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Sample records for assured isolation facility

  1. Licensing an assured isolation facility for low-level radioactive waste. Volume 1: Licensing strategy and issues

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  2. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, D.J.; Bauser, M.A. [Morgan, Lewis and Bockius, Washington, DC (United States); Baird, R.D. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application.

  3. Licensing an assured isolation facility for low-level radioactive waste. Volume 2: Recommendations on the content and review of an application

    International Nuclear Information System (INIS)

    Silverman, D.J.; Bauser, M.A.; Baird, R.D.

    1998-07-01

    This report provides a detailed set of proposed criteria and guidance for the preparation of a license application for an assured isolation facility (AIF). The report is intended to provide a detailed planning basis upon which a prospective applicant may begin pre-licensing discussions with the Nuclear Regulatory Commission and initiate development of a license application. The report may also be useful to the NRC or to state regulatory agencies that may be asked to review such an application. Volume 1 of this report provides background information, and describes the licensing approach and methodology. Volume 2 identifies specific information that is recommended for inclusion in a license application

  4. Quality Assurance for Operation of Nuclear Facilities

    International Nuclear Information System (INIS)

    Park, C. G.; Kwon, H. I.; Kim, K. H.; Oh, Y. W.; Lee, Y. G.; Ha, J. H.; Lim, N. J.

    2008-12-01

    This report describes QA activities performed within 'Quality Assurance for Nuclear facility project' and results thereof. Efforts were made to maintain and improve quality system of nuclear facilities. Varification activities whether quality system was implemented in compliance with requirements. QA department assisted KOLAS accredited testing and calibration laboratories, ISO 9001 quality system, establishment of QA programs for R and D, and carried out reviews and surveys for development of quality assurance technologies. Major items of this report are as follows : - Development and Improvement of QA Programs - QA Activities - Assessment of Effectiveness and Adequacy for QA Programs

  5. Exploratory Shaft Facility quality assurance impact evaluation

    International Nuclear Information System (INIS)

    1987-08-01

    This report addresses the impact of the quality assurance practices used for the Exploratory Shaft Facility (ESF) design, and construction in licensing as part of the repository. Acceptance criteria used for evaluating the suitability of ESF QA practices are based on documents that had not been invoked for repository design or construction activities at the time of this evaluation. This report identifies the QA practices necessary for ESF design and construction licensability. A review and evaluation of QA practices for ESF design and construction resulted in the following conclusions. QA practices were found to be acceptable with a few exceptions. QA practices for construction activities were found to be insufficiently documented in implementing procedures to allow a full and effective evaluation for licensing purposes. Recommendations are provided for mitigating impacts to ensure compatibility of the QA practices with those considered necessary for repository licensing. 8 refs., 3 tabs

  6. QART - the CERN facility for quality assurance

    CERN Multimedia

    Katarina Anthony

    2011-01-01

    How would your detector perform in a very high magnetic field? Or at 60°C and high humidity? Will it work for 10 or more years? Answering these questions requires specialised and thorough testing. This can be done at the Quality Assurance and Reliability Testing Laboratory (QART) - a top-notch testing facility based at CERN, providing invaluable support for CERN projects. The QART lab has become a service in 2011, and invites all projects to use its equipment and expertise.   A portable high-sensitivity infra-red thermal imaging video camera (top left) is used to observe the thermal profile of a silicon strip sensor (top right). The thermal images taken before (bottom left) and after (bottom right) applying voltage to the device clearly show a hot spot developing on the sensor, indicating a serious defect. The infra-red camera is an example of the variety of sophisticated equipment in the QART lab available to CERN projects for the analysis of problems and enviro...

  7. 200 Area Liquid Effluent Facilities -- Quality assurance program plan

    International Nuclear Information System (INIS)

    Fernandez, L.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements

  8. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    International Nuclear Information System (INIS)

    Frazier, T.P.

    1994-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans

  9. Near-facility environmental monitoring quality assurance project plan

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1997-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near facility environmental monitoring performed by Waste Management Federal Services, Inc., Northwest Operations and supersedes WHC-EP-0538-2. This plan applies to all sampling and monitoring activities performed by waste management Federal Services, Inc., Northwest Operations in implementing facility environmental monitoring at the Hanford Site

  10. Project quality assurance plant: Sodium storage facility, project F-031

    International Nuclear Information System (INIS)

    Shultz, J.W.; Shank, D.R.

    1994-11-01

    The Sodium Storage Facility Project Quality Assurance Plan delineates the quality assurance requirements for construction of a new facility, modifications to the sodium storage tanks, and tie-ins to the FFTF Plant. This plan provides direction for the types of verifications necessary to satisfy the functional requirements within the project scope and applicable regulatory requirements determined in the Project Functional Design Criteria (FDC), WHC-SD-FF-FDC-009

  11. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1991-06-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs

  12. Near-Facility Environmental Monitoring Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    MCKINNEY, S.M.

    2000-01-01

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the preoperational and near-facility environmental monitoring directed by Waste Management Technical Services and supersedes HNF-EP-0538-4. This plan applies to all sampling and monitoring activities performed by Waste Management Technical Services in implementing near-facility environmental monitoring at the Hanford Site. This Quality Assurance Project Plan is required by U.S. Department of Energy Order 5400.1 (DOE 1990) as a part of the Environmental Monitoring Plan (DOE-RL 1997) and is used to define: Environmental measurement and sampling locations used to monitor environmental contaminants near active and inactive facilities and waste storage and disposal sites; Procedures and equipment needed to perform the measurement and sampling; Frequency and analyses required for each measurement and sampling location; Minimum detection level and accuracy; Quality assurance components; and Investigation levels. Near-facility environmental monitoring for the Hanford Site is conducted in accordance with the requirements of U.S. Department of Energy Orders 5400.1 (DOE 1990), 5400.5 (DOE 1993), 5484.1 (DOE 1990), and 435.1 (DOE 1999), and DOE/EH-O173T (DOE 1991). It is Waste Management Technical Services' objective to manage and conduct near-facility environmental monitoring activities at the Hanford Site in a cost-effective and environmentally responsible manner that is in compliance with the letter and spirit of these regulations and other environmental regulations, statutes, and standards

  13. Recommendations for a Software Quality Assurance Plan for the CMR Facility at LANL

    International Nuclear Information System (INIS)

    Adams, K.; Matthews, S. D.; McQueen, M. A.

    1998-01-01

    The Nuclear Materials Technology (NMT) organizations 1 and 3 within the Chemical and Metallurgical Research (CMR) facility at the Los Alamos National Laboratory are working to achieve Waste Isolation Pilot Plant (WIPP) certification to enable them to transport their TRU waste to WIPP. This document is intended to provide not only recommendations to address the necessary software quality assurance activities to enable the NMT-1 and NMT-3 organizations to be WIPP compliant but is also meant to provide a template for the final Software Quality Assurance Plan (SQAP). This document specifically addresses software quality assurance for all software used in support of waste characterization and analysis. Since NMT-1 and NMT-3 currently have several operational software products that are used for waste characterization and analysis, these software quality assurance recommendations apply to the operations, maintenance and retirement of the software and the creation and development of any new software required for waste characterization and analyses

  14. Life cycle costs for disposal and assured isolation of low-level radioactive waste in Connecticut

    International Nuclear Information System (INIS)

    Chau, B.; Sutherland, A.A.; Baird, R.D.

    1998-03-01

    This document presents life cycle costs for a low-level radioactive disposal facility and a comparable assured isolation facility. Cost projections were based on general plans and assumptions, including volume projections and operating life, provided by the Connecticut Hazardous Waste Management Service, for a facility designed to meet the State's needs. Life cycle costs include the costs of pre-construction activities, construction, operations, closure, and post-closure institutional control. In order to provide a better basis for understanding the relative magnitude of near-term costs and future costs, the results of present value analysis of ut-year costs are provided

  15. Quality assurance system for sitting high risk facilities

    International Nuclear Information System (INIS)

    Rodriguez, Aymee; Peralta, Jose L.; Fernandez, Manuel

    1999-01-01

    The paper shows how we have conceived and designed the quality assurance system for the site selection process of an area for sitting the facility of high risk in correspondence with the approved methodology. The results obtained in the implementation of the system have permitted the satisfactory performance of each one the expected stage, defining the most favorable sectors in order to continue the studies of the repository site for the disposal of low and intermedium. (author)

  16. Waste isolation facility description: bedded salt

    Energy Technology Data Exchange (ETDEWEB)

    1976-09-01

    The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria. (LK)

  17. Waste isolation facility description: bedded salt

    International Nuclear Information System (INIS)

    1976-09-01

    The waste isolation facility is designed to receive and store three basic types of solidified wastes: high-level wastes, intermediate level high-gamma transuranic waste, and low-gamma transuranic wastes. The facility under consideration in this report is designed for bedded salt at a depth of approximately 1800 ft. The present design for the facility includes an area which would be used initially as a pilot facility to test the viability of the concept, and a larger facility which would constitute the final storage area. The total storage area in the pilot facility is planned to be 77 acres and in the fuel facility 1601 acres. Other areas for shaft operations and access would raise the overall size of the total facility to slightly less than 2,000 acres. The following subjects are discussed in detail: surface facilities, shaft design and characteristics, design and construction of the underground waste isolation facility, ventilation systems, and design requirements and criteria

  18. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

    2008-03-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

  19. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

    Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

    2008-01-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

  20. Quality Assurance Framework Implementation Guide for Isolated Community Power Systems

    Energy Technology Data Exchange (ETDEWEB)

    Esterly, Sean R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Baring-Gould, Edward I. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Burman, Kari A. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Greacen, Chris [Independent Consultant (United States)

    2017-08-15

    This implementation guide is a companion document to the 'Quality Assurance Framework for Mini-Grids' technical report. This document is intended to be used by one of the many stakeholder groups that take part in the implementation of isolated power systems. Although the QAF could be applied to a single system, it was designed primarily to be used within the context of a larger national or regional rural electrification program in which many individual systems are being installed. This guide includes a detailed overview of the Quality Assurance Framework and provides guidance focused on the implementation of the Framework from the perspective of the different stakeholders that are commonly involved in expanding energy development within specific communities or regions. For the successful long-term implementation of a specific rural electrification program using mini-grid systems, six key stakeholders have been identified that are typically engaged, each with a different set of priorities 1. Regulatory agency 2. Governmental ministry 3. System developers 4. Mini-utility 5. Investors 6. Customers/consumers. This document is broken into two distinct sections. The first focuses on the administrative processes in the development and operation of community-based mini-grid programs, while the second focuses on the process around the installation of the mini-grid project itself.

  1. Quality Assurance Program Plan (QAPP) Waste Encapsulation and Storage Facility (WESF)

    International Nuclear Information System (INIS)

    ROBINSON, P.A.

    2000-01-01

    This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD

  2. Recommendations for quality assurance programs in nuclear medicine facilities. Radiation recommendations series

    International Nuclear Information System (INIS)

    Segal, P.; Hamilton, D.R.

    1984-10-01

    The publication provides the elements that should be considered by nuclear medicine facilities to improve their existing programs or develop new quality assurance programs. The important administrative aspects of quality assurance programs are stressed. Each facility is encouraged to adopt those elements of the recommended program that are appropriate to its individual needs and resources

  3. Application of quality assurance to radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    Nuclear power generation and the use of radioactive materials in medicine, research and industry produce radioactive wastes. In order to assure that wastes are managed safely, the implementation of appropriate management control is necessary. This IAEA publication deals with quality assurance principles for safe disposal. This report may assist managers responsible for safe disposal of radioactive waste in achieving quality in their work; and to regulatory bodies to provide guidance for their licensee waste disposal programmes. 17 refs.

  4. Application of quality assurance to radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1996-08-01

    Nuclear power generation and the use of radioactive materials in medicine, research and industry produce radioactive wastes. In order to assure that wastes are managed safely, the implementation of appropriate management control is necessary. This IAEA publication deals with quality assurance principles for safe disposal. This report may assist managers responsible for safe disposal of radioactive waste in achieving quality in their work; and to regulatory bodies to provide guidance for their licensee waste disposal programmes. 17 refs

  5. Experimental equipment for an advanced ISOL facility

    International Nuclear Information System (INIS)

    Baktash, C.; Lee, I.Y.; Rehm, K.E.

    1999-01-01

    This report summarizes the proceedings and recommendations of the Workshop on the Experimental Equipment for an Advanced ISOL Facility which was held at Lawrence Berkeley National Laboratory on July 22--25, 1998. The purpose of this workshop was to discuss the performance requirements, manpower and cost estimates, as well as a schedule of the experimental equipment needed to fully exploit the new physics which can be studied at an advanced ISOL facility. An overview of the new physics opportunities that would be provided by such a facility has been presented in the White Paper that was issued following the Columbus Meeting. The reactions and experimental techniques discussed in the Columbus White Paper served as a guideline for the formulation of the detector needs at the Berkeley Workshop. As outlined a new ISOL facility with intense, high-quality beams of radioactive nuclei would provide exciting new research opportunities in the areas of: the nature of nucleonic matter; the origin of the elements; and tests of the Standard Model. After an introductory section, the following equipment is discussed: gamma-ray detectors; recoil separators; magnetic spectrographs; particle detectors; targets; and apparatus using non-accelerated beams

  6. 40 CFR 256.42 - Recommendations for assuring facility development.

    Science.gov (United States)

    2010-07-01

    ... facilities and practices to be developed by responsible State and substate agencies or by the private sector... sector initiatives in order to meet the identified facility needs. (e) In any area having fewer than 2... establish procedures for choosing which facilities will get priority for technical or financial assistance...

  7. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  8. Quality Assurance Program description, Defense Waste Processing Facility (DWPF)

    International Nuclear Information System (INIS)

    Maslar, S.R.

    1992-01-01

    This document describes the Westinghouse Savannah River Company's (WSRC) Quality Assurance Program for Defense Waste Processing at the Savannah River Site (SRS). WSRC is the operating contractor for the US Department of Energy (DOE) at the SRS. The following objectives are achieved through developing and implementing the Quality Assurance Program: (1) Ensure that the attainment of quality (in accomplishing defense high-level waste processing objectives at the SRS) is at a level commensurate with the government's responsibility for protecting public health and safety, the environment, the public investment, and for efficiently and effectively using national resources. (2) Ensure that high-level waste from qualification and production activities conform to requirements defined by OCRWM. These activities include production processes, equipment, and services; and products that are planned, designed, procured, fabricated, installed, tested, operated, maintained, modified, or produced

  9. The BNCT facility at the HFR Petten: Quality assurance for reactor facilities in clinical trials

    International Nuclear Information System (INIS)

    Moss, R.; Watkins, P.; Vroegindeweij, C.; Stecher-Rasmussen, F.; Huiskamp, R.; Ravensberg, K.; Appelman, K.; Sauerwein, W.; Hideghety, K.; Gabel, D.

    2001-01-01

    The first clinical trial in Europe of Boron Neutron Capture Therapy (BNCT) for the treatment of glioblastoma was opened in July 1997. The trial is a Phase I study with the principal aim to establish the maximum tolerated radiation dose and the dose limiting toxicity under defined conditions. It is the first time that a clinical application could be realised on a completely multi-national scale. The treatment takes place at the High Flux Reactor (HFR) in Petten, the Netherlands, is operated by an international team of experts under the leadership of a German radiotherapist, and treats patients coming from different European countries. It has therefore been necessary to create a very specialised organisation and contractual structure with the support of administrations from different countries, who had to find and adapt solutions within existing laws that had never foreseen such a situation. Furthermore, the treatment does not take place in an hospital environment and even more so, the facility is at a nuclear research reactor. Hence, special efforts were made on quality assurance, in order that the set-up at the facility and the personnel involved complied, as closely as possible, with similar practices in conventional radiotherapy departments. (author)

  10. Proposed quality assurance manual for the Office of Waste Isolation

    International Nuclear Information System (INIS)

    1977-01-01

    The manual provides guidelines for assuring safe and reliable siting, design, procurement and construction, operation, and decommissioning of a radioactive waste repository. The organization of the program is given and the program itself is defined. The program includes the site evaluation, site selection, design, procurement, fabrication, installation, and testing of any system or component that is safety related. It also included all necessary documentation and auditing

  11. Standard guide for establishing a quality assurance program for uranium conversion facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 This guide provides guidance and recommended practices for establishing a comprehensive quality assurance program for uranium conversion facilities. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate health and safety practices and determine the applicability of regulatory limitations prior to use. 1.3 The basic elements of a quality assurance program appear in the following order: FUNCTION SECTION Organization 5 Quality Assurance Program 6 Design Control 7 Instructions, Procedures & Drawings 8 Document Control 9 Procurement 10 Identification and Traceability 11 Processes 12 Inspection 13 Control of Measuring and Test Equipment 14 Handling, Storage and Shipping 15 Inspection, Test and Operating Status 16 Control of Nonconforming Items 17 Corrective Actions 18 Quality Assurance Records 19 Audits 20 TABLE 1 NQA-1 Basic Requirements Relat...

  12. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hall, L.R.

    1995-05-30

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

  13. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    International Nuclear Information System (INIS)

    Hall, L.R.

    1995-01-01

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1

  14. 21 CFR 1000.55 - Recommendation for quality assurance programs in diagnostic radiology facilities.

    Science.gov (United States)

    2010-04-01

    ... facilities where more than one department operates x-ray equipment, to the chief medical officer of the..., improved image quality, and/or financial savings will compensate for the resources required for the program... generally be delegated a basic quality assurance role by the practitioner in charge. Responsibility for...

  15. Long term assurance of supply of back end of fuel cycle facilities and services

    International Nuclear Information System (INIS)

    1978-01-01

    The paper deals with the long-term assurance of supply of the back end of fuel cycle facilities and services. 11 fundamental questions are posed and commented on by representatives of 7 countries. Non-proliferation aspects are not considered as they will be discussed elsewhere

  16. Quality assurance aspects of the major procurements for the Large Coil Test Facility

    International Nuclear Information System (INIS)

    Taylor, D.J.; Thompson, P.B.; Ryan, T.L.; Queen, C.C.; Halstead, E.L.; Murphy, J.L.; Wood, R.J.

    1983-01-01

    The Large Coil Test Facility (LCTF) project is comprised of the test stand, supporting cryogenic systems, instrumentation, data acquisition, and utilities necessary for testing the large superconducting coils of the Large Coil Program (LCP). A significant portion of the facility hardware has been obtained through procurement actions with industrial suppliers. This paper addresses the project's experience in formulation and execution of quality assurance (QA) actions relative to several of the major items procured. Project quality assurance planning and specific features related to procurement activities for several of the more specialized test facility components are described. These component procurements include: (1) the coil test stand's major structural item (the bucking post) purchased from foreign industry; (2) fabrication and testing of high-current power supplies; (3) industrial fabrication of specialized instrumentation (voltage-tap signal conditioning modules); and (4) fabrication, installation, and testing of the liquid helium piping system

  17. Quality assurance in the enriched uranium operations NDA facility

    Energy Technology Data Exchange (ETDEWEB)

    May, P.K.; Ceo, R.N. [Oak Ridge Y-12 Plant, TN (United States)

    1997-11-01

    The Nondestructive Analysis (NDA) Facility at the Oak Ridge Y-12 Plant has characterized process wastes for Enriched Uranium Operations since 1978. Since that time, over 50,000 items have been analyzed. Analysis results are used to determine whether or not recovery of uranium from process wastes is economically feasible. Our instrument complement includes one large segmented gamma scanner (SGS), two smaller SGS, two solution assay systems (SAS), and Active Well Coincidence Counter (AWCC). The large SGS is used for analyzing High Efficiency Particulate Air (HEPA) filters ant 208-L drums filled with combustible contaminated waste. The smaller SGS are used to analyze 4-L containers of ash and leached residues. The SAS are used to analyze 125 ml bottles of aqueous or organic waste solutions that may contain uranium. The gamma-based NDA techniques are used to identify which process wastes can be discarded, and which must be recycled. The AWCC is used to analyze high-density materials which are not amenable to gamma-ray analysis. 1 ref., 4 figs.

  18. Review of Regulatory Quality Assurance Requirements for the Operation of Nuclear R and D Facilities

    International Nuclear Information System (INIS)

    Kwon, Hyuk Il; Lim, Nam Jin

    2005-01-01

    Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation, including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently, nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/ contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. In this paper, the context of amended Atomic Energy laws were reviewed to confirm quality assurance measures and identify additional QA activities, if any, that is required by the amendment

  19. Software quality assurance plan for the National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project's controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy's (DOE's) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project

  20. A process for establishing a financial assurance plan for LLW disposal facilities

    International Nuclear Information System (INIS)

    Smith, P.

    1993-04-01

    This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided

  1. A process for establishing a financial assurance plan for LLW disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Smith, P. [EG and G Idaho, Inc., Idaho Falls, ID (United States). National Low-Level Waste Management Program

    1993-04-01

    This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided.

  2. National Ignition Facility quality assurance plan for laser materials and optical technology

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials & Optical Technology (LM&OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM&OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies.

  3. Base isolation for nuclear power and nuclear material facilities

    International Nuclear Information System (INIS)

    Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

    1989-01-01

    This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

  4. A facility for long term evaluation and quality assurance of LHCb Vertex Detector modules

    CERN Document Server

    Marinho, F; Dimattia, R; Doherty, F; Dumps, R; Gersabeck, M; Melone, J; Parkes, C; Saavedra, A; Tobin, M

    2007-01-01

    This note describes the facility developed for long term evaluation and quality assurance of the LHCb Vertex Detector modules, known as the 'Glasgow Burn-in System'. This facility was developed to ensure that the modules conform to stringent quality levels. The system was able to uncover any weaknesses that could be introduced during the manufacturing and assembly of the components or during the transport of the modules to CERN. The system consisted of: a high resolution microscope for visual inspections; and a burn-in system to operate cooled modules in vacuum. The main components of the burn-in system were a vacuum system, a cooling system and a DAQ system.

  5. Quality assurance project plan for the UMTRA technical assistance contractor hydrochemistry facility. Final report

    International Nuclear Information System (INIS)

    1993-07-01

    The Uranium Mill Tailings Remedial Action (UMTRA) hydrochemistry facility is used to perform a limited but important set of services for the UMTRA Project. Routine services include support of field-based hydrological and geochemical operations and water sampling activities. Less commonly, the hydrology and geochemistry staff undertake special studies and site characterization studies at this facility. It is also used to train hydrologists, geochemists, and groundwater sampling crews. A review of this Quality Assurance Project Plan (QAPP) shall be accomplished once each calendar year. This review will be targeted to be accomplished not sooner than 6 months and not later than 18 months after the last review

  6. Software quality assurance plan for the National Ignition Facility integrated computer control system

    Energy Technology Data Exchange (ETDEWEB)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project`s controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy`s (DOE`s) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project.

  7. Application of quality assurance to the design, procurement and construction of the fast flux test facility

    International Nuclear Information System (INIS)

    Garland, D.L.; Glasscock, R.B.

    1978-01-01

    Experience has clearly demonstrated the need for effective quality assurance programmes throughout the design, procurement and construction phases of the Fast Flux Test Facility (FFTF). Formal quality assurance programmes for FFTF have contributed significantly to the achievement of project objectives thus far in a safe, reliable and predictable manner. Quality assurance programmes empolyed by major FFTF Project participants are based on the requirements of RDT Standard F 2-2, one of the first and most comprehensive standards of its kind. RDT F 2-2 is similar in its basic requirements to ANSI N45.2 and other quality assurance programme standards but differs in its degree of specificity, particularly in its coverage of development activities. RDT F 2-2 is widely applied to a variety of large and small nuclear energy development projects and technology programmes. Full implementation of RDT F 2-2 across the FFTF Project has had its problems and rewards. Problems have been encountered involving misinterpretation or overapplication of requirements. In some instances the problems pointed to the need for more specific requirements, and so the standard was amended to rectify the shortcomings. One valuable lesson learned is that feedback of use experience is essential to the development of a living, viable standard which can be beneficially applied to other projects. Benefits and cost savings have accrued from the preventive aspects of RDT F 2-2. Some examples of experiences and resulting amendments to RDT F 2-2, and their favourable impact on facility costs and schedule, are discussed in this paper. (author)

  8. Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea

    International Nuclear Information System (INIS)

    Kwon, H.I.; Lim, N.J.

    2006-01-01

    Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of nuclear installations, and is supplemented by the Enforcement Decree and Enforcement Regulation of the Act. These Atomic Energy laws include provisions on the construction permission and the operation license of nuclear installations, such as nuclear power reactors, research reactors, nuclear ships, nuclear fuel fabrication facilities, spent fuel treatment facilities, etc. Regulatory requirements for the regulatory inspection and the safety measures for operation are also defined in the laws. The Notice of the MOST prescribes specific issues including regulatory requirements and technical standards, as entrusted by the AEA, the Decree and the Regulation. Detailed QA requirements for nuclear installations are specified differently, depending upon the type of facility. The guidelines for safety reviews and regulatory inspections are developed by the Korea Institute of Nuclear Safety (KINS), which is an exclusive organization for safety regulation of nuclear installations in Korea. In this paper, the context of the Atomic Energy laws were reviewed to confirm the

  9. Quality assurance guidance for low-level radioactive waste disposal facility: Final report

    International Nuclear Information System (INIS)

    Pittiglio, C.L. Jr.

    1989-01-01

    This document provides guidance to an applicant on meeting the quality control (QC) requirements for a low-level waste (LLW) disposal facility. The QC requirements are the basis for developing of a quality assurance (QA) program and for the guidance provided herein. The criteria are basic to any QA program. The document specifically establishes QA guidance for the design, construction, and operation of those structures, systems, components, as well as, for site characterization activities necessary to meet the performance objectives and to limit exposure to our release of radioactivity. 7 refs

  10. National Ignition Facility quality assurance plan for laser materials and optical technology

    International Nuclear Information System (INIS)

    Wolfe, C.R.

    1996-05-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This subtier Quality Assurance Plan (QAP) applies to activities of the Laser Materials ampersand Optical Technology (LM ampersand OT) organization and its subcontractors. It responds to the NIF Quality Assurance Program Plan (QAPP, L-15958-2, NIF-95-499) and Department of Energy (DOE) Order 5700.6C. This Plan is organized according to 10 Quality Assurance (QA) criteria and subelements of a management system as outlined in the NIF QAPP. This Plan describes how those QA requirements are met. This Plan is authorized by the Associate Project Leader for the LM ampersand OT organization, who has assigned responsibility to the Optics QA engineer to maintain this plan, with the assistance of the NIF QA organization. This Plan governs quality-affecting activities associated with: design; procurement; fabrication; testing and acceptance; handling and storage; and installation of NIF Project optical components into mounts and subassemblies

  11. Production and quality assurance automation in the Goddard Space Flight Center Flight Dynamics Facility

    Science.gov (United States)

    Chapman, K. B.; Cox, C. M.; Thomas, C. W.; Cuevas, O. O.; Beckman, R. M.

    1994-01-01

    The Flight Dynamics Facility (FDF) at the NASA Goddard Space Flight Center (GSFC) generates numerous products for NASA-supported spacecraft, including the Tracking and Data Relay Satellites (TDRS's), the Hubble Space Telescope (HST), the Extreme Ultraviolet Explorer (EUVE), and the space shuttle. These products include orbit determination data, acquisition data, event scheduling data, and attitude data. In most cases, product generation involves repetitive execution of many programs. The increasing number of missions supported by the FDF has necessitated the use of automated systems to schedule, execute, and quality assure these products. This automation allows the delivery of accurate products in a timely and cost-efficient manner. To be effective, these systems must automate as many repetitive operations as possible and must be flexible enough to meet changing support requirements. The FDF Orbit Determination Task (ODT) has implemented several systems that automate product generation and quality assurance (QA). These systems include the Orbit Production Automation System (OPAS), the New Enhanced Operations Log (NEOLOG), and the Quality Assurance Automation Software (QA Tool). Implementation of these systems has resulted in a significant reduction in required manpower, elimination of shift work and most weekend support, and improved support quality, while incurring minimal development cost. This paper will present an overview of the concepts used and experiences gained from the implementation of these automation systems.

  12. Quality assurance guidance for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Pittiglio, C.L. Jr.; Hedges, D.

    1991-04-01

    This document provides guidance to an applicant on meeting the quality control (QC) requirements of 10 CFR 61.12(j) for a low-level radioactive waste (LLRW) disposal facility. The QC requirements, plus audits and managerial controls requirements, establish the need for developing a quality assurance (QA) program and the guidance provided herein. The criteria developed for this document are similar to the criteria developed for Appendix B to Title 10 of the Code of Federal Regulations (10 CFR) Part 50. Although Appendix B is not a regulatory requirement for an LLRW disposal facility, the criteria that were developed for 10 CFR Part 50 are basic to any QA program. This document establishes QA guidance for the design, construction, and operation of those structures, engineered or natural systems, and components whose function is required to meet the performance objectives of Subpart C of 10 CFR Part 61 and to limit exposure to or release of radioactivity. 7 refs

  13. Biosecurity measures in 48 isolation facilities managing highly infectious diseases.

    Science.gov (United States)

    Puro, Vincenzo; Fusco, Francesco M; Schilling, Stefan; Thomson, Gail; De Iaco, Giuseppina; Brouqui, Philippe; Maltezou, Helena C; Bannister, Barbara; Gottschalk, René; Brodt, Hans-Rheinhard; Ippolito, Giuseppe

    2012-06-01

    Biosecurity measures are traditionally applied to laboratories, but they may also be usefully applied in highly specialized clinical settings, such as the isolation facilities for the management of patients with highly infectious diseases (eg, viral hemorrhagic fevers, SARS, smallpox, potentially severe pandemic flu, and MDR- and XDR-tuberculosis). In 2009 the European Network for Highly Infectious Diseases conducted a survey in 48 isolation facilities in 16 European countries to determine biosecurity measures for access control to the facility. Security personnel are present in 39 facilities (81%). In 35 facilities (73%), entrance to the isolation area is restricted; control methods include electronic keys, a PIN system, closed-circuit TV, and guards at the doors. In 25 facilities (52%), identification and registration of all staff entering and exiting the isolation area are required. Access control is used in most surveyed centers, but specific lacks exist in some facilities. Further data are needed to assess other biosecurity aspects, such as the security measures during the transportation of potentially contaminated materials and measures to address the risk of an "insider attack."

  14. Seismic Isolation Studies and Applications for Nuclear Facilities

    International Nuclear Information System (INIS)

    Choun, Young Sun

    2005-01-01

    Seismic isolation, which is being used worldwide for buildings, is a well-known technology to protect structures from destructive earthquakes. In spite of the many potential advantages of a seismic isolation, however, the applications of a seismic isolation to nuclear facilities have been very limited because of a lack of sufficient knowledge about the isolation practices. The most important advantage of seismic isolation applications in nuclear power plants is that the safety and reliability of the plants can be remarkably improved through the standardization of the structures and equipment regardless of the seismic conditions of the sites. The standardization of structures and equipment will reduce the capital cost and design/construction schedule for future plants. Also, a seismic isolation can facilitate decoupling of the design and development for equipment, piping, and components due to the use of the generic in-structure response spectra associated with the standardized plant. Moreover, a seismic isolation will improve the plant safety margin against the design basis earthquake (DBE) as well as a beyond design basis seismic event due to its superior seismic performance. A number of seismic isolation systems have been developed and tested since 1970s, and some of them have been applied to conventional structures in several countries of high seismicity. In the nuclear field, there have been many studies on the applicability of such seismic isolation systems, but the application of a seismic isolation is very limited. Currently, there are some discussions on the application of seismic isolation systems to nuclear facilities between the nuclear industries and the regulatory agencies in the U.S.. In the future, a seismic isolation for nuclear facilities will be one of the important issues in the nuclear industry. This paper summarizes the past studies and applications of a seismic isolation in the nuclear industry

  15. Applicability of base-isolation R and D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1989-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. This paper reviews the research and development (R and D) programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R and D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R and D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant

  16. Software quality assurance in the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Froehlich, Gary K.; Ogden, Harvey C.; Byle, Kathleen A.

