is an index which can be used to request data of interest. Access to the information held is not limited to Sandia personnel. The purpose of the Transportation Technical Environmental Information Center is to collect, analyze, store, and make available descriptions of the environment of transportation expressed in engineering terms. The data stored in the Center are expected to be useful in a variety of transportation related analyses. Formulations of environmental criteria for shipment of cargo, risk assessments, and detailed structural analyses of shipping containers are examples where these data have been applied. For purposes of indexing and data retrieval, the data are catalogued under two major headings: Normal and Abnormal Environments

  13. 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

  14. Transportation Technical Environmental Information Center index

    Energy Technology Data Exchange (ETDEWEB)

    Davidson, C.A.; Foley, J.T.

    1982-06-01

    In an effort to determine the environmental intensities to which energy materials in transit may be exposed, a Data Center of technical environmental information has been established by Sandia National Laboratories, Division 5523, for the DOE Office of Transportation Fuel Storage. This document is an index which can be used to request data of interest. Access to the information held is not limited to Sandia personnel.

  15. Transportation Technical Environmental Information Center index

    International Nuclear Information System (INIS)

    Davidson, C.A.; Foley, J.T.

    1982-06-01

    In an effort to determine the environmental intensities to which energy materials in transit may be exposed, a Data Center of technical environmental information has been established by Sandia National Laboratories, Division 5523, for the DOE Office of Transportation Fuel Storage. This document is an index which can be used to request data of interest. Access to the information held is not limited to Sandia personnel

  16. Hanford Site environmental management specification

    International Nuclear Information System (INIS)

    Grygiel, M.L.

    1998-01-01

    The US Department of Energy, Richland Operations Office (RL) uses this Hanford Site Environmental Management Specification (Specification) to document top-level mission requirements and planning assumptions for the prime contractors involved in Hanford Site cleanup and infrastructure activities under the responsibility of the US Department of Energy, Office of Environmental Management. This Specification describes at a top level the activities, facilities, and infrastructure necessary to accomplish the cleanup of the Hanford Site and assigns this scope to Site contractors and their respective projects. This Specification also references the key National Environmental Policy Act of 1969 (NEPA), Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), and safety documentation necessary to accurately describe the cleanup at a summary level. The information contained in this document reflects RL's application of values, priorities, and critical success factors expressed by those involved with and affected by the Hanford Site project. The prime contractors and their projects develop complete baselines and work plans to implement this Specification. These lower-level documents and the data that support them, together with this Specification, represent the full set of requirements applicable to the contractors and their projects. Figure 1-1 shows the relationship of this Specification to the other basic Site documents. Similarly, the documents, orders, and laws referenced in this specification represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents

  17. Hanford Site environmental management specification

    Energy Technology Data Exchange (ETDEWEB)

    Grygiel, M.L.

    1998-06-10

    The US Department of Energy, Richland Operations Office (RL) uses this Hanford Site Environmental Management Specification (Specification) to document top-level mission requirements and planning assumptions for the prime contractors involved in Hanford Site cleanup and infrastructure activities under the responsibility of the US Department of Energy, Office of Environmental Management. This Specification describes at a top level the activities, facilities, and infrastructure necessary to accomplish the cleanup of the Hanford Site and assigns this scope to Site contractors and their respective projects. This Specification also references the key National Environmental Policy Act of 1969 (NEPA), Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), and safety documentation necessary to accurately describe the cleanup at a summary level. The information contained in this document reflects RL`s application of values, priorities, and critical success factors expressed by those involved with and affected by the Hanford Site project. The prime contractors and their projects develop complete baselines and work plans to implement this Specification. These lower-level documents and the data that support them, together with this Specification, represent the full set of requirements applicable to the contractors and their projects. Figure 1-1 shows the relationship of this Specification to the other basic Site documents. Similarly, the documents, orders, and laws referenced in this specification represent only the most salient sources of requirements. Current and contractual reference data contain a complete set of source documents.

  18. 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

  19. 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

  20. 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

  1. 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.

  2. TECHNICAL RISK RATING OF DOE ENVIRONMENTAL PROJECTS - 9153

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. 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

  8. Technical guidelines for environmental dredging of contaminated sediments

    Science.gov (United States)

    2008-09-01

    This report provides technical guidelines for evaluating : environmental dredging as a sediment remedy component. This document : supports the Contaminated Sediment Remediation Guidance for : Hazardous Waste Sites, released by the U.S. Environmental ...

  9. 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

  10. Shale oil and gas: technical and environmental files

    International Nuclear Information System (INIS)

    Schilansky, Jean-Louis; Quehen, Audrey; Appert, Olivier; Aurengo, Andre; Candel, Sebastien; Chanin, Marie-Lise; Geoffron, Patrice; Goffe, Bruno; Marsily, Ghislain de; Pouzet, Andre; Schnapper, Dominique; Tardieu, Bernard

    2016-01-01

    This publication proposes information regarding technical and environmental issues related to shale oil and gas extraction and exploitation. It addresses various topics: hydraulic fracturing (techniques, quantity assessment, regulation), water consumption and management (problematic, quantity assessment, regulation), additives and management of production fluids (a necessary taking into account, quantity assessment, regulation), surface aquifers (surface sheets and exploration activity, quantity assessment, regulation), activity footprint (ground footprint and impact on landscape, quantity assessment, regulation), end of activity and site future (return to the initial condition, quantity assessment, regulation), seismicity (manageable seismic risks, quantity assessment, regulations), greenhouse gas emissions (development, quantity assessment, regulation), issues related to health aspects (general and specific risks, epidemiological studies)

  11. 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)

  12. Environmental Aspects of the Engineering Training at Technical University

    Directory of Open Access Journals (Sweden)

    V. V. Bushueva

    2015-01-01

    Full Text Available Problem relevance. The article gives a justification for a need to train professionally competent, ecologically oriented engineers capable to create new equipment taking into account the ecological characteristics. Such approach expresses a requirement coherence to develop technical systems and technologies taking into account, both technical reliability and human and environmental safety. Today, in conditions of modern industrial production it is an important point in engineer’s activity. So to train future engineers who meet these requirements new forms and methods are to be found.Objectives. To prove that involvement of creative student’s teams in training the future ecologically oriented engineers is of importance. The organisational structure and methods of activities along with the principles of revitalizing search for engineering ideas and solutions to develop environmentally safe technical systems and technologies allow us to solve more complicated problems. This is the important characteristic in activities of creative groups. The article considers a significance of the future engineer’s responsibility in terms of environment safety. It gives "Methodical advices to analyse the operational impacts of technical systems on the human and environment" to show that there is a need in development of reliable and environment-safe technical systems.Novelty of this work is a technique for the organization and forms of student creative team’s activities. It represents a revised and updated option of a technique of the creative teams working at the industrial enterprises in France. The revised technique takes into consideration both the specifics of student's audience at technical university and the environment-oriented tasks to be solved. Efficiency of search and solution of environment-oriented engineering tasks is enhanced owing to use of revitalizing methods for the creative team’s activities, which are widely used today in student

  13. Electric cars: technical characteristics and environmental impacts

    Energy Technology Data Exchange (ETDEWEB)

    Helmers, Eckard; Marx, Patrick [Trier University of Applied Sciences, Birkenfeld (Germany). Institut fuer Angewandtes Stoffstrommanagement (IfaS)

    2012-12-15

    Electric vehicles have been identified as being a key technology in reducing future emissions and energy consumption in the mobility sector. The focus of this article is to review and assess the energy efficiency and the environmental impact of battery electric cars (BEV), which is the only technical alternative on the market available today to vehicles with internal combustion engine (ICEV). Electricity onboard a car can be provided either by a battery or a fuel cell (FCV). The technical structure of BEV is described, clarifying that it is relatively simple compared to ICEV. Following that, ICEV can be 'e-converted' by experienced personnel. Such an e-conversion project generated reality-close data reported here. Practicability of today's BEV is discussed, revealing that particularly small-size BEVs are useful. This article reports on an e-conversion of a used Smart. Measurements on this car, prior and after conversion, confirmed a fourfold energy efficiency advantage of BEV over ICEV, as supposed in literature. Preliminary energy efficiency data of FCV are reviewed being only slightly lower compared to BEV. However, well-to-wheel efficiency suffers from 47% to 63% energy loss during hydrogen production. With respect to energy efficiency, BEVs are found to represent the only alternative to ICEV. This, however, is only true if the electricity is provided by very efficient power plants or better by renewable energy production. Literature data on energy consumption and greenhouse gas (GHG) emission by ICEV compared to BEV suffer from a 25% underestimation of ICEV-standardized driving cycle numbers in relation to street conditions so far. Literature data available for BEV, on the other hand, were mostly modeled and based on relatively heavy BEV as well as driving conditions, which do not represent the most useful field of BEV operation. Literature data have been compared with measurements based on the converted Smart, revealing a distinct GHG emissions

  14. 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

  15. 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.

  16. Environmental restoration and remediation technical data management plan

    International Nuclear Information System (INIS)

    Key, K.T.; Fox, R.D.

    1994-02-01

    The tasks performed in the Remedial Investigation/Feasibility Study (RI/FS) work plan for each Hanford Site operable unit must meet the requirements of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) and the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al 1992). An extensive amount of data will be generated in the evaluation and remediation of hazardous waste sites at the Site. The data must be of sufficient quality, as they will be used to evaluate the need, select the method(s), and support the full remediation of the waste sites as stipulated in the Tri-Party Agreement. In particular, a data management plan (DMP) is to be included in an RI/FS work plan for managing the technical data obtained during the characterization of an operable unit, as well as other data related to the study of the operable unit. Resource Conservation and Recovery Act of 1976 (RCRA) sites are involved in the operable unit. Thus, the data management activities for the operable unit should be applied consistently to RCRA sites in the operable unit as well. This DMP provides common direction for managing-the environmental technical data of all defined operable units at the Hanford Site during the RI/FS activities. Details specific to an operable unit will be included in the actual work plan of that operable unit

  17. 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

  18. K Basins environmental impact statement technical input document

    International Nuclear Information System (INIS)

    Bergsman, K.H.; Bergmann, D.W.; Costley, G.E.; Jansky, M.T.; McCormack, R.L.; Monthey, M.J.; Praga, A.N.; Ullah, J.K.; Willis, W.L.

    1995-10-01

    This document describes the technical input necessary to develop and evaluate the alternatives within the Environmental Impact Statement for the Management of Spent Nuclear Fuel From the K Basins at the Hanford Site

  19. 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

  20. Directed Technical Change and Economic Growth Effects of Environmental Policy

    DEFF Research Database (Denmark)

    Kruse-Andersen, Peter Kjær

    2016-01-01

    A Schumpeterian growth model is developed to investigate how environmental policy affects economic growth when environmental policy also affects the direction of technical change. In contrast to previous models, production and pollution abatement technologies are embodied in separate intermediate...... unambiguously directs research efforts toward pollution abatement technologies and away from production technologies. This directed technical change reduces economic growth and pollution emission growth. Simulation results indicate that even large environmental policy reforms have small economic growth effects....... However, these economic growth effects have relatively large welfare effects which suggest that static models and exogenous growth models leave out an important welfare effect of environmental policy....

  1. Environmental macroeconomics : Environmental policy, business cycles, and directed technical change

    NARCIS (Netherlands)

    Fischer, Carolyn; Heutel, Garth

    Environmental economics has traditionally fallen in the domain of microeconomics, but approaches from macroeconomics have recently been applied to studying environmental policy. We focus on two macroeconomic tools and their application to environmental economics. First, real-business-cycle models

  2. The Office of Environmental Management technical reports: A bibliography

    International Nuclear Information System (INIS)

    1996-01-01

    The Office of Environmental Management's (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1994 through June 30, 1995. This information is divided into the following categories: Focus Areas, Cross-Cutting Programs, and Support Programs. In addition, a category for general information is included. EM's Office of Science and Technology sponsors this bibliography

  3. 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

  4. Analysis of general specifications for nuclear facilities environmental monitoring vehicles

    International Nuclear Information System (INIS)

    Xu Xiaowei

    2014-01-01

    At present, with the nuclear energy more increasingly extensive application, the continuous stable radiation monitoring has become the focus of the public attention. The main purpose of the environmental monitoring vehicle for the continuous monitoring of the environmental radiation dose rate and the radionuclides concentration in the medium around nuclear facilities is that the environmental radiation level and the radioactive nuclides activity in the environment medium are measured. The radioactive pollution levels, the scope contaminated and the trends of the pollution accumulation are found out. The change trends for the pollution are observed and the monitoring results are explained. The domestic demand of the environmental monitoring for the nuclear facilities is shown in this report. The changes and demands of the routine environmental monitoring and the nuclear emergency monitoring are researched. The revision opinions for EJ/T 981-1995 General specifications for nuclear facilities environmental monitoring vehicles are put forward. The purpose is to regulate domestic environmental monitoring vehicle technical criterion. The criterion makes it better able to adapt and serve the environmental monitoring for nuclear facilities. The technical guarantee is provided for the environmental monitoring of the nuclear facilities. (authors)

  5. 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.

  6. 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

  7. 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

  8. 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

  9. Environmental licensing of nuclear facilities: compatibility of technical competencies

    International Nuclear Information System (INIS)

    Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

    1996-01-01

    The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.)

  15. Environmental Measurements Laboratory fiscal year 1998: Accomplishments and technical activities

    Energy Technology Data Exchange (ETDEWEB)

    Erickson, M.D.

    1999-01-01

    The Environmental Measurements Laboratory (EML) is government-owned, government-operated, and programmatically under the DOE Office of Environmental Management. The Laboratory is administered by the Chicago Operations Office. EML provides program management, technical assistance and data quality assurance for measurements of radiation and radioactivity relating to environmental restoration, global nuclear nonproliferation, and other priority issues for the Department of Energy, as well as for other government, national, and international organizations. This report presents the technical activities and accomplishments of EML for Fiscal Year 1998.

  16. 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

  17. 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

  18. 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

  19. 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

  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/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

  1. Environmental data quality problems: ''Technical'' vs. ''legal'' defensibility

    International Nuclear Information System (INIS)

    Luker, R.S.; Brooks, M.C.; Stagg, D.D.

    1995-01-01

    Two significant aspects of environmental data quality are currently being emphasized throughout the industry as critical precursors to environmental decision making: technical integrity and legal defensibility. Because audit findings and consequent perceptions by a client often pose more questions than answers--especially with respect to the ''systemic'' nature and significance of problems based on nonstatistical, ad hoc sampling of large programs--quality assurance in environmental restoration must do more than implement traditional administrative controls. A major problem persists in achieving a consensus opinion between quality assurance and technical staff on the significance of various data problems. This case study compares and contrasts ''technical integrity'' and ''legal defensibility'', and provides performance measures developed to optimize both components in a large, complex DOE environmental restoration program. Performance measures of both administrative and technical processes are being used to ensure that conclusions drawn concerning ''systematic'' problems are not premature, and are founded on thorough, representative aspects of the program. Improved methods to reach consensus opinions on environmental decision-making are imperative and environmental data quality, the cornerstone on which the decisions are built, must be not only scientifically solid, but perceived as solid, if stakeholders are to be satisfied

  2. Significance of technical rules for environmental pollution control

    International Nuclear Information System (INIS)

    Grefen, K.

    1989-01-01

    Technical rules for environmental pollution control are very important in times of intensified technical progress and especially in view of the alterations of the legislative basis of the European Market in 1992. In the fields of jurisprudence, science and technology they serve as a decision-making aid for authorities, specialists in plant development and operation and the preparatory stages of international legislation. The topic is explained by the development of guidelines with the VDI-Commission on Air Pollution Prevention. (orig.) [de

  3. 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

  4. The Office of Environmental Management technical reports: a bibliography

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Office of Environmental Management`s (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1995 through Sept. 30, 1996. This information is divided into the following categories: Focus Areas and Crosscutting Programs. Support Programs, Technology Integration and International Technology Exchange are now included in the General category. EM`s Office of Science and Technology sponsors this bibliography.

  5. The Office of Environmental Management technical reports: a bibliography

    International Nuclear Information System (INIS)

    1997-07-01

    The Office of Environmental Management''s (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1995 through Sept. 30, 1996. This information is divided into the following categories: Focus Areas and Crosscutting Programs. Support Programs, Technology Integration and International Technology Exchange are now included in the General category. EM''s Office of Science and Technology sponsors this bibliography

  6. 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

  7. 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)

  8. The Office of Environmental Management technical reports: A bibliography

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    The Office of Environmental Management`s (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1995--that were published from October 1, 1996--September 30, 1997. This information is divided into the following categories: Miscellaneous, Focus Areas and Crosscutting Programs, Support Programs, Technology Integration and International Technology Exchange, are now included in the Miscellaneous category. The Office of Environmental Management within the Department of Energy (DOE) is responsible for environmental restoration, waste management, technology development and facility transition and management. Subjects include: subsurface contaminants; mixed waste characterization, treatment and disposal; radioactive tank waste remediation; plutonium; deactivation and decommissioning; robotics; characterization, monitoring, and sensor technology; and efficient separations. 880 refs.

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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.

  14. Environmental Research Division technical progress report: January 1986--October 1987

    International Nuclear Information System (INIS)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases

  15. Environmental Research Division technical progress report, January 1984-December 1985

    International Nuclear Information System (INIS)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter

  16. Environmental Research Division technical progress report, January 1984-December 1985

    Energy Technology Data Exchange (ETDEWEB)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter.

  17. Environmental Research Division technical progress report: January 1986--October 1987

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases.

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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.

  4. 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)

  5. 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.)

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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

  11. In situ leaching of uranium: Technical, environmental and economic aspects

    International Nuclear Information System (INIS)

    1989-01-01

    Within the framework of its activities in nuclear raw materials the International Atomic Energy Agency has convened a series of meetings to discuss various aspects of uranium ore processing technology, recovery of uranium from non-conventional resources and development of projects for the production of uranium concentrates including economic aspects. As part of this continuing effort to discuss and document important aspects of uranium production the IAEA convened a Technical Committee Meeting on Technical, Economic and Environmental Aspects of In-Situ Leaching. Although the use of this technique is limited by geological and economic constraints, it has a significant potential to produce uranium at competitive prices. This is especially important in the current uranium market which is mainly characterised by large inventories, excess production capability and low prices. This situation is not expected to last indefinitely but it is unlikely to change drastically in the next ten years or so. This Technical Committee Meeting was held in Vienna from 3 to 6 November 1987 with the attendance of 24 participants from 12 countries. Eight papers were presented. Technical sessions covered in-situ mining research, environmental and licensing aspects and restoration of leached orebodies; the technological status of in-situ leaching, the current status and future prospects of in-situ leaching of uranium in Member States, general aspects of planning and implementation of in-situ projects and the economics of in-situ leaching. Refs, figs and tabs

  12. Pipeline abandonment - a discussion paper on technical and environmental issues

    International Nuclear Information System (INIS)

    1996-11-01

    The technical and environmental issues associated with pipeline abandonment were reviewed to provide a basis for the development of guidelines that companies could follow in order to abandon oil and gas pipelines in an environmentally safe and economic manner. Some of the topics discussed include land use management, ground subsidence, soil and groundwater contamination, erosion and the potential to create water conduits. A major issue still to be resolved, i.e., the legal and financial aspects of pipeline abandonment, was addressed. An industry-financed fund has been created to cover the cost of reclamation and abandonment of orphaned pipelines and certain associated pipeline facilities. 30 refs., 4 tabs., 3 figs

  13. 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

  14. 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

  15. Technical Guidelines for Environmental Dredging of Contaminated Sediments

    Science.gov (United States)

    2008-09-01

    material from barges to adjacent rehandling facilities or to move material relatively short distances. Conveyors can also be used to transfer ...by direct dumping or unloading into a chute or conveyor . Truck transport of treated material to landfills may also be considered. The material...environmental dredging for purposes of a feasibility study, remedial design , and implementation. The scope of this document is limited to the technical

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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)

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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...

  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. Sandia Laboratories technical capabilities. Auxiliary capabilities: environmental health information science

    International Nuclear Information System (INIS)

    1975-09-01

    Sandia Laboratories is an engineering laboratory in which research, development, testing, and evaluation capabilities are integrated by program management for the generation of advanced designs. In fulfilling its primary responsibility to ERDA, Sandia Laboratories has acquired extensive research and development capabilities. The purpose of this series of documents is to catalog the many technical capabilities of the Laboratories. After the listing of capabilities, supporting information is provided in the form of highlights, which show applications. This document deals with auxiliary capabilities, in particular, environmental health and information science. (11 figures, 1 table) (RWR)

  9. 78 FR 39284 - Technical Guidance for Assessing Environmental Justice in Regulatory Analysis

    Science.gov (United States)

    2013-07-01

    ... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-OA-2013-0320; FRL-9830-1] Technical Guidance for Assessing Environmental Justice in Regulatory Analysis AGENCY: Environmental Protection Agency (EPA). ACTION: Notice... Environmental Protection Agency (EPA) issued for public comment a document entitled, ``Technical Guidance for...

  10. The Environmental Trilogy project: Balancing technical, institutional, and cultural perspectives to environmental management

    International Nuclear Information System (INIS)

    Kurstedt, Pamela S.; Jim, Russell; Wadsworth, Bonnie C.W.; Burke, William H.; Kurstedt, Harold A. Jr.

    1992-01-01

    'The significant problems we face cannot be solved at the same level of thinking we were at when we created them.' Albert Einstein. I've identified an initial set of three perspectives important to building an integrated, comprehensive approach to managing the environment - technical, institutional, and cultural. I've constructed an holistic model (called the Environmental Trilogy) for environmental management, encompassing at least these three perspectives and their interrelationships. In this paper, I outline the model and report the results of a working session facilitated at Virginia Tech in Blacksburg, Virginia, in October 1991, involving three representatives from each of the technical, institutional, and cultural perspectives. The institutional members of this group were people who understand institutional effects, rather than those who represent institutions. The working group discussed and analyzed the technical-institutional, technical-cultural, and institutional-cultural inter- relationships of the environmental trilogy. The goals of the working group were to put structure on the environmental trilogy model, to facilitate the definition of variables, and explore relationships between and among variables. The working group members are to continue studying issues and components, perspectives, connections, and cause-and-effect in the models and report back to interested parties. The outcome is projected to be a more holistic, integrated view of the environment. (author)

  11. 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

  12. 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.

  13. 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...

  14. 78 FR 27235 - Technical Guidance for Assessing Environmental Justice in Regulatory Analysis

    Science.gov (United States)

    2013-05-09

    ... Justice in Regulatory Analysis.'' The purpose of this guidance is to provide EPA analysts with technical...-566-2363. Mail: Technical Guidance for Assessing Environmental Justice in Regulatory Analysis... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-OA-2013-0320; FRL-9810-5] Technical Guidance for Assessing...

  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. 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.

  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. Recommended environmental dose calculation methods and Hanford-specific parameters

    International Nuclear Information System (INIS)

    Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V.; Davis, J.S.

    1993-03-01

    This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document

  20. Recommended environmental dose calculation methods and Hanford-specific parameters

    Energy Technology Data Exchange (ETDEWEB)

    Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V. (Pacific Northwest Lab., Richland, WA (United States)); Davis, J.S. (Westinghouse Hanford Co., Richland, WA (United States))

    1993-03-01

    This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document.

  1. 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...

  2. Environmental State and Trends at Technical University of Denmark

    DEFF Research Database (Denmark)

    Gabriel, Søren; Nørgaard, Jørgen

    1998-01-01

    The paper is part of the ECCOCAMPUS-project. It first describes some students projects investigating energy consumption patterns, etc. The main part of the paper illustrates by tables and graphs the energy and environmental situation at the Technical University of Denmark, such as the consumption...... of electricity, heat, and water, as well as the waste production. These data are provided for the period from 1980-1995, and normalized by floor space, number of students, number of employes and by annual budget. These data indicate a significant growth in the energy consumption, especially marked per capita......, because the number of students has declined by 25%. Finally are very briefly outlined, how the University Administration is now giving higher priority to saving electricity....

  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. New strategies for designing inexpensive but selective bioadsorbants for environmental pollutants: Selection of specific ligands and their cell surface expression. Technical progress report, September 15, 1996 -September 14, 1997

    International Nuclear Information System (INIS)

    Iverson, B.

    1997-01-01

    'Progress for the last twelve months has revolved around setting up an antibody engineering and surface display system for use with a metal-complex binding antibody. (1) The author has isolated genes for the V regions of the heavy and light chains for the Ru(bpy)3 specific monoclonal AC1106 (Shreder, K S., Hariman, A., and Iverson, B.L., J. Am. Chem. Soc. 1996, 118, 3192-3201). This antibody binds Ru(bpy), derivatives with better than nanomolar affinity, and will serve as the generic metal-complex binding pocket. Cloning antibody genes from hybridomas is complicated by the fact that primers must be found that amplify the particular heavy and light chain genes in the hybridoma of interest. Antibody gene amplification primers are generally designed to amplify antibody repertoires from lymphocyte mRNA isolated from animals. While cloning repertoires from animals is routinely successful due to the diverse population of target m RNA, hybridomas have a single target sequence. Therefore, multiple primers and conditions must be tried before the correct primer combination is identified.'

  7. 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)

  8. A technical and environmental comparison between hydrogen and some fossil fuels

    International Nuclear Information System (INIS)

    Nicoletti, Giovanni; Arcuri, Natale; Nicoletti, Gerardo; Bruno, Roberto

    2015-01-01

    Highlights: • Hydrogen as new non-conventional energy system. • Technical and environmental comparison between different type of fuels. • Combustion products analysis. • Technical and environmental quality indexes for investigated fuels. • Proposal of a suitable new energy scenario supplied by hydrogen. - Abstract: The exploitation of some fossil fuels such as oil, intended as gasoline or diesel fuel, natural gas and coal, currently satisfy the majority of the growing world energy demand, but they are destined to run out relatively quickly. Beyond this point, their combustion products are the main cause of some global problems such as the greenhouse effect, the hole in the ozone layer, acid rains and generalized environment pollution, so their impact is extremely harmful. Therefore, it is clear that a solution to the energy problem can be obtained only through the use of renewable sources and by means of the exploitation of new low-polluting fuels. In this scenario an important role might be played by hydrogen, which is able to define a new energy system that is more sustainable and cleaner than current systems. For the comparison of the different fuels investigated in this paper, a methodology, which defines appropriate technical and environmental quality indexes, has been developed. These indexes are connected to the pollution produced by combustion reactions and to their intrinsic characteristics of flammability and expansiveness linked to the use of the considered fuels. An appropriate combination of these indexes, in the specific sector of utilization, allows to evaluate a global environmental index for the investigated fuels, highlighting that hydrogen reaches the highest score. In the final part of the paper, a new hydrogen energy economy that would lead to solving the serious environmental problems that damages all the ecosystems of the planet earth, is presented

  9. 324 and 327 Facilities Environmental Effluent Specifications

    International Nuclear Information System (INIS)

    JOHNSON, D.L.

    1999-01-01

    These effluent specifications address requirements for the 324/321 Facilities, which are undergoing stabilization activities. Effluent specifications are imposed to protect personnel, the environment and the public, by ensuring adequate implementation and compliance with federal and state regulatory requirements and Hanford programs

  10. 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

  11. 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…

  12. 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...

  13. Technical efficiency under alternative environmental regulatory regimes: The case of Dutch horticulture

    International Nuclear Information System (INIS)

    Van der Vlist, Arno J.; Withagen, Cees; Folmer, Henk

    2007-01-01

    We consider the performance of small and medium sized enterprises in Dutch horticulture under different environmental policy regimes across time. We address the question whether technical performance differs under these alternative regulatory regimes to test Porter's hypothesis that stricter environmental regulation reduces technical inefficiency. For this purpose, we use a stochastic production frontier framework allowing for inclusion of policy variables to measure the effect of alternative environmental policy regimes on firms' performance. The main result is that stricter environmental policy regimes have indeed reduced technical inefficiencies in Dutch horticulture. The estimation results indicate amongst others that the 1997 agreement on energy, nutrient and pesticides use enhances technical efficiency. Firms under the strict environmental policy regime are found to be more technically efficient than those under a lax regime, thereby supporting the claims by Porter and Van der Linde (Porter, M., Van der Linde, C., 1995. Green and Competitive: Ending the stalemate. Harvard Business Review 73, pp. 120-137) concerning Dutch horticulture. (author)

  14. 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

  15. 77 FR 22772 - Environmental Management Site-Specific Advisory Board

    Science.gov (United States)

    2012-04-17

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board AGENCY: Office of Environmental Management, Department of Energy. ACTION: Notice of renewal. SUMMARY: Pursuant to Section 14(a)(2... Secretariat, General Services Administration, notice is hereby given that the Environmental Management Site...

  16. 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

  17. Creating an Overall Environmental Quality Index - Technical Report

    Science.gov (United States)

    A better estimate of overall environmental quality is needed to improve our understanding of the relationship between environmental conditions and humanhealth. Described in this report is the effort to construct an environmental quality index representing multiple domains of the ...

  18. The Environmental Kuznets Curve: Exploring a Fresh Specification

    OpenAIRE

    David Bradford; Rebecca Schlieckert; Stephen H. Shore

    2000-01-01

    Using a new specification, we reanalyze the data on worldwide environmental quality investigated by Gene Grossman and Alan Krueger in a well-known paper on the environmental Kuznets curve (which postulates an inverse U shaped relationship between income level and pollution). The new specification enables us to draw conclusions from fixed effects estimation. In general, we find support for the environmental Kuznets curve for some pollutants and for its rejection in other cases. The fresh speci...

  19. 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

  20. 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)

  1. 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...

  2. 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

  3. Impact of Environmental Regulation and Technical Progress on Industrial Carbon Productivity: An Approach Based on Proxy Measure

    Directory of Open Access Journals (Sweden)

    Huan Zhang

    2016-08-01

    Full Text Available This research aims to study the main influencing factors of China’s industrial carbon productivity by incorporating environmental regulation and technical progress into an econometric model. The paper focuses on data from 35 of China’s industrial sectors and covers the period from 2006 to 2014, in order to examine the impact of environmental regulation and technical progress on carbon productivity. Methods applied include panel fixed effect model, panel random effect model and two stage least squares with instrumental variables (IV-2SLS. The effect of environmental regulation and technical progress has industrial heterogeneity. The paper subdivides industrial sectors into capital and technology intensive, resource intensive and labor intensive sectors according to factor intensiveness. The estimation results of the subgroups have uncovered that for capital and technology intensive and resource intensive sectors, environmental regulation has a more significant impact than technical progress; while for labor intensive sectors, innovation more significantly influences carbon productivity. In addition, foreign direct investment (FDI and industrialization level facilitate improving carbon productivity for the full sample. By contrast, industrial structure inhibits the overall industrial carbon productivity. The industry-specific results indicate that for capital and technology intensive sectors, optimizing of the industrial structure can improve carbon productivity; for resource intensive sectors, FDI and energy consumption structure should be emphasized more; for labor intensive sectors, industrialization levels help enhance carbon productivity. Finally the industrial sector-specific policy suggestions are proposed.

  4. 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)

  5. 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

  6. 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

  7. THE RELATIONSHIP BETWEEN TECHNICAL AND SOCIAL NORMS IN ENVIRONMENTAL PROJECT

    OpenAIRE

    Jasminka Lažnjak

    1992-01-01

    In the article the relationship between system of technical and system of social norms in ecological project has been considered from constructivist standpoint in sociology of technology. For adequate solution of technological problem of enviromental pollution by hydrocarbons is necessary to define beside technical also system of social norms. Sociological analysis of accidents in transportation of hydrocarbons is suggested in purpose of clear definition of responsibilities of certain social ...

  8. 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

  9. 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)

  10. Technical efficiency under alternative environmental regulatory regimes : the case of Dutch horticulture

    NARCIS (Netherlands)

    Vlist, van der A.J.; Withagen, C.A.A.M.; Folmer, H.

    2007-01-01

    We consider the performance of small and medium sized enterprises in Dutch horticulture under different environmental policy regimes across time. We address the question whether technical performance differs under these alternative regulatory regimes to test Porter's hypothesis that stricter

  11. Technical Review Guidelines for Environmental Impact Assessments in the Tourism, Energy and Mining Sectors

    Science.gov (United States)

    EPA coordinated a regional collaborative process with Central America and Dominican Republic Free Trade Agreement (CAFTA-DR) partners to develop Environmental Impact Assessment (EIA) Technical Review Guidelines for three sectors.