    2000-01-01

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP), located in southeast New Mexico, is a deep geologic repository for the permanent disposal of transuranic waste generated by DOE defense-related activities. Sandia National Laboratories (SNL), in its role as scientific advisor to the DOE, is responsible for evaluating the long-term performance of the WIPP. This risk-based Performance Assessment (PA) is accomplished in part through the use of numerous scientific modeling codes, which rely for some of their inputs on data gathered during characterization of the site. The PA is subject to formal requirements set forth in federal regulations. In particular, the components of the calculation fall under the configuration management and software quality assurance aegis of the American Society of Mechanical Engineers(ASME) Nuclear Quality Assurance (NQA) requirements. This paper describes SNL's implementation of the NQA requirements regarding software quality assurance (SQA). The description of the implementation of SQA for a PA calculation addresses not only the interpretation of the NQA requirements, it also discusses roles, deliverables, and the resources necessary for effective implementation. Finally, examples are given which illustrate the effectiveness of SNL's SQA program, followed by a detailed discussion of lessons learned

  17. Software quality assurance in the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Froehlich, G.K.; Ogden, H.C.; Byle, K.A.

    2000-01-01

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP), located in southeast New Mexico, is a deep geologic repository for the permanent disposal of transuranic waste generated by DOE defense-related activities. Sandia National Laboratories (SNL), in its role as scientific advisor to the DOE, is responsible for evaluating the long-term performance of the WIPP. This risk-based Performance Assessment (PA) is accomplished in part through the use of numerous scientific modeling codes, which rely for some of their inputs on data gathered during characterization of the site. The PA is subject to formal requirements set forth in federal regulations. In particular, the components of the calculation fall under the configuration management and software quality assurance aegis of the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance (NQA) requirements. This paper describes SNL's implementation of the NQA requirements regarding software quality assurance (SQA). The description of the implementation of SQA for a PA calculation addresses not only the interpretation of the NQA requirements, it also discusses roles, deliverables, and the resources necessary for effective implementation. Finally, examples are given which illustrate the effectiveness of SNL's SQA program, followed by a detailed discussion of lessons learned

  18. Seismic isolation rubber bearings for nuclear facilities

    International Nuclear Information System (INIS)

    Fujita, Takafumi

    1991-01-01

    This paper describes results of biaxial breaking tests by compression and shear and by tension and shear for seismic isolation rubber bearings with bolted-type connections. The bearings used in the tests were low-damping rubber bearings, high-damping rubber bearings, and lead-rubber bearings. Three modes of failure of the bolted-type bearings were observed in the tests. They are the breaking failure by tension and shear; the breaking failure by compression and shear; and the buckling failure by compression and shear. The first and the second modes of failures are almost independent of the types and the sizes of the bearings. The breaking conditions of those failure modes are described in the axial-stress-shear-strain plane. This expression is useful for the evaluation of safety margins of the bearings. The paper outlines the basic design of the nuclear-grade bearings which were used for large-scale rubber bearing tests in a research project for seismic isolation of FBR plants. It also discusses the protection method against aging and the quality control which are important for implementation. (orig./HP)

  19. Seismic isolation rubber bearings for nuclear facilities

    International Nuclear Information System (INIS)

    Fujita, Takafumi

    1989-01-01

    This paper describes results of biaxial breaking tests by compression and shear and by tension and shear for seismic isolation rubber bearings with bolted-type connections. The bearings used in the tests were low-damping rubber bearings, high-damping rubber bearings, and lead-rubber bearings. Three modes of failure of the bolted-type bearings were observed in the tests. They are the breaking failure by tension and shear; the breaking failure by compression and shear; and the buckling failure by compression and shear. The first and the second modes of failures are almost independent of the types and the sizes of the bearings. The breaking conditions of those failure modes are described in the axial stress-shear strain plane. This expression is useful for the evaluation of safety margins of the bearings. The paper outlines the basic design of the nuclear-grade bearings which were used for large-scale rubber bearing tests in a research project for seismic isolation of fast breeder reactor (FBR) plants. The paper also discusses the protection method against aging and the quality control which are important for implementation

  20. Quality Assurance Project Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    International Nuclear Information System (INIS)

    Lewis, Michael G.

    2016-01-01

    This quality assurance project plan describes the technical requirements and quality assurance activities of the environmental data collection/analyses operations to close Central Facilities Area Sewage treatment Plant Lagoon 3 and the land application area. It describes the organization and persons involved, the data quality objectives, the analytical procedures, and the specific quality control measures to be employed. All quality assurance project plan activities are implemented to determine whether the results of the sampling and monitoring performed are of the right type, quantity, and quality to satisfy the requirements for closing Lagoon 3 and the land application area.

  1. Quality Assurance Project Plan for Closure of the Central Facilities Area Sewage Treatment Plant Lagoon 3 and Land Application Area

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Michael G. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-10-01

    This quality assurance project plan describes the technical requirements and quality assurance activities of the environmental data collection/analyses operations to close Central Facilities Area Sewage treatment Plant Lagoon 3 and the land application area. It describes the organization and persons involved, the data quality objectives, the analytical procedures, and the specific quality control measures to be employed. All quality assurance project plan activities are implemented to determine whether the results of the sampling and monitoring performed are of the right type, quantity, and quality to satisfy the requirements for closing Lagoon 3 and the land application area.

  2. Quality assurance during fabrication of high-damping rubber isolation bearings

    Energy Technology Data Exchange (ETDEWEB)

    Way, D.; Greaves, W.C. [Base Isolation Consultants, Inc., San Francisco, CA (United States)

    1995-12-01

    Successful implementation of a high-damping rubber (HDR) base isolation project requires the application of Quality Assurance/Quality Control (QA/QC) methodology through all phases of the bearing fabrication process. HDR base isolation bearings must be fabricated with uniform physical characteristics while being produced in large quantities. To satisfy this requirement, manufacturing processes must be controlled. Prototype tests that include dynamic testing of small samples of rubber are necessary. Stringent full scale bearing testing must be carried out prior to beginning production, during which manufacturing is strictly regulated by small rubber sample and production bearing testing. All such activities should be supervised and continuously inspected by independent and experienced QA/QC personnel.

  3. An advanced ISOL facility based on ATLAS

    International Nuclear Information System (INIS)

    Nolen, J. A.

    1999-01-01

    The Argonne concept for an accelerator complex for efficiently producing high-quality radioactive beams from ion source energy up to 6-15 MeV/u is described. The Isotope-Separator-On-Line (ISOL) method is used. A high-power driver accelerator produces radionuclides in a target that is closely coupled to an ion source and mass separator. By using a driver accelerator which can deliver a variety of beams and energies the radionuclide production mechanisms can be chosen to optimize yields for the species of interest. To effectively utilize the high beam power of the driver two-step target/ion source geometries are proposed (1) Neutron production with intermediate energy deuterons on a primary target to produce neutron-rich fission products in a secondary 238 U target, and (2) Fragmentation of neutron-rich heavy ion rich fission products in a secondary beams such as 18 O in a target/catcher geometry. Heavy ion beams with total energies in the 1-10 GcV range are also available for radionuclide production via high-energy spallation reactions. At the present time R and D is in progress to develop superconducting resonator structures for a driver linac to cover the energy range up to 100 MeV per nucleon for heavy ions and 200 MeV for protons. The post accelerator scheme is based on using existing ISOL-type 1+ ion source technology followed by CW Radio Frequency Quadruple (RFQ) accelerators and superconducting linacs including the present ATLAS accelerator. A full-scale prototype of the first-stage RFQ has been successfully tested with RF at full design voltage and tests with ion beams are in progress. A benchmark beam, 132 Sn at 7 MeV/u, requires two stripping stages, one a gas stripper at very low velocity after the first RFQ section, and one a foil stripper at higher velocity after a superconducting-linac injector

  4. An advanced ISOL facility based on ATLAS

    CERN Document Server

    Nolen, J A; Pardo, R C; Savard, G; Rehm, K E; Schiffer, J P; Henning, W F; Jiang, C L; Ahmad, L; Back, B B; Kaye, R A; Petra, M; Portillo, M; Greene, J; Clifft, B E; Specht, J R; Janssens, R V F; Siemssen, R H; Gómez, I; Reed, C B; Hassanein, A M

    1999-01-01

    The Argonne concept for an accelerator complex for efficiently producing high-quality radioactive beams from an ion source energy up to 6-15 MeV/u is described. The Isotope-Separator-On-Line (ISOL) method is used. A high-power $9 driver accelerator produces radionuclides in a target that is closely coupled to an ion source and mass separator. By using a driver accelerator which can deliver a variety of beams and energies the radionuclide production mechanisms $9 can be chosen to optimize yields for the species of interest. To effectively utilize the high beam power of the driver two-step target /ion source geometries are proposed: (1) Neutron production with intermediate energy deuterons on $9 a primary target to produce neutron- rich fission products in a secondary /sup 238/U target, and (2) Fragmentation of neutron-rich heavy ion beams such as /sup 18/O in a target/catcher geometry. Heavy ion beams with total energies in $9 the 1-10 GeV range are also available for radionuclide production via high-energy sp...

  5. Applicability of base-isolation R ampersand D in non-reactor facilities to a nuclear reactor plant

    International Nuclear Information System (INIS)

    Seidensticker, R.W.; Chang, Y.W.

    1990-01-01

    Seismic isolation is gaining increased attention worldwide for use in a wide spectrum of critical facilities, ranging from hospitals and computing centers to nuclear power plants. While the fundamental principles and technology are applicable to all of these facilities, the degree of assurance that the actual behavior of the isolation systems is as specified varies with the nature of the facility involved. Obviously, the level of effort to provide such assurance for a nuclear power plant will be much greater than that required for, say, a critical computer facility. The question, therefore, is to what extent can research and development (R ampersand D) for non-nuclear use be used to provide technological data needed for seismic isolation of a nuclear power plant. This question, of course is not unique to seismic isolation. Virtually every structural component, system, or piece of equipment used in nuclear power plants is also used in non- nuclear facilities. Experience shows that considerable effort is needed to adapt conventional technology into a nuclear power plant. Usually, more thorough analysis is required, material and fabrication quality-control requirements are more stringent as are controls on field installation. In addition, increased emphasis on maintainability and inservice inspection throughout the life of the plant is generally required to gain acceptance in nuclear power plant application. This paper reviews the R ampersand D programs ongoing for seismic isolation in non-nuclear facilities and related experience and makes a preliminary assessment of the extent to which such R ampersand D and experience can be used for nuclear power plant application. Ways are suggested to improve the usefulness of such non-nuclear R ampersand D in providing the high level of confidence required for the use of seismic isolation in a nuclear reactor plant. 2 refs

  6. Reliability and safety program plan outline for the operational phase of a waste isolation facility

    International Nuclear Information System (INIS)

    Ammer, H.G.; Wood, D.E.

    1977-01-01

    A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

  7. Waste Management facilities cost information: System Cost Model Software Quality Assurance Plan. Revision 2

    International Nuclear Information System (INIS)

    Peterson, B.L.; Lundeen, A.S.

    1996-02-01

    In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for truck and rail, which include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation's generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities. For the product to be effective and useful the SCM users must have a high level of confidence in the data generated by the software model. The SCM Software Quality Assurance Plan is part of the overall SCM project management effort to ensure that the SCM is maintained as a quality product and can be relied on to produce viable planning data. This document defines tasks and deliverables to ensure continued product integrity, provide increased confidence in the accuracy of the data generated, and meet the LITCO's quality standards during the software maintenance phase. 8 refs., 1 tab

  8. Waste Management facilities cost information: System Cost Model Software Quality Assurance Plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, B.L.; Lundeen, A.S.

    1996-02-01

    In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for truck and rail, which include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation`s generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities. For the product to be effective and useful the SCM users must have a high level of confidence in the data generated by the software model. The SCM Software Quality Assurance Plan is part of the overall SCM project management effort to ensure that the SCM is maintained as a quality product and can be relied on to produce viable planning data. This document defines tasks and deliverables to ensure continued product integrity, provide increased confidence in the accuracy of the data generated, and meet the LITCO`s quality standards during the software maintenance phase. 8 refs., 1 tab.

  9. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

  10. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

  11. ISOL science at the Holifield Radioactive Ion Beam Facility

    Energy Technology Data Exchange (ETDEWEB)

    Beene, James R [ORNL; Bardayan, Daniel W [ORNL; Galindo-Uribarri, Alfredo {nmn} [ORNL; Gross, Carl J [ORNL; Jones, K. L. [University of Tennessee, Knoxville (UTK); Liang, J Felix [ORNL; Nazarewicz, Witold [ORNL; Stracener, Daniel W [ORNL; Tatum, B Alan [ORNL; Varner Jr, Robert L [ORNL

    2011-01-01

    The Holi eld Radioactive Ion Beam Facility, located in Oak Ridge, Tennessee, is operated as a National User Facility for the U.S. Department of Energy, producing high quality ISOL beams of short-lived, radioactive nuclei for studies of exotic nuclei, astrophysics research, and various societal applications. The primary driver, the Oak Ridge Isochronous Cyclotron, produces rare isotopes by bombarding highly refractory targets with light ions. The radioactive isotopes are ionized, formed into a beam, mass selected, injected into the 25-MV Tandem, accelerated, and used in experiments. This article reviews HRIBF and its science.

  12. Recent developments at the ISOL facility of GSI Darmstadt

    CERN Document Server

    Roeckl, E; Burkard, K; Döring, J; Grawe, H; Hüller, W; Kirchner, R; Mazzocchi, C; Mukha, I; Plettner, C

    2003-01-01

    The research programme pursued at the ISOL facility of GSI Darmstadt focuses on the study of decay properties of nuclei along the N congruent with Z line between the double shell closures at sup 5 sup 6 Ni and sup 1 sup 0 sup 0 Sn. In this report, the major scientific achievements obtained in the past two years are reviewed, with particular emphasis being put on the detection techniques.

  13. Quality assurance for BNCT at nuclear facilities. A necessary burden or the unavoidable seal of approval

    International Nuclear Information System (INIS)

    Moss, R.; Morrissey, J.; Sauerwein, W.; Hideghety, K.; Rassow, J.; Stecher-Rasmussen, F.

    2000-01-01

    The BNCT clinical trial at the HFR Petten is performed on a completely multi-national basis. The irradiation facility is located in one country (The Netherlands), is operated by an international team of experts under the leadership of a radiotherapist from another country (Germany) and treats patients coming from different European countries. In gaining the necessary approval, it became apparent, especially in the many discussions with the (Dutch) Health authorities that Quality Assurance (QA) would be and is a critical aspect. This is even more so, in the case of BNCT, where it was not only a (relatively) new experimental treatment (in 1996/97) about to be performed for the first time in Europe, but it was to be performed in a non-hospital environment and furthermore in a nuclear research reactor. It was necessary therefore to comply, as closely as possible, with similarly accepted practices in conventional radiotherapy. Despite QA being a sometimes burdensome task, this paper nevertheless raises the issue as to whether it is necessary or whether it is the seal of approval for BNCT as an acceptable mode of treatment in mainstream radiotherapy. (author)

  14. Mandatory quality assurance programmes for diagnostic radiology facilities in Ontario, Canada

    International Nuclear Information System (INIS)

    Rainbow, A.J.

    1989-01-01

    Regulations made under the Healing Arts Radiation Protection (HARP) Act, Government of Ontario, Canada, were promulgated in the form of a safety Code in November, 1985. These regulations require a minimum technical quality assurance (QA) programme for all diagnostic radiology facilities in the Province. The mandatory QA programme requires certain tests and procedures to be carried out at specified intervals. The tests include photographic quality control, patient entrance exposure measurement, collimation, half-value layer, phototiming parameters, fluoroscopic parameters including maximum patient entrance exposure rate, resolution, limit timer and automatic brightness control, and tomographic parameters including fulcrum accuracy, thickness of cut and mechanical stability. Records of the results of these tests must be kept for at least 6 years. A set of HARP guidelines published in June 1987 includes a description of appropriate measuring methods for each test together with a set of forms for recording the results of such tests. The regulations specify limiting values for a number of equipment performance parameters, including the maximum allowable patient skin entrance exposure values for common radiographic projections. (author)

  15. A plan for the implementation of assurance requirements in compliance with 40 CFR 191.14 at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1987-12-01

    The purpose of this document is to describe the Assurance Requirements Implementation Plan for the Waste Isolation Pilot Plant (WIPP). This Plan addresses the requirements that have been promulgated by the US Environmental Protection Agency (EPA) standard ''Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes; Final Rule'' (The Standard). It should be pointed out that portions of this standard have been vacated and remanded to the EPA by the First Circuit Court (NRDC vs EPA). The reasons for remanding were unrelated to the Assurance Requirement provisions. As a result, it is anticipated that when a new Standard is promulgated, the Assurance Requirements in the current Standard will remain intact. The Second Modification to the Consultation and Cooperation Agreement with the State of New Mexico acknowledges the necessity for continuing ''as though the provisions remain applicable''. The Plan will be revised as necessary in response to any changes in the Standard resulting from the court's decision. The WIPP Project was authorized by Public Law as a defense activity of the US Department of Energy (DOE) with the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes that result from defense activities of the US. The WIPP Project is exempted from regulation by the Nuclear Regulatory Commission (NRC). The mission of the WIPP Project is to conduct research, demonstration, and siting studies relevant to permanent disposal of transuranic (TRU) wastes. 4 refs

  16. Tuberculosis Laboratory Diagnosis Quality Assurance among Public Health Facilities in West Amhara Region, Ethiopia.

    Science.gov (United States)

    Shiferaw, Melashu Balew; Hailu, Hiwot Amare; Fola, Abebe Alemu; Derebe, Mulatu Melese; Kebede, Aimro Tadese; Kebede, Abayneh Admas; Emiru, Manamnot Agegne; Gelaw, Zelalem Dessie

    2015-01-01

    Reliable smear microscopy is an important component of Directly Observed Treatment Scheme (DOTS) strategy for TB control program in countries with limited resources. Despite external quality assessment is established in Ethiopia, there is lower TB detection rate (48%) in Amhara region compared to the World Health Organization (WHO) estimate (70%). This highlights the quality of smear microscopy needs to be evaluated. Therefore, the aim of this study was to assess the quality of sputum smear microscopy performance among health center laboratories in West Amhara region, Ethiopia. A cross sectional study was conducted from July 08, 2013 to July 07, 2014. Data were collected from 201 public health center laboratories using a structured questionnaire. Slides were collected based on Lot Quality Assurance Sampling (LQAS) method and rechecked blindly by trained laboratory technologists. The data were entered into EPI info V.7 and smear quality indicators and AFB results were analyzed by SPSS version 20. Among 201 laboratories enrolled in this study, 47 (23.4%) laboratories had major errors. Forty one (20.4%) laboratories had a total of 67 false negative and 29 (14.4%) laboratories had a total of 68 false positive results. Specimen quality, smear thickness and evenness were found poor in 134 (66.7%), 133 (66.2%) and 126 (62.7%) laboratories, respectively. Unavailability of microscope lens cleaning solution (AOR: 2.90; 95% CI: 1.25-6.75; P: 0.013) and dirty smears (AOR: 2.65; 95% CI: 1.14-6.18; P: 0.024) were correlated with false negative results whereas no previous EQA participation (AOR: 3.43; 95% CI: 1. 39-8.45; P: 0.007) was associated with false positive results. The performance of health facilities for sputum smear microscopy was relatively poor in West Amhara region. Hence, strengthening the EQA program and technical support on sputum smear microscopy are recommended to ensure quality tuberculosis diagnostic service.

  17. Tuberculosis Laboratory Diagnosis Quality Assurance among Public Health Facilities in West Amhara Region, Ethiopia.

    Directory of Open Access Journals (Sweden)

    Melashu Balew Shiferaw

    Full Text Available Reliable smear microscopy is an important component of Directly Observed Treatment Scheme (DOTS strategy for TB control program in countries with limited resources. Despite external quality assessment is established in Ethiopia, there is lower TB detection rate (48% in Amhara region compared to the World Health Organization (WHO estimate (70%. This highlights the quality of smear microscopy needs to be evaluated. Therefore, the aim of this study was to assess the quality of sputum smear microscopy performance among health center laboratories in West Amhara region, Ethiopia.A cross sectional study was conducted from July 08, 2013 to July 07, 2014. Data were collected from 201 public health center laboratories using a structured questionnaire. Slides were collected based on Lot Quality Assurance Sampling (LQAS method and rechecked blindly by trained laboratory technologists. The data were entered into EPI info V.7 and smear quality indicators and AFB results were analyzed by SPSS version 20.Among 201 laboratories enrolled in this study, 47 (23.4% laboratories had major errors. Forty one (20.4% laboratories had a total of 67 false negative and 29 (14.4% laboratories had a total of 68 false positive results. Specimen quality, smear thickness and evenness were found poor in 134 (66.7%, 133 (66.2% and 126 (62.7% laboratories, respectively. Unavailability of microscope lens cleaning solution (AOR: 2.90; 95% CI: 1.25-6.75; P: 0.013 and dirty smears (AOR: 2.65; 95% CI: 1.14-6.18; P: 0.024 were correlated with false negative results whereas no previous EQA participation (AOR: 3.43; 95% CI: 1. 39-8.45; P: 0.007 was associated with false positive results.The performance of health facilities for sputum smear microscopy was relatively poor in West Amhara region. Hence, strengthening the EQA program and technical support on sputum smear microscopy are recommended to ensure quality tuberculosis diagnostic service.

  18. Automated damage test facilities for materials development and production optic quality assurance at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Battersby, C.; Dickson, R.; Jennings, R.; Kimmons, J.; Kozlowski, M. R.; Maricle, S.; Mouser, R.; Runkel, M.; Schwartz, S.; Sheehan, L. M.; Weinzapfel, C.

    1998-01-01

    The Laser Program at LLNL has developed automated facilities for damage testing optics up to 1 meter in diameter. The systems were developed to characterize the statistical distribution of localized damage performance across large-aperture National Ignition Facility optics. Full aperture testing is a key component of the quality assurance program for several of the optical components. The primary damage testing methods used are R:1 mapping and raster scanning. Automation of these test methods was required to meet the optics manufacturing schedule. The automated activities include control and diagnosis of the damage-test laser beam as well as detection and characterization of damage events

  19. Quality assurance during construction of civil engineering structures important to safety of nuclear facilities

    International Nuclear Information System (INIS)

    2011-11-01

    The present manual is developed to deal with quality assurance aspect of civil engineering structures in a greater detail. This manual gives detail to develop QA plans specific to multifarious activities of civil engineering construction

  20. Quality assurance and quality control for the confinement physics research facility (CPRF) and ZTH experiment

    International Nuclear Information System (INIS)

    Kewish, R.W. Jr.

    1989-01-01

    In compliance with DOE order 5700.6B, which establishes policies to assure quality achievement in DOE programs, the authors instituted a quality assurance and quality control program whose primary goal is to assure that reliable components are available with which to assemble the CPRF/ZTH experiment. The Code of Federal Regulations 10 CFR 50, Appendix B, and the ANSI standard N45.2 were used as a primary source of guidance in establishing a plan for our QA program. Accepted codes, such as the National Electric Code (NEC), and standards adopted by organizations such as ANSI, IEEE, ASME, and NEMA were used in the design and production of components in keeping with the primary goal of the CPRF program. In setting up the CPRF/ZTH quality assurance program it was their intention to have these standards apply to all suppliers, both within and outside the Laboratory. 5 refs., 5 figs

  1. Quality assurance grading guidelines for research and development at DOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    Powell, T.B.; Morris, R.N.

    1993-01-01

    The quality assurance (QA) requirements for the US Department of Energy (DOE) are established in DOE Order 5700.6C. This order is applicable for all DOE departmental elements, management, and maintenance and operating contractors and requires that documented Quality Assurance Programs (QAPs) are prepared at all levels; it has one attachment. The DOE Office of Energy Research (DOE-ER) has issued a standard to ensure implementation of the full intent of this order in the ER community.

  2. Quality Assurance Program Plan for the Waste Sampling and Characterization Facility

    International Nuclear Information System (INIS)

    Grabbe, R.R.

    1995-01-01

    The objective of this Quality Assurance Plan is to provide quality assurance (QA) guidance, implementation of regulatory QA requirements, and quality control (QC) specifications for analytical service. This document follows the Department of Energy (DOE)-issued Hanford Analytical Services Quality Assurance Plan (HASQAP) and additional federal [10 US Code of Federal Regulations (CFR) 830.120] QA requirements that HASQAP does not cover. This document describes how the laboratory implements QA requirements to meet the federal or state requirements, provides what are the default QC specifications, and/or identifies the procedural information that governs how the laboratory operates. In addition, this document meets the objectives of the Quality Assurance Program provided in the WHC-CM-4-2, Section 2.1. This document also covers QA elements that are required in the Guidelines and Specifications for Preparing Quality Assurance Program Plans (QAPPs), (QAMS-004), and Interim Guidelines and Specifications for Preparing Quality Assurance Product Plans (QAMS-005) from the Environmental Protection Agency (EPA). A QA Index is provided in the Appendix A

  3. Quality assurance criteria for Waste Isolation Pilot Plant performance assessment modeling

    International Nuclear Information System (INIS)

    1995-07-01

    The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) as a deep geologic repository for transuranic (TRU) and TRU-mixed wastes generated by DOE Defense Program activities. Regulatory agencies, including the Environmental Protection Agency (EPA) and New Mexico Environment Department, will be forced to rely upon system modeling to determine the potential compliance of the WIPP facility with federal regulations. Specifically, long-term modeling efforts are focused on compliance with 40 CFR Part 268, ''Land Disposal Restrictions,'' and 40 CFR Part 191, ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes.'' DOE plans to use the similar conceptual models and numerical codes to demonstrate compliance under both of these regulations. Sandia National Laboratories (SNL) has been developing a system model that will be used to demonstrate potential waste migration from the WIPP facility. Because the geologic system underlying the WIPP site is not completely understood, the software code to model the system must be developed to exacting standards for its predictions to be reliable and defensible. This is a complex model that consists of many submodules used to describe various migration pathways and processes that affect potential waste migration

  4. Model for deployment of a Quality Assurance System in the nuclear fuel cycle facilities using Project Management techniques

    Energy Technology Data Exchange (ETDEWEB)

    Lage, Ricardo F.; Ribeiro, Saulo F.Q., E-mail: rflage@gmail.com, E-mail: quintao.saulo@gmail.com [Industrias Nucleares do Brasil (INB), Rio de Janeiro, RJ (Brazil)

    2015-07-01

    The Nuclear Safety is the main goal in any nuclear facility. In this sense the Norm CNEN-NN-1.16 classifies the quality assurance issue as a management system to be deployed and implemented by the organization to achieving security goals. Quality Assurance is a set of systematic and planned actions necessary to provide adequate confidence ensuring that a structure, system, component or installation will work satisfactorily in s. Hence, the Quality Assurance System (QAS) is a complete and comprehensive methodology, going far beyond a management plan quality from the perspective of project management. The fundamental of QAS requirements is all activities that influence the quality, involving organizational, human resources, procurement, nuclear safety, projects, procedures and communication. Coordination of all these elements requires a great effort by the team responsible because it usually involves different areas and different levels of hierarchy within the organization. The objectives and desired benefits should be well set for everyone to understand what it means to be achieved and how to achieve. The support of senior management is critical at this stage, providing guidelines and resources necessary to get the job elapse clearly and efficiently, on time, cost and certain scope. The methodology of project management processes can be applied to facilitate and expedite the implementation of this system. Many of the principles of the QAS are correlated with knowledge areas of project management. The proposed model for implementation of a QAS in the nuclear fuel cycle facilities considered the best project management practices according to the Project Management Book of Knowledge (PMBOK - 5th edition) of the Project Management Institute (PMI). This knowledge is considered very good practices around the world. Since the model was defined, the deployment process becomes more practical and efficient, providing reduction in deployment time, better management of human

  5. Model for deployment of a Quality Assurance System in the nuclear fuel cycle facilities using Project Management techniques

    International Nuclear Information System (INIS)

    Lage, Ricardo F.; Ribeiro, Saulo F.Q.

    2015-01-01

    The Nuclear Safety is the main goal in any nuclear facility. In this sense the Norm CNEN-NN-1.16 classifies the quality assurance issue as a management system to be deployed and implemented by the organization to achieving security goals. Quality Assurance is a set of systematic and planned actions necessary to provide adequate confidence ensuring that a structure, system, component or installation will work satisfactorily in s. Hence, the Quality Assurance System (QAS) is a complete and comprehensive methodology, going far beyond a management plan quality from the perspective of project management. The fundamental of QAS requirements is all activities that influence the quality, involving organizational, human resources, procurement, nuclear safety, projects, procedures and communication. Coordination of all these elements requires a great effort by the team responsible because it usually involves different areas and different levels of hierarchy within the organization. The objectives and desired benefits should be well set for everyone to understand what it means to be achieved and how to achieve. The support of senior management is critical at this stage, providing guidelines and resources necessary to get the job elapse clearly and efficiently, on time, cost and certain scope. The methodology of project management processes can be applied to facilitate and expedite the implementation of this system. Many of the principles of the QAS are correlated with knowledge areas of project management. The proposed model for implementation of a QAS in the nuclear fuel cycle facilities considered the best project management practices according to the Project Management Book of Knowledge (PMBOK - 5th edition) of the Project Management Institute (PMI). This knowledge is considered very good practices around the world. Since the model was defined, the deployment process becomes more practical and efficient, providing reduction in deployment time, better management of human

  6. Department of Energy Operation Quality Assurance Program for the Waste Isolation Pilot Plant (WIPP) Project (Carlsbad, New Mexico)

    International Nuclear Information System (INIS)

    1987-12-01

    The purpose of this plan is to describe the Quality Assurance (QA)reverse arrow Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Project Participants: the Scientific Advisor (Sandia National Laboratory) and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the Pre-Operational and Operational phases of the WIPP Project not addressed under the construction phase. This plan also requires the QA Programs for DOE and Project Participants to be structured so as to comply with this plan and ANSI-ASME NQA-1. The prime responsibility for Operational Quality Assurance rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Scientific Advisor and the Management and Operating Contractor. Overviews of selected operational and testing activities will be are conducted in accordance with prescribed requirements and that adequate documentation of these activities is maintained. 4 figs

  7. Quality assurance for external personnel monitoring in nuclear industrial facilities, CNNC

    International Nuclear Information System (INIS)

    Zhang Yansheng; Dai Jun; Li Taosheng

    1993-01-01

    More than 6000 personnel are currently being monitored for occupational exposure in CNNC, China. Personnel monitoring is one of the important items of radiation protection. The data of individual dose are not only indispensable for radiation safety assessment but also the basis for radiation protection measures to be taken. Possibly, it could provide basic information for epidemiological studies, optimization procedure of radiation protection (risk/benefit analyses) and medical or legal purposes. Obviously, personnel monitoring and its quality assurance are very significant

  8. Overview of the Quality Assurance Program Applied to the Performance Assessment of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Pickering, S.Y.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first deep geologic repository for radioactive waste disposal in the world to be certified by a regulator. Rigorous, nuclear-industry quality assurance (QA) requirements were imposed by the US Environmental Protection Agency. As the Scientific Advisor to the US Department of Energy, Sandia National Laboratories applied these standards to the experimental studies and performance assessment used in the certification process. The QA program ensured that activities conducted by SNL were traceable, transparent, reviewed, reproducible, and retrievable. As a result, regulators and stakeholders were able to evaluate and ultimately certify and accept the WIPP

  9. Nuclear decay data measurements at the INEL ISOL facility

    International Nuclear Information System (INIS)

    Greenwood, R.C.; Helmer, R.G.; Putnam, M.H.; Struttmann, D.A.; Watts, K.D.