  12. 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

  13. 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

  14. 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

  15. THE RELATIONSHIP BETWEEN TECHNICAL AND SOCIAL NORMS IN ENVIRONMENTAL PROJECT

    Directory of Open Access Journals (Sweden)

    Jasminka Lažnjak

    1992-12-01

    Full Text Available In the article the relationship between system of technical and system of social norms in ecological project has been considered from constructivist standpoint in sociology of technology. For adequate solution of technological problem of enviromental pollution by hydrocarbons is necessary to define beside technical also system of social norms. Sociological analysis of accidents in transportation of hydrocarbons is suggested in purpose of clear definition of responsibilities of certain social actors and for modification of existing laws for enviromental protection (the paper is published in Croatian.

  16. Technical progress of nuclear energy: economic and environmental prospects

    International Nuclear Information System (INIS)

    Naudet, G.

    1994-01-01

    This document deals with three different aspects of the nuclear energy: first the operating and economic performances of nuclear power plants in the world, the French nuclear competitiveness. Then, the technical and economic perspectives about reactors and fuels cycle and the advantages towards atmospheric pollution are discussed to favour a new worldwide nuclear development. (TEC). 8 refs., 4 figs., 6 tabs

  17. 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

  18. A Technical, Economic, and Environmental Performance of Grid-Connected Hybrid (Photovoltaic-Wind) Power System in Algeria

    OpenAIRE

    Saheb-Koussa, Djohra; Koussa, Mustapha; Said, Nourredine

    2013-01-01

    This paper studies the technical, economic, and environmental analysis of wind and photovoltaic power systems connected to a conventional grid. The main interest in such systems is on-site consumption of the produced energy, system hybridization, pooling of resources, and contribution to the environment protection. To ensure a better management of system energy, models have been used for determining the power that the constituting subsystems can deliver under specific weather conditions. Simu...

  19. Information management architecture for an integrated computing environment for the Environmental Restoration Program. Environmental Restoration Program, Volume 3, Interim technical architecture

    International Nuclear Information System (INIS)

    1994-09-01

    This third volume of the Information Management Architecture for an Integrated Computing Environment for the Environmental Restoration Program--the Interim Technical Architecture (TA) (referred to throughout the remainder of this document as the ER TA)--represents a key milestone in establishing a coordinated information management environment in which information initiatives can be pursued with the confidence that redundancy and inconsistencies will be held to a minimum. This architecture is intended to be used as a reference by anyone whose responsibilities include the acquisition or development of information technology for use by the ER Program. The interim ER TA provides technical guidance at three levels. At the highest level, the technical architecture provides an overall computing philosophy or direction. At this level, the guidance does not address specific technologies or products but addresses more general concepts, such as the use of open systems, modular architectures, graphical user interfaces, and architecture-based development. At the next level, the technical architecture provides specific information technology recommendations regarding a wide variety of specific technologies. These technologies include computing hardware, operating systems, communications software, database management software, application development software, and personal productivity software, among others. These recommendations range from the adoption of specific industry or Martin Marietta Energy Systems, Inc. (Energy Systems) standards to the specification of individual products. At the third level, the architecture provides guidance regarding implementation strategies for the recommended technologies that can be applied to individual projects and to the ER Program as a whole

  20. ANL Technical Support Program for DOE Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J.; Bourcier, W.L.; Morgan, L.E.; Nielsen, J.K.; Steward, S.A.; Ewing, R.C.; Wang, L.M.; Han, W.T.; Tomozawa, M.

    1992-03-01

    This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal

  1. Environmental management system for transportation maintenance operations : [technical brief].

    Science.gov (United States)

    2014-04-01

    This report provides the framework for the environmental management system to analyze : greenhouse gas emissions from transportation maintenance operations. The system enables user : to compare different scenarios and make informed decisions to minim...

  2. 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

  3. 78 FR 33416 - Notification of a Public Meeting of the Science Advisory Board Environmental Justice Technical...

    Science.gov (United States)

    2013-06-04

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL--9819-3] Notification of a Public Meeting of the Science... Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces a public meeting of the SAB Environmental Justice Technical Guidance Review Panel to provide advice through...

  4. 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

  5. Technical evaluation of WIPP by the New Mexico environmental evaluation group

    International Nuclear Information System (INIS)

    Neill, R.

    1988-01-01

    The Waste Isolation Pilot Plant (WIPP) is a repository under construction in southeastern New Mexico for the disposal of 14.1 million curies of defense transuranic (TRU) waste. The US Department of Energy (DOE) plans to start storing waste in the underground facility in October 1988 for a 5-yr research and demonstration period. Since the State of New Mexico had a number of concerns in 1978 regarding the impact on health and safety of the proposed WIPP facility for disposal of radioactive waste, the DOE agreed to fund an independent technical review and evaluation of the planned repository, resulting in the creation of the Environmental Evaluation Group (EEG). This full-time multidisciplinary group has published 39 major reports to date, testified before the New Mexico Legislature and the US Congress, and has disseminated the results of analyses to DOE, the governor, the legislature, the Congress, the scientific community, and the general public. While the disposal of radioactive defense mill tailings and defense high-level wastes are both subject to US Nuclear Regulatory Commission (NRC) licensing, Congress specifically chose not to have defense TRU waste disposal licensed by the NRC. This has placed a heavy burden on EEG as the only full-time technical review agency on WIPP, but without regulatory authority

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. Northeast Regional environmental impact study: Waste disposal technical report

    Science.gov (United States)

    Saguinsin, J. L. S.

    1981-04-01

    The potential for cumulative and interactive environmental impacts associated with the conversion of multiple generating stations in the Northeast is assessed. The estimated quantities and composition of wastes resulting from coal conversion, including ash and SO2 scrubber sludge, are presented. Regulations governing the use of ash and scrubber sludge are identified. Currently available waste disposal schemes are described. The location, capacity, and projected life of present and potential disposal sites in the region are identified. Waste disposal problems, both hazardous and nonhazardous, are evaluated. Environmental regulations within the region as they pertain to coal conversion and as they affect the choice of conversion alternatives are discussed. A regional waste management strategy for solid waste disposal is developed.

  12. The Hanford Environmental Dose Reconstruction (HEDR) Project: Technical approach

    International Nuclear Information System (INIS)

    Napier, B.A.; Freshley, M.D.; Gilbert, R.O.; Haerer, H.A.; Morgan, L.G.; Rhoads, R.E.; Woodruff, R.K.

    1990-01-01

    Historical measurements and current assessment techniques are being combined to estimate potential radiation doses to people from radioactive releases to the air, the Columbia River, soils, and ground water at the Hanford Site since 1944. Environmental contamination from these releases has been monitored, at varying levels of detail, for 45 yr. Phase I of the Hanford Environmental Reconstruction Project will estimate the magnitude of potential doses, their areal extends, and their associated uncertainties. The Phase I study area comprises 10 counties in eastern Washington and northern Oregon, within a 100-mi radius of the site, including a stretch of the Columbia River that was most significantly affected. These counties contain a range of projected and measured contaminant levels, environmental exposure pathways, and population groups. Phase I dose estimates are being developed for the periods 1944 through 1947 for air pathways and 1964 through 1966 for river pathways. Important radionuclide/pathway combinations include fission products, such as 131 I, in milk for early atmospheric releases and activation products, such as 32 P and 65 Zn, in fish for releases to the river. Potential doses range over several orders of magnitude within the study area. We will expand the time periods and study are in three successive phases, as warranted by results of Phase I

  13. 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

  14. Technical and environmental analysis of biofuel dryers; Teknisk och miljoemaessig analys av biobraensletorkar

    Energy Technology Data Exchange (ETDEWEB)

    Muenter, M; Hagman, U; Harnevie, H; Johansen, H; Kristensson, I; Westermark, M; Viberg, T [Vattenfall Energimarknad, Stockholm (Sweden)

    1999-03-01

    A study regarding technology and environmental impact of the drying process of biofuels has been conducted. In the study two different types of dryers are analyzed. The result from the study shows that emissions of primarily hydrocarbons is high from the direct technic. The emission can be decreased considerably by improving the burner of the dryer. For the indirect technic the evaporated water give rise to problems in the sewage treatment plant. Studies show that biological treatment will result in an acceptable condensate.

  15. 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

  16. 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

  17. 76 FR 50204 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2011-08-12

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY...-Wide Environmental Impact Statement (EIS) Committee of the Environmental Management Site- Specific... management in the areas of environmental restoration, waste management, and related activities. Purpose of...

  18. 76 FR 55370 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2011-09-07

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY...-Wide Environmental Impact Statement (EIS) Committee of the Environmental Management Site- Specific... the areas of environmental restoration, waste management, and related activities. Purpose of the...

  19. 78 FR 68101 - Environmental Issues Associated With New Reactors and Specific Environmental Guidance for...

    Science.gov (United States)

    2013-11-13

    ... New Reactors and Specific Environmental Guidance for Integral Pressurized Water Reactors Reviews... Environmental Issues Associated with New Reactors'' and draft ISG ESP/ COL-ISG-027, ``Interim Staff Guidance on...://www.regulations.gov and search for Docket ID NRC-2013-0212 for ESP/COL- ISG-026 or NRC-2013-0211 for...

  20. Economic evaluation of technical, environmental and institutional barriers on biomass residue collection cost in California

    International Nuclear Information System (INIS)

    Sethi, P.; Tiangco, V.; Dee, V.; Simons, G.; Lee, Y.; Yomogida, D.

    1999-01-01

    This paper deals with the economic impacts of the technical, environmental, and institutional barriers in the production, harvesting, and processing of various biomass fuels in California. For each biomass fuel, a base case scenario was developed to characterize the procedures of harvesting, processing and transporting. An economic model was utilized to project the biomass production costs supplied to direct-combustion power plants for each technical, environmental, and institutional barrier. These results will enable the California Energy Commission to identify the most significant barriers to economical biomass energy production (production, harvesting, and processing). (author)

  1. Environmental Science and Research Foundation. Annual technical report, April 11, 1994--December 31, 1994

    International Nuclear Information System (INIS)

    Reynolds, T.D.; Morris, R.C.; Markham, O.D.

    1995-06-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office, by the Environmental Science and Research Foundation (Foundation) for work under contract DE-AC07-94ID13268. The Foundation began, on April 11, 1994, to conduct environmental surveillance near to and distant from the Idaho National Engineering Laboratory, provide environmental public relations and education related to INEL natural resource issues, and conduct ecological and radioecological research benefiting major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Infrastructure

  2. Environmental Science and Research Foundation. Annual technical report, April 11, 1994--December 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Reynolds, T.D.; Morris, R.C.; Markham, O.D. [eds.

    1995-06-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office, by the Environmental Science and Research Foundation (Foundation) for work under contract DE-AC07-94ID13268. The Foundation began, on April 11, 1994, to conduct environmental surveillance near to and distant from the Idaho National Engineering Laboratory, provide environmental public relations and education related to INEL natural resource issues, and conduct ecological and radioecological research benefiting major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Infrastructure.

  3. Pipeline abandonment: a discussion paper on technical and environmental issues

    International Nuclear Information System (INIS)

    Etherington, K.

    1996-01-01

    Formation of government/industry joint steering committee to oversee a review of pipeline abandonment and preparation of a discussion paper was reported. The review became urgent in view of the fact that many of the pipeline systems are nearing the end of their useful life, and the current absence of guidelines in Canada to deal with pipeline abandonment, or to offer guidance on ways of assessing abandonment costs and funding. In view of this situation the safety and the environmental, financial, and legal implications of abandoned pipelines have become an increasing concern to regulatory authorities and the oil and gas industry. Issues to be dealt with in the discussion paper include subsidence, contamination, water crossing, erosion, land management, restoration, utility and pipeline crossings, creation of water conduits, the cost of abandonment, operator choice of abandonment options, and the level of surface disturbance associated with such options

  4. 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

  5. 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...

  6. 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

  7. 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

  8. Critical considerations on the environmental protection. On the technical regulatory guide of air

    Energy Technology Data Exchange (ETDEWEB)

    Rasch, R

    1978-11-01

    The author critically examines the problem of environmental protection maintaining living conditions even with further development of technology. He deals in detail with the success-promising slogans put forth plastics and hydrochloric acid, nuclear energy, as well as keeping the air clean, sulfur dioxide as main topic from the viewpoint of environmental protection. Furthermore, the technical regulatory guides in maintaining clean air and flue gas purification are treated.

  9. Technical Data Management Center: a focal point for meteorological and other environmental transport computing technology

    International Nuclear Information System (INIS)

    McGill, B.; Maskewitz, B.F.; Trubey, D.K.

    1981-01-01

    The Technical Data Management Center, collecting, packaging, analyzing, and distributing information, computer technology and data which includes meteorological and other environmental transport work is located at the Oak Ridge National Laboratory, within the Engineering Physics Division. Major activities include maintaining a collection of computing technology and associated literature citations to provide capabilities for meteorological and environmental work. Details of the activities on behalf of TDMC's sponsoring agency, the US Nuclear Regulatory Commission, are described

  10. Technical approach to finalizing sensible soil cleanup levels at the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Carr, D.; Hertel, B.; Jewett, M.; Janke, R.; Conner, B.

    1996-01-01

    The remedial strategy for addressing contaminated environmental media was recently finalized for the US Department of Energy's (DOE) Fernald Environmental Management Project (FEMP) following almost 10 years of detailed technical analysis. The FEMP represents one of the first major nuclear facilities to successfully complete the Remedial Investigation/Feasibility Study (RI/FS) phase of the environmental restoration process. A critical element of this success was the establishment of sensible cleanup levels for contaminated soil and groundwater both on and off the FEMP property. These cleanup levels were derived based upon a strict application of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) regulations and guidance, coupled with positive input from the regulatory agencies and the local community regarding projected future land uses for the site. The approach for establishing the cleanup levels was based upon a Feasibility Study (FS) strategy that examined a bounding range of viable future land uses for the site. Within each land use, the cost and technical implications of a range of health-protective cleanup levels for the environmental media were analyzed. Technical considerations in driving these cleanup levels included: direct exposure routes to viable human receptors; cross- media impacts to air, surface water, and groundwater; technical practicality of attaining the levels; volume of affected media; impact to sensitive environmental receptors or ecosystems; and cost. This paper will discuss the technical approach used to support the finalization of the cleanup levels for the site. The final cleanup levels provide the last remaining significant piece to the puzzle of establishing a final site-wide remedial strategy for the FEMP, and positions the facility for the expedient completion of site-wide remedial activities

  11. Environmental Science and Research Foundation annual technical report: Calendar year 1996

    International Nuclear Information System (INIS)

    Morris, R.C.; Blew, R.D.

    1997-01-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation's mission to DOE-ID provides support in several key areas. The authors conduct an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provide environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research in the Idaho National Environmental Research Park. This research benefits major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. The major accomplishments of the Foundation and its University Affiliates during the calendar year 1996 are discussed

  12. Environmental Science and Research Foundation, Inc. annual technical report: Calendar year 1997

    International Nuclear Information System (INIS)

    Reynolds, R.D.; Warren, R.W.

    1998-05-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation's mission to DOE-ID provides support in several key areas. The Foundation conducts an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provides environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research on the Idaho National Environmental Research Park. This research benefits major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. Summaries are included of the individual research projects

  13. Environmental Science and Research Foundation annual technical report: Calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Morris, R.C.; Blew, R.D. [eds.

    1997-07-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation`s mission to DOE-ID provides support in several key areas. The authors conduct an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provide environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research in the Idaho National Environmental Research Park. This research benefits major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. The major accomplishments of the Foundation and its University Affiliates during the calendar year 1996 are discussed.

  14. Environmental Science and Research Foundation, Inc. annual technical report: Calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Reynolds, R.D.; Warren, R.W. [eds.

    1998-05-01

    This Annual Technical Report describes work conducted for the Department of Energy, Idaho Operations Office (DOE-ID), by the Environmental Science and Research Foundation (Foundation). The Foundation`s mission to DOE-ID provides support in several key areas. The Foundation conducts an environmental monitoring and surveillance program over an area covering much of the upper Snake River Plain, and provides environmental education and support services related to Idaho National Engineering and Environmental Laboratory (INEEL) natural resource issues. Also, the Foundation, with its University Affiliates, conducts ecological and radioecological research on the Idaho National Environmental Research Park. This research benefits major DOE-ID programs including Waste Management, Environmental Restoration, Spent Nuclear Fuels, and Land Management Issues. Summaries are included of the individual research projects.