    1991-01-01

    In recent years, the use of the mass separation technique coupled on-line to a source of fission product nuclides has provided a wealth of new information on the nuclear decay properties of such nuclides. In addition to their relevance in basic studies of nuclear properties of neutron-rich nuclei, the fission product nuclides as a group, because of their intimate link with energy production in fission reactors, occupy a unique position in the field of applied nuclear decay data. Further, in addition to their critical role in nuclear reactor technology (decay heat source term, environmental concerns, etc.), such data have important applications in astrophysical calculations involving the rapid neutron capture process (r-process) of elemental synthesis in stellar environments. The scope of the nuclear decay data measurements being undertaken using the Idaho National Engineering Laboratory's (INEL) isotope separation on-line (ISOL) facility is focused on a systematic study of the gross nuclear decay properties of short-lived fission product isotopes, i.e., ground-state half-lives, beta-decay energies and beta-decay feeding (or beta-strength) distributions. In this paper, the authors discuss the results of new measurements of beta-decay energies and feeding distributions

  10. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

  11. The meteorological monitoring audit, preventative maintenance and quality assurance programs at a former nuclear weapons facility

    International Nuclear Information System (INIS)

    Maxwell, D.R.

    1995-01-01

    The purposes of the meteorological monitoring audit, preventative maintenance, and quality assurance programs at the Rocky Flats Environmental Technology Site (Site), are to (1) support Emergency Preparedness (EP) programs at the Site in assessing the transport, dispersion, and deposition of effluents actually or potentially released into the atmosphere by Site operations; and (2) provide information for onsite and offsite projects concerned with the design of environmental monitoring networks for impact assessments, environmental surveillance activities, and remediation activities. The risk from the Site includes chemical and radioactive emissions historically related to nuclear weapons component production activities that are currently associated with storage of large quantities of radionuclides (plutonium) and radioactive waste forms. The meteorological monitoring program provides information for site-specific weather forecasting, which supports Site operations, employee safety, and Emergency Preparedness operations

  12. Waste isolation facility description for the spent fuel cycle, bedded salt

    International Nuclear Information System (INIS)

    1977-05-01

    Details are given on surface facilities, shafts and hoists, mine facilities, ventilation systems, land improvements, and utilities. Accidents, confinement, and safety criteria are covered. Appendices are provided on mine layout and development, mine operations, shaft construction information, and analysis concerning canister rupture inside the proposed waste isolation facility

  13. Financial assurances

    International Nuclear Information System (INIS)

    Paton, R.F.

    1990-01-01

    US Ecology is a full service waste management company. The company operates two of the nation's three existing low-level radioactive waste (LLRW) disposal facilities and has prepared and submitted license applications for two new LLRW disposal facilities in California and Nebraska. The issue of financial assurances is an important aspect of site development and operation. Proper financial assurances help to insure that uninterrupted operation, closure and monitoring of a facility will be maintained throughout the project's life. Unfortunately, this aspect of licensing is not like others where you can gauge acceptance by examining approved computer codes, site performance standards or applying specific technical formulas. There is not a standard financial assurance plan. Each site should develop its requirements based upon the conditions of the site, type of design, existing state or federal controls, and realistic assessments of future financial needs. Financial assurances at U.S. Ecology's existing sites in Richland, Washington, and Beatty, Nevada, have been in place for several years and are accomplished in a variety of ways by the use of corporate guarantees, corporate capital funds, third party liability insurance, and post closure/long-term care funds. In addressing financial assurances, one can divide the issue into three areas: Site development/operations, third party damages, and long-term care/cleanup

  14. Quality assurance requirements for control of procurement items and services for nuclear fuel reprocessing facilities

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Requirements and guidelines are provided for the control of activities to be exercised during procurement of items and services which affect the quality of nuclear facilities. These requirements and guidelines apply to procurement activities for items and services such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, constructing, erecting, installing, inspecting, texting, maintaining and modifying

  15. Development and implementation of a comprehensive quality assurance program at a community endoscopy facility.

    Science.gov (United States)

    Hilsden, Robert Jay; Rostom, Alaa; Dubé, Catherine; Pontifex, Darlene; McGregor, S Elizabeth; Bridges, Ronald J

    2011-10-01

    Quality assurance (QA) is a process that includes the systematic evaluation of a service, institution of improvements and ongoing evaluation to ensure that effective changes were made. QA is a fundamental component of any organized colorectal cancer screening program. However, it should play an equally important role in opportunistic screening. Establishing the processes and procedures for a comprehensive QA program can be a daunting proposition for an endoscopy unit. The present article describes the steps taken to establish a QA program at the Forzani & MacPhail Colon Cancer Screening Centre (Calgary, Alberta) - a colorectal cancer screening centre and nonhospital endoscopy unit that is dedicated to providing colorectal cancer screening-related colonoscopies. Lessons drawn from the authors' experience may help others develop their own initiatives. The Global Rating Scale, a quality assessment and improvement tool developed for the gastrointestinal endoscopy services of the United Kingdom's National Health Service, was used as the framework to develop the QA program. QA activities include monitoring the patient experience through surveys, creating endoscopist report cards on colonoscopy performance, tracking and evaluating adverse events and monitoring wait times.

  16. Development and Implementation of a Comprehensive Quality Assurance Program at a Community Endoscopy Facility

    Directory of Open Access Journals (Sweden)

    Robert J Hilsden

    2011-01-01

    Full Text Available Quality assurance (QA is a process that includes the systematic evaluation of a service, institution of improvements and ongoing evaluation to ensure that effective changes were made. QA is a fundamental component of any organized colorectal cancer screening program. However, it should play an equally important role in opportunistic screening. Establishing the processes and procedures for a comprehensive QA program can be a daunting proposition for an endoscopy unit. The present article describes the steps taken to establish a QA program at the Forzani & MacPhail Colon Cancer Screening Centre (Calgary, Alberta – a colorectal cancer screening centre and nonhospital endoscopy unit that is dedicated to providing colorectal cancer screening-related colonoscopies. Lessons drawn from the authors’ experience may help others develop their own initiatives. The Global Rating Scale, a quality assessment and improvement tool developed for the gastrointestinal endoscopy services of the United Kingdom’s National Health Service, was used as the framework to develop the QA program. QA activities include monitoring the patient experience through surveys, creating endoscopist report cards on colonoscopy performance, tracking and evaluating adverse events and monitoring wait times.

  17. EORTC Radiation Oncology Group quality assurance platform: Establishment of a digital central review facility

    International Nuclear Information System (INIS)

    Fairchild, Alysa; Aird, Edwin; Fenton, Paul A.; Gregoire, Vincent; Gulyban, Akos; Lacombe, Denis; Matzinger, Oscar; Poortmans, Philip; Ruyskart, Pascal; Weber, Damien C.; Hurkmans, Coen W.

    2012-01-01

    Objective: Quality assurance (QA) in clinical trials is essential to ensure treatment is safely and effectively delivered. As QA requirements have increased in complexity in parallel with evolution of radiation therapy (RT) delivery, a need to facilitate digital data exchange emerged. Our objective is to present the platform developed for the integration and standardization of QART activities across all EORTC trials involving RT. Methods: The following essential requirements were identified: secure and easy access without on-site software installation; integration within the existing EORTC clinical remote data capture system; and the ability to both customize the platform to specific studies and adapt to future needs. After retrospective testing within several clinical trials, the platform was introduced in phases to participating sites and QART study reviewers. Results: The resulting QA platform, integrating RT analysis software installed at EORTC Headquarters, permits timely, secure, and fully digital central DICOM-RT based data review. Participating sites submit data through a standard secure upload webpage. Supplemental information is submitted in parallel through web-based forms. An internal quality check by the QART office verifies data consistency, formatting, and anonymization. QART reviewers have remote access through a terminal server. Reviewers evaluate submissions for protocol compliance through an online evaluation matrix. Comments are collected by the coordinating centre and institutions are informed of the results. Conclusions: This web-based central review platform facilitates rapid, extensive, and prospective QART review. This reduces the risk that trial outcomes are compromised through inadequate radiotherapy and facilitates correlation of results with clinical outcomes.

  18. Apparatus for isolating electric generators or like other facilities upon occurrence of earthquakes

    International Nuclear Information System (INIS)

    Toshimitsu, Satoru.

    1983-01-01

    Purpose: To prevent, upon occurrence of failures in a facility with poor earthquake-proof performance, undesired secondary effects caused by the above failures from prevailing on other facilities with excellent earthquake-proof performance. Constitution: An isolation valve is disposed at the midway of pipeways communicating facilities of different earthquake-proof performances. When the occurrence of earthquake and the magnitude thereof are detected and judged by an earthquake detection and control device, the isolation valve between the facility of excellent earthquake-proof performance and the facility of poor earthquake-proof performance is opened. Consequently, if the facility of poor earthquake-proof performance is failed, no fluid is issued from the facility of the excellent earthquake-proof performance to thereby improve the earthquake safety. (Kawakami, Y.)

  19. SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M [Mayo Clinic, Rochester, MN (United States)

    2016-06-15

    Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

  20. SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

    International Nuclear Information System (INIS)

    Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M

    2016-01-01

    Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

  1. [Quality assurance of pain care in Austria : Classification of management facilities].

    Science.gov (United States)

    Jaksch, Wolfgang; Likar, Rudolf; Folkes, Erika; Machold, Klaus; Herbst, Friedrich; Pils, Katharina; Stippl, Peter; Lettner, Sandra; Alfons, Mildred; Crevenna, Richard; Wiederer, Christian; Dieber, Janina; Glehr, Reinhold

    2017-11-01

    In Austria there is no nationwide coverage of pain management, which meets even approximately international criteria. At present there are about 30 interdisciplinary pain management offices and clinics providing care according to a concept of the Austrian Pain Society (ÖSG), about 10 other outpatient pain clinics are located in district and country hospitals. A few years ago, there still were about 50 pain clinics. Yet closure of outpatient clinics and cost-cutting measures in the health sector jeopardize adequate pain relief for patients with chronic pain conditions.Hence, the supply of care for approx. 1.8 mio. Austrians with chronic pain is not guaranteed due to lack of a comprehensive demand planning of pain care facilities. Furthermore, existing structures such as specialized clinics or emergency services in hospitals are primarily based on the personal commitment of individuals. At present, the various centres for pain management in Austria are run with very different operating times, so that for 74% of the chronic pain patients the desired requirements for outpatient pain management are not met and about 50 full-time pain clinics are missing.Under the patronage of the Austrian Pain Society, various national specialist societies have defined the structure and quality criteria for pain management centres in Austria, include, among others, proof of training, cooperation in interdisciplinary teams or minimum number of new patients per year, depending on the classification of the institution.This stepwise concept of care provision for pain patients is intended as first step to help improve the care of pain patients in Austria!

  2. Status of U.S. Plans for an Advanced ISOL Facility. A Brief Report

    International Nuclear Information System (INIS)

    Bertrand, F.E.

    1998-01-01

    A brief discussion is provided of the current status of plans to build an advanced ISOL radioactive ion beam facility in the US. Designs for this new facility, which was recommended as the next major construction project of the DOE Nuclear Physics Program Office, have been proposed by two US national laboratories, Argonne National Laboratory and Oak Ridge National Laboratory. The new facility will provide orders-of-magnitude higher radioactive beam currents than existing facilities of this type and will cost in the range of $250 million

  3. Quality assurance system for sitting high risk facilities; Sistema de aseguramiento de la calidad para el emplazamiento de obras de alto riesgo

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, Aymee; Peralta, Jose L.; Fernandez, Manuel [Centro de Tecnologia Nuclear, San Jose de las Lajas (Cuba)

    1999-11-01

    The paper shows how we have conceived and designed the quality assurance system for the site selection process of an area for sitting the facility of high risk in correspondence with the approved methodology. The results obtained in the implementation of the system have permitted the satisfactory performance of each one the expected stage, defining the most favorable sectors in order to continue the studies of the repository site for the disposal of low and intermedium. (author) 7 refs., 1 tab.

  4. Versatile data acquisition system and the ISOL facility TRISTAN

    International Nuclear Information System (INIS)

    Gill, R.L.; Stelts, M.L.; Chrien, R.E.; Manzella, V.; Liou, H.I.; Shostak, S.

    1980-01-01

    The on-line mass separator, TRISTAN, is located at Brookhaven's High Flux Beam Reactor. A Nielsen-type ion source, which can contain up to 8g. of 235 U in an external beam with a flux of approx. 2 x 10 9 n/cm 2 /sec is used to generate short-lived fission products. A Users Group has been formed to coordinate research between University groups and BNL. Developments planned for TRISTAN include FEBIAD, surface ionization and negative-surface ionization-type ion sources, and a He-jet system as well as construction of new experimental facilities. An off-line separator, ISTU, is available for the development program. A versatile, modular data acquisition system to service experiments on TRISTAN and other nuclear research facilities at the HFBR using Camac interfacing is described. Standard, commercially-available electronic instruments and computer programs, such as FORTRAN and system routines, are used throughout. Simple interfaces have been built to adapt non-Camac equipment to Camac input registers

  5. In-Source Laser Resonance Ionization at ISOL Facilities

    CERN Document Server

    Marsh, Bruce; Feddosseev, Valentin

    Resonance ionization laser ion source development has been carried out at two radioactive ion beam facilities: ISOLDE (CERN, Switzerland) and the IGISOL facility (Jyvaskyla, Finland). The scope of the Resonance Ionization Laser Ion Source has been extended to 27 elements with the development of new three-step ionization schemes for Sb, Sc, Dy, Y and Au. The efficiencies were determined to be in the range of 2 - 20 %. Additionally, a new two-step ionization scheme has been developed for bismuth in an off-line atomic beam unit. The scheme relies on ionization via a strong and broad auto-ionizing resonance at an energy of 63196.79 cm$^{−1}$. This scheme may offer an improvement over the existing RILIS efficiency and will be more convenient for use during resonance ionization spectroscopy of Bi isotopes. The RILIS can be used as a spectroscopic tool to probe features such as the hyperfine structures and the isotope-shifts of radioisotopes with low production rates. By coupling a laser scanning process that dire...

  6. Guidance for the design and management of a maintenance plan to assure safety and improve the predictability of a DOE nuclear irradiation facility. Final report

    International Nuclear Information System (INIS)

    Booth, R.S.; Kryter, R.C.; Shepard, R.L.; Smith, O.L.; Upadhyaya, B.R.; Rowan, W.J.

    1994-10-01

    A program is recommended for planning the maintenance of DOE nuclear facilities that will help safety and enhance availability throughout a facility's life cycle. While investigating the requirements for maintenance activities, a major difference was identified between the strategy suitable for a conventional power reactor and one for a research reactor facility: the latter should provide a high degree of predicted availability (referred to hereafter as ''predictability'') to its users, whereas the former should maximize total energy production. These differing operating goals necessitate different maintenance strategies. A strategy for scheduling research reactor facility operation and shutdown for maintenance must balance safety, reliability,and predicted availability. The approach developed here is based on three major elements: (1) a probabilistic risk analysis of the balance between assured reliability and predictability (presented in Appendix C), (2) an assessment of the safety and operational impact of maintenance activities applied to various components of the facility, and (3) a data base of historical and operational information on the performance and requirements for maintenance of various components. These factors are integrated into a set of guidelines for designing a new highly maintainable facility, for preparing flexible schedules for improved maintenance of existing facilities, and for anticipating the maintenance required to extend the life of an aging facility. Although tailored to research reactor facilities, the methodology has broader applicability and may therefore be used to improved the maintenance of power reactors, particularly in anticipation of peak load demands

  7. The ISOL exotic beam facility at LNS: the EXCYT project

    International Nuclear Information System (INIS)

    Ciavola, G.; Calabretta, L.; Cuttone, G.; Di Bartolo, G.; Finocchiaro, P.; Gammino, S.; Gu, M.; Migneco, E.; Raia, G.; Rifuggiato, D.; Rovelli, A.; Vinciguerra, D.; Qin, J.; Wollnik, H.

    1997-01-01

    The aim of the EXCYT project (exotics with cyclotron and tandem) is the development of a facility for producing and accelerating exotic beams from 0.2 up to 8 MeV/amu. EXCYT is based on the ''two accelerators'' method. A K=800 superconducting cyclotron, axially injected by the ECR ion source SERSE, will deliver the primary beam. Such a beam will produce the required nuclear species in a modified ISOLDE type target-source complex. When required, a 15 MV tandem Van der Graaff will accelerate the secondary beams. Both accelerators are existing and operational at Laboratorio Nazionale del Sud. Concerning the status of the project, progress has been made in most of the key issues of the project, like the construction of SERSE, cyclotron upgrading, modification of the existing building, high resolution mass separator, and diagnostic equipment for low energy, low intensity beams. (orig.)

  8. The ISOL exotic beam facility at LNS: the EXCYT project

    Energy Technology Data Exchange (ETDEWEB)

    Ciavola, G.; Calabretta, L.; Cuttone, G.; Di Bartolo, G.; Finocchiaro, P.; Gammino, S.; Gu, M.; Migneco, E.; Raia, G.; Rifuggiato, D.; Rovelli, A.; Vinciguerra, D. [Istituto Nazionale di Fisica Nucleare, Catania (Italy); Qin, J. [Institute of Atomic Energy, Beijing (China); Wollnik, H. [Giessen Univ. (Germany)

    1997-04-01

    The aim of the EXCYT project (exotics with cyclotron and tandem) is the development of a facility for producing and accelerating exotic beams from 0.2 up to 8 MeV/amu. EXCYT is based on the ``two accelerators`` method. A K=800 superconducting cyclotron, axially injected by the ECR ion source SERSE, will deliver the primary beam. Such a beam will produce the required nuclear species in a modified ISOLDE type target-source complex. When required, a 15 MV tandem Van der Graaff will accelerate the secondary beams. Both accelerators are existing and operational at Laboratorio Nazionale del Sud. Concerning the status of the project, progress has been made in most of the key issues of the project, like the construction of SERSE, cyclotron upgrading, modification of the existing building, high resolution mass separator, and diagnostic equipment for low energy, low intensity beams. (orig.). 8 refs.

  9. Production and quality assurance in the SIT Africa Mediterranean fruit fly (Diptera: Tephritidae) rearing facility in South Africa

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, B [Plant Protection Division, ARC Infruitec-Nietvoorbij Fruit, Vine and Wine Institute, Stellenbosch, 7599 (South Africa); Rosenberg, S; Arnolds, L; Johnson, J [SIT Africa (Pty) Ltd., Stellenbosch, 7599 (South Africa)

    2007-03-15

    A mass-rearing facility for Mediterranean fruit fly Ceratitis capitata (Wiedemann) was commissioned in Stellenbosch in 1999 to produce sterile male fruit flies for a sterile insect technique (SIT) project in commercial fruit orchards and vineyards in the Western Cape province of South Africa. The mass-rearing procedure was largely based on systems developed by the FAO/IAEA Agriculture and Biotechnology Laboratory, Seibersdorf, Austria. A number of genetic sexing strains were used to produce only males for release. Initial cramped rearing and quality management conditions were alleviated in 2001 with the construction of a new adult rearing room and quality control laboratory. In 2002 a comprehensive Quality Management System was implemented, and in 2003 an improved genetic sexing strain, VIENNA 8, was supplied by the FAO/IAEA Laboratory in Seibersdorf. For most of the first 3 years the facility was unable to supply the required number of sterile male Mediterranean fruit flies for the SIT program without importing sterile male pupae from another facility. From mid-2002, after the quality management system was implemented, both production and quality improved but remained below optimum. After the introduction of the VIENNA 8 genetic sexing strain, and together with an improvement in the climate control equipment, production stability, and quality assurance parameters improved substantially. The critical factors influencing production and quality were an inadequate rearing infrastructure, problems with the quality of the larval diet, and the initial absence of a quality management system. The results highlight the importance of effective quality management, the value of a stable and productive genetic sexing strain, and the necessity for a sound funding base for the mass-rearing facility. (author) [Spanish] La facilidad para criar en masa la mosca mediterranea de la fruta, Ceratitis capitata (Wiedemann) fue comisionada en Stellenbosch en 1999 para producir machos

  10. A versatile data acquisition system and the ISOL facility TRISTAN

    International Nuclear Information System (INIS)

    Gill, R.L.; Stelts, M.L.; Chrien, R.E.; Manzella, V.; Liou, H.; Shostak, S.

    1981-01-01

    We have constructed a versatile, modular data acquisition system to service experiments on TRISTAN and other nuclear research facilities at the HFBR using CAMAC interfacing. Standard, commercially-available electronic instruments and computer programs, such as FORTRAN and system routines, are used throughout. Simple interfaces have been built to adapt non-CAMAC equipment to CAMAC input registers. Up to eight different experiments can be multiplexed on the branch highway by a fast microprogrammed branch driver with a 4096 word memory. The branch driver delivers pre-processed data to a bus which links devices such as a central processor, 1 megaword core memory, tape drives, discs, display processor and terminal. The following features are offered: two 8192 channel pulse height analyzers, a 3-parameter coincidence unit, 4 multiscalers, a timed sequence of delayed γ-ray spectra (33 spectra of 4096 channels each), a 2-parameter (pulse height versus time-of-flight) analyzer, 16 scalers and 24 experimental interlocks. Up to 100 different spectra are available to users for display during an experiment. (orig./RW)

  11. Quality Assurance Grading Guidelines for Research and Development at DOE Facilities (DOE Order 5700.6C)

    Energy Technology Data Exchange (ETDEWEB)

    Powell, T.B.

    1992-01-01

    The quality assurance (QA) requirements for the U.S. Department of Energy (DOE) are established in DOE Order 5700.6C. This order is applicable for all DOE departmental elements, management, and maintenance and operating contractors and requires that documented Quality Assurance Programs (QAPs) are prepared at all levels; it has one attachment. The DOE Office of Energy Research (DOE-ER) has issued a standard to ensure implementation of the full intent of this order in the ER community.

  12. Quality assurance grading guidelines for research and development at DOE facilities. DOE Order 5700.6C

    Energy Technology Data Exchange (ETDEWEB)

    Powell, T.B.; Morris, R.N.

    1992-10-01

    The quality assurance (QA) requirements for the US Department of Energy (DOE) are established in DOE Order 5700.6C. This order is applicable for all DOE departmental elements, management, and maintenance and operating contractors and requires that documented Quality Assurance Programs (QAPS) are prepared at all levels; it has one attachment. The DOE Office of Energy Research (DOE-ER) has issued a standard to ensure implementation of the full intent of this order in the ER community. This report discusses order 5700.6C in relation to research with DOE.

  13. Uranium and thorium mining regulations: Amendments relating to financial assurances and decommissioning of uranium mining facilities. Consultative document

    Energy Technology Data Exchange (ETDEWEB)

    Brooks, G L [Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations

    1993-12-23

    The purpose of this document is to describe the objectives, scope, substance and application of proposed amendments to the Uranium and Thorium Mining Regulations; in particular, amendments relating to the provision of financial assurances for the decommissioning of Canadian uranium mines. (author).

  14. Uranium and thorium mining regulations: Amendments relating to financial assurances and decommissioning of uranium mining facilities. Consultative document

    International Nuclear Information System (INIS)

    Brooks, G.L.

    1993-01-01

    The purpose of this document is to describe the objectives, scope, substance and application of proposed amendments to the Uranium and Thorium Mining Regulations; in particular, amendments relating to the provision of financial assurances for the decommissioning of Canadian uranium mines. (author)

  15. Factors associated with malaria microscopy diagnostic performance following a pilot quality-assurance programme in health facilities in malaria low-transmission areas of Kenya, 2014.

    Science.gov (United States)

    Odhiambo, Fredrick; Buff, Ann M; Moranga, Collins; Moseti, Caroline M; Wesongah, Jesca Okwara; Lowther, Sara A; Arvelo, Wences; Galgalo, Tura; Achia, Thomas O; Roka, Zeinab G; Boru, Waqo; Chepkurui, Lily; Ogutu, Bernhards; Wanja, Elizabeth

    2017-09-13

    Malaria accounts for ~21% of outpatient visits annually in Kenya; prompt and accurate malaria diagnosis is critical to ensure proper treatment. In 2013, formal malaria microscopy refresher training for microscopists and a pilot quality-assurance (QA) programme for malaria diagnostics were independently implemented to improve malaria microscopy diagnosis in malaria low-transmission areas of Kenya. A study was conducted to identify factors associated with malaria microscopy performance in the same areas. From March to April 2014, a cross-sectional survey was conducted in 42 public health facilities; 21 were QA-pilot facilities. In each facility, 18 malaria thick blood slides archived during January-February 2014 were selected by simple random sampling. Each malaria slide was re-examined by two expert microscopists masked to health-facility results. Expert results were used as the reference for microscopy performance measures. Logistic regression with specific random effects modelling was performed to identify factors associated with accurate malaria microscopy diagnosis. Of 756 malaria slides collected, 204 (27%) were read as positive by health-facility microscopists and 103 (14%) as positive by experts. Overall, 93% of slide results from QA-pilot facilities were concordant with expert reference compared to 77% in non-QA pilot facilities (p malaria diagnosis. Microscopists who had recently completed refresher training and worked in a QA-pilot facility performed the best overall. The QA programme and formal microscopy refresher training should be systematically implemented together to improve parasitological diagnosis of malaria by microscopy in Kenya.

  16. Metrology's role in quality assurance

    International Nuclear Information System (INIS)

    Zeederberg, L.B.

    1982-01-01

    Metrology, the science of measurement, is playing an increasing role in modern industry as part of an on-going quality assurance programme. At Escom, quality assurance was critical during the construction of the Koeberg nuclear facility, and also a function in controlling services provided by Escom. This article deals with the role metrology plays in quality assurance

  17. Revitalizing quality assurance

    International Nuclear Information System (INIS)

    Hawkins, F.C.

    1998-01-01

    The image of someone inspecting or auditing often comes to mind when people hear the term quality assurance. Although partially correct, this image is not the complete picture. The person doing the inspecting or auditing is probably part of a traditional quality assurance organization, but that organization is only one aspect of a properly conceived and effectively implemented quality assurance system whose goal is improved facility safety and reliability. This paper introduces the underlying philosophies and basic concepts of the International Atomic Energy Agency's new quality assurance initiative that began in 1991 as part of a broad Agency-wide program to enhance nuclear safety. The first product of that initiative was publication in 1996 of a new Quality Assurance Code 50-C/SG-Q and fourteen related Safety Guides. This new suite of documents provide the technical and philosophical foundation upon which Member States can base their quality assurance programs. (author)

  18. Methicillin-resistant Staphylococcus aureus isolates from surfaces and personnel at a hospital laundry facility.

    Science.gov (United States)

    Michael, K E; No, D; Roberts, M C

    2016-09-01

    Examine a clinical laundry facility for the presence of methicillin-resistant Staphylococcus aureus (MRSA) on environmental surfaces and among personnel. Nasal and face samples along with surface samples were collected four times in 2015. MRSA isolates were confirmed using standardized biochemical assays and molecular characterization. MRSA was identified in 33/120 (28%) samples from the dirty and 3/120 (3%) samples from the clean environmental areas. MRSA isolates included: (dirty) ST5 SCCmec type II, ST8 SCCmec type IV, ST231 SCCmec type II, ST239 SCCmec type III, ST239 SCCmec type IV, ST256 SCCmec type IV and (clean) ST5 SCCmec type II and ST8 SCCmec type IV. Five different employees were MRSA positive, 4/8 (50%) from the dirty: and 1/15 (6·7%) from the clean, but there was a 10-fold higher MRSA carriage 6/22 (27%) dirty vs 1/38 (2·6%) clean when all 50 human samples were combined. MRSA prevalence was significantly higher (28 vs 3%) in dirty vs clean areas within the laundry facility suggesting a greater risk for personnel on the dirty side. This is the first report of isolation and characterization of MRSA from surfaces and personnel from a clinical laundry facility. © 2016 The Society for Applied Microbiology.

  19. Proceedings of the first international seminar on seismic base isolation for nuclear power facilities

    International Nuclear Information System (INIS)

    1989-01-01

    The First International Seminar on Seismic Base Isolation of Nuclear Power Facilities was organized by the authors of this paper. It was held in San Francisco, California, USA, on August 21--22, 1989, in conjunction with the tenth International Conference on Structural Mechanics in Reactor Technology (SMiRT-10). The purpose of the seminar was to provide an international forum for discussion on the application of base isolation to nuclear power plants and of its effectiveness in reducing seismic loads and permitting standard plant designs. It also provided an opportunity for technical interchange between base isolation system designers, structural engineers, and nuclear power plant engineers. Seismic isolation is certainly one of the most significant earthquake engineering developments in recent years. This was clearly demonstrated by the very large attendance at this seminar and the various papers presented. Isolation system act as filters that reduce the seismic forces and increase the ability of isolated structures and their contents to withstand the damaging effects of earthquake motions. Each individual paper has been cataloged separately

  20. Isolation facilities for highly infectious diseases in Europe--a cross-sectional analysis in 16 countries.

    Directory of Open Access Journals (Sweden)

    Stefan Schilling

    Full Text Available BACKGROUND: Highly Infectious Diseases (HIDs are (i easily transmissible form person to person; (ii cause a life-threatening illness with no or few treatment options; and (iii pose a threat for both personnel and the public. Hence, even suspected HID cases should be managed in specialised facilities minimizing infection risks but allowing state-of-the-art critical care. Consensus statements on the operational management of isolation facilities have been published recently. The study presented was set up to compare the operational management, resources, and technical equipment among European isolation facilities. Due to differences in geography, population density, and national response plans it was hypothesized that adherence to recommendations will vary. METHODS AND FINDINGS: Until mid of 2010 the European Network for Highly Infectious Diseases conducted a cross-sectional analysis of isolation facilities in Europe, recruiting 48 isolation facilities in 16 countries. Three checklists were disseminated, assessing 44 items and 148 specific questions. The median feedback rate for specific questions was 97.9% (n = 47/48 (range: n = 7/48 (14.6% to n = 48/48 (100%. Although all facilities enrolled were nominated specialised facilities' serving countries or regions, their design, equipment and personnel management varied. Eighteen facilities fulfilled the definition of a High Level Isolation Unit'. In contrast, 24 facilities could not operate independently from their co-located hospital, and five could not ensure access to equipment essential for infection control. Data presented are not representative for the EU in general, as only 16/27 (59.3% of all Member States agreed to participate. Another limitation of this study is the time elapsed between data collection and publication; e.g. in Germany one additional facility opened in the meantime. CONCLUSION: There are disparities both within and between European countries regarding the design

  1. A new high-temperature plasma ion source for the TRISTAN ISOL facility

    International Nuclear Information System (INIS)

    Piotrowski, A.; Gill, R.L.; McDonald, D.C.