  15. 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

  16. 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

  17. Environmental Impact Report from Santa Rita Hydroelectric Power Plant (Minas Gerais State - Brazil): technical strategic for its elaboration

    International Nuclear Information System (INIS)

    Souza, J.A. de; Marques Neto, F.P.

    1989-01-01

    The steps for developing the technical strategies used on the elaboration of Environmental Impact Report from Santa Rita Hydroelectric Power Plant, Minas Gerais State, are described, including the influence area, technical requirements, impact identification, technical selection of mitigative measures, impact meaning and strategy for evaluating the identified impacts. (C.G.C.)

  18. Eighth experts meeting on environmental radioactivity monitoring: Technical and organisational means for an optimised measurement of ambient radioactivity in the environment of nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    The plant-specific emission monitoring and environmental monitoring near nuclear facilities are part of the items of the agreement between the EC and the IAEA, for mutual rapid information in the case of accidents. The lectures presented to the technical discussion meeting deal with the legal and technical aspects involved. Dispersion models, computer-aided dispersion models, computer-aided information systems and advanced programs as well as measuring techniques and results of the emission monitoring and environmental monitoring near nuclear facilities are the aspects of main interest discussed at the meeting. (DG) [de

  19. 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)

  20. 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)

  1. Technical and environmental characterisation of recycled aggregate for reuse in bricks

    Directory of Open Access Journals (Sweden)

    Sorlini Sabrina

    2017-01-01

    Full Text Available Waste mud coming from an aggregate washing plant was formerly used as filling material for a pond, aimed at the recovery of an abandoned quarry. Once completed the filling capacity of the pond, the need for identifying a possible reuse of mud produced by the plant arose in order to avoid landfill disposal. Therefore, mud has been geometrically, physically and chemically characterised for its recovery as construction material. A variety of tests was carried out on mud samples as required by EN technical specifications and by Italian environmental standards, focusing particularly on leaching behaviour. The tested material showed satisfactory physical and chemical properties and a release of pollutants below the limits set by the Italian code. Many mix-designs for the production of unfired bricks made of waste mud, sand and straw, stabilised and non-stabilised with lime, gypsum or cement, were developed. The bricks were tested in order to evaluate mechanical properties and leaching behaviour. Mud bricks provided remarkable compressive strength, even if not suitable for structural elements. The use as interior design to minimise humidity changes and to facilitate a thermal insulation is fostered, thus strengthening the so-called green building economy.

  2. 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)

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 75 FR 7577 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-02-22

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda: Call to...

  8. 75 FR 65615 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-10-26

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda Call to...

  9. 76 FR 57981 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2011-09-19

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

  10. 77 FR 2283 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-01-17

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

  11. 76 FR 36100 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2011-06-21

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

  12. 76 FR 17118 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2011-03-28

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board Chairs AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory Committee Act (Pub... areas of environmental restoration, waste management, and related activities. Tentative Agenda Topics...

  13. 76 FR 62054 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2011-10-06

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board Chairs AGENCY... of the Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory... environmental restoration, waste management, and related activities. Tentative Agenda Topics [cir] EM Program...

  14. 77 FR 29997 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-05-21

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

  15. 77 FR 37390 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-06-21

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda: Call to Order...

  16. 75 FR 82003 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-12-29

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda: Call to...

  17. 75 FR 19379 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-04-14

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda Call to...

  18. 76 FR 78909 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2011-12-20

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... the areas of environmental restoration, waste management, and related activities. Tentative Agenda...

  19. 77 FR 6790 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-02-09

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

  20. 75 FR 51026 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-08-18

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... the areas of environmental restoration, waste management and related activities. Tentative Agenda...

  1. US DoE's Environmental Management Site-Specific Advisory Board 15 Years of Community Involvement

    International Nuclear Information System (INIS)

    Nielson, M.; Brennan, C.A.

    2009-01-01

    This paper provides an overview of the U.S. Department of Energy's Environmental Management Site-Specific Advisory Board (EM SSAB) from its roots in the early 1990's at the Keystone Center to its current activities. The EM SSAB has a unique mandate to provide input regarding the cleanup of nuclear legacy sites in the United States. Chartered under the Federal Advisory Committee Act, the EM SSAB today comprises eight local boards. The Office of Environmental Management has made public participation a fundamental component of its cleanup mission and has found that the EM SSAB has contributed greatly to bringing community values and priorities to the cleanup decision-making processes. Public participation that involves ongoing community engagement has inherent challenges; the EM SSAB has additional challenges that reflect the political and technical nature of the Agency's work. (authors)

  2. 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

  3. Los Alamos National Laboratory Environmental Restoration Project quarterly technical report, April--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-18

    This quarterly report describes the technical status of activities in the Los Alamos National Laboratory Environmental Restoration (ER) Project. Each activity is identified by an activity data sheet number, a brief title describing the activity or the technical area where the activity is located, and the name of the project leader. The Hazardous and Solid Waste Amendments (HSWA) portion of the facility operating permit requires the submission of a technical progress report on a quarterly basis. This report, submitted to fulfill the permit`s requirement, summarizes the work performed and the results of sampling and analysis in the ER Project. Suspect waste found include: Radionuclides, high explosives, metals, solvents and organics. The data provided in this report have not been validated. These data are considered ``reviewed data.``

  4. Ranking of biomass pellets by integration of economic, environmental and technical factors

    International Nuclear Information System (INIS)

    Sultana, Arifa; Kumar, Amit

    2012-01-01

    Interest in biomass as a renewable energy source has increased recently in response to a need to reduce greenhouse gas (GHG) emissions. The objective of this study is to develop a multi-criteria assessment model and rank different biomass feedstock-based pellets, in terms of their suitability for use in large heat and power generation plants and show the importance of environmental, economical and technical factors in making decision about different pellets. Five pellet alternatives, each produced from a different sustainable biomass feedstock i.e., wood, straw, switchgrass, alfalfa and poultry litter, are ranked according to eleven criteria, using the Preference Ranking Organization Method for Enrichment and Evaluation (PROMETHEE). Both quantitative and qualitative criteria are considered, including environmental, technical and economic factors. Three scenarios, namely base case, environmental and economic, are developed by changing the weight assigned to different criteria. In the base case scenario, equal weights are assigned to each criterion. In the economic and environmental scenarios, more weight is given to the economic and environmental factors, respectively. Based on the PROMETHEE rankings, wood pellets are the best source of energy for all scenarios followed by switchgrass, straw, poultry litter and alfalfa pellets except economic scenario, where straw pellets held higher position than switchgrass pellets. Sensitivity analysis on weights, threshold values, preference function and production cost indicate that the ranking was stable. The ranking in all scenarios remained same when qualitative criteria were omitted from the model; this indicates the stronger influence of quantitative criteria. -- Highlights: ► This study ranks the pellets produced from different biomass feedstocks. ► The ranking of the pellets is based on technical, economical and environmental factors. ► This study uses PROMETHEE method for ranking pellets based on a range of

  5. 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.

  6. Technical procedures for ecology: Environmental field program, Deaf Smith County Site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including walkover surveys for threatened, endangered, or candidate species; vegetation classification and mapping; reclamation planning; wetland and floodplain determination and characterization of playas; wildlife habitat mapping methods; mammal sampling; bird survey methods; reptile and amphibian survey methods; preexisting environmental; stress and disturbance studies methods; voucher specimens for plants; and voucher specimens to wildlife. 9 refs., 5 figs., 1 tab

  7. 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

  8. Technical data summary supporting the spent nuclear fuel environmental impact statement, November 1993

    International Nuclear Information System (INIS)

    Geddes, R.L.; Claxton, R.E.; Lengel, J.D.

    1993-11-01

    This report has been compiled by the WSRC Nuclear Materials Processing Division's Planning Section at the request of the Office of Spent Fuel Management and Special Projects (EM-37) to support issuance of the Spent Nuclear Fuel Environmental Impact Statement. Savannah River site data evaluates five programmatic options including open-quotes No Actionclose quotes ranging up to transfer of all DOE responsibility spent fuel to the SRS. For each option, a range of management/disposition scenarios has been examined. Each case summary provides information relative to the technical proposal, technical issues, environmental impacts, and projected costs for a 50 period (to 2044) when it is assumed that the material will be dispositioned from the SRS. It must be recognized that this report was prepared under severe time constraints and contains many simplifications and assumptions. It is highly recommended that significant additional study be performed before basing key decisions upon the data contained in this report. It represents a best effort by a significant group of technical personnel familiar with nuclear materials processing, handlings and storage but it is likely that careful scrutiny will reveal numerous discrepancies and omissions. The bulk of the effort went into defining the engineering approaches necessary to execute the various mission scenarios. Collection and/or calculation of much of the various waste, emission, and utility consumption data, so important to an Environmental Impact Statement, has not been completed at this time

  9. Final Technical Close out Report University Research Program in Robotics for Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    James S. Tulenko; Carl Crane

    2004-01-01

    The report covers the 2003-04 contract period, with a retrospective of the 11 years for the contract, from 1993 to 2004. This includes personnel, technical publications and reports, plus research laboratories employed. Specific information is given in eight research areas, reporting on all technology developed and/or deployed by the University of Florida

  10. Sex-specific selection under environmental stress in seed beetles.

    Science.gov (United States)

    Martinossi-Allibert, I; Arnqvist, G; Berger, D

    2017-01-01

    Sexual selection can increase rates of adaptation by imposing strong selection in males, thereby allowing efficient purging of the mutation load on population fitness at a low demographic cost. Indeed, sexual selection tends to be male-biased throughout the animal kingdom, but little empirical work has explored the ecological sensitivity of this sex difference. In this study, we generated theoretical predictions of sex-specific strengths of selection, environmental sensitivities and genotype-by-environment interactions and tested them in seed beetles by manipulating either larval host plant or rearing temperature. Using fourteen isofemale lines, we measured sex-specific reductions in fitness components, genotype-by-environment interactions and the strength of selection (variance in fitness) in the juvenile and adult stage. As predicted, variance in fitness increased with stress, was consistently greater in males than females for adult reproductive success (implying strong sexual selection), but was similar in the sexes in terms of juvenile survival across all levels of stress. Although genetic variance in fitness increased in magnitude under severe stress, heritability decreased and particularly so in males. Moreover, genotype-by-environment interactions for fitness were common but specific to the type of stress, sex and life stage, suggesting that new environments may change the relative alignment and strength of selection in males and females. Our study thus exemplifies how environmental stress can influence the relative forces of natural and sexual selection, as well as concomitant changes in genetic variance in fitness, which are predicted to have consequences for rates of adaptation in sexual populations. © 2016 European Society For Evolutionary Biology. Journal of Evolutionary Biology © 2016 European Society For Evolutionary Biology.

  11. 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

  12. 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

  13. Technical- and environmental-efficiency analysis of irrigated cotton-cropping systems in Punjab, Pakistan using data envelopment analysis.

    Science.gov (United States)

    Ullah, Asmat; Perret, Sylvain R

    2014-08-01

    Cotton cropping in Pakistan uses substantial quantities of resources and adversely affects the environment with pollutants from the inputs, particularly pesticides. A question remains regarding to what extent the reduction of such environmental impact is possible without compromising the farmers' income. This paper investigates the environmental, technical, and economic performances of selected irrigated cotton-cropping systems in Punjab to quantify the sustainability of cotton farming and reveal options for improvement. Using mostly primary data, our study quantifies the technical, cost, and environmental efficiencies of different farm sizes. A set of indicators has been computed to reflect these three domains of efficiency using the data envelopment analysis technique. The results indicate that farmers are broadly environmentally inefficient; which primarily results from poor technical inefficiency. Based on an improved input mix, the average potential environmental impact reduction for small, medium, and large farms is 9, 13, and 11 %, respectively, without compromising the economic return. Moreover, the differences in technical, cost, and environmental efficiencies between small and medium and small and large farm sizes were statistically significant. The second-stage regression analysis identifies that the entire farm size significantly affects the efficiencies, whereas exposure to extension and training has positive effects, and the sowing methods significantly affect the technical and environmental efficiencies. Paradoxically, the formal education level is determined to affect the efficiencies negatively. This paper discusses policy interventions that can improve the technical efficiency to ultimately increase the environmental efficiency and reduce the farmers' operating costs.

  14. 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

  15. 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

  16. Variation of Phenolic Content in Globe Artichoke in Relation to Biological, Technical and Environmental Factors

    Directory of Open Access Journals (Sweden)

    Sara Lombardo

    2009-12-01

    Full Text Available In Italy, globe artichoke production is prevailingly concentrated in the South and islands, where it provides an important contribution to the agricultural economy. In recent years, there has been a renewed interest in this crop as a promising source of polyphenols, a heterogeneous class of secondary metabolites characterized by various healthy properties well-documented in literature. The phenolic fraction, present in the different artichoke plant parts, varies widely in relation to biotic and abiotic factors. Therefore, the present study aimed at evaluating the variation of phenolic content in globe artichoke in relation to biological, technical and environmental factors. Two field-experiments were carried out in Sicily (South Italy in two representative cultivation areas, in order to examine the effects of genotype, head fraction, season conditions, planting density and arrangement on the globe artichoke phenolic concentration. Both the total polyphenols and the individual phenolic compounds detected were notably genotype- dependent. Particularly, the high level of caffeoylquinic acids (chlorogenic acid, among others and apigenin 7- O-glucuronide, reported respectively by “Violetto di Sicilia” and “Romanesco clone C3”, could be used to encourage globe artichoke fresh consumption. Total polyphenols content also resulted more abundant in specific accumulation sites within the inflorescence, such as the floral stem and receptacle, and for most of genotypes it decreased during the second year in response to the different meteorological conditions. Additionally, total polyphenols content significantly and linearly increased as plant density increased from 1.0 to 1.8 plant m-2 and it significantly increased by 13% passing from single to twin rows plant arrangement.

  17. Variation of Phenolic Content in Globe Artichoke in Relation to Biological, Technical and Environmental Factors

    Directory of Open Access Journals (Sweden)

    Giovanni Mauromicale

    2011-02-01

    Full Text Available In Italy, globe artichoke production is prevailingly concentrated in the South and islands, where it provides an important contribution to the agricultural economy. In recent years, there has been a renewed interest in this crop as a promising source of polyphenols, a heterogeneous class of secondary metabolites characterized by various healthy properties well-documented in literature. The phenolic fraction, present in the different artichoke plant parts, varies widely in relation to biotic and abiotic factors. Therefore, the present study aimed at evaluating the variation of phenolic content in globe artichoke in relation to biological, technical and environmental factors. Two field-experiments were carried out in Sicily (South Italy in two representative cultivation areas, in order to examine the effects of genotype, head fraction, season conditions, planting density and arrangement on the globe artichoke phenolic concentration. Both the total polyphenols and the individual phenolic compounds detected were notably genotype- dependent. Particularly, the high level of caffeoylquinic acids (chlorogenic acid, among others and apigenin 7- O-glucuronide, reported respectively by “Violetto di Sicilia” and “Romanesco clone C3”, could be used to encourage globe artichoke fresh consumption. Total polyphenols content also resulted more abundant in specific accumulation sites within the inflorescence, such as the floral stem and receptacle, and for most of genotypes it decreased during the second year in response to the different meteorological conditions. Additionally, total polyphenols content significantly and linearly increased as plant density increased from 1.0 to 1.8 plant m-2 and it significantly increased by 13% passing from single to twin rows plant arrangement.

  18. 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

  19. A technical, economic, and environmental performance of grid-connected hybrid (photovoltaic-wind) power system in Algeria.

    Science.gov (United States)

    Saheb-Koussa, Djohra; Koussa, Mustapha; Said, Nourredine

    2013-01-01

    This paper studies the technical, economic, and environmental analysis of wind and photovoltaic power systems connected to a conventional grid. The main interest in such systems is on-site consumption of the produced energy, system hybridization, pooling of resources, and contribution to the environment protection. To ensure a better management of system energy, models have been used for determining the power that the constituting subsystems can deliver under specific weather conditions. Simulation is performed using MATLAB-SIMULINK. While, the economic and environmental study is performed using HOMER software. From an economic point of view, this allows to compare the financial constraints on each part of the system for the case of Adrar site which is located to the northern part of the south of Algeria. It also permits to optimally size and select the system presenting the best features on the basis of two parameters, that is, cost and effectiveness. From an environmental point of view, this study allows highlighting the role of renewable energy in reducing gas emissions related to greenhouse effects. In addition, through a set of sensitivity analysis, it is found that the wind speed has more effects on the environmental and economic performances of grid-connected hybrid (photovoltaic-wind) power systems.