    1987-01-01

    A vigorous program of ion-source development at TRISTAN has led to several types of ion sources that are especially suited to extended operation at a reactor-based ISOL facility. The latest of these is a high-temperature plasma ion source in which a 5-g /sup 235/U target is located in the cathode and can be heated to 2500 0 C. The ion source has a lifetime of > 1000 h and produces a wide array of elements, including palladium. Off-line investigations indicate that the source functions primarily in an electron impact mode of ionization and exhibits typical ionization efficiencies of > 30% for xenon

  2. A new high-temperature plasma ion source for the TRISTAN ISOL facility

    International Nuclear Information System (INIS)

    Piotrowski, A.; Gill, R.L.; McDonald, D.C.

    1987-01-01

    A vigorous program of ion-source development at TRISTAN has led to several types of ion sources that are especially suited to extended operation at a reactor-based ISOL facility. The latest of these is a high-temperature plasma ion source in which a 5-g 235 U target is located in the cathode and can be heated to 2500 0 C. The ion source has a lifetime of >1000 h and produces a wide array of elements, including palladium. Off-line investigations indicate that the source functions primarily in an electron impact mode of ionization and exhibits typical ionization efficiencies of >30% for xenon. (orig.)

  3. New high temperature plasma ion source for the TRISTAN ISOL facility

    International Nuclear Information System (INIS)

    Piotrowski, A.; Gill, R.L.; McDonald, D.C.

    1986-08-01

    A vigorous program of ion source development at TRISTAN has led to several types of ion sources that are especially suited to extended operation at a reactor-based ISOL facility. The latest of these is a high temperature plasma ion source in which a 5 gm 235 U target is located in the cathode and can be heated to 2500 0 C. The ion source has a lifetime of >1000 hours and produces a wide array of elements, including Pd. Off-line investigations indicate that the source functions primarily in an electron impact mode of ionization and exhibits typical ionzation efficiencies of >30% for Xe

  4. Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

  5. DOE financial assurance presentation

    International Nuclear Information System (INIS)

    Huck, R.

    1990-01-01

    The presentation topic is California's approach to license application review in meeting financial assurances for the proposed Ward Valley site. The purpose of the presentation is to provide information on specific financial assurance provisions contained in 10 CFR Part 61 and how California intends to satisfy those requirements. Also, as rate setter, California intends to demonstrate how it will assure allowable costs to the rate base though a financial prudency review. The key provisions of financial assurance are: 10 CFR Section 61.61 - This provision requires an applicant to demonstrate its ability to finance licensed activities; 10 CFR Section 61.62 - This provision requires an applicant to provide assurance that sufficient funds will be available for site closure and stabilization; and 10 CFR Section 61.63 - This provision requires an applicant to provide 'a copy of a binding arrangement, such as a lease, between the applicant and the disposal site owner, so that sufficient funds will be available to cover the costs of the institutional control period.' To assist California in its determination of financial assurance compliance to be demonstrated by the applicant for Part 61 requirements, is NUREG guidance document 1199 'Standard Format and Content of a License Application for a Low-Level Radioactive Waste (LLRW) Disposal Facility.' The detailed financial assurance provisions of NUREG 1199 are then embodied in NUREG 1200, 'Standard Review Plant for the Review of a License Application for a LLRW Disposal Facility.'

  6. Quality assurance

    International Nuclear Information System (INIS)

    Kunich, M.P.; Vieth, D.L.

    1989-01-01

    This paper provides a point/counterpoint view of a quality assurance director and a project manager. It presents numerous aspects of quality assurance requirements along with analyses as to the value of each

  7. Results of Use of WHO Global Salm-Surv External Quality Assurance System for Antimicrobial Susceptibility Testing of Salmonella Isolates from 2000 to 2007

    DEFF Research Database (Denmark)

    Hendriksen, Rene S.; Seyfarth, Anne Mette; Jensen, Arne Bent

    2009-01-01

    laboratories in 102 countries participated in at least one EQAS iteration. A large number of laboratories reported results for the E. coli ATCC 25922 reference strain which were outside the quality control ranges. Critical deviations for susceptibility testing of the Salmonella isolates varied from 4% in 2000......An international External Quality Assurance System (EQAS) for antimicrobial susceptibility testing of Salmonella was initiated in 2000 by the World Health Organization (WHO) Global Salm-Surv in order to enhance the capacities of national reference laboratories to obtain reliable data....... In particular, further training and dissemination of information on quality control, appropriate interpretive criteria (breakpoints), and harmonization of the methodology worldwide through WHO Global Salm-Surv and other programs will contribute to the generation of comparable and reliable antimicrobial...

  8. Shielding assessment for the proposed HRIBF upgrade to the National ISOL Facility

    International Nuclear Information System (INIS)

    Slater, C.O.; Olsen, D.K.; Johnson, J.O.; Lillie, R.A.; Gabriel, T.A.

    1997-04-01

    An upgrade of the existing ORNL Holifield Radioactive Ion Beam Facility (HRIBF) to the National Radioactive Ion Beam Isotope Separator On Line (RIB ISOL) Facility is being proposed. Part of the upgrade involves increasing the source proton energy and current, resulting in more intense, higher energy radiation. Shielding requirements for the proposed upgrade to the HRIBF have been assessed with respect to weight, space, and dose-rate constraints. Shielding assessments were made for operating, shutdown, and accident conditions. The results indicate reasonable shielding solutions for the target room except for the marginal dose rate on the roof. Shielding requirements in the target room were greatly reduced by decisions to move the target to a more interior room and to direct the proton beam downward into the target. A slightly more difficult shielding problem arises for proton beam extraction losses from the cyclotron. Here, the assumed isotropic beam losses (hence, neutron emissions) mean higher roof dose rates than those over the target room unless substantial localized shielding is placed over the cyclotron. Shutdown dose rates were found to present no problems. While dose rates through the sides of the facility during accident conditions will probably satisfy the accident dose-rate constraints, dose rates above the roof will be well above the constraints unless a solution is devised to shield the locations where beam losses are likely to occur. Ground activation analysis was postponed for this study

  9. Quality assurance manual: Volume 2, Appendices

    International Nuclear Information System (INIS)

    Oijala, J.E.

    1988-06-01

    This paper contains quality assurance information on departments of the Stanford Linear Accelerator Center. Particular quality assurance policies and standards discussed are on: Mechanical Systems; Klystron and Microwave Department; Electronics Department; Plant Engineering; Accelerator Department; Purchasing; and Experimental Facilities Department

  10. Use of base isolation techniques for the design of high-level waste storage facility enclosure at INEL

    International Nuclear Information System (INIS)

    Vallenas, J.M.; Wong, Chun K.; Beer, M.J.

    1993-08-01

    Current Department of Energy criteria for facilities subjected to natural hazards provide guidelines to place facilities or portions of facilities into usage categories. Usage categories are based on characteristics such as mission dependence, type of hazardous materials involved, and performance goals. Seismic requirements are significantly more stringent for facilities falling into higher ''hazard facility use categories''. A special problem arises in cases where a facility or portion of a facility is dependent on another facility of lower ''hazard facility use category'' for support or protection. Creative solutions can minimize the cost Unpact of ensuring that the lower category item does not compromise the performance of the higher category item. In this paper, a base isolation solution is provided for a ''low hazard facility use category'' weather enclosure designed so it will not collapse onto a ''high hazard facility use category'' high level waste storage facility at INEL. This solution is compared to other more conventional procedures. Details, practical limitations, licensing and regulatory considerations, and cost comparisons are provided

  11. Backfill barriers: the use of engineered barriers based on geologic materials to assure isolation of radioactive wastes in a repository

    International Nuclear Information System (INIS)

    Apps, J.A.; Cook, N.G.W.

    1981-06-01

    A preliminary assessment is made to show that canisters fabricated of nickel-iron alloys, and surrounded by a suitable backfill, may produce an engineered barrier where the canister material is thermodynamically stable with respect to its environment. As similar conditions exist in nature, the performance of such systems as barriers to isolate radionuclides can be predicted over very long periods, of the order of 10 6 years

  12. The Earthscope USArray Array Network Facility (ANF): Metadata, Network and Data Monitoring, Quality Assurance During the Second Year of Operations

    Science.gov (United States)

    Eakins, J. A.; Vernon, F. L.; Martynov, V.; Newman, R. L.; Cox, T. A.; Lindquist, K. L.; Hindley, A.; Foley, S.

    2005-12-01

    The Array Network Facility (ANF) for the Earthscope USArray Transportable Array seismic network is responsible for: the delivery of all Transportable Array stations (400 at full deployment) and telemetered Flexible Array stations (up to 200) to the IRIS Data Management Center; station command and control; verification and distribution of metadata; providing useful remotely accessible world wide web interfaces for personnel at the Array Operations Facility (AOF) to access state of health information; and quality control for all data. To meet these goals, we use the Antelope software package to facilitate data collection and transfer, generation and merging of the metadata, real-time monitoring of dataloggers, generation of station noise spectra, and analyst review of individual events. Recently, an Antelope extension to the PHP scripting language has been implemented which facilitates the dynamic presentation of the real-time data to local web pages. Metadata transfers have been simplified by the use of orb transfer technologies at the ANF and receiver end points. Web services are being investigated as a means to make a potentially complicated set of operations easy to follow and reproduce for each newly installed or decommissioned station. As part of the quality control process, daily analyst review has highlighted areas where neither the regional network bulletins nor the USGS global bulletin have published solutions. Currently four regional networks (Anza, BDSN, SCSN, and UNR) contribute data to the Transportable Array with additional contributors expected. The first 100 stations (42 new Earthscope stations) were operational by September 2005 with all but one of the California stations installed. By year's end, weather permitting, the total number of stations deployed is expected to be around 145. Visit http://anf.ucsd.edu for more information on the project and current status.

  13. Development of an evaluation method for seismic isolation systems of nuclear power facilities. Development of crossover piping design method for seismic isolation systems

    International Nuclear Information System (INIS)

    Otoyo, Teruyoshi; Otani, Akihito; Otani, Akihito; Fukushima, Shunsuke; Jimbo, Masakazu; Yamamoto, Tomofumi; Sakakida, Takaaki; Onishi, Shigenobu

    2014-01-01

    In the conceptual design of seismic isolation systems of nuclear power facilities, there exist two types of installation. The first type is to isolate both the reactor and the turbine buildings, the other is to isolate only the reactor building. In the latter type, the crossover piping, which installed between the isolated and the non-isolated buildings, is excited and deformed by the different motions of those buildings. In this study, shaking tests of 1/10 scaled model of the main steam piping and FEM analyses under multiple support excitation conditions have been performed to investigate the vibration behavior of the crossover piping. It was confirmed that modal time-history analyses could be in good agreement with the shaking test results. Also, Numerous combination methods were investigated by comparing response spectrum analyses and modal time-history analyses. In conclusion, response spectrum analyses using SRSS combinations could correspond to time-history analyses. (author)

  14. Quality-Assurance Program Plan

    International Nuclear Information System (INIS)

    Kettell, R.A.

    1981-05-01

    This Quality Assurance Program Plan (QAPP) is provided to describe the Quality Assurance Program which is applied to the waste management activities conducted by AESD-Nevada Operations at the E-MAD Facility located in Area 25 of the Nevada Test Site. The AESD-Nevada Operations QAPP provides the necessary systematic and administrative controls to assure activities that affect quality, safety, reliability, and maintainability during design, procurement, fabrication, inspection, shipments, tests, and storage are conducted in accordance with established requirements

  15. SENSITIVITY OF MOLDS ISOLATED FROM WAREHOUSES OF FOOD PRODUCTION FACILITY ON SELECTED ESSENTIAL OILS

    Directory of Open Access Journals (Sweden)

    Łukasz Kręcidło

    2015-07-01

    Full Text Available Storage of raw materials is one of steps in food production chain. The aim of this study was to estimate the influence of selected essential oils on the growth of four fungal strains: Trichoderma viride, Rhizomucor miehei, Penicillium chrysogenum, Penicillium janthinellum. Strains were isolated from warehouses of the food production facility. Selected essential oils: thyme oil, rosewood oil and rosemary oil were used to assess antifungal activity. Chemical composition of essential oils was determined by Gas Chromatography-Mass Spectroscopy (GC-MS. Antifungal activity of essential oils was estimated in relative to peracetic acid (PAA and sterile water with Tween 80 (0,5%. The influence of essential oils on fungal growth was carried by medium poisoning method. Increment of fungal mycelium was measured every day by 10 days. The thyme essential oils totally inhibited fungal growth in the lowest concentration of 1 mm3·cm-3. The most resistant strain was Penicillium janthinellum.

  16. Assessment of Gamma Radiation Resistance of Spores Isolated from the Spacecraft Assembly Facility During MSL Assembly

    Science.gov (United States)

    Chopra, Arsh; Ramirez, Gustavo A.; Vaishampayan, Parag A.; Venkateswaran, Kasthuri J.

    2011-01-01

    Spore forming bacteria, a common inhabitant of spacecraft assembly facilities, are known to tolerate extreme environmental conditions such as radiation, desiccation, and high temperatures. Since the Viking era (early 1970's), spores have been utilized to assess the degree and level of microbiological contamination on spacecraft and their associated spacecraft assembly facilities. There is a growing concern that desiccation and extreme radiation resistant spore forming microorganisms associated with spacecraft surfaces can withstand space environmental conditions and subsequently proliferate on another solar body. Such forward contamination would certainly jeopardize future life detection or sample return technologies. It is important to recognize that different classes of organisms are critical while calculating the probability of contamination, and methods must be devised to estimate their abundances. Microorganisms can be categorized based on radiation sensitivity as Type A, B, C, and D. Type C represents spores resistant to radiation (10% or greater survival above 0.8 Mrad gamma radiation). To address these questions we have purified 96 spore formers, isolated during planetary protection efforts of Mars Science Laboratory assembly for gamma radiation resistance. The spores purified and stored will be used to generate data that can be used further to model and predict the probability of forward contamination.

  17. Towards improvement in quality assurance

    International Nuclear Information System (INIS)

    1987-03-01

    This first document in the series of the International Nuclear Safety Advisory Group (INSAG) Technical Notes is a general guideline for the establishment of effective quality assurance procedures at nuclear facilities. It sets out primary requirements such as quality objectives, methods for measuring the effectiveness of the quality assurance programme, priority of activities in relation to importance of safety of items, motivation of personnel

  18. Quality assurance

    International Nuclear Information System (INIS)

    Cante; Feger; Genevray; Hennion; Moneyron; Monneyron; Normand; Rastoin; Silberstein; Vaujour.

    1976-01-01

    The general principles of quality assurance and their applications within the French industrial and commercial regulations are presented. The conditions for the practical application of quality assurance to the different stages of the life of a nuclear power station (design, development, operation) are considered and a special mention is made of nuclear fuels and liquid sodium cooled reactors [fr

  19. 49 CFR 195.575 - Which facilities must I electrically isolate and what inspections, tests, and safeguards are...

    Science.gov (United States)

    2010-10-01

    ... electrical transmission tower footings, ground cables, or counterpoise, or in other areas where it is... Corrosion Control § 195.575 Which facilities must I electrically isolate and what inspections, tests, and... other structures as a single unit. (b) You must install one or more insulating devices where electrical...

  20. Quality assurance

    International Nuclear Information System (INIS)

    1996-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (NRA SR) was focused on support of quality assurance programmes development at responsible organizations Bohunice V-1 and V-v and Mochovce NPPs and their inspection. Development of the level two documentation of a partial quality assurance programme for NPP operation continued at Mochovce NPP. Most of documentation has been submitted to NRA SR for comments and approval. NRA SR invited a mission of French experts to Mochovce NPP to review preparation and performance of internal audits that would be beneficial for improvement in this kind activities at the NPP. Bohunice NPP continued in development of a partial quality assurance programme for operation. The Quality Assurance Programme submitted to NRA SR for approval. Based on a request of Bohunice NPPs, NRA SR consulted the draft quality assurance programme developed by Siemens for stage of the 'Basic Design' of V-1 NPP upgrading. The programme had not been submitted for approval to NRA SR prior to completion of works by Siemens. Based on an internal audit that had been performed, corrective measures were proposed to meet requirements on review and approval of suppliers quality assurance programmes. Requirements related to the quality assurance at nuclear installations were prepared to be incorporated into principles of a act on peaceful use of nuclear power in Slovak Republic

  1. Conceptual aspects of fiscal interactions between local governments and federally-owned, high-level radioactive waste-isolation facilities

    International Nuclear Information System (INIS)

    Bjornstad, D.J.; Johnson, K.E.

    1981-01-01

    This paper examines a number of ways to transfer revenues between a federally-owned high level radioactive waste isolation facility (hereafter simply, facility) and local governments. Such payments could be used to lessen fiscal disincentives or to provide fiscal incentives for communities to host waste isolation facilities. Two facility characteristics which necessitate these actions are singled out for attention. First, because the facility is federally owned, it is not liable for state and local taxes and may be viewed by communities as a fiscal liability. Several types of payment plans to correct this deficiency are examined. The major conclusion is that while removal of disincentives or creation of incentives is possible, plans based on cost compensation that fail to consider opportunity costs cannot create incentives and are likely to create disincentives. Second, communities other than that in which the facility is sited may experience costs due to the siting and may, therefore, oppose it. These costs (which also accrue to the host community) arise due to the element of risk which the public generally associates with proximity to the transport and storage of radioactive materials. It is concluded that under certain circumstances compensatory payments are possible, but that measuring these costs will pose difficulty

  2. Production of exotic, short lived carbon isotopes in ISOL-type facilities

    CERN Document Server

    Franberg, Hanna; Köster, Ulli; Ammann, Markus

    2008-01-01

    The beam intensities of short-lived carbon isotopes at Isotope Separation On-Line (ISOL) facilities have been limited in the past for technical reasons. The production of radioactive ion beams of carbon isotopes is currently of high interest for fundamental nuclear physics research. To produce radioactive ions a target station consisting of a target in a container connected to an ion source via a transfer line is commonly used. The target is heated to vaporize the product for transport. Carbon in elementary form is a very reactive element and react strongly with hot metal surfaces. Due to the strong chemisorption interaction, in the target and ion source unit, the atoms undergo significant retention on their way from the target to the ion source. Due to this the short lived isotopes decays and are lost leading to low ion yields. A first approach to tackle these limitations consists of incorporating the carbon atoms into less reactive molecules and to use materials for the target housing and the transfer line ...

  3. National waste terminal storage program. Supplementary quality-assurance requirements

    International Nuclear Information System (INIS)

    Garland, D.L.

    1980-01-01

    The basic Quality Assurance Program Requirements standard for the National Waste Terminal Storage Program has been developed primarily for nuclear reactors and other fairly well established nuclear facilities. In the case of waste isolation, however, there are many ongoing investigations for which quality assurance practices and requirements have not been well defined. This paper points out these problems which require supplementary requirements. Briefly these are: (1) the language barrier, that is geologists and scientists are not familiar with quality assurance (QA) terminology; (2) earth sciences deal with materials that cannot be characterized as easily as metals or other materials that are reasonably homogeneous; (3) development and control of mathematical models and associated computer programs; (4) research and development

  4. Quality assurance

    OpenAIRE

    Cauchi, Maurice A.M.

    1993-01-01

    The concept of quality assurance refers more specifically to the process of objectifying and clearly enunciating goals, and providing means of assessing the outcomes. In this article the author mentions four fundamental elements of quality assurance which should be applied in the medical profession in Malta. These elements should relate to professional performance, resource utilisation, risk management and patient satisfaction. The aim of the medical professionals in Malta is to provide the b...

  5. Summary of 1988 WIPP [Waste Isolation Pilot Plant] Facility horizon gas flow measurements

    International Nuclear Information System (INIS)

    Stormont, J.C.

    1990-11-01

    Numerous gas flow measurements have been made at the Waste Isolation Pilot Plant (WIPP) Facility horizon during 1988. All tests have been pressure decay or constant pressure tests from single boreholes drilled from the underground excavations. The test fluid has been nitrogen. The data have been interpreted as permeabilities and porosities by means of a transient numerical solution method. A closed-form steady-state approximation provides a reasonable order-of-magnitude permeability estimate. The effective resolution of the measurement system is less than 10 -20 m 2 . Results indicate that beyond 1 to 5 m from an excavation, the gas flow is very small and the corresponding permeability is below the system resolution. Within the first meter of an excavation, the interpreted permeabilities can be 5 orders of magnitude greater than the undisturbed or far-field permeability. The interpreted permeabilities in the region between the undisturbed region and the first meter from an excavation are in the range of 10 -16 to 10 -20 m 2 . Measurable gas flow occurs to a greater depth into the roof above WIPP excavations of different sizes and ages than into the ribs and floor. The gas flows into the formation surrounding the smallest excavation tested are consistently lower than those at similar locations surrounding larger excavations of comparable age. Gas flow measured in the interbed layers near the WIPP excavations is highly variable. Generally, immediately above and below excavations, relatively large gas flow is measured in the interbed layers. These results are consistent with previous measurements and indicate a limited disturbed zone surrounding WIPP excavations. 31 refs., 99 figs., 5 tabs

  6. 40 CFR 160.35 - Quality assurance unit.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Quality assurance unit. 160.35 Section... LABORATORY PRACTICE STANDARDS Organization and Personnel § 160.35 Quality assurance unit. (a) A testing facility shall have a quality assurance unit which shall be responsible for monitoring each study to assure...

  7. Mobile genetic elements of Pseudomonas aeruginosa isolates from hydrotherapy facility and respiratory infections.

    Science.gov (United States)

    Pereira, S G; Cardoso, O

    2014-03-01

    The content of mobile genetic elements in Pseudomonas aeruginosa isolates of a pristine natural mineral water system associated with healthcare was compared with clinical isolates from respiratory infections. One isolate, from the therapy pool circuit, presented a class 1 integron, with 100% similarity to a class 1 integron contained in plasmid p4800 of the Klebsiella pneumoniae Kp4800 strain, which is the first time it has been reported in P. aeruginosa. Class 1 integrons were found in 25.6% of the clinical isolates. PAGI1 orf3 was more prevalent in environmental isolates, while PAGI2 c105 and PAGI3 sg100 were more prevalent in clinical isolates. Plasmids were not observed in either population. © 2013 The Authors Clinical Microbiology and Infection © 2013 European Society of Clinical Microbiology and Infectious Diseases.

  8. Quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, B.M.; Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the quality assurance and quality control practices of Hanford Site environmental monitoring and surveillance programs. Samples are analyzed according to documented standard analytical procedures. This section discusses specific measures taken to ensure quality in project management, sample collection, and analytical results.

  9. Quality assurance

    International Nuclear Information System (INIS)

    Gillespie, B.M.; Gleckler, B.P.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report summarizes the quality assurance and quality control practices of Hanford Site environmental monitoring and surveillance programs. Samples are analyzed according to documented standard analytical procedures. This section discusses specific measures taken to ensure quality in project management, sample collection, and analytical results

  10. Experimental infection of one-day-old chicks with Salmonella Serotypes Previously isolated from poultry facilities, wild birds, and swine

    Directory of Open Access Journals (Sweden)

    E de Sousa

    2013-12-01

    Full Text Available In order to maintain the high production and export rates achieved by the Brazilian poultry industry, it is necessary to prevent and control certain disease agents, such as Salmonella spp. Using bacterial cultures, the aim of the present study was to investigate the prevalence of Salmonella spp. in specimens collected from broiler facilities. Local wild birds were also sampled, as well as the feces of swine housed on the poultry farm. After sample collection, the isolated serotypes were subsequently inoculated into broiler chicks to determine their effects. Positive samples were collected from the following locations in the poultry facilities: poultry litter (S. serotype 4,5,12:R:-; S. Heidelberg; S. Infantis, broiler feces (S. Heidelberg; S. serotype 6,7:R:-; S. serotype 4,5,12:R:-; S. Tennessee, water (S. Glostrup; S. serotype 6,8:d:-;, and lesser mealworms (Alphitobius diaperinus found in the litter (S. Tennessee. Among the 36 wild birds captured, S. Heidelberg was isolated from one bird's organs and intestinal contents (Colaptes campestris, and S. Enteritidis was isolated from another bird's intestinal contents (Zenaida auriculata. Salmonella Panama and Salmonella Typhimurium were isolated from swine feces. One-day-old chicks (150 were divided into 10 groups of 15 animals each. Each group was orally inoculated with a previously isolated serotype of Salmonella. Soft stools were observed on the cage floor and around the birds' cloaca between 3 and 12 days post-infection (dpi. The different serotypes of Salmonella used to inoculate the chicks were re-isolated from the spleen, liver, and cecal content samples of the infected birds on 15 and 21 dpi.

  11. [Integrated quality assurance].

    Science.gov (United States)

    Bögel, K; Stöhr, K

    1994-07-01

    The definition of terms and connotation of "Quality", "Quality Assurance" and "Integration" lead to an analysis and understanding of inhibiting and fostering factors of the "Health Triad" of people, animals and environment. Although "Quality" is largely or ultimately determined by the consumer, there are considerable differences as this term is applied by (a) the individual consumer, (b) the dynamic producer defending or gaining markets, (c) those engaged in traditional product manufacturing, or (d) governments setting (minimum) requirements for the sake of free trade. "Quality Assurance" offers cooperation of partners all along the food chain from "pasture to table". The managerial process turned into a continuum of responsibility and agreement on processes and product characteristics. This overcomes the disadvantages of strategies stressing distinct defense barriers. In practice this philosophy of a predominant role of defence barriers proved largely partnership destructive, in that it permitted to shift responsibilities for failures and to claim administrative competence according to momentary situations and interests. "Integrated Quality Assurance" means mutual agreement of two or more partners along the food chain (e. g. feed producers, farmers, animal health industry, veterinarians and food processors) on product characteristics and production methods. It involves essential system elements including facilities, materials, manpower, information, transport, management etc. Different principles and procedures of quality assurance have been introduced in practice, including agriculture and food processing. These different approaches are not mutually exclusive but largely of complementary nature.(ABSTRACT TRUNCATED AT 250 WORDS)

  12. Vibration isolation in a free-piston driven expansion tube facility

    Science.gov (United States)

    Gildfind, D. E.; Jacobs, P. A.; Morgan, R. G.

    2013-09-01

    The stress waves produced by rapid piston deceleration are a fundamental feature of free-piston driven expansion tubes, and wave propagation has to be considered in the design process. For lower enthalpy test conditions, these waves can traverse the tube ahead of critical flow processes, severely interfering with static pressure measurements of the passing flow. This paper details a new device which decouples the driven tube from the free-piston driver, and thus prevents transmission of stress waves. Following successful incorporation of the concept in the smaller X2 facility, it has now been applied to the larger X3 facility, and results for both facilities are presented.

  13. Nuclear fuel quality assurance

    International Nuclear Information System (INIS)

    1976-01-01

    Full text: Quality assurance is used extensively in the design, construction and operation of nuclear power plants. This methodology is applied to all activities affecting the quality of a nuclear power plant in order to obtain confidence that an item or a facility will perform satisfactorily in service. Although the achievement of quality is the responsibility of all parties participating in a nuclear power project, establishment and implementation of the quality assurance programme for the whole plant is a main responsibility of the plant owner. For the plant owner, the main concern is to achieve control over the quality of purchased products or services through contractual arrangements with the vendors. In the case of purchase of nuclear fuel, the application of quality assurance might be faced with several difficulties because of the lack of standardization in nuclear fuel and the proprietary information of the fuel manufacturers on fuel design specifications and fuel manufacturing procedures. The problems of quality assurance for purchase of nuclear fuel were discussed in detail during the seminar. Due to the lack of generally acceptable standards, the successful application of the quality assurance concept to the procurement of fuel depends on how much information can be provided by the fuel manufacturer to the utility which is purchasing fuel, and in what form and how early this information can be provided. The extent of information transfer is basically set out in the individual vendor-utility contracts, with some indirect influence from the requirements of regulatory bodies. Any conflict that exists appears to come from utilities which desire more extensive control over the product they are buying. There is a reluctance on the part of vendors to permit close insight of the purchasers into their design and manufacturing procedures, but there nevertheless seems to be an increasing trend towards release of more information to the purchasers. It appears that

  14. The Assured Storage Integrated Management System: What is it and what will it cost?

    International Nuclear Information System (INIS)

    Kerr, T.A.; Newberry, W.F.

    1996-01-01

    The Assured Storage Integrated Management System for low-level radioactive waste as an alternative to traditional disposal is attracting favorable attention from many states, regulators, processors, and low-level radioactive waste generators. open-quotes Assured storageclose quotes is defined as a management system for safely isolating waste, while preserving options for its long-term management, through: robust, accessible facilities; planned preventive maintenance; and sureties adequate to address contingencies or implement future alternatives. Following introduction of the concept in RADWASTE Magazine, the Connecticut Hazardous Waste Management Service (among several others) requested a briefing on the idea. The Connecticut Hazardous Waste Management Service then requested that the National Low-Level Waste Management Program at the Idaho National Engineering Laboratory evaluate the life cycle costs of the Assured Storage Integrated Management System versus traditional disposal. Building on some of that work, this paper discusses the concept of an Assured Storage Integrated Management System for low-level radioactive waste as well as examines cost elements of the Assured Storage Integrated Management System in comparison to traditional disposal facilities. Further analyses conducted for the Connecticut study will more clearly define and quantify potential differences in life-cycle costs between the Assured Storage Integrated Management System and traditional disposal

  15. Mineralogy in the Waste Isolation Pilot Plant (WIPP) facility stratigraphic horizon

    International Nuclear Information System (INIS)

    Stein, C.L.

    1985-09-01

    Forty-six samples were selected for this study from two cores, one extending 50 ft up through the roof of the WIPP facility and the other penetrating 50 ft below the facility floor. These samples, selected from approximately every other foot of core length, represent the major lithologies present in the immediate vicinity of the WIPP facility horizon: ''clean'' halite, polyhalitic halite, argillaceous halite, and mixed polyhalitic-argillaceous halite. Samples were analyzed for non-NaCl mineralogy by determining weight percents of water- and EDTA-insoluble residues, which were then identified by x-ray diffraction. In general, WIPP halite contains at most 5 wt % non-NaCl residue. The major mineral constituents are quartz, magnesite, anhydrite, gypsum, polyhalite, and clays. Results of this study confirm that, in previous descriptions of WIPP core, trace mineral quantities have been visually overestimated by approximately an order of magnitude. 9 refs., 5 figs., 5 tabs

  16. Quality assurance

    International Nuclear Information System (INIS)

    Hiller, G.H.

    1979-01-01

    This compendium intends to give fast bibliographic information and to fill the visible gap between documentation and general bibliographic information. The reader is given an outline of quality assurance and some examples of techniques from the relevant literature. The practical engineer, who is always short of time, is thus offered a quick survey and a fast deepening of his understanding by means of literature dealing specifically with his unresolved problems. The mansucript has been kept in tis original form in order to speed up tis publication. The RKW technical department limited itself to checking its contents and the adherence to the established information goals. (orig.) 891 RW/orig. 892 MB [de

  17. Quality assurance techniques for activation analysis

    International Nuclear Information System (INIS)

    Becker, D.A.

    1984-01-01

    The principles and techniques of quality assurance are applied to the measurement method of activation analysis. Quality assurance is defined to include quality control and quality assessment. Plans for quality assurance include consideration of: personnel; facilities; analytical design; sampling and sample preparation; the measurement process; standards; and documentation. Activation analysis concerns include: irradiation; chemical separation; counting/detection; data collection, and analysis; and calibration. Types of standards discussed include calibration materials and quality assessment materials

  18. Quality assurance program plan for Building 324

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides an overview of the quality assurance program for Building 324. This plan supersedes the PNNL Nuclear Facilities Quality Management System Description, PNL-NF-QMSD, Revision 2, dated March 1996. The program applies to the facility safety structures, systems, and components and to activities that could affect safety structures, systems, and components. Adherence to the quality assurance program ensures the following: US Department of Energy missions and objectives are effectively accomplished; Products and services are safe, reliable, and meet or exceed the requirements and expectations of the user; Hazards to the public, to Hanford Site and facility workers, and to the environment are minimized. The format of this Quality Assurance Program Plan is structured to parallel that of 10 CFR 83 0.120, Quality Assurance Requirements

  19. Site selection report basalt waste isolation program near-surface test facility

    International Nuclear Information System (INIS)

    Sharpe, S.D.

    1978-01-01

    A site selection committee was established to review the information gathered on potential sites and to select a site for the Near-Surface Test Facility Phase I. A decision was made to use a site on the north face of Gable Mountain located on the Hanford Site. This site provided convenient access to the Pomona Basalt Flow. This flow was selected for use at this site because it exhibited the characteristics established in the primary criteria. These criteria were: the flows thickness; its dryness; its nearness to the surface; and, its similarities to basalt units which are candidates for the repository. After the selection of the Near-Surface Test Facility Phase I Site, the need arose for an additional facility to demonstrate safe handling, storage techniques, and the physical effects of radioactive materials on an in situ basalt formation. The committee reviewed the sites selected for Phase I and chose the same site for locating Phase II of the Near-Surface Test Facility

  20. Quality assurance manual: Volume 2, Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Oijala, J.E.

    1988-06-01

    This paper contains quality assurance information on departments of the Stanford Linear Accelerator Center. Particular quality assurance policies and standards discussed are on: Mechanical Systems; Klystron and Microwave Department; Electronics Department; Plant Engineering; Accelerator Department; Purchasing; and Experimental Facilities Department. (LSP)

  1. Quality assurance manual: Volume 1

    International Nuclear Information System (INIS)

    Oijala, J.E.

    1988-06-01

    Stanford Linear Accelerator Center (SLAC) is a DOE-supported research facility that carries out experimental and theoretical research in high energy physics and developmental work in new techniques for particle acceleration and experimental instrumentation. The purpose of this manual is to describe SLAC quality assurance policies and practices in various parts of the Laboratory

  2. MCNP study for epithermal neutron irradiation of an isolated liver at the Finnish BNCT facility.

    Science.gov (United States)

    Kotiluoto, P; Auterinen, I

    2004-11-01

    A successful boron neutron capture treatment (BNCT) of a patient with multiple liver metastases has been first given in Italy, by placing the removed organ into the thermal neutron column of the Triga research reactor of the University of Pavia. In Finland, FiR 1 Triga reactor with an epithermal neutron beam well suited for BNCT has been extensively used to irradiate patients with brain tumors such as glioblastoma and recently also head and neck tumors. In this work we have studied by MCNP Monte Carlo simulations, whether it would be beneficial to treat an isolated liver with epithermal neutrons instead of thermal ones. The results show, that the epithermal field penetrates deeper into the liver and creates a build-up distribution of the boron dose. Our results strongly encourage further studying of irradiation arrangement of an isolated liver with epithermal neutron fields.

  3. Comparison of quality assurance for performance and safety characteristics of the facility for Boron Neutron Capture therapy in Petten/NL with medical electron accelerators

    International Nuclear Information System (INIS)

    Rassow, Juergen; Stecher-Rasmussen, Finn; Voorbraak, Wim; Moss, Ray; Vroegindeweij, Corine; Hideghety, Katalin; Sauerwein, Wolfgang

    2001-01-01

    Background and purpose: The European Council Directive on health protection 97/43/EURATOM requires radiotherapy quality assurance programmes for performance and safety characteristics including acceptance and repeated tests. For Boron Neutron Capture therapy (BNCT) at the High Flux Reactor (HFR) in Petten/NL such a programme has been developed on the basis of IEC publications for medical electron accelerators. Results: The fundamental differences of clinical dosimetry for medical electron accelerators and BNCT are presented and the order of magnitude of dose components and their stability and that of the main other influencing parameter 10 B concentration for BNCT patient treatments. A comparison is given for requirements for accelerators and BNCT units indicating items which are not transferable, equal or additional. Preliminary results of in vivo measurements done with a set of 55 Mn, 63 Cu and 197 Au activation foils for all single fields for the four fractions at all 15 treated patients show with <±4% up to now a worse reproducibility than the used dose monitoring systems (±1.5%) caused by influence of hair position on the foil-skull distance. Conclusions: Despite the more complex clinical dosimetry (because of four relevant dose components, partly of different linear energy transfer (LET)) BNCT can be regulated following the principles of quality assurance procedures for therapy with medical electron accelerators. The reproducibility of applied neutron fluence (proportional to absorbed doses) and the main safety aspects are equal for all teletherapy methods including BNCT

  4. Optimizing charge breeding techniques for ISOL facilities in Europe: Conclusions from the EMILIE project

    Energy Technology Data Exchange (ETDEWEB)

    Delahaye, P., E-mail: delahaye@ganil.fr; Jardin, P.; Maunoury, L. [GANIL, CEA/DSM-CNRS/IN2P3, Blvd. Becquerel, BP 55027, 14076 Caen Cedex 05 (France); Galatà, A.; Patti, G. [INFN–Laboratori Nazionali di Legnaro, Viale dell’Università 2, 35020 Legnaro (Padova) (Italy); Angot, J.; Lamy, T.; Thuillier, T. [LPSC–Université Grenoble Alpes–CNRS/IN2P3, 53 rue des Martyrs, 38026 Grenoble Cedex (France); Cam, J. F.; Traykov, E.; Ban, G. [LPC Caen, 6 Blvd. Maréchal Juin, 14050 Caen Cedex (France); Celona, L. [INFN–Laboratori Nazionali del Sud, via S. Sofia 62, 95125 Catania (Italy); Choinski, J.; Gmaj, P. [Heavy Ion Laboratory, University of Warsaw, ul. Pasteura 5a, 02 093 Warsaw (Poland); Koivisto, H.; Kolhinen, V.; Tarvainen, O. [Department of Physics, University of Jyväskylä, PB 35 (YFL), 40351 Jyväskylä (Finland); Vondrasek, R. [Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, Illinois 60439 (United States); Wenander, F. [ISOLDE, CERN, 1211 Geneva 23 (Switzerland)

    2016-02-15

    The present paper summarizes the results obtained from the past few years in the framework of the Enhanced Multi-Ionization of short-Lived Isotopes for Eurisol (EMILIE) project. The EMILIE project aims at improving the charge breeding techniques with both Electron Cyclotron Resonance Ion Sources (ECRIS) and Electron Beam Ion Sources (EBISs) for European Radioactive Ion Beam (RIB) facilities. Within EMILIE, an original technique for debunching the beam from EBIS charge breeders is being developed, for making an optimal use of the capabilities of CW post-accelerators of the future facilities. Such a debunching technique should eventually resolve duty cycle and time structure issues which presently complicate the data-acquisition of experiments. The results of the first tests of this technique are reported here. In comparison with charge breeding with an EBIS, the ECRIS technique had lower performance in efficiency and attainable charge state for metallic ion beams and also suffered from issues related to beam contamination. In recent years, improvements have been made which significantly reduce the differences between the two techniques, making ECRIS charge breeding more attractive especially for CW machines producing intense beams. Upgraded versions of the Phoenix charge breeder, originally developed by LPSC, will be used at SPES and GANIL/SPIRAL. These two charge breeders have benefited from studies undertaken within EMILIE, which are also briefly summarized here.

  5. Quality assurance and demolition: 2006 symposium

    International Nuclear Information System (INIS)

    Thierfeldt, S.

    2006-01-01

    The '2006 Symposium: Quality Assurance and Demolition' jointly organized by compra GmbH and Brenk Systemplanung GmbH this year again focused on quality assurance and the demolition of nuclear facilities as its main topics. The papers presented ranged from issues of clearance and disposal to demolition technologies and status reports about specific demolition projects. The sixteen presentations at the '2006 Symposium: Quality Assurance and Demolition' offered an interesting and very topical cross section of decommissioning and demolition of nuclear facilities in Germany. In 2007, the conference about similar main topics will again be held at the Schloss Bensberg Grand Hotel. (orig.)

  6. Computational design of high efficiency release targets for use at ISOL facilities

    CERN Document Server

    Liu, Y

    1999-01-01

    This report describes efforts made at the Oak Ridge National Laboratory to design high-efficiency-release targets that simultaneously incorporate the short diffusion lengths, high permeabilities, controllable temperatures, and heat-removal properties required for the generation of useful radioactive ion beam (RIB) intensities for nuclear physics and astrophysics research using the isotope separation on-line (ISOL) technique. Short diffusion lengths are achieved either by using thin fibrous target materials or by coating thin layers of selected target material onto low-density carbon fibers such as reticulated-vitreous-carbon fiber (RVCF) or carbon-bonded-carbon fiber (CBCF) to form highly permeable composite target matrices. Computational studies that simulate the generation and removal of primary beam deposited heat from target materials have been conducted to optimize the design of target/heat-sink systems for generating RIBs. The results derived from diffusion release-rate simulation studies for selected t...

  7. A facile approach for screening isolated nanomagnetic behavior for bit-patterned media

    International Nuclear Information System (INIS)

    Thiyagarajah, Naganivetha; Ng, Vivian; Asbahi, Mohamed; Yakovlev, Nikolai L; Yang, Joel K W; Wong, Rick T J; Low, Kendrick W M

    2014-01-01

    Bit-patterned media (BPM) fabricated by the direct deposition of magnetic material onto prepatterned arrays of nanopillars is a promising approach for increasing magnetic recording of areal density. One of the key challenges of this approach is to identify and control the magnetic interaction between the bits (on top of the nanopillars) and the trench material between the pillars. Using independent techniques, including magnetic force microscopy, the variable-angle magneto-optic Kerr effect, and remanence curves, we were able to determine the presence and relative intensities of exchange and dipolar interactions in Co-Pd multilayer-based BPM fabricated by direct deposition. We found that for pitches of 30 nm or less, there were negligible exchange interactions, and the bits were found to be magnetically isolated. As we move to higher densities, the absence of exchange interactions indicates that direct deposition is a promising approach to BPM fabrication. (papers)

  8. 10 CFR 61.63 - Financial assurances for institutional controls.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Financial assurances for institutional controls. 61.63... RADIOACTIVE WASTE Financial Assurances § 61.63 Financial assurances for institutional controls. (a) Prior to... the Commission to ensure that changes in inflation, technology and disposal facility operations are...

  9. 21 CFR 58.35 - Quality assurance unit.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 1 2010-04-01 2010-04-01 false Quality assurance unit. 58.35 Section 58.35 Food... LABORATORY PRACTICE FOR NONCLINICAL LABORATORY STUDIES Organization and Personnel § 58.35 Quality assurance unit. (a) A testing facility shall have a quality assurance unit which shall be responsible for...

  10. Quality assurance in Hanford site defense waste operations

    International Nuclear Information System (INIS)

    Wojtasek, R.D.

    1989-01-01

    This paper discusses quality assurance as an integral part of conducting waste management operations. The storage, treatment, and disposal of radioactive and non- radioactive hazardous wastes at Hanford are described. The author reports that quality assurance programs provide confidence that storage, treatment, and disposal facilities and systems perform as intended. Examples of how quality assurance is applied to Hanford defense waste operations are presented

  11. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's plan to decommission and reclaim exploratory shafts and related facilities

    International Nuclear Information System (INIS)

    Fenster, D.F.; Schubert, J.P.; Zellmer, S.D.; Harrison, W.; Simpson, D.G.; Busch, J.S.

    1984-07-01

    The following recommendations are made for improving the Office of Nuclear Waste Isolation's plan for decommissioning and reclaiming exploratory shafts and other facilities associated with site characterization: (1) Discuss more comprehensively the technical aspects of activities related to decommissioning and reclamation. More detailed information will help convince the staff of the US Nuclear Regulatory Commission and others that the activities as outlined in the plan are properly structured and that the stated goals can be achieved. (2) Address in considerably greater detail how the proposed activities will satisfy specific federal, state, and local laws and regulations. (3) State clearly the precise purpose of the plan, preferably at the beginning and under an appropriate heading. (4) Also under an appropriate heading and immediately after the section on purpose, describe the scope of the plan. The tasks covered by this plan and closely related tasks covered by other appropriate plans should be clearly differentiated. (5) Discuss the possible environmental effects of drilling the exploratory shaft, excavating drifts in salt, and drilling boreholes as part of site characterization. Mitigation activities should be designed to counter specific potential impacts. High priority should be given to minimizing groundwater contamination and restoring the surface to a condition consistent with the proposed land use following completion of characterization activities at sites not chosen for repository construction. (6) Define ambiguous technical terms, either in the text when first introduced or in an appended glossary

  12. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    Energy Technology Data Exchange (ETDEWEB)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI.

  13. Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

    International Nuclear Information System (INIS)

    Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

    1992-12-01

    This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S ampersand A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S ampersand A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI

  14. Set up and programming of an ALICE Time-Of-Flight trigger facility and software implementation for its Quality Assurance (QA) during LHC Run 2

    CERN Document Server

    Toschi, Francesco

    2016-01-01

    The Cosmic and Topology Trigger Module (CTTM) is the main component of a trigger based on the ALICE TOF detector. Taking advantage of the TOF fast response, this VME board implements the trigger logic and delivers several L0 trigger outputs, used since Run 1, to provide cosmic triggers and rare triggers in pp, p+Pb and Pb+Pb data taking. Due to TOF DCS architectural change of the PCs controlling the CTTM (from 32 bits to 64 bits) it is mandatory to upgrade the software related to the CTTM including the code programming the FPGA firmware. A dedicated CTTM board will be installed in a CERN lab (Meyrin site), with the aim of recreating the electronics chain of the TOF trigger, to get a comfortable porting of the code to the 64 bit environment. The project proposed to the summer student is the setting up of the CTTM and the porting of the software. Moreover, in order to monitor the CTTM Trigger board during the real data taking, the implementation of a new Quality Assurance (QA) code is also crucial, together wit...

  15. Grenada; Second Review Under the Extended Credit Facility, Request For a Waiver of a Performance Criterion, Request for Modification of Performance Criteria and Financing Assurances Review

    OpenAIRE

    International Monetary Fund

    2015-01-01

    EXECUTIVE SUMMARY Extended Credit Facility (ECF) Arrangement. The program was approved on June 26, 2014 and the first review completed on December 12, 2014. Grenada has received SDR 4.04 million (about US$5.9 million) so far under the arrangement and the equivalent of SDR 2 million (about US$3 million) will be made available upon Executive Board completion of the second review. Debt restructuring. Grenada has achieved a critical milestone in its debt restructuring, reaching agreement on key r...

  16. Quality Assurance - Construction

    DEFF Research Database (Denmark)

    Gaarslev, Axel

    1996-01-01

    Gives contains three main chapters:1. Quality Assurance initiated by external demands2. Quality Assurance initiated by internal company goals3. Innovation strategies......Gives contains three main chapters:1. Quality Assurance initiated by external demands2. Quality Assurance initiated by internal company goals3. Innovation strategies...

  17. S. 705: A Bill to assure fair consideration of the interests of states likely to be affected by the establishment of low-level radioactive waste disposal facilities. Introduced in the Senate of the United States, One Hundredth First Congress, First Session, April 5, 1989

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    S. 705 is a bill to assure fair consideration of the interests of states likely to be affected by the establishment of low-level radioactive waste disposal facilities. Notification of adjacent states is proposed when waste disposal operations are contemplated at border sites

  18. 40 CFR 300.510 - State assurances.

    Science.gov (United States)

    2010-07-01

    ... assure the availability of hazardous waste treatment or disposal facilities which: (i) Have adequate... subdivision thereof at the time of disposal of hazardous substances therein and a remedial action is... was publicly operated at the time of the disposal of hazardous substances. For other facilities...

  19. Introduction to quality assurance

    International Nuclear Information System (INIS)

    Kaden, W.

    1980-01-01

    In today's interpretation 'quality assurance' means 'good management'. Quality assurance has to cover all phases of a work, but all quality assurance measures must be adapted to the relevance and complexity of the actual task. Examples are given for the preparation of quality classes, the organization of quality assurance during design and manufacturing and for auditing. Finally, efficiency and limits of quality assurance systems are described. (orig.)

  20. FESA Quality Assurance

    CERN Multimedia

    CERN. Geneva

    2015-01-01

    FESA is a framework used by 100+ developers at CERN to design and implement the real-time software used to control the accelerators. Each new version must be tested and qualified to ensure that no backward compatibility issues have been introduced and that there is no major bug which might prevent accelerator operations. Our quality assurance approach is based on code review and a two-level testing process. The first level is made of unit-test (Python unittest & Google tests for C++). The second level consists of integration tests running on an isolated test environment. We also use a continuous integration service (Bamboo) to ensure the tests are executed periodically and the bugs caught early. In the presentation, we will explain the reasons why we took this approach, the results and some thoughts on the pros and cons.

  1. DOE'S remedial action assurance program

    International Nuclear Information System (INIS)

    Welty, C.G. Jr.; Needels, T.S.; Denham, D.H.

    1984-10-01

    The formulation and initial implementation of DOE's Assurance Program for Remedial Action are described. It was initiated in FY 84 and is expected to be further implemented in FY 85 as the activities of DOE's Remedial Action programs continue to expand. Further APRA implementation will include additional document reviews, site inspections, and program office appraisals with emphasis on Uranium Mill Tailings Remedial Action Program and Surplus Facilities Management Program

  2. Backfill barriers: the use of engineered barriers based on geologic materials to assure isolation of radioactive wastes in a repository. [Nickel-iron alloys

    Energy Technology Data Exchange (ETDEWEB)

    Apps, J.A.; Cook, N.G.W.

    1981-06-01

    A preliminary assessment is made to show that canisters fabricated of nickel-iron alloys, and surrounded by a suitable backfill, may produce an engineered barrier where the canister material is thermodynamically stable with respect to its environment. As similar conditions exist in nature, the performance of such systems as barriers to isolate radionuclides can be predicted over very long periods, of the order of 10/sup 6/ years.

  3. Bacillus nealsonii sp. nov., isolated from a spacecraft-assembly facility, whose spores are gamma-radiation resistant

    Science.gov (United States)

    Venkateswaran, Kasthuri; Kempf, Michael; Chen, Fei; Satomi, Masataka; Nicholson, Wayne; Kern, Roger

    2003-01-01

    One of the spore-formers isolated from a spacecraft-assembly facility, belonging to the genus Bacillus, is described on the basis of phenotypic characterization, 16S rDNA sequence analysis and DNA-DNA hybridization studies. It is a Gram-positive, facultatively anaerobic, rod-shaped eubacterium that produces endospores. The spores of this novel bacterial species exhibited resistance to UV, gamma-radiation, H2O2 and desiccation. The 18S rDNA sequence analysis revealed a clear affiliation between this strain and members of the low G+C Firmicutes. High 16S rDNA sequence similarity values were found with members of the genus Bacillus and this was supported by fatty acid profiles. The 16S rDNA sequence similarity between strain FO-92T and Bacillus benzoevorans DSM 5391T was very high. However, molecular characterizations employing small-subunit 16S rDNA sequences were at the limits of resolution for the differentiation of species in this genus, but DNA-DNA hybridization data support the proposal of FO-92T as Bacillus nealsonii sp. nov. (type strain is FO-92T =ATCC BAAM-519T =DSM 15077T).

  4. Waste Management Quality Assurance Plan

    International Nuclear Information System (INIS)

    2006-01-01

    The WMG QAP is an integral part of a management system designed to ensure that WMG activities are planned, performed, documented, and verified in a manner that assures a quality product. A quality product is one that meets all waste acceptance criteria, conforms to all permit and regulatory requirements, and is accepted at the offsite treatment, storage, and disposal facility. In addition to internal processes, this QA Plan identifies WMG processes providing oversight and assurance to line management that waste is managed according to all federal, state, and local requirements for waste generator areas. A variety of quality assurance activities are integral to managing waste. These QA functions have been identified in the relevant procedures and in subsequent sections of this plan. The WMG QAP defines the requirements of the WMG quality assurance program. These requirements are derived from Department of Energy (DOE) Order 414.1C, Quality Assurance, Contractor Requirements Document, the LBNL Operating and Assurance Program Plan (OAP), and other applicable environmental compliance documents. The QAP and all associated WMG policies and procedures are periodically reviewed and revised, as necessary, to implement corrective actions, and to reflect changes that have occurred in regulations, requirements, or practices as a result of feedback on work performed or lessons learned from other organizations. The provisions of this QAP and its implementing documents apply to quality-affecting activities performed by the WMG; WMG personnel, contractors, and vendors; and personnel from other associated LBNL organizations, except where such contractors, vendors, or organizations are governed by their own WMG-approved QA programs

  5. Tritium systems test assembly quality assurance program

    International Nuclear Information System (INIS)

    Kerstiens, F.L.; Wilhelm, R.C.

    1986-07-01

    A quality assurance program should establish the planned and systematic actions necessary to provide adequate confidence that fusion facilities and their subsystems will perform satisfactorily in service. The Tritium Systems Test Assembly (TSTA) Quality Assurance Program has been designed to assure that the designs, tests, data, and interpretive reports developed at TSTA are valid, accurate, and consistent with formally specified procedures and reviews. The quality consideration in all TSTA activities is directed toward the early detection of quality problems, coupled with timely and positive disposition and corrective action

  6. Quality assurance program plan for low-level waste at the WSCF Laboratory

    International Nuclear Information System (INIS)

    Morrison, J.A.

    1994-01-01

    The purpose of this document is to provide guidance for the implementation of the Quality Assurance Program Plan (QAPP) for the management of low-level waste at the Waste Sampling and Characterization Facility (WSCF) Laboratory Complex as required by WHC-CM-4-2, Quality Assurance Manual, which is based on Quality Assurance Program Requirements for Nuclear Facilities, NQA-1 (ASME)

  7. Creation and Plan of an Underground Geologic Radioactive Waste Isolation Facility at the Nizhnekansky Rock Massif in Russia

    International Nuclear Information System (INIS)

    Gupalo, T A; Kudinov, K G; Jardine, L J; Williams, J

    2004-01-01

    This joint geologic repository project in Russia was initiated in May 2002 between the United States (U.S.) International Science and Technology Center (ISTC) and the Federal State Unitary Enterprise ''All-Russian Research and Design Institute of Production Engineering'' (VNIPIPT). The project (ISTC Partner Project 2377) is funded by the U.S. Department of Energy Office of Civilian Radioactive Waste Management (DOE-RW) for a period of 2-1/2 years. ISTC project activities were integrated into other ongoing geologic repository site characterization activities near the Mining and Chemical Combine (MCC K-26) site. This allowed the more rapid development of a plan for an underground research laboratory, including underground design and layouts. It will not be possible to make a final choice between the extensively studied Verkhne-Itatski site or the Yeniseiski site for construction of the underground laboratory during the project time frame because additional data are needed. Several new sources of data will become available in the next few years to help select a final site. Studies will be conducted at the 1-km deep borehole at the Yeniseisky site where drilling started in 2004. And in 2007, after the scheduled shutdown of the last operating reactor at the MCC K-26 site, data will be collected from the rock massif as the gneiss rock cools, and the cool-down responses modeled. After the underground laboratory is constructed, the data collected and analyzed, this will provide the definitive evidence regarding the safety of the proposed geologic isolation facilities for radioactive wastes (RW). This data will be especially valuable because they will be collected at the same site where the wastes will be subsequently placed, rather than on hypothetical input data only. Including the operating costs for 10 to 15 years after construction, the cost estimate for the laboratory is $50M. With additional funding from non-ISTC sources, it will be possible to complete this

  8. NSR&D Program Fiscal Year (FY) 2015 Call for Proposals Mitigation of Seismic Risk at Nuclear Facilities using Seismic Isolation

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    Seismic isolation (SI) has the potential to drastically reduce seismic response of structures, systems, or components (SSCs) and therefore the risk associated with large seismic events (large seismic event could be defined as the design basis earthquake (DBE) and/or the beyond design basis earthquake (BDBE) depending on the site location). This would correspond to a potential increase in nuclear safety by minimizing the structural response and thus minimizing the risk of material release during large seismic events that have uncertainty associated with their magnitude and frequency. The national consensus standard America Society of Civil Engineers (ASCE) Standard 4, Seismic Analysis of Safety Related Nuclear Structures recently incorporated language and commentary for seismically isolating a large light water reactor or similar large nuclear structure. Some potential benefits of SI are: 1) substantially decoupling the SSC from the earthquake hazard thus decreasing risk of material release during large earthquakes, 2) cost savings for the facility and/or equipment, and 3) applicability to both nuclear (current and next generation) and high hazard non-nuclear facilities. Issue: To date no one has evaluated how the benefit of seismic risk reduction reduces cost to construct a nuclear facility. Objective: Use seismic probabilistic risk assessment (SPRA) to evaluate the reduction in seismic risk and estimate potential cost savings of seismic isolation of a generic nuclear facility. This project would leverage ongoing Idaho National Laboratory (INL) activities that are developing advanced (SPRA) methods using Nonlinear Soil-Structure Interaction (NLSSI) analysis. Technical Approach: The proposed study is intended to obtain an estimate on the reduction in seismic risk and construction cost that might be achieved by seismically isolating a nuclear facility. The nuclear facility is a representative pressurized water reactor building nuclear power plant (NPP) structure

  9. Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1

    International Nuclear Information System (INIS)

    1997-01-01

    This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste

  10. Computer software quality assurance

    International Nuclear Information System (INIS)

    Ives, K.A.

    1986-06-01

    The author defines some criteria for the evaluation of software quality assurance elements for applicability to the regulation of the nuclear industry. The author then analyses a number of software quality assurance (SQA) standards. The major extracted SQA elements are then discussed, and finally specific software quality assurance recommendations are made for the nuclear industry

  11. Data Quality Assurance Governance

    OpenAIRE

    Montserrat Gonzalez; Stephanie Suhr

    2016-01-01

    This deliverable describes the ELIXIR-EXCELERATE Quality Management Strategy, addressing EXCELERATE Ethics requirement no. 5 on Data Quality Assurance Governance. The strategy describes the essential procedures and practices within ELIXIR-EXCELERATE concerning planning of quality management, performing quality assurance and controlling quality. It also depicts the overall organisation of ELIXIR with emphasis on authority and specific responsibilities related to quality assurance.

  12. Multinational Quality Assurance

    Science.gov (United States)

    Kinser, Kevin

    2011-01-01

    Multinational colleges and universities pose numerous challenges to the traditional models of quality assurance that are designed to validate domestic higher education. When institutions cross international borders, at least two quality assurance protocols are involved. To guard against fraud and abuse, quality assurance in the host country is…

  13. Quality Assurance Requirements and Description

    International Nuclear Information System (INIS)

    Ram Murthy

    2002-01-01

    The Quality Assurance Requirements and Description (QARD) is the principal Quality Assurance (QA) document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the QA program [INTRODUCTION :1p2s (NOT A REQUIREMENT)]. The QARD contains regulatory requirements and program commitments necessary for the development of an effective QA program [INTRODUCTION :1p3s (NOT A REQUIREMENT)]. Implementing documents must be based on, and be consistent with the QARD. The QARD applies to the following: (1) Acceptance of spent nuclear fuel and high-level waste. (2) Transport of spent nuclear fuel and high-level waste. (3) Storage of spent nuclear fuel through receipt of storage cask certification or a facility operating license. (4) Monitored Geologic Repository, including the site characterization activities [Exploratory Studies Facility (ESF) and surface based testing], through receipt of an operating license. (5) High-level waste form development through qualification, production, and acceptance. (6) Characterization of DOE spent nuclear fuel, and conditioning through acceptance of DOE spent nuclear fuel. Section 2.0, Quality Assurance Program, defines in greater detail criteria for determining work subject to the QARD

  14. Effect of the Affordable Medicines Facility--malaria (AMFm) on the availability, price, and market share of quality-assured artemisinin-based combination therapies in seven countries: a before-and-after analysis of outlet survey data.

    Science.gov (United States)

    Tougher, Sarah; Ye, Yazoume; Amuasi, John H; Kourgueni, Idrissa A; Thomson, Rebecca; Goodman, Catherine; Mann, Andrea G; Ren, Ruilin; Willey, Barbara A; Adegoke, Catherine A; Amin, Abdinasir; Ansong, Daniel; Bruxvoort, Katia; Diallo, Diadier A; Diap, Graciela; Festo, Charles; Johanes, Boniface; Juma, Elizabeth; Kalolella, Admirabilis; Malam, Oumarou; Mberu, Blessing; Ndiaye, Salif; Nguah, Samuel B; Seydou, Moctar; Taylor, Mark; Rueda, Sergio Torres; Wamukoya, Marilyn; Arnold, Fred; Hanson, Kara

    2012-12-01

    Malaria is one of the greatest causes of mortality worldwide. Use of the most effective treatments for malaria remains inadequate for those in need, and there is concern over the emergence of resistance to these treatments. In 2010, the Global Fund launched the Affordable Medicines Facility--malaria (AMFm), a series of national-scale pilot programmes designed to increase the access and use of quality-assured artemisinin based combination therapies (QAACTs) and reduce that of artemisinin monotherapies for treatment of malaria. AMFm involves manufacturer price negotiations, subsidies on the manufacturer price of each treatment purchased, and supporting interventions such as communications campaigns. We present findings on the effect of AMFm on QAACT price, availability, and market share, 6-15 months after the delivery of subsidised ACTs in Ghana, Kenya, Madagascar, Niger, Nigeria, Uganda, and Tanzania (including Zanzibar). We did nationally representative baseline and endpoint surveys of public and private sector outlets that stock antimalarial treatments. QAACTs were identified on the basis of the Global Fund's quality assurance policy. Changes in availability, price, and market share were assessed against specified success benchmarks for 1 year of AMFm implementation. Key informant interviews and document reviews recorded contextual factors and the implementation process. In all pilots except Niger and Madagascar, there were large increases in QAACT availability (25·8-51·9 percentage points), and market share (15·9-40·3 percentage points), driven mainly by changes in the private for-profit sector. Large falls in median price for QAACTs per adult equivalent dose were seen in the private for-profit sector in six pilots, ranging from US$1·28 to $4·82. The market share of oral artemisinin monotherapies decreased in Nigeria and Zanzibar, the two pilots where it was more than 5% at baseline. Subsidies combined with supporting interventions can be effective in

  15. The application of quality assurance

    International Nuclear Information System (INIS)

    Lovatt, G.B.