  20. A Technical, Economic, and Environmental Performance of Grid-Connected Hybrid (Photovoltaic-Wind Power System in Algeria

    Directory of Open Access Journals (Sweden)

    Djohra Saheb-Koussa

    2013-01-01

    Full Text Available This paper studies the technical, economic, and environmental analysis of wind and photovoltaic power systems connected to a conventional grid. The main interest in such systems is on-site consumption of the produced energy, system hybridization, pooling of resources, and contribution to the environment protection. To ensure a better management of system energy, models have been used for determining the power that the constituting subsystems can deliver under specific weather conditions. Simulation is performed using MATLAB-SIMULINK. While, the economic and environmental study is performed using HOMER software. From an economic point of view, this allows to compare the financial constraints on each part of the system for the case of Adrar site which is located to the northern part of the south of Algeria. It also permits to optimally size and select the system presenting the best features on the basis of two parameters, that is, cost and effectiveness. From an environmental point of view, this study allows highlighting the role of renewable energy in reducing gas emissions related to greenhouse effects. In addition, through a set of sensitivity analysis, it is found that the wind speed has more effects on the environmental and economic performances of grid-connected hybrid (photovoltaic-wind power systems.

  1. 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

  2. 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

  3. 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.

  4. 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.

  5. 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, ...

  6. 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...

  7. 1998 Chemical Technology Division Annual Technical Report. Applying chemical innovation to environmental problems

    International Nuclear Information System (INIS)

    Ackerman, J.P.; Einziger, R.E.; Gay, E.C.; Green, D.W.; Miller, J.F.

    1999-01-01

    The Chemical Technology (CMT) Division is a diverse technical organization with principal emphases in environmental management and development of advanced energy sources. The Division conducts research and development in three general areas: (1) development of advanced power sources for stationary and transportation applications and for consumer electronics, (2) management of high-level and low-level nuclear wastes and hazardous wastes, and (3) electrometallurgical treatment of spent nuclear fuel. The Division also performs basic research in catalytic chemistry involving molecular energy resources, mechanisms of ion transport in lithium battery electrolytes, and the chemistry of technology-relevant materials. In addition, the Division operates the Analytical Chemistry Laboratory, which conducts research in analytical chemistry and provides analytical services for programs at Argonne National Laboratory (ANL) and other organizations. Technical highlights of the Division's activities during 1998 are presented

  8. 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

  9. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed

  10. Specification and Aggregation Errors in Environmentally Extended Input-Output Models

    NARCIS (Netherlands)

    Bouwmeester, Maaike C.; Oosterhaven, Jan

    This article considers the specification and aggregation errors that arise from estimating embodied emissions and embodied water use with environmentally extended national input-output (IO) models, instead of with an environmentally extended international IO model. Model specification errors result

  11. 77 FR 51789 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-08-27

    ... management and related activities. Tentative Agenda Call to Order, Introductions, Review of Agenda... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act...

  12. 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

  13. 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

  14. 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

  15. Recommended environmental dose calculation methods and Hanford-specific parameters. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V. [Pacific Northwest Lab., Richland, WA (United States); Davis, J.S. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-03-01

    This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document.

  16. M-X Environmental Technical Report. Environmental Characteristics of Alternative Designated Areas, Water Resources.

    Science.gov (United States)

    1980-12-29

    approximately half will be returned as wastewater. Properly treated wastewater can be reused for such activities as irrigation and groundwater recharge...PUNTA DE AGUA CANADIAN RESERVOIR CREEK (NM) STATE LINE CREEK (TX) RIVER (TX) (NM) (07227100) (07227140) (07227448) (07227470) Mean specific conductance... reuse of treated waste- water. This would reduce the effective consumptive use of the demands presented by about 50 percent. GROUNDWATER RELATED IMPACTS

  17. 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

  18. 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.

  19. EPRI-DOE Conference on Environmentally-Enhanced Hydropower Turbines: Technical Papers

    Energy Technology Data Exchange (ETDEWEB)

    Hogan, T. [Alden Research Laboratory, Inc., Holden, MA (United States)

    2011-12-01

    The EPRI-DOE Conference on Environmentally-Enhanced Hydropower Turbines was a component of a larger project. The goal of the overall project was to conduct the final developmental engineering required to advance the commercialization of the Alden turbine. As part of this effort, the conference provided a venue to disseminate information on the status of the Alden turbine technology as well as the status of other advanced turbines and research on environmentally-friendly hydropower turbines. The conference was also a product of a federal Memorandum of Understanding among DOE, USBR, and USACE to share technical information on hydropower. The conference was held in Washington, DC on May 19 and 20, 2011 and welcomed over 100 attendees. The Conference Organizing Committee included the federal agencies with a vested interest in hydropower in the U.S. The Committee collaboratively assembled this conference, including topics from each facet of the environmentally-friendly conventional hydropower research community. The conference was successful in illustrating the readiness of environmentally-enhanced hydropower technologies. Furthermore, the topics presented illustrated the need for additional deployment and field testing of these technologies in an effort to promote the growth of environmentally sustainable hydropower in the U.S. and around the world.

  20. 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

  1. 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

  2. The effects of environmental regulation and technical progress on CO2 Kuznets curve: An evidence from China

    International Nuclear Information System (INIS)

    Yin, Jianhua; Zheng, Mingzheng; Chen, Jian

    2015-01-01

    Based on environmental Kuznets curve theory, a panel data model which takes environmental regulation and technical progress as its moderating factors was developed to analyse the institutional and technical factors that affect the path of low-carbon economic development. The results indicated that there was a CO 2 emission Kuznets curve seen in China. Environmental regulation had a significant moderating effect on the curve, and the inflection of CO 2 emissions could come substantially earlier under stricter environmental regulation. Meanwhile, the impact of technical progress on the low-carbon economic development path had a longer hysteresis effect but restrained CO 2 emission during its increasing stage and accelerated its downward trend during the decreasing stage which was conducive to emission reduction. Strict environmental regulation could force the high-carbon emitting industries to transfer from the eastern regions to the central or the western regions of China, which would make the CO 2 Kuznets curve higher in its increasing stage and lower in its decreasing stage than that under looser regulation. Furthermore, energy efficiency, energy structure, and industrial structure exerted a significant direct impact on CO 2 emissions; we should consider the above factors as essential in the quest for low-carbon economic development. - Highlights: • Estimate moderating effect of environmental regulation and technical progress on EKC. • There was a CO 2 emission Kuznets curve in effect in China. • Environmental regulation presents significant moderating effect on EKC. • Technical progress moderates the relationship between income and CO 2 emissions

  3. HANFORD SITE SOLID WASTE MANAGEMENT ENVIRONMENTAL IMPACT STATEMENT TECHNICAL INFORMATION DOCUMENT [SEC 1 THRU 4

    International Nuclear Information System (INIS)

    FRITZ, L.L.

    2004-01-01

    This Technical Information Document (TID) provides engineering data to support DOE/EIS-0286, ''Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement''. Assumptions and waste volumes used to calculate engineering data are also provided in this document. This chapter provides a brief description of: the Solid Waste Management Program (including a description of waste types and known characteristics of waste covered under the program), the Hanford Site (including a general discussion of the operating areas), and the alternatives analyzed. The Hanford Site Solid Waste Management Program and DOE/EIS-0286 address solid radioactive waste types generated by various activities from both onsite and offsite generators. The Environmental Restoration (ER) waste management activities are not within the scope of DOE/EIS-0286 or this TID. Activities for processing and disposal of immobilized low-activity waste (ILAW) are not within the scope of the Solid Waste Management Program and this TID

  4. Low Energy Accelerator Laboratory Technical Area 53, Los Alamos National Laboratory. Environmental assessment

    International Nuclear Information System (INIS)

    1995-04-01

    This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the Department of Energy (DOE) were to construct and operate a small research and development laboratory building at Technical Area (TA) 53 at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico. DOE proposes to construct a small building to be called the Low Energy Accelerator Laboratory (LEAL), at a previously cleared, bladed, and leveled quarter-acre site next to other facilities housing linear accelerator research activities at TA-53. Operations proposed for LEAL would consist of bench-scale research, development, and testing of the initial section of linear particle accelerators. This initial section consists of various components that are collectively called an injector system. The anticipated life span of the proposed development program would be about 15 years

  5. ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1992--September 1993

    International Nuclear Information System (INIS)

    Bates, J.K.; Bourcier, W.L.; Bradley, C.R.

    1994-06-01

    This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal

  6. 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.)

  7. [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

  8. 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

  9. Technical, environmental, and economic assessment of deploying advanced coal power technologies in the Chinese context

    International Nuclear Information System (INIS)

    Zhao Lifeng; Xiao Yunhan; Gallagher, Kelly Sims; Wang Bo; Xu Xiang

    2008-01-01

    The goal of this study is to evaluate the technical, environmental, and economic dimensions of deploying advanced coal-fired power technologies in China. In particular, we estimate the differences in capital cost and overall cost of electricity (COE) for a variety of advanced coal-power technologies based on the technological and economic levels in 2006 in China. This paper explores the economic gaps between Integrated Gasification Combined Cycle (IGCC) and other advanced coal power technologies, and compares 12 different power plant configurations using advanced coal power technologies. Super critical (SC) and ultra super critical (USC) pulverized coal (PC) power generation technologies coupled with pollution control technologies can meet the emission requirements. These technologies are highly efficient, technically mature, and cost-effective. From the point of view of efficiency, SC and USC units are good choices for power industry. The net plant efficiency for IGCC has reached 45%, and it has the best environmental performance overall. The cost of IGCC is much higher, however, than that of other power generation technologies, so the development of IGCC is slow throughout the world. Incentive policies are needed if IGCC is to be deployed in China

  10. Information management systems for integrating the technical data and regulatory requirements of environmental restoration activities

    International Nuclear Information System (INIS)

    Geffen, C.A.; Garrett, B.A.; Walter, M.B.

    1990-03-01

    Current environmental regulations require that comprehensive planning be conducted before remediating a hazardous waste site to characterize the nature and extent of site contamination, calculate the risk to the public, and assess the effectiveness of various remediation technologies. Remediation of Department of Energy (DOE) sites contaminated with hazardous or mixed wastes will require the effective integration of scientific and engineering data with regulatory and institutional requirements. The information management challenge presented by waste site cleanup activities goes beyond merely dealing with the large quantity of data that will be generated. The information must be stored, managed, and presented in a way that provides some consistency in approach across sites, avoids duplication of effort, and facilitates responses to requests for information from the regulators and the public. This paper provides background information on the regulatory requirements for data gathering and analysis for environmental restoration activities, and outlines the data and information management requirements for completing the pre-remediation phases of an environmental restoration project. Information management systems for integrating the regulatory and institutional requirements of the environmental restoration process with the technical data and analysis requirements are also described. 7 refs

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. An overview of remedial action technical information support activities funded by the US Department of Energy's Office of Environmental Restoration

    International Nuclear Information System (INIS)

    Owen, P.T.

    1990-01-01

    In 1979 the US Department of Energy (DOE) established the Remedial Action Program Information Center (RAPIC) at the Oak Ridge National Laboratory (ORNL) to provide technical information support to the DOE's Remedial Action Programs, which comprise: Formerly Utilized Sites Remedial Action Program (FUSRAP), Surplus Facilities Management Program (SFMP), and Uranium Mill Tailings Remedial Action Program (UMTRAP). Specific information activities that RAPIC performs to support the DOE's programs include: maintaining a computerized bibliographic database containing approximately 7000 annotated references relevant to remediation work at radioactively contaminated sites; publishing an annual bibliography, Nuclear Facility Decommissioning and Site Remedial Actions, A Selected Bibliography, ORNL/EIS-154; maintaining a document repository and providing copies of requested publications; and performing manual and computerized searches of the technical literature. The most important RAPIC function is serving as a focal point for remedial action information. With these extensive resources at its command, RAPIC is in a unique position to provide a comprehensive information base to the remedial action and environmental restoration community

  17. 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.

  18. 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

  19. 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

  20. 76 FR 5147 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2011-01-28

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  1. 77 FR 59598 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-09-28

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  2. 75 FR 13269 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2010-03-19

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Hanford AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford. The Federal Advisory Committee Act... is to make recommendations to DOE-EM and site management in the areas of environmental restoration...

  3. 75 FR 65310 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2010-10-22

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada Test Site. The Federal Advisory... Board is to make recommendations to DOE-EM and site management in the areas of environmental restoration...

  4. 75 FR 54600 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-09-08

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  5. 75 FR 66074 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-10-27

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  6. 75 FR 8050 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2010-02-23

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Hanford AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford. The Federal Advisory Committee Act... is to make recommendations to DOE-EM and site management in the areas of environmental restoration...

  7. 75 FR 24686 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-05-05

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  8. 76 FR 80355 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2011-12-23

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... make recommendations to DOE-EM and site management in the areas of environmental restoration, waste...

  9. 75 FR 9404 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-03-02

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  10. 75 FR 56526 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2010-09-16

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Initiative Workshop of the Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  11. 75 FR 82004 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2010-12-29

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management, and...

  12. 77 FR 4027 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2012-01-26

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management, and...

  13. 77 FR 43583 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-07-25

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  14. 75 FR 61711 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-10-06

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  15. 76 FR 80354 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2011-12-23

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management, and...

  16. 75 FR 82002 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2010-12-29

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  17. 76 FR 61350 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2011-10-04

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... make recommendations to DOE-EM and site management in the areas of environmental restoration, waste...

  18. 76 FR 4645 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2011-01-26

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Hanford AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management, and...

  19. 75 FR 6018 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2010-02-05

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Hanford AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford (known locally as the Hanford Advisory... and site management in the areas of environmental restoration, waste management, and related...

  20. 77 FR 12044 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2012-02-28

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Nevada AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub... Board is to make recommendations to DOE-EM and site management in the areas of environmental restoration...

  1. 76 FR 48148 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2011-08-08

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act... recommendations to DOE-EM and site management in the areas of environmental restoration, waste management and...

  2. Comparative analysis of concentrating solar power and photovoltaic technologies: Technical and environmental evaluations

    International Nuclear Information System (INIS)

    Desideri, U.; Zepparelli, F.; Morettini, V.; Garroni, E.

    2013-01-01

    Highlights: ► Life cycle was assessed for both concentrated solar power and photovoltaic systems. ► The PV plant has a higher environmental impact than the CSP plant. ► The Global Warming Potential is lower for the CSP than for the PV plant. ► The energy payback time is lower for the CSP than for the PV plant. -- Abstract: Solar energy is an important alternative energy source to fossil fuels and theoretically the most available energy source on the earth. Solar energy can be converted into electric energy by using two different processes: by means of thermodynamic cycles and the photovoltaic conversion. Solar thermal technologies, sometimes called thermodynamic solar technologies, operating at medium (about 500 °C) and high temperatures (about 1000 °C), have recently attracted a renewed interest and have become one of the most promising alternatives in the field of solar energy utilization. Photovoltaic conversion is very interesting, although still quite expensive, because of the absence of moving components and the reduced operating and management costs. The main objectives of the present work are: •to carry out comparative technical evaluations on the amount of electricity produced by two hypothetical plants, located on the same site, for which a preliminary design was made: a solar thermal power plant with parabolic trough collectors and a photovoltaic plant with a single-axis tracking system; •to carry out a comparative analysis of the environmental impact derived from the processes of electricity generation during the whole life cycle of the two hypothetical power plants. First a technical comparison between the two plants was made assuming that they have the same nominal electric power and then the same total covered surface. The methodology chosen to evaluate the environmental impact associated with the power plants is the Life Cycle Assessment (LCA). It allows to analyze all the phases of the life cycle of the plants, from the extraction of

  3. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  4. Introducing IT-Based environmental simulation courses at Slovak technical universities

    NARCIS (Netherlands)

    Hensen, J.L.M.; Hraska, J.; Mallory-Hill, S.M.; Rabenseifer, F.; Maldonado, E.; Yannas, Y.

    1998-01-01

    Since the 1995/96 academic year, four Slovak universities (Slovak Technical University Bratislava, Technical University Kosice, Slovak Agricultural University Nitra and Technical University Zvolen) in cooperation with two EU universities (University of Strathclyde Glasgow and Eindhoven University of

  5. 76 FR 59392 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2011-09-26

    ... Welcome and Introductions, Committee Business Items: [cir] Approve October 12, 2011, Meeting Agenda, [cir... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Northern New Mexico... meeting of the Environmental Monitoring, Surveillance and Remediation Committee and Waste Management...

  6. Proceedings of the 34. AMOP technical seminar on environmental contamination and response 2011

    International Nuclear Information System (INIS)

    2011-01-01

    The 34th AMOP Arctic and marine oilspill conference was held in Banff, Alberta, Canada, from October 4th to October 6th, 2011. The aim of the Arctic and marine oilspill program (AMOP), which was started in 1978 by Environment Canada, is to help improve understanding of oil spills which occur in the Arctic marine environment and the technology for cleaning them up. This technical seminar is held every year by the Emergencies Science and Technology Section (ESTS) of Environment Canada and provides attendees with the opportunity to hear about some of the latest technologies and to discuss with other experts in the field of Arctic and marine environmental contamination and response. 38 out of the 61 papers presented during this conference have been catalogued separately for inclusion in this database

  7. Environmental assessment for operations, upgrades, and modifications in SNL/NM Technical Area IV

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The proposed action for this EA for Sandia National Laboratories/New Mexico Technical Area IV, includes continuing existing operations, modification of an existing accelerator (Particle Beam Fusion Accelerator II) to support defnese-related Z-pinch experiments, and construction of two transformer oil storage tanks to support the expansion of the Advanced Pulsed Power Research Module, a single pulse accelerator. Based on the analyses in the EA, DOE believes that the proposed action is not a major federal action significantly affecting the quality of the human environment within the meaning of NEPA and CEQ NEPA implementing regulations in 40 CFR 1508.18 and 1508.27. Therefore, an environmental impact statement is not required, and a Finding of No Significant Impact is issued.

  8. Technical and Environmental Change in Spain: Agrarian Underdevelopment or “European Dragon”?

    Directory of Open Access Journals (Sweden)

    Ricardo Robledo Hernández

    2013-06-01

    Full Text Available The belittling view of Spanish agriculture, the main source of employment until 1950, was a constant reference in the socioeconomic analyses carried out until the end of last century. This became one of the clichés that nourished the Hispanic inferiority complex, to which writers like Joaquin Costa contributed. The revision of agrarian history has helped to correct the image of social and economic underdevelopment in two ways. Firstly, the better knowledge of the technical innovation processes. Secondly, the environmental and biological limits the Spanish agricultural activity suffered. The latter statement is also useful to underline the risks of productivism after the destruction and redirection of the innovation systems by the Franco regime, when the opportunities for farming development offered by the Republican agricultural reform disappeared

  9. Technical, economical and environmental aspects of the production of biodiesel in Italy

    International Nuclear Information System (INIS)

    Camaggio, G.; Paiano, A.; Tricase, C.

    2006-01-01

    The events of the last years have put under the spotlight the politic and economic instability of the energy sources from crude oil. This has brought to the necessity to exploit alternative sources, such as bio fuels. It is possible to suppose for Italy, for a long time dependent from abroad energy supplying, that the development of biofuel industry will be an opportunity, also thanks to its background agriculture: it can rise, in fact, to an important role, thanks to biomass energy exploitation. In this paper will be made an analysis about the material and energy flows of the entire production chain of biodiesel obtained from sunflower, in order to evaluate its potential from technical, economic and environmental point of view

  10. Economical, environmental and technical analysis of building integrated photovoltaic systems in Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Seng, Lim Yun [Department of Physical Science, Electrical and Electronic Engineering, Tunku Abdul Rahman University, 53300 Setapak, Kuala Lumpur (Malaysia); Lalchand, G.; Sow Lin, Gladys Mak [Malaysia Energy Centre, Building Integrated Photovoltaic Project (Malaysia)

    2008-06-15

    Malaysia has identified photovoltaic systems as one of the most promising renewable sources. A great deal of efforts has been undertaken to promote the wide applications of PV systems. With the recent launch of a PV market induction programme known as SURIA 1000 in conjunction with other relevant activities undertaken under the national project of Malaysia Building Integrated Photovoltaic (MBIPV), the market of PV systems begins to be stimulated in the country. As a result, a wide range of technical, environmental and economic issues with regard to the connection of PV systems to local distribution networks becomes apparent. Numerous studies were therefore carried out in collaboration with Malaysian Energy Centre to address a number of those important issues. The findings of the studies are presented in the paper and can be served as supplementary information to parties who are directly and indirectly involved in the PV sector in Malaysia. (author)

  11. Economical, environmental and technical analysis of building integrated photovoltaic systems in Malaysia

    International Nuclear Information System (INIS)

    Seng, Lim Yun; Lalchand, G.; Sow Lin, Gladys Mak

    2008-01-01

    Malaysia has identified photovoltaic systems as one of the most promising renewable sources. A great deal of efforts has been undertaken to promote the wide applications of PV systems. With the recent launch of a PV market induction programme known as SURIA 1000 in conjunction with other relevant activities undertaken under the national project of Malaysia Building Integrated Photovoltaic (MBIPV), the market of PV systems begins to be stimulated in the country. As a result, a wide range of technical, environmental and economic issues with regard to the connection of PV systems to local distribution networks becomes apparent. Numerous studies were therefore carried out in collaboration with Malaysian Energy Centre to address a number of those important issues. The findings of the studies are presented in the paper and can be served as supplementary information to parties who are directly and indirectly involved in the PV sector in Malaysia. (author)

  12. Environmental assessment for operations, upgrades, and modifications in SNL/NM Technical Area IV

    International Nuclear Information System (INIS)

    1996-04-01

    The proposed action for this EA for Sandia National Laboratories/New Mexico Technical Area IV, includes continuing existing operations, modification of an existing accelerator (Particle Beam Fusion Accelerator II) to support defnese-related Z-pinch experiments, and construction of two transformer oil storage tanks to support the expansion of the Advanced Pulsed Power Research Module, a single pulse accelerator. Based on the analyses in the EA, DOE believes that the proposed action is not a major federal action significantly affecting the quality of the human environment within the meaning of NEPA and CEQ NEPA implementing regulations in 40 CFR 1508.18 and 1508.27. Therefore, an environmental impact statement is not required, and a Finding of No Significant Impact is issued

  13. Independent technical review of the Sandia National Laboratories Environmental Restoration Project

    International Nuclear Information System (INIS)

    1994-11-01

    An Independent Technical Review was conducted of the Environmental Restoration Project. The objective of the review was recommendations, from a commercial perspective, on a systems level path forward to safe, minimum cost and schedule project completion. The work presented represents the consensus analysis and recommendations of thirteen individuals with varied backgrounds, expertise, and experience. The ITR team recommends that the barriers to the opportunity described in the diagnosis be eliminated using an integrated DOE-Sandia system approach. Piecemeal changes will not result in the desired commercial efficiency. DOE needs to operate as the contracting agency for a Major System Acquisition. If it does not, commercial performance will not be achieved regardless of the contractor. Likewise, Sandia needs to establish and implement the necessary project structure and management systems to operate with commercial contractor like efficiency

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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.)

  19. 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

  20. Age and Environmental Concern: Some Specification of Effects.

    Science.gov (United States)

    Honnold, Julie A.

    1984-01-01

    Distinguishes possible aging, cohort, and period effects, explaining time series differences by age groups in the General Social Survey data. Results indicate that the decline in environmental concern among most age groups can be accounted for by period effects, but an aging effect is important among young adults. (Author/JN)

  1. The"minimum information about an environmental sequence" (MIENS) specification

    Energy Technology Data Exchange (ETDEWEB)

    Yilmaz, P.; Kottmann, R.; Field, D.; Knight, R.; Cole, J.R.; Amaral-Zettler, L.; Gilbert, J.A.; Karsch-Mizrachi, I.; Johnston, A.; Cochrane, G.; Vaughan, R.; Hunter, C.; Park, J.; Morrison, N.; Rocca-Serra, P.; Sterk, P.; Arumugam, M.; Baumgartner, L.; Birren, B.W.; Blaser, M.J.; Bonazzi, V.; Bork, P.; Buttigieg, P. L.; Chain, P.; Costello, E.K.; Huot-Creasy, H.; Dawyndt, P.; DeSantis, T.; Fierer, N.; Fuhrman, J.; Gallery, R.E.; Gibbs, R.A.; Giglio, M.G.; Gil, I. San; Gonzalez, A.; Gordon, J.I.; Guralnick, R.; Hankeln, W.; Highlander, S.; Hugenholtz, P.; Jansson, J.; Kennedy, J.; Knights, D.; Koren, O.; Kuczynski, J.; Kyrpides, N.; Larsen, R.; Lauber, C.L.; Legg, T.; Ley, R.E.; Lozupone, C.A.; Ludwig, W.; Lyons, D.; Maguire, E.; Methe, B.A.; Meyer, F.; Nakieny, S.; Nelson, K.E.; Nemergut, D.; Neufeld, J.D.; Pace, N.R.; Palanisamy, G.; Peplies, J.; Peterson, J.; Petrosino, J.; Proctor, L.; Raes, J.; Ratnasingham, S.; Ravel, J.; Relman, D.A.; Assunta-Sansone, S.; Schriml, L.; Sodergren, E.; Spor, A.; Stombaugh, J.; Tiedje, J.M.; Ward, D.V.; Weinstock, G.M.; Wendel, D.; White, O.; Wikle, A.; Wortman, J.R.; Glockner, F.O.; Bushman, F.D.; Charlson, E.; Gevers, D.; Kelley, S.T.; Neubold, L.K.; Oliver, A.E.; Pruesse, E.; Quast, C.; Schloss, P.D.; Sinha, R.; Whitely, A.

    2010-10-15

    We present the Genomic Standards Consortium's (GSC) 'Minimum Information about an ENvironmental Sequence' (MIENS) standard for describing marker genes. Adoption of MIENS will enhance our ability to analyze natural genetic diversity across the Tree of Life as it is currently being documented by massive DNA sequencing efforts from myriad ecosystems in our ever-changing biosphere.

  2. Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1996-01-01

    Much of the US Department of Energy's (DOE's) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL's main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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

  9. 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)

  10. 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

  11. 75 FR 26743 - Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To...

    Science.gov (United States)

    2010-05-12

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 12779-005] Pacific Gas and Electric Company; Notice of Environmental Site Review and Technical Meetings To Discuss Information and Monitoring Needs for a License Application for a Pilot Project May 5, 2010. a. Type of Application: Draft Pilot License Application. b. Project N...

  12. 77 FR 2282 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-01-17

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... the Environmental Management Site-Specific Advisory Board, Paducah. This notice announces the... Management Officer. [FR Doc. 2012-831 Filed 1-12-12; 4:15 pm] BILLING CODE 6405-01-P ...

  13. 76 FR 20651 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2011-04-13

    ... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board Chairs AGENCY... a meeting on April 13-14, 2011 of the Environmental Management Site-Specific Advisory Board Chairs... R. Butler, Acting Deputy Committee Management Officer. [FR Doc. 2011-8970 Filed 4-8-11; 4:15 pm...

  14. Technical assistance from state health departments for communities engaged in policy, systems, and environmental change: the ACHIEVE Program.

    Science.gov (United States)

    Hefelfinger, Jenny; Patty, Alice; Ussery, Ann; Young, Walter

    2013-10-24

    This study assessed the value of technical assistance provided by state health department expert advisors and by the staff of the National Association of Chronic Disease Directors (NACDD) to community groups that participated in the Action Communities for Health, Innovation, and Environmental Change (ACHIEVE) Program, a CDC-funded health promotion program. We analyzed quantitative and qualitative data reported by community project coordinators to assess the nature and value of technical assistance provided by expert advisors and NACDD staff and the usefulness of ACHIEVE resources in the development and implementation of community action plans. A grounded theory approach was used to analyze and categorize phrases in text data provided by community coordinators. Open coding placed conceptual labels on text phrases. Frequency distributions of the quantitative data are described and discussed. The most valuable technical assistance and program support resources were those determined to be in the interpersonal domain (ie, interactions with state expert advisors, NACDD staff, and peer-to-peer support). The most valuable technical assistance events were action institutes, coaches' meetings, webinars, and technical assistance conference calls. This analysis suggests that ACHIEVE communities valued the management and training assistance provided by expert advisors and NACDD staff. State health department expert advisors provided technical guidance and support, including such skills or knowledge-based services as best-practice strategies, review and discussion of community assessment data, sustainability planning, and identification of possible funding opportunities. NACDD staff led development and implementation of technical assistance events.

  15. ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

    2011-06-07

    Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear

  16. 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

  17. 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

  18. 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

  19. Set up of an environmental monitoring system, Shchuchye, Russia - technical assistance - 59042

    International Nuclear Information System (INIS)

    Belbeze, Stephane; Hallouin, Matthieu

    2012-01-01

    An intergovernmental agreement on cooperation about chemical weapon destruction was signed between France and the Russian federation on 14. February 2006 in the context of a Global Partnership dedicated to preventing catastrophic terrorism and the proliferation of weapons of mass destruction. It came into effect on 25 April 2007 after ratification by both countries. The present demonstrated project was launched as part of this collaboration on the Shchuchye site (Russia - Kurgan Oblast). The project concerned the environmental surveillance system for the Shchuchye site required for the safe operation of the installation used to destroy chemical weapons. The aim was to implement equipments and methods of analysis for very low concentrations of pollutants in the three environmental compartments: air, water and soil. This has been achieved with the help of industry and other organizations in France (Environment/SA for supplies, INERIS and Antea Group) and Russia (ROST Association and EKROS Engineering). This system takes account of the normal operation of the installation as well as incident management. It includes 11 stationary atmospheric measuring stations constructed by Environment/SA and EKROS Engineering including ASTEK dedicated toxic gas detector: 'Terminator FOV-1', 3 mobile atmospheric measuring stations, 2 mobile soil and water measuring stations, 4 sampling cars constructed by Environment/SA and EKROS Engineering, a complete Chemical analysis laboratory which can handle ppb analysis of toxic gases, organics and minerals pollutants, an information collection center and a meteo station which can retrieve, display and archive all the data or alarm from the stationary and mobile stations. Antea Group has provided a technical expertise and various negotiations during the negotiation phase, the project initiation files and contracts redaction, the project Monitoring and reporting to stakeholders, the Rex. Up to 2009, No other site of the world uses such an

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Lineage-specific responses of microbial communities to environmental change.

    Science.gov (United States)

    Youngblut, Nicholas D; Shade, Ashley; Read, Jordan S; McMahon, Katherine D; Whitaker, Rachel J

    2013-01-01

    A great challenge facing microbial ecology is how to define ecologically relevant taxonomic units. To address this challenge, we investigated how changing the definition of operational taxonomic units (OTUs) influences the perception of ecological patterns in microbial communities as they respond to a dramatic environmental change. We used pyrosequenced tags of the bacterial V2 16S rRNA region, as well as clone libraries constructed from the cytochrome oxidase C gene ccoN, to provide additional taxonomic resolution for the common freshwater genus Polynucleobacter. At the most highly resolved taxonomic scale, we show that distinct genotypes associated with the abundant Polynucleobacter lineages exhibit divergent spatial patterns and dramatic changes over time, while the also abundant Actinobacteria OTUs are highly coherent. This clearly demonstrates that different bacterial lineages demand different taxonomic definitions to capture ecological patterns. Based on the temporal distribution of highly resolved taxa in the hypolimnion, we demonstrate that change in the population structure of a single genotype can provide additional insight into the mechanisms of community-level responses. These results highlight the importance and feasibility of examining ecological change in microbial communities across taxonomic scales while also providing valuable insight into the ecological characteristics of ecologically coherent groups in this system.

  7. Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

  8. 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...

  9. Technical, economic and environmental potential of co-firing of biomass in coal and natural gas fired power plants in the Netherlands

    International Nuclear Information System (INIS)

    Van Ree, R.; Korbee, R.; Eenkhoorn, S.; De Lange, T.; Groenendaal, B.