    1988-01-01

    The paper concerns the application of quality assurance to structures, systems and components for the design, construction and operation of nuclear power plant and fuel reprocessing plant. A description is given of:- the requirements for quality assurance, the establishment of quality assurance arrangements, quality assurance documents structure, and quality assurance manuals and programmes. Quality assurance procedures and auditing are also discussed. (U.K.)

  16. Quality assurance of nuclear energy

    International Nuclear Information System (INIS)

    1994-12-01

    It consists of 14 chapters, which are outline of quality assurance of nuclear energy, standard of quality assurance, business quality assurance, design quality assurance, purchase quality assurance, production quality assurance, a test warranty operation warranty, maintenance warranty, manufacture of nuclear power fuel warranty, computer software warranty, research and development warranty and quality audit.

  17. High assurance SPIRAL

    Science.gov (United States)

    Franchetti, Franz; Sandryhaila, Aliaksei; Johnson, Jeremy R.

    2014-06-01

    In this paper we introduce High Assurance SPIRAL to solve the last mile problem for the synthesis of high assurance implementations of controllers for vehicular systems that are executed in today's and future embedded and high performance embedded system processors. High Assurance SPIRAL is a scalable methodology to translate a high level specification of a high assurance controller into a highly resource-efficient, platform-adapted, verified control software implementation for a given platform in a language like C or C++. High Assurance SPIRAL proves that the implementation is equivalent to the specification written in the control engineer's domain language. Our approach scales to problems involving floating-point calculations and provides highly optimized synthesized code. It is possible to estimate the available headroom to enable assurance/performance trade-offs under real-time constraints, and enables the synthesis of multiple implementation variants to make attacks harder. At the core of High Assurance SPIRAL is the Hybrid Control Operator Language (HCOL) that leverages advanced mathematical constructs expressing the controller specification to provide high quality translation capabilities. Combined with a verified/certified compiler, High Assurance SPIRAL provides a comprehensive complete solution to the efficient synthesis of verifiable high assurance controllers. We demonstrate High Assurance SPIRALs capability by co-synthesizing proofs and implementations for attack detection and sensor spoofing algorithms and deploy the code as ROS nodes on the Landshark unmanned ground vehicle and on a Synthetic Car in a real-time simulator.

  18. Quality assurance during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1994-01-01

    The general requirements applicable to the quality assurance of the Finnish nuclear power plants are presented in the Council of State Decision (395/91) and in the guide YVL 1.4. This guide specifies the quality assurance requirements to be applied during the operation of the nuclear power plants as well as of the other nuclear facilities. Quality assurance applies to all the activities and organizations with a bearing on the safe operation of the nuclear power plants. (5 refs.)

  19. Quality assurance system in nuclear engineering

    International Nuclear Information System (INIS)

    Adams, H.W.; Hoensch, V.

    1985-01-01

    Due to the close connection between the German Atomic Energy Law and the nuclear control regulations, quality systems in nuclear engineering have taken on a special form. Quality assurance systems as a stipulated organisation of structure and procedure to assure quality have implications for the organisation of the electric supply company at the planning, erection and commissioning stage and for the organisation of the nuclear power station facility. To supervise the application and effectiveness of the stipulated organisation of structure and procedure internally and externally among contractors, special organisation units have been set up at the plant suppliers, manufactures, electric supply companies and nuclear power station facilities, which in the electric supply field go by the name of Quality Assurance Supervision. (orig.) [de

  20. Hanford Tanks Initiative quality assurance implementation plan

    International Nuclear Information System (INIS)

    Huston, J.J.

    1998-01-01

    Hanford Tanks Initiative (HTI) Quality Assurance Implementation Plan for Nuclear Facilities defines the controls for the products and activities developed by HTI. Project Hanford Management Contract (PHMC) Quality Assurance Program Description (QAPD)(HNF-PRO599) is the document that defines the quality requirements for Nuclear Facilities. The QAPD provides direction for compliance to 10 CFR 830.120 Nuclear Safety Management, Quality Assurance Requirements. Hanford Tanks Initiative (HTI) is a five-year activity resulting from the technical and financial partnership of the US Department of Energy's Office of Waste Management (EM-30), and Office of Science and Technology Development (EM-50). HTI will develop and demonstrate technologies and processes for characterization and retrieval of single shell tank waste. Activities and products associated with HTI consist of engineering, construction, procurement, closure, retrieval, characterization, and safety and licensing

  1. The motivation-based calving facility: Social and cognitive factors influence isolation seeking behaviour of Holstein dairy cows at calving

    DEFF Research Database (Denmark)

    Rørvang, Maria Vilain; Herskin, Mette S.; Jensen, Margit Bak

    2018-01-01

    solution may be to allow the cow to seek isolation prior to calving. This study examined whether pre-parturient dairy cows will isolate in an individual calving pen placed in a group calving setting and whether a closing gate in this individual calving pen will cause more cows to isolate prior to calving....... Danish Holstein cows (n = 66) were housed in groups of six in a group pen with access to six individual calving pens connected to the group area. Cows were trained to use one of two isolation opportunities i.e. individual calving pens with functional closing gates (n = 35) allowing only one cow access...... at a time, or individual calving pens with permanently open gates allowing free cow traffic between group area and individual pen (n = 31). The response variables were calving site, calving behaviour and social behaviour. Unexpectedly, a functional gate did not facilitate isolation seeking, perhaps because...

  2. Transuranic Waste Characterization Quality Assurance Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-30

    This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.

  3. Transuranic Waste Characterization Quality Assurance Program Plan

    International Nuclear Information System (INIS)

    1995-01-01

    This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes

  4. ONWI [Office of Nuclear Waste Isolation] 30% design review findings report for Exploratory Shaft Facility, Deaf Smith site

    International Nuclear Information System (INIS)

    1987-01-01

    This document describes a review of the standards for the design of the high-level radioactive waste facility at the Deaf Smith, Texas site. It includes public comments and the official responses to the designs produced to date

  5. Facile synthesis of the cyclohexane fragment of enacloxins, a series of antibiotics isolated from Frateuria sp. W-315.

    Science.gov (United States)

    Saito, Aki; Igarashi, Wataru; Furukawa, Hiroyuki; Yamada, Teiko; Kuwahara, Shigefumi; Kiyota, Hiromasa

    2014-01-01

    An efficient and good yield synthesis of the cyclohexane moiety of enacyloxins, a series of antibiotics isolated from Frateuria sp. W-315, was achieved from d-quinic acid using a successive Barton-McCombie deoxygenation.

  6. Proposal and experimental validation of analytical models for seismic and vibration isolation devices in nuclear and non-nuclear facilities

    International Nuclear Information System (INIS)

    Serino, G.; Bonacina, G.; Bettinali, F.

    1993-01-01

    Two analytical-experimental models of HDLRBs having different levels of approximations are presented. Comparison with available experimental data shows that a non-linear hysteretic model, defined by three rubber parameters only, allows a very good complete simulation of the dynamic behavior of the isolation devices. A simpler equivalent linear viscous model reproduces less exactly the experimental behavior, but permits a good prediction of peak response values in the earthquake analysis of an isolated structure, if bearing stiffness and damping parameters are properly selected. The models have been used in preliminary design and subsequent check of the isolation system of two different types of Gas-Insulated Electric Substations (GIS), in view of possible future installation of isolated GISes in areas of high seismic risk. (author)

  7. Quality assurance in radiodiagnosis

    International Nuclear Information System (INIS)

    Ghilardi Netto, T.; Sao Paulo Univ., Ribeirao Preto

    1983-01-01

    The following topics are dealt with: 1) the importance of the application of a quality assurance program in radiodiagnosis, with its main consequences : improvement of imaging quality, reduction of the patient expossure rate, cost reduction and 2) how to introduce the quality assurance control in the radiodiagnostic area. (M.A.) [pt

  8. Authentication Assurance Levels

    International Nuclear Information System (INIS)

    Kouzes, Richard T.; Cash, James R.; Devaney, David M.; Geelhood, Bruce D.; Hansen, Randy R.; Melton, Ronald B.; Pitts, W. Karl

    2002-01-01

    This Common Criteria approach has been applied to create a definition of Authentication Assurance Levels that can quantify the level of assurance reached for a system subject to a set of authentication procedures. The arms-control authentication application of the Common Criteria expands on more typical information security evaluations in that it must contend with information barriers and preclude sophisticated intentional subversion attempts.

  9. Quality assurance program

    International Nuclear Information System (INIS)

    Brooks, G.L.

    The concept of levels of quality assurance as applied to CANDU-type nuclear power plant components, i.e. maintaining an appropriate cost/benefit ratio, is introduced. The design process itself has quality assurance features by virtue of multi-level review. (E.C.B.)

  10. Laboratory quality assurance

    International Nuclear Information System (INIS)

    Delvin, W.L.

    1977-01-01

    The elements (principles) of quality assurance can be applied to the operation of the analytical chemistry laboratory to provide an effective tool for indicating the competence of the laboratory and for helping to upgrade competence if necessary. When used, those elements establish the planned and systematic actions necessary to provide adequate confidence in each analytical result reported by the laboratory (the definition of laboratory quality assurance). The elements, as used at the Hanford Engineering Development Laboratory (HEDL), are discussed and they are qualification of analysts, written methods, sample receiving and storage, quality control, audit, and documentation. To establish a laboratory quality assurance program, a laboratory QA program plan is prepared to specify how the elements are to be implemented into laboratory operation. Benefits that can be obtained from using laboratory quality assurance are given. Experience at HEDL has shown that laboratory quality assurance is not a burden, but it is a useful and valuable tool for the analytical chemistry laboratory

  11. Principal provisions of engineering and geological survey methodology in designing and construction of underground laboratory as a part of facility of RW underground isolation

    International Nuclear Information System (INIS)

    Prokopova, O.A.

    2006-01-01

    The most critical moment is the choice of a site for radioactive waste geological repository. Here the role of engineering and geological prospecting as a basis for the construction of a facility for underground isolation appears especially important; it is followed by finding a suitable area and subsequent allocation of the site and facility construction sites. The decision on the selection of construction site for the underground repository is taken by the principle 'descent from the general to the particular', which is a continuous process with the observance of stages in research for the design and exploration work. Each stage of research is typified by specific scale and methods of geological and geophysical studies and scientific research to be fulfilled in scopes sufficient for solution of basic problems for the designing. (author)

  12. /B(E2) values from low-energy Coulomb excitation at an ISOL facility: the /N=80,82 Te isotopes

    Science.gov (United States)

    Barton, C. J.; Caprio, M. A.; Shapira, D.; Zamfir, N. V.; Brenner, D. S.; Gill, R. L.; Lewis, T. A.; Cooper, J. R.; Casten, R. F.; Beausang, C. W.; Krücken, R.; Novak, J. R.

    2003-01-01

    B(E2;0+1→2+1) values for the unstable, neutron-rich nuclei 132,134Te were determined through Coulomb excitation, in inverse kinematics, of accelerated beams of these nuclei. The systematics of measured B(E2) values from the ground state to the first excited state have been extended to the N=82 shell closure in the Te nuclei and have been compared with the predictions of different theories. The measurements were performed at the Holifield Radioactive Ion Beam Facility (HRIBF) using the GRAFIK detector. The success of this approach, which couples a 5.7% efficient through-well NaI(Tl) γ-ray detector with thin foil microchannel plate beam detectors, also demonstrates the feasibility for Coulomb excitation studies of neutron-rich nuclei even further from the valley of beta stability, both at present-generation ISOL facilities and at the proposed Rare Isotope Accelerator.

  13. Application of Quality Assurance to MCandA systems

    International Nuclear Information System (INIS)

    Skinner, A.J.; Delvin, W.L.

    1986-01-01

    Quality Assurance has been applied to the MCandA function within the Department of Energy's Savannah River Operations Office. It was applied to both the activities used to operate the MCandA Branch and the activities used by the Branch to overview the MCandA function of DOE/SR's contractor. In this paper, the principles of quality assurance are reviewed and their application at DOE/SR is discussed. In addition, quality assurance can be applied to the broader MCandA functions required of those facilities producing, using, and handling nuclear materials. Application of quality assurance to those broader functions is also discussed

  14. Quality assurance program plan fuel supply shutdown project

    International Nuclear Information System (INIS)

    Metcalf, I.L.

    1998-01-01

    This Quality Assurance Program plan (QAPP) describes how the Fuel Supply Shutdown (FSS) project organization implements the quality assurance requirements of HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) and the B and W Hanford Company Quality Assurance Program Plan (QAPP), FSP-MP-004. The QAPP applies to facility structures, systems, and components and to activities (e.g., design, procurement, testing, operations, maintenance, etc.) that could affect structures, systems, and components. This QAPP also provides a roadmap of applicable Project Hanford Policies and Procedures (PHPP) which may be utilized by the FSS project organization to implement the requirements of this QAPP

  15. The motivation-based calving facility: Social and cognitive factors influence isolation seeking behaviour of Holstein dairy cows at calving.

    Science.gov (United States)

    Rørvang, Maria Vilain; Herskin, Mette S; Jensen, Margit Bak

    2018-01-01

    In order to improve animal welfare it is recommended that dairy farmers move calving cows from the herd to individual pens when calving is imminent. However, the practicality of moving cows has proven a challenge and may lead to disturbance of the cows rather than easing the process of calving. One solution may be to allow the cow to seek isolation prior to calving. This study examined whether pre-parturient dairy cows will isolate in an individual calving pen placed in a group calving setting and whether a closing gate in this individual calving pen will cause more cows to isolate prior to calving. Danish Holstein cows (n = 66) were housed in groups of six in a group pen with access to six individual calving pens connected to the group area. Cows were trained to use one of two isolation opportunities i.e. individual calving pens with functional closing gates (n = 35) allowing only one cow access at a time, or individual calving pens with permanently open gates allowing free cow traffic between group area and individual pen (n = 31). The response variables were calving site, calving behaviour and social behaviour. Unexpectedly, a functional gate did not facilitate isolation seeking, perhaps because the cows were not able to combine a learnt response with the motivation to isolate. Dominant cows had the highest chance of calving in an individual calving pen. If an alien calf was present in the group pen or any of the individual pens, cows were less likely to calve in an individual calving pen. Future studies should allow cows easy access to an individual calving pen and explore what motivates pre-parturient cows to seek isolation in order to facilitate voluntary use of individual calving pens.

  16. The motivation-based calving facility: Social and cognitive factors influence isolation seeking behaviour of Holstein dairy cows at calving

    Science.gov (United States)

    Herskin, Mette S.; Jensen, Margit Bak

    2018-01-01

    In order to improve animal welfare it is recommended that dairy farmers move calving cows from the herd to individual pens when calving is imminent. However, the practicality of moving cows has proven a challenge and may lead to disturbance of the cows rather than easing the process of calving. One solution may be to allow the cow to seek isolation prior to calving. This study examined whether pre-parturient dairy cows will isolate in an individual calving pen placed in a group calving setting and whether a closing gate in this individual calving pen will cause more cows to isolate prior to calving. Danish Holstein cows (n = 66) were housed in groups of six in a group pen with access to six individual calving pens connected to the group area. Cows were trained to use one of two isolation opportunities i.e. individual calving pens with functional closing gates (n = 35) allowing only one cow access at a time, or individual calving pens with permanently open gates allowing free cow traffic between group area and individual pen (n = 31). The response variables were calving site, calving behaviour and social behaviour. Unexpectedly, a functional gate did not facilitate isolation seeking, perhaps because the cows were not able to combine a learnt response with the motivation to isolate. Dominant cows had the highest chance of calving in an individual calving pen. If an alien calf was present in the group pen or any of the individual pens, cows were less likely to calve in an individual calving pen. Future studies should allow cows easy access to an individual calving pen and explore what motivates pre-parturient cows to seek isolation in order to facilitate voluntary use of individual calving pens. PMID:29346399

  17. Success and failure of nuclear power plant Quality Assurance when applied to research and development activities

    Energy Technology Data Exchange (ETDEWEB)

    Michels, R.D.; Stark, W.A.; Eberhart, C.F.

    1986-01-01

    Quality Assurance in some form or fashion has been practiced at research and development laboratories and facilities for quite some time. This quality assurance effort has largely been that of the scientist taking good notes as the experiment or observation is conducted to provide adequate documentation of the research and development effort. With the advent of the national laboratories participating in such projects as the Waste Isolation Project Plant (WIPP), Three Mile Island, and the National Waste Storage Program, a need for planned, systematic quality assurance for research and development activities has come into being. Based on experience evolved from nuclear power plant and facility construction, the government has chosen to utilize for these new projects the criteria developed for use in construction of power plants. While these criteria have worked reasonably well in the construction, maintenance, and operation of those nuclear plants, their application to research and development activities has not been an unqualified success. This paper compares and contrasts four criteria; surveillance, inspection, procurement, and calibration for application in the research and development situation, and nuclear power plants.

  18. Success and failure of nuclear power plant Quality Assurance when applied to research and development activities

    International Nuclear Information System (INIS)

    Michels, R.D.; Stark, W.A.; Eberhart, C.F.

    1986-01-01

    Quality Assurance in some form or fashion has been practiced at research and development laboratories and facilities for quite some time. This quality assurance effort has largely been that of the scientist taking good notes as the experiment or observation is conducted to provide adequate documentation of the research and development effort. With the advent of the national laboratories participating in such projects as the Waste Isolation Project Plant (WIPP), Three Mile Island, and the National Waste Storage Program, a need for planned, systematic quality assurance for research and development activities has come into being. Based on experience evolved from nuclear power plant and facility construction, the government has chosen to utilize for these new projects the criteria developed for use in construction of power plants. While these criteria have worked reasonably well in the construction, maintenance, and operation of those nuclear plants, their application to research and development activities has not been an unqualified success. This paper compares and contrasts four criteria; surveillance, inspection, procurement, and calibration for application in the research and development situation, and nuclear power plants

  19. An operational health physics quality assurance program

    International Nuclear Information System (INIS)

    Costigan, S.A.; McAtee, J.L. III; Somers, W.M.; Huchton, R.L.

    1996-01-01

    DOE Order 5700.6C, Quality Assurance, stipulates QA requirements for all DOE activities. This order is now codified as 10CFR830.120, Nuclear Safety Management, Quality Assurance Requirements, which is applicable to DOE nuclear facilities. A Quality Assurance Management Plan (QAMP) was developed by the Health Physics Operations Group (ESH-1) at Los Alamos National Laboratory (LANL). The goal of the ESH-1 QAMP is to ensure that operational radiation protection activities meet the criteria outlined in DOE Order 5700.6C, DOE-ER-STD-6001-92 and 10CFR830.120. The ten required elements are QA Program, Personal Training and Qualifications, Quality Improvement, Documents and Records, Work Processes, Design, Procurement, Inspection and Acceptance Testing, Management Assessment and Independent Assessment. The QAMP has been useful for the development of QAMPs at nuclear facilities and has helped ensure uniformity of institutional requirements where Health Physics services are deployed to facilities. To implement a subset of QAMP requirements, a Quality Assurance Self-Evaluation Program (QASE) was established. This program provides a novel self-audit mechanism for the formal identification and correction of non-conforming items related to Operational Health Physics. Additionally, the QASE is a useful management tool for Radiological Control Technician Supervisors and staff and provides a tracking mechanism for ongoing problem areas. Data have been Collected for two calendar years on a number of concerns that fall into four general categories: radiological posting and labeling, instrumentation, monitoring requirements, and radiological documents/records

  20. Quality Assistance Objectives for Nondestructive Assay at the Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    CANTALOUB, M.G.

    2000-01-01

    The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed

  1. Cold vacuum drying facility design requirements

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1999-01-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified

  2. Cold vacuum drying facility design requirements

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1999-07-01

    This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

  3. Quality assurance of metabolomics.

    Science.gov (United States)

    Bouhifd, Mounir; Beger, Richard; Flynn, Thomas; Guo, Lining; Harris, Georgina; Hogberg, Helena; Kaddurah-Daouk, Rima; Kamp, Hennicke; Kleensang, Andre; Maertens, Alexandra; Odwin-DaCosta, Shelly; Pamies, David; Robertson, Donald; Smirnova, Lena; Sun, Jinchun; Zhao, Liang; Hartung, Thomas

    2015-01-01

    Metabolomics promises a holistic phenotypic characterization of biological responses to toxicants. This technology is based on advanced chemical analytical tools with reasonable throughput, including mass-spectroscopy and NMR. Quality assurance, however - from experimental design, sample preparation, metabolite identification, to bioinformatics data-mining - is urgently needed to assure both quality of metabolomics data and reproducibility of biological models. In contrast to microarray-based transcriptomics, where consensus on quality assurance and reporting standards has been fostered over the last two decades, quality assurance of metabolomics is only now emerging. Regulatory use in safety sciences, and even proper scientific use of these technologies, demand quality assurance. In an effort to promote this discussion, an expert workshop discussed the quality assurance needs of metabolomics. The goals for this workshop were 1) to consider the challenges associated with metabolomics as an emerging science, with an emphasis on its application in toxicology and 2) to identify the key issues to be addressed in order to establish and implement quality assurance procedures in metabolomics-based toxicology. Consensus has still to be achieved regarding best practices to make sure sound, useful, and relevant information is derived from these new tools.

  4. Software quality assurance handbook

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    There are two important reasons for Software Quality Assurance (SQA) at Allied-Signal Inc., Kansas City Division (KCD): First, the benefits from SQA make good business sense. Second, the Department of Energy has requested SQA. This handbook is one of the first steps in a plant-wide implementation of Software Quality Assurance at KCD. The handbook has two main purposes. The first is to provide information that you will need to perform software quality assurance activities. The second is to provide a common thread to unify the approach to SQA at KCD. 2 figs.

  5. CrossRef Optimizing charge breeding techniques for ISOL facilities in Europe: Conclusions from the EMILIE project

    CERN Document Server

    Delahaye, P; Angot, J; Cam, J F; Traykov, E; Ban, G; Celona, L; Choinski, J; Gmaj, P; Jardin, P; Koivisto, H; Kolhinen, V; Lamy, T; Maunoury, L; Patti, G; Thuillier, T; Tarvainen, O; Vondrasek, R; Wenander, F

    2016-01-01

    The present paper summarizes the results obtained from the past few years in the framework of the Enhanced Multi-Ionization of short-Lived Isotopes for Eurisol (EMILIE) project. The EMILIE project aims at improving the charge breeding techniques with both Electron Cyclotron Resonance Ion Sources (ECRIS) and Electron Beam Ion Sources (EBISs) for European Radioactive Ion Beam (RIB) facilities. Within EMILIE, an original technique for debunching the beam from EBIS charge breeders is being developed, for making an optimal use of the capabilities of CW post-accelerators of the future facilities. Such a debunching technique should eventually resolve duty cycle and time structure issues which presently complicate the data-acquisition of experiments. The results of the first tests of this technique are reported here. In comparison with charge breeding with an EBIS, the ECRIS technique had lower performance in efficiency and attainable charge state for metallic ion beams and also suffered from issues related to beam c...

  6. Quality assurance and management

    International Nuclear Information System (INIS)

    Newcomb, W.E.

    1989-01-01

    This paper traces the evolution of the quality assurance program of an office of waste management development (OWTD). The program's needs and commitment are examined. The author reports on the role of program and technical managers in such a program

  7. RAVEN Quality Assurance Activities

    Energy Technology Data Exchange (ETDEWEB)

    Cogliati, Joshua Joseph [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    This report discusses the quality assurance activities needed to raise the Quality Level of Risk Analysis in a Virtual Environment (RAVEN) from Quality Level 3 to Quality Level 2. This report also describes the general RAVEN quality assurance activities. For improving the quality, reviews of code changes have been instituted, more parts of testing have been automated, and improved packaging has been created. For upgrading the quality level, requirements have been created and the workflow has been improved.

  8. Quality assurance in radiotherapy

    International Nuclear Information System (INIS)

    Groth, S.; Meghzifene, A.; Tatsuzaki, H.; Levin, V.; Izewska, J.

    2001-01-01

    Quality assurance in the management of a patient receiving radiation therapy and the role of the radiation oncologist and medical physicist in this process is described. The constraints on available personnel are recognised and the need for further education resources and IAEA activities in education for both groups described. IAEA activities in the clinical and dosimetric aspects and the resultant publications and education have contributed to a culture of quality assurance. (author)

  9. Quality assurance in NDT

    International Nuclear Information System (INIS)

    Krishnamoorthy, K.

    2010-01-01

    The importance of Nondestructive Testing (NDT) as a Quality Control/Quality Assurance tool in the industrial domain cannot be over-emphasized. With the rapid advancement in research and technology, the NDT field is becoming larger and more sophisticated day by day. Innovative research in materials science and digital technology is paving the way for more and more new methods in NDT technology. Although the NDT technology has improved over the years, the basic 'human factor' underlying the success of the NDT field remains the same. There are two major factors that influence the 'Quality Assurance in NDT'. First, knowledgeable and skilled NDT Operators are the most important factor in assuring the reliable test results. Second, the Management oversight of the NDT operations plays a major role in assuring the overall quality of NDT. Management responsibilities include the implementation of a Quality Management System (QMS) that focuses on the NDT operations and apply all the elements of Quality Assurance relevant to NDT. Whether the NDT operations are performed in-house or by a contractor, periodic Management Self-assessments should include the following question: How can the Management assess and improve the 'Quality Assurance in NDT'? This paper attempts to answer the above question. Some practical examples are provided to illustrate the potential quality incidents that could lead to costly failures, and the role of NDT Operator and the Management in preventing such quality incidents. Also, some guidelines are provided on how the Management can apply the elements of Quality Assurance to NDT in order to assess and improve the 'Quality Assurance in NDT'. (author)

  10. Structural concept of angle type of hot isolation valve and its test program at an out-of-pile test facility

    Energy Technology Data Exchange (ETDEWEB)

    Hada, Kazuhiko; Fujisaki, Katsuo; Shibata, Taijyu; Inagaki, Yoshiyuki; Hino, Ryutaro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Koiso, Hiroshi

    1997-02-01

    The Japanese safety regulation generally requires to set an isolation valve at the penetration of the reactor containment vessel on the secondary helium piping system which connects a steam reforming hydrogen production system, located outside the reactor building, to an intermediate heat exchanger (IHX) in the HTTR reactor system. The hot secondary helium which is heated up to the high temperature of 905degC and at the high pressure of 4.1MPa is passing through the isolation valve. So far, such a hot isolation valve has not been industrialized. The present report presents a proposal of a structural design concept of an angle valve as a promising candidate of the hot isolation valve, and a proposal on a test program for demonstrating the technological feasibility of the concept at an out-of-pile test facility before installing at the HTTR. A closing time and a leak rate at a valve seat are the key design parameters for developing the design concept. To set a reasonable value to each parameter, safety requirements on the isolation valve were discussed at first. The target closing time and the acceptable design limit of leak rate at the valve seat for meeting the requirements were specified 30 seconds and 10 STP cm{sup 3}/s, respectively. A nickel-base superalloy Hastelloy XR is feasible as such a valve seat material as to withstand the internal/external pressure of 4.1MPa at the high temperature of 905degC, the severest loading conditions of the valve seat at the accident of secondary helium pipe rupture. Correlation of leak rate at the ambient temperature to that at an operating temperature (900degC) is one of key test subjects of test program at an out-of-pile test facility. Leak rate at the operating temperature is the real parameter to be checked but only the leak rate at the ambient temperature is measured at regulatory examination in service. A test method to develop such correlation was proposed. (author)

  11. Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

    International Nuclear Information System (INIS)

    1977-06-01

    The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems

  12. Quality assurance FY 1995 site support program plan WBS 6.7.2.5

    Energy Technology Data Exchange (ETDEWEB)

    Dell, L.D.

    1994-09-01

    This report is a summary of the quality assurance plan and program for the Westinghouse Hanford Company. The quality assurance plan verifies that the appropriate quality assurance programs and controls are applied to activities that affect quality related to work in: waste management; environmental activities (restoration, remediation, and monitoring); implementation of environmental, state, local, and federal regulations; tri-party agreement activities; facility operation and deactivation/transition to shutdown; new facility construction and operation.

  13. Quality assurance FY 1995 site support program plan WBS 6.7.2.5

    International Nuclear Information System (INIS)

    Dell, L.D.

    1994-09-01

    This report is a summary of the quality assurance plan and program for the Westinghouse Hanford Company. The quality assurance plan verifies that the appropriate quality assurance programs and controls are applied to activities that affect quality related to work in: waste management; environmental activities (restoration, remediation, and monitoring); implementation of environmental, state, local, and federal regulations; tri-party agreement activities; facility operation and deactivation/transition to shutdown; new facility construction and operation

  14. 40 CFR 792.35 - Quality assurance unit.

    Science.gov (United States)

    2010-07-01

    ... monitoring each study to assure management that the facilities, equipment, personnel, methods, practices... schedule sheet of all studies conducted at the testing facility indexed by test substance and containing... management immediately. (4) Periodically submit to management and the study director written status reports...

  15. Mammography quality assurance in Morocco

    International Nuclear Information System (INIS)

    Zaoui, F.; Talsmat, K.; Lalaoui, K.

    2001-01-01

    The 'Centre National de l'Energie, des Sciences et des Techniques Nucleaires' (CNESTEN) realised, from February 1999 to March 2000, a quality control of 41 mammography facilities in Morocco. The protocol and standards adopted for achieving the control of elements constituting the mammography chain are those elaborated by GIM and Qualix association. Statistics and conformities results are presented. The program was performed in order to demonstrate to the practitioners in mammography field, the utility and necessity to have a national quality assurance policy. The main objective of CNESTEN is to be accredited by the Moroccan government as a reference laboratory in quality control and dose evaluation in medical imaging and radiotherapy. To achieve this goal the CNESTEN has set up Medical Physic Unit well trained and equipped with the necessary instruments. (author)

  16. Development of a Comprehensive Plan for Scientific Research, Exploration, and Design: Creation of an Underground Radioactive Waste Isolation Facility at the Nizhnekansky Rock Massif

    International Nuclear Information System (INIS)

    Jardine, L J

    2005-01-01

    ISTC Partner Project No.2377, ''Development of a General Research and Survey Plan to Create an Underground RW Isolation Facility in Nizhnekansky Massif'', funded a group of key Russian experts in geologic disposal, primarily at Federal State Unitary Enterprise All-Russian Design and Research Institute of Engineering Production (VNIPIPT) and Mining Chemical Combine Krasnoyarsk-26 (MCC K-26) (Reference 1). The activities under the ISTC Partner Project were targeted to the creation of an underground research laboratory which was to justify the acceptability of the geologic conditions for ultimate isolation of high-level waste in Russia. In parallel to this project work was also under way with Minatom's financial support to characterize alternative sections of the Nizhnekansky granitoid rock massif near the MCC K-26 site to justify the possibility of creating an underground facility for long-term or ultimate isolation of radioactive waste (RW) and spent nuclear fuel (SNF). (Reference 2) The result was a synergistic, integrated set of activities several years that advanced the geologic repository site characterization and development of a proposed underground research laboratory better than could have been expected with only the limited funds from ISTC Partner Project No.2377 funded by the U.S. DOE-RW. There were four objectives of this ISTC Partner Project 2377 geologic disposal work: (1) Generalize and analyze all research work done previously at the Nizhnekansky granitoid massif by various organizations; (2) Prepare and issue a declaration of intent (DOI) for proceeding with an underground research laboratory in a granite massif near the MCC K-26 site. (The DOI is similar to a Record of Decision in U.S. terminology). (3) Proceeding from the data obtained as a result of scientific research and exploration and design activities, prepare a justification of investment (JOI) for an underground research laboratory in as much detail as the available site characterization

  17. Application of the Management System for Facilities and Activities. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities.