    2000-01-01

    In this paper the technical, economic, and environmental potential of co-firing of biomass in existing Dutch coal and natural gas fired power plants, and industrial combined-cycles (CC), is addressed. Main criteria that are considered are: the availability and contractibility of biomass for energy purposes; the (technical) operation of the conventional fossil fuel based processes may not be disturbed; the gaseous and liquid plant emissions have to comply to those applicable for power plants/CCs, the commercial applicability of the solid residues may not be negatively influenced; applicable additional biomass conversion technologies must be commercially available; the necessary additional investment costs must be acceptable from an economic point of view, and the co-firing option must result in a substantial CO 2 -emission reduction. The main result of the study described in the paper is the presentation of a clear and founded indication of the total co-firing potential of biomass in existing power plants and industrial CCs in the Netherlands. This potential is determined by considering both technical, economic, and environmental criteria. In spite of the fact that the co-firing potential for the specific Dutch situation is presented, the results of the criteria considered are more generally applicable, and therefore are also very interesting for potential co-firing initiatives outside of the Netherlands

  10. Technical procedures for implementation of acoustics site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-09-01

    The purpose and scope of the technical procedure for processing data from the tethered meteorological system are covered. Definitions, interfaces, and concurrent data needs are also addressed. This technical procedure describes how to control, organize, verify, and archive tethered meteorological system data. These data will be received at the processing location from the field measurement location and are part of the characterization of the Deaf Smith County Site, Texas for the salt repository program. These measurements will be made in support of the sound propagation study and are a result of environmental data requirements for acoustics. 6 refs., 15 figs., 5 tabs

  11. Environmental Restoration Site-Specific Plan for the Paducah Gaseous Diffusion Plant, FY 93

    International Nuclear Information System (INIS)

    1993-01-01

    This report provides an overview of the major Environmental Restoration (ER) concerns at Paducah Gaseous Diffusion Plant (PGDP). The identified solid waste management units at PGDP are listed. In the Department of Energy (DOE) Five Year Plan development process, one or more waste management units are addressed in a series of activity data sheets (ADSs) which identify planned scope, schedule, and cost objectives that are representative of the current state of planned technical development for individual or multiple sites

  12. 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...

  13. 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...

  14. 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...

  15. 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.

  16. 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.

  17. 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

  18. 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.)

  19. 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.

  20. ANL technical support program for DOE Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J.; Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L.; Ewing, R.C.; Wang, L.; Li, H.; Tomozawa, M.

    1993-05-01

    A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods

  1. Weeks Island brine diffuser site study: baseline conditions and environmental assessment technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-12

    This technical report presents the results of a study conducted at two alternative brine diffuser sites (A and B) proposed for the Weeks Island salt dome, together with an analysis of the potential physical, chemical, and biological effects of brine disposal for this area of the Gulf of Mexico. Brine would result from either the leaching of salt domes to form or enlarge oil storage caverns, or the subsequent use of these caverns for crude oil storage in the Strategic Petroleum Reserve (SPR) program. Brine leached from the Weeks Island salt dome would be transported through a pipeline which would extend from the salt dome either 27 nautical miles (32 statute miles) for Site A, or 41 nautical miles (47 statute miles) for Site B, into Gulf waters. The brine would be discharged at these sites through an offshore diffuser at a sustained peak rate of 39 ft/sup 3//sec. The disposal of large quantities of brine in the Gulf could have a significant impact on the biology and water quality of the area. Physical and chemical measurements of the marine environment at Sites A and B were taken between September 1977 and July 1978 to correlate the existing environmental conditions with the estimated physical extent of tthe brine discharge as predicted by the MIT model (US Dept. of Commerce, 1977a). Measurements of wind, tide, waves, currents, and stratification (water column structure) were also obtained since the diffusion and dispersion of the brine plume are a function of the local circulation regime. These data were used to calculate both near- and far-field concentrations of brine, and may also be used in the design criteria for diffuser port configuration and verification of the plume model. Biological samples were taken to characterize the sites and to predict potential areas of impact with regard to the discharge. This sampling focused on benthic organisms and demersal fish. (DMC)

  2. Technical, environmental, and socioeconomic factors associated with dry-cooled nuclear energy centers

    International Nuclear Information System (INIS)

    1976-04-01

    The report includes a review of the current state-of-the-art of dry-cooling technology for industrial and power-generating facilities and an evaluation of its technical potential and cost for large nuclear power plants. Criteria are formulated for coarse screening of the arid regions of the Western United States to select a surrogate site for more detailed site-specific analyses. The screening criteria included seismic considerations, existing transportation facilities, institutional and jurisdictional constraints, waste heat dissipation effects, water requirements, and ecologic and socioeconomic considerations. The Galt site near Las Vegas, Nevada was selected for the surrogate site analysis to assess important issues related to the construction and operation of twelve dry-cooled nuclear power plants at an arid location remote from major load centers. The assessment covers geotechnical, atmospheric and hydrologic considerations, special aspects of transporting large equipment overland to the site from seaports, analyses of potential transmission routes to major load centers, local institutional and taxing provisions, and ecologic and socioeconomic impacts

  3. Technical, environmental, and socioeconomic factors associated with dry-cooled nuclear energy centers

    Energy Technology Data Exchange (ETDEWEB)

    1976-04-01

    The report includes a review of the current state-of-the-art of dry-cooling technology for industrial and power-generating facilities and an evaluation of its technical potential and cost for large nuclear power plants. Criteria are formulated for coarse screening of the arid regions of the Western United States to select a surrogate site for more detailed site-specific analyses. The screening criteria included seismic considerations, existing transportation facilities, institutional and jurisdictional constraints, waste heat dissipation effects, water requirements, and ecologic and socioeconomic considerations. The Galt site near Las Vegas, Nevada was selected for the surrogate site analysis to assess important issues related to the construction and operation of twelve dry-cooled nuclear power plants at an arid location remote from major load centers. The assessment covers geotechnical, atmospheric and hydrologic considerations, special aspects of transporting large equipment overland to the site from seaports, analyses of potential transmission routes to major load centers, local institutional and taxing provisions, and ecologic and socioeconomic impacts.

  4. Environmental Restoration Site-Specific Plan for the Portsmouth Gaseous Diffusion Plant, FY 93

    International Nuclear Information System (INIS)

    1993-01-01

    The purpose of this Site-Specific Plan (SSP) is to describe past, present, and future activities undertaken to implement Environmental Restoration and Waste Management goals at the Portsmouth Gaseous Diffusion Plant (PORTS). The SSP is presented in sections emphasizing Environmental Restoration description of activities, resources, and milestones

  5. Goal specificity: a proxy measure for improvements in environmental outcomes in collaborative governance.

    Science.gov (United States)

    Biddle, Jennifer C; Koontz, Tomas M

    2014-12-01

    Collaborative governance critics continually call for evidence to support its prevalent use. As is often the case in environmental policy, environmental outcomes occur at a rate incompatible with political agendas. In addition, a multitude of possibly confounding variables makes it difficult to correlate collaborative governance processes with environmental outcomes. The findings of this study offer empirical evidence that collaborative processes have a measurable, beneficial effect on environmental outcomes. Through the use of a unique paired-waterbody design, our dataset reduced the potential for confounding variables to impact our environmental outcome measurements. The results of a path analysis indicate that the output of setting specific pollutant reduction goals is significantly related to watershed partnerships' level of attainment of their environmental improvement goals. The action of setting specific goals (e.g. percentage of load reductions in pollutant levels) is fostered by sustained participation from partnership members throughout the lifecycle of the collaborative. In addition, this study demonstrates the utility of logic modeling for environmental planning and management, and suggests that the process of setting specific pollutant reduction goals is a useful proxy measure for reporting progress towards improvements in environmental outcomes when long-term environmental data are not available. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. 78 FR 14088 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-03-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act requires that public notice of this meeting be announced in the Federal Register.

  7. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  8. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  9. Technical assessment of environmental and cost implications of superconducting super collider decommissioning

    International Nuclear Information System (INIS)

    Chen, S.Y.; Opelka, J.H.; Chambers, W.C.; Stavrou, J.

    1988-07-01

    Potential environmental and cost implications of decommissioning the proposed Superconducting Super Collider (SSC) are examined. One decommissioning alternative is selected for general assessment. That alternative includes removal of the major sources of radioactivity induced during operation and temporary entombment of remaining underground facilities. On the suface, the campus complex would be left in place for future use, but most other aboveground features would be dismantled and removed. Because of the low level of radioactivity that would be induced in SSC components during system operation, potential radiological impacts to the environment from decommissioning would be benign, and the estimated total occupational radiation dose to workers would be less that 5 person-rem. Potential nonradiological impacts of decommissioning are not evaluated because of the lack of site-specific data. The total estimated cost of decommissioning operations is $38 million. Although few current regulations are explicitly applicable, the SSC decommissioning operation should not encounter any difficulty in complying with potentially applicable regulatory constraints. Upon completion of decommissioning, the SSC site surface could be returned to unrestricted use, but it is recommended that a degree of institutional control and environmental monitoring be carried out for a short period following decommissioning. 11 refs., 8 figs., 6 tabs

  10. 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

  11. 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.

  12. 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

  13. Development and validation of Burkholderia pseudomallei-specific real-time PCR assays for clinical, environmental or forensic detection applications.

    Directory of Open Access Journals (Sweden)

    Erin P Price

    Full Text Available The bacterium Burkholderia pseudomallei causes melioidosis, a rare but serious illness that can be fatal if untreated or misdiagnosed. Species-specific PCR assays provide a technically simple method for differentiating B. pseudomallei from near-neighbor species. However, substantial genetic diversity and high levels of recombination within this species reduce the likelihood that molecular signatures will differentiate all B. pseudomallei from other Burkholderiaceae. Currently available molecular assays for B. pseudomallei detection lack rigorous validation across large in silico datasets and isolate collections to test for specificity, and none have been subjected to stringent quality control criteria (accuracy, precision, selectivity, limit of quantitation (LoQ, limit of detection (LoD, linearity, ruggedness and robustness to determine their suitability for environmental, clinical or forensic investigations. In this study, we developed two novel B. pseudomallei specific assays, 122018 and 266152, using a dual-probe approach to differentiate B. pseudomallei from B. thailandensis, B. oklahomensis and B. thailandensis-like species; other species failed to amplify. Species specificity was validated across a large DNA panel (>2,300 samples comprising Burkholderia spp. and non-Burkholderia bacterial and fungal species of clinical and environmental relevance. Comparison of assay specificity to two previously published B. pseudomallei-specific assays, BurkDiff and TTS1, demonstrated comparable performance of all assays, providing between 99.7 and 100% specificity against our isolate panel. Last, we subjected 122018 and 266152 to rigorous quality control analyses, thus providing quantitative limits of assay performance. Using B. pseudomallei as a model, our study provides a framework for comprehensive quantitative validation of molecular assays and provides additional, highly validated B. pseudomallei assays for the scientific research community.

  14. Background information and technical basis for assessment of environmental implications of magnetic fusion energy

    International Nuclear Information System (INIS)

    Cannon, J.B.

    1983-08-01

    This report contains background information for assessing the potential environmental implications of fusion-based central electric power stations. It was developed as part of an environmental review of the Magnetic Fusion Energy Program. Transition of the program from demonstration of purely scientific feasibility (breakeven conditions) to exploration of engineering feasibility suggests that formal program environmental review under the National Environmental Policy Act is timely. This report is the principal reference upon which an environmental impact statement on magnetic fusion will be based

  15. 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

  16. Technical procedures for implementation of background environmental radioactivity site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-09-01

    The purpose of this technical procedure is to describe the method for performing field maintenance on low-volume air samplers and the associated topics of personnel and organization, procedure preparation, documentation, and quality assurance. The scope of this procedure includes the maintenance of low-volume air samplers in the field and does not encompass maintenance performed by the manufacturer

  17. Technical Specifications: Fermi-2 (Docket No. 50-341). Appendix A to License No. NPF-43

    International Nuclear Information System (INIS)

    1985-07-01

    Limiting conditions for operation and surveillance requirements are presented for reactor 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; and radiological environmental monitoring

  18. 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.

  19. SIMS study on statistics and environmental factors in health. Final technical report to Department of Energy

    International Nuclear Information System (INIS)

    1982-07-01

    This final technical report to DOE consists of five individual technical reports and one working paper by members of the SIMS Study at Stanford. Research topics include testing goodness-of-fit for the distribution of errors in regression models, mathematical models of cancer and their use in risk assessment, pollutant standards index (Psi), osteosarcomas among beagles exposed to 239 Plutonium, air pollution and respiratory disease, and models of human exposure to air pollution. Individual summaries of the six reports are indexed separately

  20. National Institute for Global Environmental Change. Final Technical Report 1990-2007

    Energy Technology Data Exchange (ETDEWEB)

    Athanasios Toulopoulos

    2007-11-01

    Research conducted by the six NIGEC Regional Centers during recent years is reported. An overview of the NIGEC program from its beginnings provides a description and evaluation of the program's vision, strategy and major accomplishments. The program's purpose was to support academic research on environmental change in regions of the country that had historically received relatively little federal funding. The overall vision of NIGEC may be stated as the performance of academic research on the regional interactions between ecosystems and climate. NIGEC's research presents important evidence on the impacts of climate variability and change, and in some cases adaptability, for a broad range of both managed and unmanaged ecosystems, and has thereby documented significant regional issues on the environmental responses to climate change. NIGEC's research has demonstrated large regional differences in the atmospheric carbon exchange budgets of croplands and forests, that there are significant variations of this exchange on diurnal, synoptic, seasonal and interannual time scales due to atmospheric variability (including temperature, precipitation and cloudiness), and that management practices and past history have predominant effects in grasslands and croplands. It is the mid-latitude forests, however, that have received more attention in NIGEC than any other specific ecosystem, and NIGEC's initiation of and participation in the AmeriFlux program, network of carbon flux measurement sites in North American old-growth forests, is generally considered to be its most significant single accomplishment. By including appendices with complete listings of NIGEC publications, principal investigators and participating institutions, this report may also serve as a useful comprehensive documentation of NIGEC.

  1. 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...

  2. 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

  3. 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...

  4. DOE Chair of Excellence in Environmental Disciplines-Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Kurunganty, Sastry; Loran, Roberto; Roque-Malherbe, Rolando; Hijazi, Yazan; Nieto, Santander; Gomez, Will A.; Duconge, Jose; Cotto, María del C.; Muniz, Carlos; Diaz, Francisco J.; Neira, Carlos F.; Marquez, Francisco; Del Valle, W.; Thommes, M.