  18. Automated data acquisition and analysis system used in the Basalt Waste Isolation Project's Near-Surface Test Facility

    International Nuclear Information System (INIS)

    Starr, J.L.

    1982-12-01

    A large minicomputer-based data acquisition and analysis system has been developed by the Basalt Waste Isolation project and is being applied to support research efforts on the response of rock (basalt) to thermal loads from simulated nuclear wastes. This system is believed to be the largest and most powerful system of its type in existence. It scans over 1000 different instruments, for three separate experiments, at a maximum frequency of once every 5 minutes. In addition to data acquisition, the system also performs the functions of data reduction, analog-to-digital conversion, computation of engineering units, data archiving, statistical analysis, and interactive graphics and reports. The system should be of general interest to those concerned with automated monitoring of instrumentation and computer graphics, as applied to large-scale engineering and scientific experimentation, especially in the fields of rock mechanics and nuclear waste disposal

  19. Spread of CTX-M-type ESßLs in isolates of E. coli from long-term care and rehabilitation facilities in Northern Italy

    Directory of Open Access Journals (Sweden)

    Elisabetta Nucleo

    2008-09-01

    Full Text Available During the period March 2003 – May 2004 at the Laboratory of Clinical Microbiology “Redaelli” LTCRF in Milan, Italy, a total of 529 E. coli, obtained from inpatients of 3 different Long Term Care Rehabilitation Facilities (LTCRFs in Northern Italy, were processed and 77 ESßLs producers (14.5% were identified by Vitek System. The results were confirmed by double-disk synergy test with tazobactam (TZP. 61/77 isolates were characterized by higher levels of resistance to cefotaxime (CTX than to ceftazidime (CAZ. (ß-lactamase production was investigated by analytical isoelectric focusing (IEF coupled with a bioassay and showed multiple (ß-lactamase bands including one enzyme with pI 8.4 that, in a bioassay, was more active on CTX,ATM than on CAZ. The presence of (ß-lactamase genes was investigated by colony blot hybridization and by PCR amplification of blaTEM, blaSHV and blaCTX-M alleles. 43/61 isolates produced both TEM-1 and CTX-M-type enzymes, 14/61 expressed only CTX-M-type while in 4 cases were found blaCTX-M, blaTEM and blaSHV genes.The remainders (16/77, characterized by high levels of resistance to both CTX and CAZ, produced TEM-1 and SHV-5 enzymes (1/16 and TEM type ESßLs (15/16. Conjugation experiments, performed in liquid medium, confermed that the ESßLs determinants were transferable. Pulsed-field gel electrophoresis profiles of genomic DNA, digested with NotI, were analysed and revealed clonal heterogeneity. Our work confirms the emergence of CTX-M-type enzymes and their spread in Northern Italy also in longterm care and rehabilitation facilities that may be an important reservoir of ES?L producing E. coli.

  20. Operating and Assurance Program Plan. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The LBL Operating and Assurance Program (OAP) is a management system and a set of requirements designed to maintain the level of performance necessary to achieve LBL`s programmatic and administrative objectives effectively and safely through the application of quality assurance and related conduct of operations and maintenance management principles. Implement an LBL management philosophy that supports and encourages continual improvement in performance and quality at the Laboratory. Provide an integrated approach to compliance with applicable regulatory requirements and DOE orders. The OAP is intended to meet the requirements of DOE Order 5700.6C, Quality Assurance. The Program also contains management system elements of DOE Orders 5480.19, Conduct of Operations Requirements for DOE Facilities; 5480.25, Safety of Accelerator Facilities; and 4330.4A, Maintenance Management Program, and is meant to integrate these elements into the overall LBL approach to Laboratory management. The requirements of this program apply to LBL employees and organizations, and to contractors and facility users as managed by their LBL sponsors. They are also applicable to external vendors and suppliers as specified in procurement documents and contracts.

  1. Quality assurance of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Frier, M.; Hesslewood, S.R.

    1980-01-01

    A practical guide has been composed for all persons involved in the preparation and use of radiopharmaceuticals on methods used in quality assurance and their applications. These methods include the calibration of ionization chamber assay calibrators, the determination of radionuclide purity, radiochemical purity and chemical purity, particle size analysis and the measurement of pH. Quality assurance procedures are described for products not described in Compendial Monographs, or where the monograph exists, additional useful information is provided; such radiopharmaceuticals include technetium, indium-labelled and iodine-labelled products. (U.K.)

  2. Software quality assurance

    CERN Document Server

    Laporte, Claude Y

    2018-01-01

    This book introduces Software Quality Assurance (SQA) and provides an overview of standards used to implement SQA. It defines ways to assess the effectiveness of how one approaches software quality across key industry sectors such as telecommunications, transport, defense, and aerospace. * Includes supplementary website with an instructor's guide and solutions * Applies IEEE software standards as well as the Capability Maturity Model Integration for Development (CMMI) * Illustrates the application of software quality assurance practices through the use of practical examples, quotes from experts, and tips from the authors

  3. Benchmarking Software Assurance Implementation

    Science.gov (United States)

    2011-05-18

    product The chicken#. (a.k.a. Process Focused Assessment ) – Management Systems ( ISO 9001, ISO 27001 , ISO 2000) – Capability Maturity Models (CMMI...Assurance PRM, RMM, Assurance for CMMI)) – Lifecycle Processes ( ISO /IEEE 15288, ISO /IEEE 12207) – COBIT, ITIL, MS SDL, OSAMM, BSIMM 5 The egg...a.k.a Product Focused Assessments) – SCAP - NIST-SCAP – ISO /OMG W3C – KDM, BPMN, RIF, XMI, RDF – OWASP Top 10 – SANS TOP 25 – Secure Code Check Lists

  4. WIPP conceptual design report. Addendum J. Support equipment in the high level waste facility of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Rieb, M.J.; Foley, R.S.

    1977-04-01

    The Aerojet Manufacturing Company (AMCO) received a contract in November 1976 to provide consulting services in assisting Holmes and Narver, Incorporated with the conceptual designs, cost estimates, and schedules of equipment used to handle waste casks, to decontaminate waste canisters and to overpack damaged or highly contaminated waste canisters for the Waste Isolation Pilot Plant (WIPP). Also, the layout of the hot cell in which canister handling, overpack and decontamination takes place was to be reviewed along with the time and motion study of the cell operations. This report has been prepared to present the results of the efforts and contains all technical and planning data developed during the program. The contents of this report are presented in three sections: (1) comments on the existing design criteria, equipment conceptual designs, hot cell design and time and motion studies of projected hot cell activities; (2) design descriptions of the equipment concepts and justification for varying from the existing concept (if a variation occurred). Drawings of each concept are provided in Appendix A. These design descriptions and drawings were used as the basis for the cost estimates; and (3) schedule projections and cost estimates for the equipment described in Section 2. Detail cost estimate backup data is provided in Appendix B

  5. Nuclear quality assurance operating philosophy: A quality-oriented approach

    International Nuclear Information System (INIS)

    Corcoran, W.R.; Geiger, J.E.; Heibel, R.E.; Cotton, J.B.; Sabol, A.R.

    1992-01-01

    Quality assurance programs have been part of the nuclear utility management process since the publication of the draft of 10CFR50 Appendix B in the late 1960s. The unwritten operational philosophy of nuclear quality assurance organizations focused on compliance with federal regulations. Adverse experiences, including operational events and extended shutdowns, prompted the gradual adoption of isolated practices extending beyond compliance orientation. These practices have an orientation that accommodates a definition of quality, a perspective of the role of nuclear quality assurance organizations in the overall concept of defense-in-depth, a definition of the segments of the nuclear quality assurance mission, and recent advances in the understanding of self-assessment. Observation of these practices at various nuclear utilities resulted in a syntheses of practices and approaches into a coherent quality-oriented nuclear quality assurance operating philosophy that is not totally adopted at any one utility

  6. Organic flow assurance, pour point depressant development through experimental design

    OpenAIRE

    Norland, Anne Kristine

    2012-01-01

    Master's thesis in Environmental technology Flow assurance is of great importance in the oil and gas industry, where the main objective is to provide and secure the transport of the well stream fluid from the reservoir to the process facilities. The main challenges in flow assurance are solid depositions in the pipelines, which can lead to reduction in the production, or in worst case completely block the pipelines. Wax deposition is a common problem in the oil industry, especially with...

  7. DOE standard: Quality assurance inspection and testing of HEPA filters

    International Nuclear Information System (INIS)

    1999-02-01

    This standard establishes essential elements for the quality assurance inspection and testing of HEPA filters by US Department of Energy (DOE)-accepted Filter Test Facilities (FTF). The standard specifies HEPA filter quality assurance inspection and testing practices established in DOE-STD-3022-98, DOE HEPA Filter Test Program, and provides a basis for the preparation of written operating procedures for primary FTF functions

  8. Quality assurance in nuclear fuel element component supply

    International Nuclear Information System (INIS)

    Jenkins, B.P.

    1987-01-01

    The paper describes the application of Quality Assurance to nuclear fuel element component supply. The Quality Assurance programme includes integrated procurement, purchasing, surveillance and receipt inspection functions. Purchasing policy is based on a consistent preference for competitive tendering. Multiple sourcing is used to encourage competitive pricing and increase security of supply. A receipt inspection facility is maintained to ensure the high product quality levels demanded by the nuclear industry. (U.K.)

  9. Manufacturing and quality assurance for the MFTF superconductor core

    International Nuclear Information System (INIS)

    Scanlan, R.M.; Johnston, J.E.; Waide, P.A.; Zeitlin, B.A.; Smith, G.B.; Nelson, C.T.

    1979-01-01

    A total of 55,000 m of multifilamentary Nb-Ti superconductor in minimum lengths of 380 m are required for the Mirror Fusion Test Facility. This conductor is a large cross-section monolith and, as such, has presented several new manufacturing challenges. In addition, a monolith requires more stringent quality assurance procedures than braids or cables. This paper describes the manufacturing steps and the quality assurance program which have been developed for the MFTF superconductor core

  10. Medicine in Ancient Assur

    DEFF Research Database (Denmark)

    Arbøll, Troels Pank

    This dissertation is a microhistorical study of a single individual named Kiṣir-Aššur who practiced medicine in the ancient city of Assur (modern northern Iraq) in the 7th century BCE. The study provides the first detailed analysis of one healer’s education and practice in ancient Mesopotamia...

  11. Quality assurance. 6. ed.

    International Nuclear Information System (INIS)

    Masing, W.

    1979-01-01

    Brief introduction to the quality sector. After some explanations of the terms of quality, feature, and defect, the article discusses the planning of quality and testing, industrial metrology, the test risk, quality assurance, quality enhancement, quality cost, and organisational problems. (RW) [de

  12. Quality Assurance Program Description

    Energy Technology Data Exchange (ETDEWEB)

    Halford, Vaughn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ryder, Ann Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    Effective May 1, 2017, led by a new executive leadership team, Sandia began operating within a new organizational structure. National Technology and Engineering Solutions of Sandia (Sandia’s) Quality Assurance Program (QAP) was established to assign responsibilities and authorities, define workflow policies and requirements, and provide for the performance and assessment of work.

  13. Providing Continuous Assurance

    NARCIS (Netherlands)

    Kocken, Jonne; Hulstijn, Joris

    2017-01-01

    It has been claimed that continuous assurance can be attained by combining continuous monitoring by management, with continuous auditing of data streams and the effectiveness of internal controls by an external auditor. However, we find that in existing literature the final step to continuous

  14. Chapter 8: Quality assurance

    International Nuclear Information System (INIS)

    2001-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (UJD) have been focused on inspection of quality assurance programmes of Slovak Power Stations, plc. and its daughter companies at Bohunice and Mochovce. Two quality assurance inspections in the area of periodical in service inspections (V-2 units) and tests of selected equipment (NPP V-2 units) and operation control (V-1 units) has been performed at NPPs Bohunice. One violation of decree on quality assurance of selected equipment has been found in the area of documentation archiving. The inspection concerning the implementation of quality assurance programme for operation of NPP Mochovce in the area of operation control has been performed focused on safety aspects of operation, operational procedures, control of operational events and feedback from operational experience. The results of this inspection were positive. Inspection of implementation of quality assurance programme for operation of radioactive waste repository (RU RAW) at the Mochovce location has been performed focused on receiving of containers, with radioactive wastes, containers handling, radiation monitoring, activities of documentation control and radiation protection at the repository site. No serious deficiencies have been found out. Also one inspection of experimental nuclear installations of VUJE Trnava at Jaslovske Bohunice site has been performed focused on procurement control, quality audits, documentation and quality records control when performing activities at experimental nuclear installations. The activity on development of internal quality assurance system continued. The implementation of this system will assure quality and effective fulfilment enlarged tasks of UJD with limited resources for its activity. The analyses of possible use of existing internal administrative control documentation as a basis for future quality system procedures was performed in co-operation with an external specialised organisation. The

  15. Application of project design peer review to improve quality assurance

    International Nuclear Information System (INIS)

    McClure, F.E.

    1989-01-01

    DOE ORDER 5481.1B Safety Analysis and Review Systems and DOE ORDER 6430.1A General Design Criteria require that the design of facilities shall incorporate the necessary Quality Assurance review requirements to assure that the established program quality assurance objectives are met in the design criteria and the construction documents. The use of Project Design Peer Review to satisfy these requirements is presented. The University of California manages the Lawrence Berkeley Laboratory, the Lawrence Livermore National Laboratory, and the Los Alamos National Scientific Laboratory. The 1988 University Seismic Safety Policy requires the use of independent Project Design Peer Review in its capital improvement and seismic reconstruction program

  16. Quality Assurance Plan, N springs expedited response action

    International Nuclear Information System (INIS)

    Jackson, G.J.

    1994-01-01

    This document is the Quality Assurance Plan (QAP) to be followed during the definitive design, construction, and operational phases for activities associated with the N Springs Expedited Response Action (ERA) for the 100-NR-2 Operable Unit (OU). Westinghouse Hanford Company (WHC) will comply with the US Department of Energy (DOE) Order 5700.6C, Quality Assurance (DOE 1989), and the US Environmental Protection Agency (EPA), EPA/530-SW-86-031, Technical Guidance Document: Construction Quality Assurance for Hazardous Waste Land Disposal Facilities (EPA 1986)

  17. Study on quality assurance for high-level radioactive waste disposal project (2). Quality assurance system for the site characterization phase in the Yucca Mountain Project

    International Nuclear Information System (INIS)

    Takada, Susumu

    2006-01-01

    The objective of this report is to assist related organizations in the development of quality assurance systems for a high-level radioactive waste disposal system. This report presents detail information with which related organizations can begin the development of quality assurance systems at an initial phase of repository development for a high-level radioactive waste disposal program, including data qualification, model validation, systems and facilities for quality assurance (e.g., technical data management system, sample management facility, etc.), and QA program applicability (items and activities). These descriptions are based on information in QA program for the Yucca Mountain Project (YMP), such as the U.S. Department of Energy (DOE) Quality Assurance Requirements and Description (QARD), DOE/RW-0333P, quality implementing procedures, and reports implemented by the procedures. Additionally, this report includes some brief recommendations for developing of quality assurance systems, such as establishment of quality assurance requirements, measures for establishment of QA system. (author)

  18. Creating Quality Assurance and International Transparency for Quality Assurance Agencies

    DEFF Research Database (Denmark)

    Kristoffersen, Dorte; Lindeberg, Tobias

    2004-01-01

    The paper presents the experiences gained in the pilot project on mutual recognition conducted by the quality assurance agencies in the Nordic countries and the future perspective for international quality assurance of national quality assurance agencies. The background of the project was the nee...

  19. BYU Food Quality Assurance Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Quality Assurance Lab is located in the Eyring Science Center in the department of Nutrition, Dietetics, and Food Science. The Quality Assurance Lab has about 10...

  20. CSER 94-012: Criticality safety evaluation report for 340 Facility

    International Nuclear Information System (INIS)

    Altschuler, S.J.

    1995-01-01

    This Criticality Safety Evaluation Report (CSER) covers the 340 Facility which acts as a collecting point for liquid and solid waste from various facilities in the 300 Area. Criticality safety is achieved by controlling the amount and concentration of the fissionable material sent to the 340 Facility from the originating facilities in the 300 Area, a method similar to that used elsewhere at Hanford for the waste tank farms. Unlike those, however, the waste received at the 340 Facility will be far less radioactive. It is concluded that present operations meet the two contingency criterion. The facility will still be safely subcritical even after two independent and concurrent failures (either of equipment or administrative controls). The solid waste storage and liquid waste will be managed separately. The solid waste storage area is classified as exempt because it contains less than 15 grams of fissionable materials. The Radioactive Liquid Waste System is classified as isolated because it contains less than one third of a minimum critical mass. The criticality safety of the 340 Facility devoted to the Radioactive Liquid Waste System (RLWS) is assured by the form and concentration of the fissile material and could also be classified as a limited control facility. However, the 340 Facility has been operated as an isolated facility which results in a more conservative limit

  1. Creating Quality Assurance and International Transparency for Quality Assurance Agencies

    DEFF Research Database (Denmark)

    Kristoffersen, Dorte; Lindeberg, Tobias

    2004-01-01

    , on the one hand, to advance internationalisation of quality assurance of higher education, and on the other hand, allow for the differences in the national approaches to quality assurance. The paper will focus on two issues: first, the strength and weaknesses of the method employed and of the use of the ENQA......The paper presents the experiences gained in the pilot project on mutual recognition conducted by the quality assurance agencies in the Nordic countries and the future perspective for international quality assurance of national quality assurance agencies. The background of the project was the need...

  2. Rollout of quality assurance interventions in labor room in two districts of Bihar, India

    OpenAIRE

    Jyoti Sharma; Sutapa B Neogi; Preeti Negandhi; Monika Chauhan; Siddharth Reddy; Ghanshyam Sethy

    2016-01-01

    Background: Quality of care at the facilities during childbirth remains a major concern. Improved quality could have the greatest dividend in saving maternal and newborn lives. Objective: The objective of this study was to implement quality assurance measures in the labor rooms of select public health facilities in two districts of Bihar. Methods: The labor room quality assurance intervention was implemented in two districts, Gaya and Purnea in Bihar. Health facilities having >200 deliveries/...

  3. The assurance management program for the Nova laser fusion project

    International Nuclear Information System (INIS)

    Levy, A.J.

    1983-01-01

    In a well managed project, Quality Assurance is an integral part of the management activities performed on a daily basis. Management assures successful performance within budget and on schedule by using all the good business, scientific, engineering, quality assurance, and safety practices available. Quality assurance and safety practices employed on Nova are put in perspective by integrating them into the overall function of good project management. The Inertial Confinement Fusion (ICF) approach is explained in general terms. The laser ICF and magnetic fusion facilities are significantly different in that the laser system is used solely as a highly reliable energy source for performing plasma physics experiments related to fusion target development; by contrast, magnetic fusion facilities are themselves the experiments. The Nova project consists of a 10-beam, 74 cm aperture neodymium-glass laser experimental facility which is being constructed by the Lawrence Livermore National Laboratory (LLNL) for the U.S. Department of Energy. Nova has a total estimated cost of $176M and will become operational in the Fall of 1984. The Nova laser will be used as the high energy driver for studying the regime of ignition for ICF. The Nova assurance management program was developed using the quality assurance (QA) approach first implemented at LLNL in early 1978. The LLNL QA program is described as an introduction to the Nova assurance management program. The Nova system is described pictorially through the Nova configuration, subsystems and major components, interjecting the QA techniques which are being pragmatically used to assure the successful completion of the project

  4. Quality assurance in microbiology

    OpenAIRE

    Arora D

    2004-01-01

    Quality assurance (QA) is the total process whereby the quality of laboratory reports can be guaranteed. The term quality control covers that part of QA, which primarily concerns the control of errors in the performance of tests and verification of test results. All materials, equipment and procedures must be adequately controlled. Culture media must be tested for sterility and performance. Each laboratory must have standard operating procedures (SOPs). QA of pre-analytical, analytical and po...

  5. Introduction to quality assurance

    International Nuclear Information System (INIS)

    Raisic, N.

    1980-01-01

    Safety requirements set forth in the regulatory requirement, codes, standards as well as other requirements for various aspects of nuclear power plant design and operation are strictly implemented through QA activities. The overall QA aim is to assure that the plant is soundly and correctly designed and that it is built, tested and operated in accordance with stringent quality standards and conservative engineering practices. In this way a high degree of freedom from faults and errors can be achieved. (orig.)

  6. Quality assurance in radiotherapy

    International Nuclear Information System (INIS)

    2003-03-01

    Good radiotherapy results and safety of treatment require the radiation to be optimally applied to a specified target area and the correct dose. According to international recommendations, the average uncertainty in therapeutic dose should not exceed 5%. The need for high precision in therapeutic dose requires quality assurance covering the entire radiotherapy process. Besides the physical and technical characteristics of the therapy equipment, quality assurance must include all radiotherapy equipment and procedures that are significant for the correct magnitude and precision of application of the therapeutic dose. The duties and responsibilities pertaining to various stages of treatment must also be precisely defined. These requirements may be best implemented through a quality system. The general requirements for supervision and quality assurance of medical radiation apparatus are prescribed in section 40 of the Radiation Act (592/1991, amendment 1142/1998) and in sections 18 and 32 of the Decree of the Ministry of Social Affairs and Health on the medical use of radiation (423/2000). Guide ST 2.2 imposes requirements on structural radiation shielding of radiotherapy equipment and the premises in which it is used, and on warning and safety arrangements. Guide ST 1.1 sets out the general safety principles for radiation practices and regulatory control procedure for the use of radiation. Guide ST 1.6 provides general requirements for operational measures in the use of radiation. This Guide sets out the duties of responsible parties (the party running a radiation practice) in respect of arranging and maintaining radiotherapy quality assurance. The principles set out in this Guide and Guide ST 6.3 may be applied to radionuclide therapy

  7. SGHWR - quality assurance documentation

    International Nuclear Information System (INIS)

    Garrard, R.S.; Caulfield, J.

    1976-01-01

    The quality assurance program for a modern power station such as an SGHWR type reactor plant must include a record of quality achievement. The case history record which is evidence of the actual quality of the plant and is a data bank of design, manufacture, and results of inspections and tests, is described. Documentation distribution, which keeps all key areas informed of plant item quality status, and the retrieval and storage of information, are briefly discussed. (U.K.)

  8. High-Assurance Spiral

    Science.gov (United States)

    2017-11-01

    HIGH-ASSURANCE SPIRAL CARNEGIE MELLON UNIVERSITY NOVEMBER 2017 FINAL TECHNICAL REPORT APPROVED FOR PUBLIC RELEASE; DISTRIBUTION UNLIMITED STINFO...MU 7. PERFORMING ORGANIZATION NAME(S) AND ADDRESS(ES) Carnegie Mellon University 5000 Forbes Ave Pittsburgh, PA 15217 8. PERFORMING ORGANIZATION...Approved for Public Release; Distribution Unlimited. Carnegie Mellon Carnegie Mellon HA SPIRAL Code Synthesis KeYmaera X Hybrid Theorem Prover

  9. Software Quality Assurance Metrics

    Science.gov (United States)

    McRae, Kalindra A.

    2004-01-01

    Software Quality Assurance (SQA) is a planned and systematic set of activities that ensures conformance of software life cycle processes and products conform to requirements, standards and procedures. In software development, software quality means meeting requirements and a degree of excellence and refinement of a project or product. Software Quality is a set of attributes of a software product by which its quality is described and evaluated. The set of attributes includes functionality, reliability, usability, efficiency, maintainability, and portability. Software Metrics help us understand the technical process that is used to develop a product. The process is measured to improve it and the product is measured to increase quality throughout the life cycle of software. Software Metrics are measurements of the quality of software. Software is measured to indicate the quality of the product, to assess the productivity of the people who produce the product, to assess the benefits derived from new software engineering methods and tools, to form a baseline for estimation, and to help justify requests for new tools or additional training. Any part of the software development can be measured. If Software Metrics are implemented in software development, it can save time, money, and allow the organization to identify the caused of defects which have the greatest effect on software development. The summer of 2004, I worked with Cynthia Calhoun and Frank Robinson in the Software Assurance/Risk Management department. My task was to research and collect, compile, and analyze SQA Metrics that have been used in other projects that are not currently being used by the SA team and report them to the Software Assurance team to see if any metrics can be implemented in their software assurance life cycle process.

  10. Assuring Software Reliability

    Science.gov (United States)

    2014-08-01

    technologies and processes to achieve a required level of confidence that software systems and services function in the intended manner. 1.3 Security Example...that took three high-voltage lines out of service and a software fail- ure (a race condition3) that disabled the computing service that notified the... service had failed. Instead of analyzing the details of the alarm server failure, the reviewers asked why the following software assurance claim had

  11. Power transformers quality assurance

    CERN Document Server

    Dasgupta, Indrajit

    2009-01-01

    About the Book: With the view to attain higher reliability in power system operation, the quality assurance in the field of distribution and power transformers has claimed growing attention. Besides new developments in the material technology and manufacturing processes of transformers, regular diagnostic testing and maintenance of any engineering product may be ascertained by ensuring: right selection of materials and components and their quality checks. application of correct manufacturing processes any systems engineering. the user`s awareness towards preventive maintenance. The

  12. Measurement quality assurance

    International Nuclear Information System (INIS)

    Eisenhower, E.H.

    1988-01-01

    The quality of a radiation protection program can be no better than the quality of the measurements made to support it. In many cases, that quality is unknown and is merely implied on the basis of a calibration of a measuring instrument. If that calibration is inappropriate or is performed improperly, the measurement result will be inaccurate and misleading. Assurance of measurement quality can be achieved if appropriate procedures are followed, including periodic quality control actions that demonstrate adequate performance. Several national measurement quality assurance (MQA) programs are operational or under development in specific areas. They employ secondary standards laboratories that provide a high-quality link between the National Bureau of Standards and measurements made at the field use level. The procedures followed by these secondary laboratories to achieve MQA will be described, as well as plans for similar future programs. A growing general national interest in quality assurance, combined with strong specific motivations for MQA in the area of ionizing radiation, will provide continued demand for appropriate national programs. Such programs must, however, employ procedures that are cost effective and must be developed with participation by all affected parties

  13. Helical Tomotherapy Quality Assurance

    International Nuclear Information System (INIS)

    Balog, John; Soisson, Emilie

    2008-01-01

    Helical tomotherapy uses a dynamic delivery in which the gantry, treatment couch, and multileaf collimator leaves are all in motion during treatment. This results in highly conformal radiotherapy, but the complexity of the delivery is partially hidden from the end-user because of the extensive integration and automation of the tomotherapy control systems. This presents a challenge to the medical physicist who is expected to be both a system user and an expert, capable of verifying relevant aspects of treatment delivery. A related issue is that a clinical tomotherapy planning system arrives at a customer's site already commissioned by the manufacturer, not by the clinical physicist. The clinical physicist and the manufacturer's representative verify the commissioning at the customer site before acceptance. Theoretically, treatment could begin immediately after acceptance. However, the clinical physicist is responsible for the safe and proper use of the machine. In addition, the therapists and radiation oncologists need to understand the important machine characteristics before treatment can proceed. Typically, treatment begins about 2 weeks after acceptance. This report presents an overview of the tomotherapy system. Helical tomotherapy has unique dosimetry characteristics, and some of those features are emphasized. The integrated treatment planning, delivery, and patient-plan quality assurance process is described. A quality assurance protocol is proposed, with an emphasis on what a clinical medical physicist could and should check. Additionally, aspects of a tomotherapy quality assurance program that could be checked automatically and remotely because of its inherent imaging system and integrated database are discussed

  14. Quality assurance in the Antares laser fusion construction project

    International Nuclear Information System (INIS)

    Reichelt, W.H.

    1984-01-01

    The Antares CO 2 laser facility came on line in November 1983 as an experimental physics facility; it is the world's largest CO 2 laser fusion system. Antares is a major component of the Department of Energy's Inertial Confinement Fusion Program. Antares is a one-of-a-kind laser system that is used in an experimental environment. Given limited project funds and tight schedules, the quality assurance program was tailored to achieve project goals without imposing oppressive constraints. The discussion will review the Antares quality assurance program and the utility of various portions to completion of the project

  15. The Management System for Facilities and Activities. Safety Requirements

    International Nuclear Information System (INIS)

    2011-01-01

    This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States in establishing and implementing effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement.

  16. Spent Nuclear Fuel Cold Vacuum Drying facility comprehensive formal design review report

    International Nuclear Information System (INIS)

    HALLER, C.S.

    1999-01-01

    The majority of the Cold Vacuum Drying Facility (CVDF) design and construction is complete; isolated portions are still in the design and fabrication process. The project commissioned a formal design review to verify the sufficiency and accuracy of current design media to assure that: (1) the design completely and accurately reflects design criteria, (2) design documents are consistent with one another, and (3) the design media accurately reflects the current design. This review is a key element in the design validation and verification activities required by SNF-4396, ''Design Verification and Validation Plan For The Cold Vacuum Drying Facility''. This report documents the results of the formal design review

  17. Specified assurance level sampling procedure

    International Nuclear Information System (INIS)

    Willner, O.