    2014-02-19

    The report Massie Chair of Excellence Program at Universidad del Turabo, contract DE-FG02-95EW12610, during the period of 9/29/1995 to 9/29/2011. The initial program aims included development of academic programs in the Environmental Sciences and Engineering, and Research and Development focused initially on environmentally friendly processes and later revised also include: renewable energy and international cooperation. From 1995 -2005, the Program at UT lead the establishment of the new undergraduate program in electrical engineering at the School of Engineering (SoE), worked on requirements to achieve ABET accreditation of the SoE B.S. Mechanical Engineering and B.S. Electrical Engineering programs, mentored junior faculty, taught undergraduate courses in electrical engineering, and revised the electrical engineering curriculum. Engineering undergraduate laboratories were designed and developed. The following research sub-project was developed: Research and development of new perovskite-alumina hydrogen permeable asymmetrical nanostructured membranes for hydrogen purification, and extremely high specific surface area silica materials for hydrogen storage in the form of ammonia, Dr. Rolando Roque-Malherbe Subproject PI, Dr. Santander Nieto and Mr. Will Gómez Research Assistants. In 2006, the Massie Chair of Excellence Program was transferred to the National Nuclear Security Agency, NNSA and DNN. DoE required a revised proposal aligned with the priorities of the Administration. The revised approved program aims included: (1) Research (2) Student Development: promote the development of minority undergraduate and graduate students through research teams, internships, conferences, new courses; and, (3) Support: (a) Research administration and (b) Dissemination through international conferences, the UT Distinguished Lecturer Series in STEM fields and at the annual Universidad del Turabo (UT) Researchers Conference. Research included: Sub-Project 1: Synthesis and

  5. Recent developments in uranium exploration, production and environmental issues. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-09-01

    The uranium industry is in a period of transition. In Europe, the industry is in transition from uranium production to site rehabilitation. The WISMUT project in Germany, which is featured in this publication, is the largest and one of the most advanced rehabilitation projects in the world. By contrast, other countries such as China, India and Argentina are expanding their industries to meet growing uranium demand. Activities in these countries, which are also described in this publication, range from new project licensing to application of new technology to increase productivity and lower costs at existing operations. Changes within the uranium industry are nowhere more evident than in the marketplace, where the price of uranium has more than doubled in the past two years. There is a discussion of the reasons for this price rise and the adequacy of production capacity to meet reactor uranium requirements. Many developing countries are striving for self-sufficiency in their uranium production capabilities. Accordingly, the papers deal with a range of topics including uranium exploration, project licensing, and research directed towards improving uranium production efficiency and costs. European papers emphasize uranium site rehabilitation, reflecting the fact that uranium production has all but ceased in Europe. These papers describe site remediation technology that is being utilized at a variety of sites ranging from tailings ponds to mine water treatment plants. The recent rapid increase in the uranium market price has dominated discussions among uranium producers and users alike. Not surprisingly the price increase was also a much-discussed topic at this Technical Meeting. One paper reviewed the reasons for the rapid price increase and the relationship between market price and uranium supply-demand relationships. Uranium production is likely to become more important to Niger's economy if the recent price increase is sustainable. Accordingly, Niger's uranium

  6. 77 FR 74838 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2012-12-18

    ...This notice announces a combined meeting of the Environmental Monitoring, Surveillance and Remediation Committee and Waste Management Committee of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico (known locally as the Northern New Mexico Citizens' Advisory Board [NNMCAB]). The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  7. 78 FR 10612 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2013-02-14

    ...This notice announces a combined meeting of the Environmental Monitoring, Surveillance and Remediation Committee and Waste Management Committee of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico (known locally as the Northern New Mexico Citizens' Advisory Board [NNMCAB]). The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  8. 77 FR 64800 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2012-10-23

    ...This notice announces a combined meeting of the Environmental Monitoring, Surveillance and Remediation Committee and Waste Management Committee of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico (known locally as the Northern New Mexico Citizens' Advisory Board [NNMCAB]). The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  9. 78 FR 4140 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2013-01-18

    ...This notice announces a combined meeting of the Environmental Monitoring, Surveillance and Remediation Committee and Waste Management Committee of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico (known locally as the Northern New Mexico Citizens' Advisory Board [NNMCAB]). The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  10. 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

  11. 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...

  12. 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.

  13. 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.

  14. 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....

  15. Environmental restoration and waste management Site-Specific Plan for the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    1993-01-01

    The United States Department of Energy (DOE) is committed to achieving and maintaining environmental regulatory compliance while responding to public concerns and emphasizing waste minimization. DOE publishes the Environmental Restoration and Waste Management Five-Year Plan (FYP) annually to document its progress towards these goals. The purpose of this Site-Specific Plan (SSP) is to describe the activities undertaken to implement the FYP goals at the DOE Oak Ridge Field Office (DOE/OR) installations and programs specifically for the Oak Ridge Reservation (ORR) and surrounding areas. This SSP addresses activities and goals to be accomplished during FY93 even through the FYP focuses on FY94

  16. Technical Management in an Age of Openness: The Political, Public, and Environmental Forest Ranger

    Science.gov (United States)

    Anderson, Sarah E.; Hodges, Heather E.; Anderson, Terry L.

    2013-01-01

    Modern bureaucracy faces trade-offs between public and congressional input and agency expertise. The U.S. Forest Service offers an opportunity to quantitatively analyze whether an agency that is required to be more open to the public and congressional input will be forced to ignore its technical expertise in managing resources. This study uses…

  17. Sandia Transportation Technical Environmental Information Center and its application to transportation risk analyses

    International Nuclear Information System (INIS)

    Foley, J.T.; Davidson, C.A.; McClure, J.D.

    1978-01-01

    Purpose of this paper is to describe an applied research activity which is fundamental to the conduct of transportation analyses: the collection, analysis, storage, and retrieval of information on the intensities of technical environments. This paper describes the collection system which provides such a service to official researchers in transportation analysis and the applications of this information in the area of risk analysis

  18. Economic and environmental consequences of technical and institutional change in Dutch dairy farming.

    NARCIS (Netherlands)

    Berentsen, P.B.M.; Giesen, G.W.J.; Renkema, J.A.

    1997-01-01

    A linear programming model of a dairy farm was used to explore the future for different types of Dutch dairy farms under different scenarios. The scenarios are consistent sets of changing factors that are considered external at farm level. The factors included are technical, such as efficiency of

  19. Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-09-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

  20. Technical and environmental assessment of the scrap tire vacuum pyrolysis process

    International Nuclear Information System (INIS)

    Roy, C.; Caumia, B. de; Lebrecque, B.; Blanchette, D.; Pakdel, H.; Roy, V.

    1991-01-01

    Tire recycling has become a necessity because of the huge piles of tires which represent a threat to the environment. There is about one worn tire produced per year and per person in the developed countries. The used tires represent a source of energy and valuable chemical products. By thermal decomposition of rubber under reduced pressure, it is possible to recover the useful compounds. A step by step approach has been used, from bench-scale batch systems, to process development and finally pilot plant, to experiment and develop vacuum pyrolysis of used tires. Yields are: 55% oil, 25% carbon black, 9% steel, 5% fiber and 6% gas. The maximum recovery of oil was performed at 415 degree C below 2 kPa abs. The specific gravity of this oil was 0.95, its gross heating value was 43 MJ/kg and total sulfur content about 0.8%. It was rich in limonene, benzol and other petrochemical components. The carbon black favorably compared with the low standard grades and may find an application in low grade rubber goods following further research and development. From an environmental point of view, the quality of the gas emissions was found to be acceptable based on the province of Quebec regulations. The aqueous phase contains toxic substances which will be eliminated after blending and burning it with pyrolysis oils used to heat up the reactor. The heat of pyrolysis for the reactions is low, estimated around 700 kJ/kg. The process has been tested in a 200 kg/h pilot plant, which positively demonstrated the possibility of continuously feeding large chunks of rubber under a vacuo. The process feasibility is promising, with returns on the investment of 31% after three years of operation. 9 refs., 4 figs., 8 tabs

  1. 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

  2. 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

  3. A paler shade of green : Environmental policy under induced technical change

    NARCIS (Netherlands)

    Di Maria, C.; Smulders, Sjak

    2017-01-01

    Conventional wisdom argues that environmental policy is less costly if it induces the development of cleaner technologies. In contrast to this argument, we show that once the second-best nature of actual economies is taken into account, the cost of environmental policy may well be larger with

  4. Combining Technical Competence and Stakeholder Impact in Environmental Education: The Gambia All Schools Nursery Competition

    Science.gov (United States)

    Paulete, Francisca E.; Orr, Blair

    2010-01-01

    Under the guidance of the Department of Forestry, the Regional Education Directorate, and Peace Corps/The Gambia, the Gambia All Schools Tree Nursery Competition, an environmental education program, was developed to introduce practical environmental education in The Gambia. Data for this report were collected using a rapid appraisal approach.…

  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. Environmental Restoration and Waste Management Site-Specific Plan (SSP) for fiscal year 1992 (FY92)

    International Nuclear Information System (INIS)

    1991-09-01

    The FY-92 Site-Specific Plan (FY-92 SSP) for environmental restoration and waste management at the Idaho National Engineering Laboratory (INEL) is designed to provide the reader with easy access to the status of environmental restoration and waste management activities at INEL. The first chapter provides background on INIEL's physical environment, site history and mission, and general information about the site and its facilities. In addition, this chapter discusses the inter-relationships between the Site Specific Plan, the Environmental Restoration and Waste Management Five-Year Plan, the environmental restoration and waste management prioritization systems, and the Activity Data Sheets (ADSs) for environmental restoration and waste management. This discussion should help readers understand what the SSP is and how it fits into the environmental restoration and waste management process at INEL. This understanding should provide the reader with a better context for understanding the discussions in the SSP as well as a better feel for how and what to comment on during the public comment period that will be held from the first of September through the end of October 1991

  7. Experts' perspective on the performance of Chinese technical guidelines for Plan Environmental Impact Assessment

    International Nuclear Information System (INIS)

    He Jia; Sun Sun; Bao Cunkuan; Chen Fan; Jiang Dahe

    2011-01-01

    This research was to evaluate the Technical Guideline (HJ/T130-2003) effectiveness based on data resource from a questionnaire survey and interviews on EIA experts. The result demonstrated that the guideline served mainly as a quality control measure for PEIA products, and only a small proportion of experts considered it effective due to its inconsistency with the newly released Chinese PEIA Regulation (2009) and poor practicability. Current status of SEA implementation in China was also studied in terms of application fields, effectiveness evaluation, and major issues to affect SEA, to conclude that SEA implementation in China is premature, and with limited effectiveness. The major problem was the lack of effective methodologies and technical tools. Recommendations for revising the PEIA Guideline and advices to improving SEA implementation in China were accordingly proposed.

  8. Development of a site specific environmental radiation assessment model for Youngkwang NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yang Geun; Song, Myung Jae; Shon, Soon Hwan; Shin, Sang Woon; Lee, Gap Bock; Yang, Kyung Hwa [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Seong Pyung; Kim, Jeong Kyu; Shin, Dae Yoon; Kim, Hyun Ku; Lee, Kyung Jin [Chosun University, Kwangju (Korea, Republic of)

    1996-12-31

    During the normal operation of nuclear power plants, a very small amount of radionuclide materials is released to the environment. The radionuclide releases to the environment may give rise to some additional radiation dose through a number of pathways. With a few exception, radionuclide transports are highly dependent on the environmental conditions such as topological features, atmospheric and oceanic conditions and socio-environmental characteristics, etc. The dose calculation in Korea are presently being performed using the models in US NRC Reg. Guide. However, these models which were originally released by the US NRC in 1977 are inadequate to deal with environmental movement of radionuclides in consideration of complex terrain, tidal condition of the Yellow Sea, and Youngkwang site specific conditions. KEPRI has developed the models to consider the site specific characteristics around Youngkwang NPPs, to give the realistic dose assessment, and to improve assurance and reliability in public dose calculation. (author). 41 figs., 70 refs.

  9. 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

  10. Strategy for assessing the technical, environmental, and engineering feasibility of subseabed disposal

    International Nuclear Information System (INIS)

    Anderson, D.R.; Boyer, D.G.; Herrmann, H.; Kelly, J.; Talbert, D.M.

    1980-01-01

    This paper presents the strategy and management techniques used in the development of the US Subseabed Disposal Program (SDP) for possible disposal of both high-level waste and spent fuel. These have been developed through joint efforts of the Department of Energy (DOE), Division of Waste Isolation, the Sandia Technical Program Manager, the Technical Program Coordinators, the Advisory Group, and the Principal Investigators. Three subsections of this paper address the various components which make up the SDP strategy and management techniques. The first section will summarize the US DOE high-level waste and spent fuel disposal program and the position that the SDP occupies within that program. The second section, the Subseabed Program Plan, addresses the technical and administrative tools which are employed to facilitate the day-to-day operation of the SDP. The third section addresses the current studies and future plans for addressing the legal, political, and international uncertainties that must be resolved prior to the time the SDP reaches the final engineering phases

  11. 15 CFR 291.4 - National industry-specific pollution prevention and environmental compliance resource centers.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false National industry-specific pollution prevention and environmental compliance resource centers. 291.4 Section 291.4 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY, DEPARTMENT OF COMMERCE NIST EXTRAMURAL PROGRAM...

  12. 75 FR 64718 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2010-10-20

    ... Test Site including decontamination, closure, re-use and/or demolition. Purpose of the Soils Committee: The purpose of the Committee is to focus on issues related to soil contamination at the Nevada Test... Industrial Sites and Soils Committees of the Environmental Management Site-Specific Advisory Board (EM SSAB...

  13. 76 FR 5365 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2011-01-31

    ... Industrial Sites and Soils Committees of the Environmental Management Site-Specific Advisory Board (EM SSAB... sites at the Nevada National Security Site including decontamination, closure, re-use and/or demolition. Purpose of the Soils Committee: The purpose of the Committee is to focus on issues related to soil...

  14. 75 FR 71677 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2010-11-24

    ... Industrial Sites and Soils Committees of the Environmental Management Site-Specific Advisory Board (EM SSAB... sites at the Nevada Test Site including decontamination, closure, re-use and/or demolition. Purpose of the Soils Committee: The purpose of the Committee is to focus on issues related to soil contamination...

  15. 78 FR 26005 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-05-03

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  16. 78 FR 73519 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-12-06

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  17. 78 FR 45518 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-07-29

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  18. 78 FR 58294 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Science.gov (United States)

    2013-09-23

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Idaho National Laboratory. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  19. 78 FR 38969 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-06-28

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  20. 78 FR 23760 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2013-04-22

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  1. 78 FR 61348 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2013-10-03

    ...On September 16, 2013, in FR Doc. 2013-22453, on page 56871, the Department of Energy (DOE) published a notice of open meeting announcing a meeting on October 2, 2013 of the Environmental Management Site-Specific Advisory Board, Portsmouth (78 FR 56871). This notice announces the cancellation of this meeting.

  2. 78 FR 65979 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-11-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  3. 77 FR 50488 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-08-21

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  4. 78 FR 12746 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-02-25

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  5. 78 FR 40130 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2013-07-03

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  6. 78 FR 75552 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-12-12

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  7. 77 FR 65374 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Science.gov (United States)

    2012-10-26

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Idaho National Laboratory. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  8. 78 FR 17192 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2013-03-20

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  9. 78 FR 44942 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-07-25

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  10. 77 FR 31837 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2012-05-30

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  11. 78 FR 63172 - Environmental Management Site-Specific Advisory Board, Paducah; Meeting

    Science.gov (United States)

    2013-10-23

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  12. 77 FR 2713 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2012-01-19

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  13. 77 FR 26273 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2012-05-03

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  14. 77 FR 24695 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-04-25

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. . 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  15. 77 FR 55813 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2012-09-11

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  16. 77 FR 47047 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2012-08-07

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  17. 78 FR 49738 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-08-15

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  18. 78 FR 64208 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2013-10-28

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  19. 77 FR 28368 - Environmental Management Site-Specific Advisory Board, Hanford

    Science.gov (United States)

    2012-05-14

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Hanford. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  20. 77 FR 18243 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2012-03-27

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  1. 78 FR 54460 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-09-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  2. 77 FR 60688 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-10-04

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  3. 78 FR 17648 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-03-22

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  4. 77 FR 18242 - Environmental Management Site-Specific Advisory Board Chairs

    Science.gov (United States)

    2012-03-27

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  5. 78 FR 23241 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-04-18

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  6. 78 FR 46330 - Environmental Management Site-Specific Advisory Board, Nevada

    Science.gov (United States)

    2013-07-31

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Nevada. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  7. 78 FR 25064 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-04-29

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  8. 78 FR 38305 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2013-06-26

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  9. 78 FR 69657 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2013-11-20

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  10. 77 FR 49442 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2012-08-16

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  11. 77 FR 13104 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-03-05

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  12. 77 FR 53192 - Environmental Management Site-Specific Advisory Board, Idaho National Laboratory

    Science.gov (United States)

    2012-08-31

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Idaho National Laboratory. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  13. 77 FR 39235 - Environmental Management Site-Specific Advisory Board, Savannah River Site

    Science.gov (United States)

    2012-07-02

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Savannah River Site. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  14. 77 FR 58364 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2012-09-20

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  15. 78 FR 78952 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-12-27

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  16. 77 FR 16021 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2012-03-19

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  17. 78 FR 16260 - Environmental Management Site-Specific Advisory Board, Paducah

    Science.gov (United States)

    2013-03-14

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  18. 77 FR 76475 - Environmental Management Site-Specific Advisory Board, Northern New Mexico

    Science.gov (United States)

    2012-12-28

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Northern New Mexico. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  19. 78 FR 30911 - Environmental Management Site-Specific Advisory Board, Oak Ridge Reservation

    Science.gov (United States)

    2013-05-23

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Oak Ridge Reservation. The Federal Advisory Committee Act (Pub. L. No. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.

  20. 78 FR 22255 - Environmental Management Site-Specific Advisory Board, Portsmouth

    Science.gov (United States)

    2013-04-15

    ...This notice announces a meeting of the Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act (Pub. L. 92-463, 86 Stat. 770) requires that public notice of this meeting be announced in the Federal Register.