    1980-11-01

    In the nuclear industry design specifications for certain quality characteristics require that the final product be inspected by a sampling plan which can demonstrate product conformance to stated assurance levels. The Specified Assurance Level (SAL) Sampling Procedure has been developed to permit the direct selection of attribute sampling plans which can meet commonly used assurance levels. The SAL procedure contains sampling plans which yield the minimum sample size at stated assurance levels. The SAL procedure also provides sampling plans with acceptance numbers ranging from 0 to 10, thus, making available to the user a wide choice of plans all designed to comply with a stated assurance level

  18. Quality assurance program plan for SNF characterization support project

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Spent Nuclear Fuel Characterization Support Project. This QAPP has been developed specifically for the Spent Nuclear Fuel Characterization Support Project, per Letter of Instruction (LOI) from Duke Engineering and Services Company, letter No. DESH-9655870, dated Nov. 22, 1996. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP) and LOI. These activities include installation of sectioning equipment and furnace, surface and subsurface examinations, sectioning for metallography, and element drying and conditioning testing, as well as project related operations within the 327 facility as it relates to the specific activities of this project. General facility activities are covered in other appropriate QA-PPS. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping,1261 and HSRCM-1, Hanford Site Radiological Control Manual. The 327 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a Babcock and Wilcox Hanford Company (BVMC) managed facility. During this transition process existing procedures and documents will be utilized until replaced by BVMC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to IO CFR 830.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be utilized in support of this project and the subject organizations are

  19. Assessment of the Forward Contamination Risk of Mars by Clean Room Isolates from Space-Craft Assembly Facilities through Aeolian Transport - a Model Study

    Science.gov (United States)

    van Heereveld, Luc; Merrison, Jonathan; Nørnberg, Per; Finster, Kai

    2017-06-01

    The increasing number of missions to Mars also increases the risk of forward contamination. Consequently there is a need for effective protocols to ensure efficient protection of the Martian environment against terrestrial microbiota. Despite the fact of constructing sophisticated clean rooms for spacecraft assembly a 100 % avoidance of contamination appears to be impossible. Recent surveys of these facilities have identified a significant number of microbes belonging to a variety of taxonomic groups that survive the harsh conditions of clean rooms. These microbes may have a strong contamination potential, which needs to be investigate to apply efficient decontamination treatments. In this study we propose a series of tests to evaluate the potential of clean room contaminants to survive the different steps involved in forward contamination. We used Staphylococcus xylosus as model organism to illustrate the different types of stress that potential contaminants will be subjected to on their way from the spacecraft onto the surface of Mars. Staphylococcus xylosus is associated with human skin and commonly found in clean rooms and could therefore contaminate the spacecraft as a result of human activity during the assembling process. The path the cell will take from the surface of the spacecraft onto the surface of Mars was split into steps representing different stresses that include desiccation, freezing, aeolian transport in a Martian-like atmosphere at Martian atmospheric pressure, and UV radiation climate. We assessed the surviving fraction of the cellular population after each step by determining the integrated metabolic activity of the survivor population by measuring their oxygen consumption rate. The largest fraction of the starting culture (around 70 %) was killed during desiccation, while freezing, Martian vacuum and short-term UV radiation only had a minor additional effect on the survivability of Staphylococcus xylosus. The study also included a simulation

  20. Auditing radiation sterilization facilities

    Science.gov (United States)

    Beck, Jeffrey A.

    The diversity of radiation sterilization systems available today places renewed emphasis on the need for thorough Quality Assurance audits of these facilities. Evaluating compliance with Good Manufacturing Practices is an obvious requirement, but an effective audit must also evaluate installation and performance qualification programs (validation_, and process control and monitoring procedures in detail. The present paper describes general standards that radiation sterilization operations should meet in each of these key areas, and provides basic guidance for conducting QA audits of these facilities.

  1. Quality assurance and demolition: 2008 symposium

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2008-01-01

    The 'Quality Assurance and Demolition Symposium, which has become a tradition established jointly by Applus RTD Deutschland GmbH (formerly compra GmbH) and Brenk Systemplanung GmbH, Aachen, was held also in 2008 with the focus on quality assurance and the demolition of nuclear facilities. The conference began with a series of lectures on knowledge and document management in general, and the use of document management systems in the nuclear field in particular. The evening lecture was presented by Axel Weis (Karlsruhe Research Center) on 'Competence Preservation in Nuclear Technology'. The 24 technical papers presented on the next 2 days of the symposium dealt with non-destructive materials testing and with special problems of radiation protection, demolition, and waste management. In 2009, the meeting will cover similar main topics and will again be held in an interesting environment, perhaps in combination with a tour of a demolition project. (orig.)

  2. Quality assurance for geologic investigations

    International Nuclear Information System (INIS)

    Delvin, W.L.; Gustafson, L.D.

    1983-01-01

    A quality assurance handbook was written to provide guidance in the application of quality assurance to geologic work activities associated with the National Waste Terminal Storage (NWTS) Program. It is intended to help geoscientists and NWTS program managers in applying quality assurance to their work activities and projects by showing how technical and quality assurance practices are integrated to provide control within those activities and projects. The use of the guidance found in this handbook should help provide consistency in the interpretation of quality assurance requirements across the various geologic activities wihtin the NWTS Program. This handbook also can assist quality assurance personnel in understanding the relationships between technical and quality assurance practices. This paper describes the handbook

  3. Quality assurance for geologic investigations

    International Nuclear Information System (INIS)

    Delvin, W.L.; Gustafson, L.D.

    1983-01-01

    A quality assurance handbook was written to provide guidance in the application of quality assurance to geologic work activities associated with the National Waste Terminal Storage (NWTS) Program. It is intended to help geoscientists and NWTS program managers in applying quality assurance to their work activitie and projects by showing how technical and quality assurance practices are integrated to provide control within those activities and projects. The use of the guidance found in this handbook should help provide consistency in the interpretation of quality assurance requirements across the various geologic activities within the NWTS Program. This handbook also can assist quality assurance personnel in understanding the relationships between technical and quality assurance practices. This paper describes the handbook

  4. Quality Assurance Program Plan (QAPP) Waste Management Project

    Energy Technology Data Exchange (ETDEWEB)

    VOLKMAN, D.D.

    1999-10-27

    This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

  5. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP facility

    International Nuclear Information System (INIS)

    GOLDBERG, H.J.

    1999-01-01

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility

  6. Bioleaching of Gold and Silver from Waste Printed Circuit Boards by Pseudomonas balearica SAE1 Isolated from an e-Waste Recycling Facility.

    Science.gov (United States)

    Kumar, Anil; Saini, Harvinder Singh; Kumar, Sudhir

    2018-02-01

    Indigenous bacterial strain Pseudomonas balearica SAE1, tolerant to e-waste toxicity was isolated from an e-waste recycling facility Exigo Recycling Pvt. Ltd., India. Toxicity tolerance of bacterial strain was analyzed using crushed (particle size ≤150 µm) waste computer printed circuit boards (PCBs)/liter (L) of culture medium. The EC 50 value for SAE1 was 325.7 g/L of the e-waste pulp density. Two-step bioleaching was then applied to achieve the dissolution of gold (Au) and silver (Ag) from the e-waste. To maximize precious metal dissolution, factors including pulp density, glycine concentration, pH level, and temperature were optimized. The optimization resulted in 68.5 and 33.8% of Au and Ag dissolution, respectively, at a pH of 9.0, a pulp density of 10 g/L, a temperature of 30 °C, and a glycine concentration of 5 g/L. This is the first study of Au and Ag bioleaching using indigenous e-waste bacteria and its analysis to determine e-waste toxicity tolerance.

  7. Alkaline Fe(III) reduction by a novel alkali-tolerant Serratia sp. isolated from surface sediments close to Sellafield nuclear facility, UK.

    Science.gov (United States)

    Thorpe, Clare L; Morris, Katherine; Boothman, Christopher; Lloyd, Jonathan R

    2012-02-01

    Extensive denitrification resulted in a dramatic increase in pH (from 6.8 to 9.5) in nitrate-impacted, acetate-amended sediment microcosms containing sediment representative of the Sellafield nuclear facility, UK. Denitrification was followed by Fe(III) reduction, indicating the presence of alkali-tolerant, metal-reducing bacteria. A close relative (99% 16S rRNA gene sequence homology) to Serratia liquefaciens dominated progressive enrichment cultures containing Fe(III)-citrate as the sole electron acceptor at pH 9 and was isolated aerobically using solid media. The optimum growth conditions for this facultatively anaerobic Serratia species were investigated, and it was capable of metabolizing a wide range of electron acceptors including oxygen, nitrate, FeGel, Fe-NTA and Fe-citrate and electron donors including acetate, lactate, formate, ethanol, glucose, glycerol and yeast extract at an optimum pH of c. 6.5 at 20 °C. The alkali tolerance of this strain extends the pH range of highly adaptable Fe(III)-reducing Serratia species from mildly acidic pH values associated with acid mine drainage conditions to alkali conditions representative of subsurface sediments stimulated for extensive denitrification and metal reduction. © 2011 Federation of European Microbiological Societies. Published by Blackwell Publishing Ltd. All rights reserved.

  8. The quality assurance liaison: Combined technical and quality assurance support

    International Nuclear Information System (INIS)

    Bolivar, S.L.; Day, J.L.

    1993-01-01

    This paper describes the role of the quality assurance liaison, the responsibilities of this position, and the evolutionary changes in duties over the last six years. The role of the quality assurance liaison has had a very positive impact on the Los Alamos Yucca Mountain Site Characterization (YW) quality assurance program. Having both technical and quality assurance expertise, the quality assurance liaisons are able to facilitate communications with scientists on quality assurance issues and requirements, thereby generating greater productivity in scientific investigations. The quality assurance liaisons help ensure that the scientific community knows and implements existing requirements, is aware of new or changing regulations, and is able to conduct scientific work within Project requirements. The influence of the role of the quality assurance liaison can be measured by an overall improvement in attitude of the staff regarding quality assurance requirements and improved job performance, as well as a decrease in deficiencies identified during both internal and external audits and surveillances. This has resulted in a more effective implementation of quality assurance requirements

  9. Hyperthermia quality assurance

    International Nuclear Information System (INIS)

    Shrivastava, P.N.; Paliwal, B.R.

    1984-01-01

    Hyperthermia Physics Center (HPC) operating under contract with the National Cancer Institute is developing a Quality Assurance program for local and regional hyperthermia. The major clinical problem in hyperthermia treatments is that they are extremely difficult to plan, execute, monitor and reproduce. A scientific basis for treatment planning can be established only after ensuring that the performance of heat generating and temperature monitoring systems are reliable. The HPC is presently concentrating on providing uniform NBS traceable calibration of thermometers and evaluation of reproducibility for power generator operation, applicator performance, phanta compositions, system calibrations and personnel shielding. The organizational plan together with recommended evaluation measurements, procedures and criteria are presented

  10. How much quality assurance?

    International Nuclear Information System (INIS)

    Beatty, R.A.; Talboy, J.H.

    1988-01-01

    This paper describes the approach used at Argonne National Laboratory to apply the techniques of quality assurance to research and development activities. The discussion includes the approach, the reasons that it is gaining acceptance, and its wide applicability. This approach is founded on the lessons learned in management of quality at Argonne National Laboratory over a period of more than 15 years. The discussion is confined to the practices at the Illinois site of the Laboratory where more than 3000 researchers and support personnel conduct basic and technology-directed research

  11. Quality assurance services

    International Nuclear Information System (INIS)

    For over 20 years the quality assurance services at the Springfields Laboratories have been concerned with manufacturing both simple and complex engineering products to the highest standard. The scientists working there have considerable expertise in the practical application of quality control and the development and design of inspection and non-destructive testing equipment. The folder contains six sheets or leaflets illustrating the work and equipment. The subjects are the mechanical standards laboratory, non-destructive testing, the digitising table, the peripheral camera, automated measurement, data handling and presentation, and the computer controlled three axis co-ordinate measuring machine. (U.K.)

  12. Reactor system safety assurance

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1984-01-01

    The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment

  13. Quality assurance program

    International Nuclear Information System (INIS)

    1977-07-01

    This topical report describes the Gibbs and Hill Quality Assurance Program and sets forth the methods to be followed in controlling quality-related activities performed by Gibbs and Hill and its contractors. The program is based on company experience in nuclear power and related work, and defines a system found effective in providing independent control of quality-related functions and documentation. The scope of the report covers activities involving nuclear safety-related structures, systems, and components covered by Gibbs and Hill' contractual obligation to the Utility Owner for each project

  14. BWR internals life assurance

    International Nuclear Information System (INIS)

    Herrera, M.L.; Stancavage, P.P.

    1988-01-01

    Boiling water reactor (BWR) internal components play an important role in power plant life extension. Many important internals were not designed for easy removal and changes in material properties and local environmental effects due to high radiation makes stress corrosion cracking more likely and more difficult to correct. Over the past several years, operating experience has shown that inspection, monitoring and refurbishment can be accomplished for internal structures with existing technology. In addition, mitigation techniques which address the causes of degradation are available to assure that life extension targets can be met. This paper describes the many considerations and aspects when evaluating life extension for reactor vessel internals

  15. Quality assurance program requirements (design and construction). Task RS 002-5. Revision 3

    International Nuclear Information System (INIS)

    1985-08-01

    This regulatory guide describes a method acceptable to the NRC staff for complying with regard to establishing and implementing the requisite quality assurance program for the design and construction of nuclear power plants. Guidance for the establishment and execution of quality assurance programs during operation and decommissioning of nuclear power plants have been or will be addressed in separate regulatory guides. Similarly, quality assurance provisions concerning fuel cycle facilities have been or will be addressed in separate regulatory guides

  16. Software Quality Assurance Audits Guidebooks

    Science.gov (United States)

    1990-01-01

    The growth in cost and importance of software to NASA has caused NASA to address the improvement of software development across the agency. One of the products of this program is a series of guidebooks that define a NASA concept of the assurance processes that are used in software development. The Software Assurance Guidebook, NASA-GB-A201, issued in September, 1989, provides an overall picture of the NASA concepts and practices in software assurance. Second level guidebooks focus on specific activities that fall within the software assurance discipline, and provide more detailed information for the manager and/or practitioner. This is the second level Software Quality Assurance Audits Guidebook that describes software quality assurance audits in a way that is compatible with practices at NASA Centers.

  17. Quality assurance records system

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the IAEA Code of Practice on Quality Assurance for Safety in Nuclear Power Plants (IAEA Safety Series No.50-C-QA), which requires that for each nuclear power plant a system for the generation, identification, collection, indexing, filing, storing, maintenance and disposition of quality assurance records shall be established and executed in accordance with written procedures and instructions. The purpose of this Safety Guide is to provide assistance in the establishment and operation of such a system. An orderly established and maintained records system is considered to be part of the means of providing a basis for an appropriate level of confidence that the activities which affect the quality of a nuclear power plant have been performed in accordance with the specific requirements and that the required quality has been achieved and is maintained

  18. Quality assurance and reliability

    International Nuclear Information System (INIS)

    Normand, J.; Charon, M.

    1975-01-01

    Concern for obtaining high-quality products which will function properly when required to do so is nothing new - it is one manifestation of a conscientious attitude to work. However, the complexity and cost of equipment and the consequences of even temporary immobilization are such that it has become necessary to make special arrangements for obtaining high-quality products and examining what one has obtained. Each unit within an enterprise must examine its own work or arrange for it to be examined; a unit whose specific task is quality assurance is responsible for overall checking, but does not relieve other units of their responsibility. Quality assurance is a form of mutual assistance within an enterprise, designed to remove the causes of faults as far as possible. It begins very early in a project and continues through the ordering stage, construction, start-up trials and operation. Quality and hence reliability are the direct result of what is done at all stages of a project. They depend on constant attention to detail, for even a minor piece of poor workmanship can, in the case of an essential item of equipment, give rise to serious operational difficulties

  19. Quality Assurance Framework for Mini-Grids

    Energy Technology Data Exchange (ETDEWEB)

    Esterly, Sean; Baring-Gould, Ian; Booth, Samuel

    2017-05-04

    To address the root challenges of providing quality power to remote consumers through financially viable mini-grids, the Global Lighting and Energy Access Partnership (Global LEAP) initiative of the Clean Energy Ministerial and the U.S. Department of Energy teamed with the National Renewable Energy Laboratory (NREL) and Power Africa to develop a Quality Assurance Framework (QAF) for isolated mini-grids. The framework addresses both alternating current (AC) and direct current (DC) mini-grids, and is applicable to renewable, fossil-fuel, and hybrid systems.

  20. 42 CFR 447.256 - Procedures for CMS action on assurances and State plan amendments.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Procedures for CMS action on assurances and State... for Inpatient Hospital and Long-Term Care Facility Services Payment Rates § 447.256 Procedures for CMS action on assurances and State plan amendments. (a) Criteria for approval. (1) CMS approval action on...

  1. Quality assurance of fuel elements

    International Nuclear Information System (INIS)

    Hoerber, J.

    1980-01-01

    The quality assurance activities for reactor fuel elements are based on a quality assurance system which implies the requirements resulting from the specifications, regulations of the authorities, national standards and international rules and regulations. The quality assurance related to production of reactor fuel will be shown for PWR fuel elements in all typical fabrication steps as conversion into UO 2 -powder, pelletizing, rodmanufacture and assembling. A wide range of destructive and nondestructive techniques is applied. Quality assurance is not only verified by testing techniques but also by process monitoring by means of parameter control in production and testing procedures. (RW)

  2. 24 CFR 232.630 - Assurance of completion.

    Science.gov (United States)

    2010-04-01

    ... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR NURSING HOMES, INTERMEDIATE CARE FACILITIES, BOARD AND CARE HOMES, AND ASSISTED... Fire Safety Equipment Special Requirements § 232.630 Assurance of completion. If the property upon...

  3. Quality Assurance in Services that gives the SSDL of Guatemala

    International Nuclear Information System (INIS)

    Davila Dieguez, L.E.

    2000-01-01

    A brief account of the activities on quality assurance carried out by the Secondary Standard Dosimetry Laboratory, General Directorate of Energy is presented. The activities are reported under facilities and equipment, audit and procedures. Also describes the facilites and equipment of the SSDL of Guatemala

  4. Locally fabricated metal step wedge for quality assurance in ...

    African Journals Online (AJOL)

    The code of safe practice for the use of x-rays in medical diagnosis requires that each x-ray facility has an appropriate quality assurance program in radiation protection, to ensure accurate diagnosis, and to keep doses as low as reasonably achievable. This requires an in-house system of regular checks and procedures.

  5. 41 CFR 101-6.205-4 - Applicability of assurances.

    Science.gov (United States)

    2010-07-01

    ... of higher education, hospital, or any other institution, insofar as the assurance relates to the... benefits to such individuals, shall be applicable to the entire institution. (c) Where an installation or... required under this § 101-6.205 shall be applicable to the entire installation or facility. [29 FR 16287...

  6. Neutron radiography for quality assurance of PHWR fuel pins

    International Nuclear Information System (INIS)

    Chandrasekharan, K.N.; Patil, B.P.; Ghosh, J.K.; Ganguly, C.

    1993-01-01

    Neutron radiography was employed for quality assurance (QA) for advanced PHWR experimental fuel pins containing mixed uranium-plutonium dioxide and thorium-plutonium dioxide pellets. Direct, transfer and track-etch techniques were utilised. The thermal neutron beam facility of APSARA research reactor at Bhabha Atomic Research Centre was used. (author). 5 refs., 16 figs., 2 tabs

  7. Genome sequences of thirty Escherichia coli O157:H7 isolates recovered from a single dairy farm and its associated off-site heifer raising facility

    Science.gov (United States)

    Cattle are the primary reservoir of Escherichia coli O157:H7, the most frequently isolated serotype of enterohemorrhagic E. coli infections among humans in North America. To evaluate the diversity of E. coli O157:H7 isolates within a single dairy herd the genomes of 30 isolates collected over a 7-ye...

  8. The quality assurance program at K & S

    Energy Technology Data Exchange (ETDEWEB)

    Slowey, T.W. [AAPM Accredited Dosimetry Calibration Laboratory, Nashville, TN (United States)

    1993-12-31

    K & S operates the largest and one of the most comprehensive Accredited Dosimetry Calibration Laboratories (ADCLs) in the American Association of Physicists in Medicine (AAPM) secondary laboratory system. It offers calibrations covering energies from Grenz-Ray (0.03-mm Al) to cesium-137 and cobalt-60, brachytherapy source and well chamber calibrations for low-activity sources, and, recently, high-dose-rate iridium-192. The present Quality Assurance (QA) program at K & S began with the AAPM Guidelines for Accreditation (Task Group No. 22 and No. 3, 1989) and grew over the past 10 years to include all aspects of providing a private, self-supporting calibration service from a free-standing independent facility. Some aspects of the QA program were prompted by the requirements of the nuclear power industry while other parts were from national consensus standards or the experiences of staff. Redundancy and teamwork are the most important characteristics of this QA program. K & S has participated in a National Institute of Standards and Technology (NIST) measurement quality assurance (MQA) program since 1982, and, in recent years, an ADCL intralaboratory intercomparison was conducted by Task Group 3 of the Radiation Therapy Committee of the AAPM. One measure of the credibility of a QA program is consistent performance on the MQA program and the ADCL intercomparisons over the past 10 years. An equally important measure of the ability of a program to assure quality results is the frequency of reported errors.

  9. Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP)

  10. The case of sustainability assurance: constructing a new assurance service

    NARCIS (Netherlands)

    O'Dwyer, B.

    2011-01-01

    This paper presents an in-depth longitudinal case study examining the processes through which practitioners in two Big 4 professional services firms have attempted to construct sustainability assurance (independent assurance on sustainability reports). Power’s (1996, 1997, 1999, 2003) theorization

  11. Radioactive wastes. Safety of storage facilities

    International Nuclear Information System (INIS)

    Devillers, Ch.

    2001-01-01

    A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

  12. SU-F-J-52: A Novel Approach to X-Ray Tube Quality Assurance for CBCT Systems in Order to Better Assess the Patient Imaging Dose in a Large, Multi-Unit Treatment Facility

    International Nuclear Information System (INIS)

    Buckley, L; Lambert, C; Nyiri, B; Gerig, L; Webb, R

    2016-01-01

    Purpose: To standardize the tube calibration for Elekta XVI cone beam CT (CBCT) systems in order to provide a meaningful estimate of the daily imaging dose and reduce the variation between units in a large centre with multiple treatment units. Methods: Initial measurements of the output from the CBCT systems were made using a Farmer chamber and standard CTDI phantom. The correlation between the measured CTDI and the tube current was confirmed using an Unfors Xi detector which was then used to perform a tube current calibration on each unit. Results: Initial measurements showed measured tube current variations of up to 25% between units for scans with the same image settings. In order to reasonably estimate the imaging dose, a systematic approach to x-ray generator calibration was adopted to ensure that the imaging dose was consistent across all units at the centre and was adopted as part of the routine quality assurance program. Subsequent measurements show that the variation in measured dose across nine units is on the order of 5%. Conclusion: Increasingly, patients receiving radiation therapy have extended life expectancies and therefore the cumulative dose from daily imaging should not be ignored. In theory, an estimate of imaging dose can be made from the imaging parameters. However, measurements have shown that there are large differences in the x-ray generator calibration as installed at the clinic. Current protocols recommend routine checks of dose to ensure constancy. The present study suggests that in addition to constancy checks on a single machine, a tube current calibration should be performed on every unit to ensure agreement across multiple machines. This is crucial at a large centre with multiple units in order to provide physicians with a meaningful estimate of the daily imaging dose.

  13. SU-F-J-52: A Novel Approach to X-Ray Tube Quality Assurance for CBCT Systems in Order to Better Assess the Patient Imaging Dose in a Large, Multi-Unit Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Buckley, L; Lambert, C; Nyiri, B; Gerig, L [The Ottawa Hospital Cancer Ctr., Ottawa, ON (Canada); Webb, R [Elekta, Montreal, Quebec (Canada)

    2016-06-15

    Purpose: To standardize the tube calibration for Elekta XVI cone beam CT (CBCT) systems in order to provide a meaningful estimate of the daily imaging dose and reduce the variation between units in a large centre with multiple treatment units. Methods: Initial measurements of the output from the CBCT systems were made using a Farmer chamber and standard CTDI phantom. The correlation between the measured CTDI and the tube current was confirmed using an Unfors Xi detector which was then used to perform a tube current calibration on each unit. Results: Initial measurements showed measured tube current variations of up to 25% between units for scans with the same image settings. In order to reasonably estimate the imaging dose, a systematic approach to x-ray generator calibration was adopted to ensure that the imaging dose was consistent across all units at the centre and was adopted as part of the routine quality assurance program. Subsequent measurements show that the variation in measured dose across nine units is on the order of 5%. Conclusion: Increasingly, patients receiving radiation therapy have extended life expectancies and therefore the cumulative dose from daily imaging should not be ignored. In theory, an estimate of imaging dose can be made from the imaging parameters. However, measurements have shown that there are large differences in the x-ray generator calibration as installed at the clinic. Current protocols recommend routine checks of dose to ensure constancy. The present study suggests that in addition to constancy checks on a single machine, a tube current calibration should be performed on every unit to ensure agreement across multiple machines. This is crucial at a large centre with multiple units in order to provide physicians with a meaningful estimate of the daily imaging dose.

  14. Quality assurance for IAEA inspection planning

    International Nuclear Information System (INIS)

    Markin, J.T.

    1986-01-01

    Under the provisions of the Treaty on Nonproliferation of Nuclear Weapons and other agreements with states, the International Atomic Energy Agency (IAEA) conducts inspections at nuclear facilities to confirm that their operation is consistent with the peaceful use of nuclear material. The Department of Safeguards at the IAEA is considering a quality assurance program for activities related to the planning of these facility inspections. In this report, we summarize recent work in writing standards for planning inspections at the types of facilities inspected by the IAEA. The standards specify the sequence of steps in planning inspections, which are: (1) administrative functions, such as arrangements for visas and travel, and communications with the state to confirm facility operating schedules and the state's acceptance of the assigned inspectors; (2) technical functions including a specification of the required inspection activities, determination of personnel and equipment resources, and a schedule for implementing the inspection activities at the facility; and (3) management functions, such as pre- and post-inspection briefings, where the planned and implemented inspection activities are reviewed

  15. Subsurface quality assurance practices

    International Nuclear Information System (INIS)

    1987-08-01

    This report addresses only the concept of applying Nuclear Quality Assurance (NQA) practices to repository shaft and subsurface design and construction; how NQA will be applied; and the level of detail required in the documentation for construction of a shaft and subsurface repository in contrast to the level of detail required in the documentation for construction of a traditional mine. This study determined that NQA practices are viable, attainable, as well as required. The study identified the appropriate NQA criteria and the repository's major structures, systems, items, and activities to which the criteria are applicable. A QA plan, for design and construction, and a list of documentation, for construction, are presented. 7 refs., 1 fig., 18 tabs

  16. Concrete quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    Holz, N. [Harza Engineering Company, Chicago, IL (United States)

    2000-08-01

    This short article reports on progress at the world's largest civil construction project, namely China's Three Gorges hydro project. Work goes on around the clock to put in place nearly 28 M m{sup 3} of concrete. At every stage of the work there is strong emphasis on quality assurance (QA) and concrete is no exception. The US company Harza Engineering has been providing QA since the mid-1980s and concrete QA has been based on international standards. Harza personnel work in the field with supervisors developing educational tools for supervising concrete construction and quality, as well as providing training courses in concrete technology. Some details on flood control, capacity, water quality and environmental aspects are given..

  17. Construction quality assurance report

    International Nuclear Information System (INIS)

    Roscha, V.

    1994-01-01

    This report provides a summary of the construction quality assurance (CQA) observation and test results, including: The results of the geosynthetic and soil materials conformance testing. The observation and testing results associates with the installation of the soil liners. The observation and testing results associated with the installation of the HDPE geomembrane liner systems. The observation and testing results associated with the installation of the leachate collection and removal systems. The observation and testing results associated with the installation of the working surfaces. The observation and testing results associated with in-plant manufacturing process. Summary of submittal reviews by Golder Construction Services, Inc. The submittal and certification of the piping material specifications. The observation and verification associated of the Acceptance Test Procedure results of the operational equipment functions. Summary of the ECNs which are incorporated into the project

  18. Quality assurance in radiation therapy: clinical aspects

    International Nuclear Information System (INIS)

    Souhami, L.

    1984-01-01

    A survey was conducted in Latin America to evaluate the clinical aspects of quality assurance in radiotherapy. A questionnaire was prepared and sent to 46 institutions. Twenty-seven centers (58.5%), from nine countries, answered the questionnaire. The study was divided into three topics: a) patient-related statistics; b) staffing and education; and c) equipment and facilities. Radiotherapy training programs are available in only 37% of the centers studied. A large number of megavoltage units are old, operating at a shorter than optimum distance with sources of very low activity. The number of high energy linear accelerators is unsatisfactory. Problems in treatment planning facilities were also identified. Regionalization of radiation therapy services is recommended as a possible way to improve quality at a reasonable cost

  19. Developing and Implementing a Quality Assurance Strategy for Electroconvulsive Therapy.

    Science.gov (United States)

    Hollingsworth, Jessa; Baliko, Beverly; McKinney, Selina; Rosenquist, Peter

    2018-04-17

    The literature provides scant guidance in effective quality assurance strategies concerning the use of electroconvulsive therapy (ECT) for the treatment of psychiatric conditions. Numerous guidelines are published that provide guidance in the delivery of care; however, little has been done to determine how a program or facility might ensure compliance to best practice for safety, tolerability, and efficacy in performing ECT. The objective of this project was to create a quality assurance strategy specific to ECT. Determining standards for quality care and clarifying facility policy were key outcomes in establishing an effective quality assurance strategy. An audit tool was developed utilizing quality criteria derived from a systematic review of ECT practice guidelines, peer review, and facility policy. All ECT procedures occurring over a 2-month period of May to June 2017 were retrospectively audited and compared against target compliance rates set for the facility's ECT program. Facility policy was adapted to reflect quality standards, and audit findings were used to inform possible practice change initiatives, were used to create benchmarks for continuous quality monitoring, and were integrated into regular hospital quality meetings. Clarification on standards of care and the use of clinical auditing in ECT was an effective starting point in the development of a quality assurance strategy. Audit findings were successfully integrated into the hospital's overall quality program, and recognition of practice compliance informed areas for future quality development and policy revision in this small community-based hospital in the southeastern United States. This project sets the foundation for a quality assurance strategy that can be used to help monitor procedural safety and guide future improvement efforts in delivering ECT. Although it is just the first step in creating meaningful quality improvement, setting clear standards and identifying areas of greatest

  20. Final Hanford Site Transuranic (TRU) Waste Characterization Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP

  1. Recent Trends in Quality Assurance

    Science.gov (United States)

    Amaral, Alberto; Rosa, Maria Joao

    2010-01-01

    In this paper we present a brief description of the evolution of quality assurance in Europe, paying particular attention to its relationship to the rising loss of trust in higher education institutions. We finalise by analysing the role of the European Commission in the setting up of new quality assurance mechanisms that tend to promote…

  2. Quality assurance of operating instructions

    International Nuclear Information System (INIS)

    Asmuss, G.

    1992-01-01

    It is pointed out that the quality assurance at nuclear power stations must be supported by national and international regulations. Quality assurance is explained using the example of the design of a pressurised water reactor. The operating and emergency manuals are discussed and examples for their structure put forward. The significance of updating is emphasised. 15 figs., 19 refs

  3. Project Specific Quality Assurance Plan

    International Nuclear Information System (INIS)

    Pedersen, K.S.

    1995-01-01

    This Quality Assurance Project Plan (QAPP) identifies the Westinghouse Hanford Co. (WHC) Quality Assurance (QA) program requirements for all contractors involved in the planning and execution of the design, construction, testing and inspection of the 200 Area Effluent BAT/AKART Implementation, Project W-291

  4. Printed Circuit Board Quality Assurance

    Science.gov (United States)

    Sood, Bhanu

    2016-01-01

    PCB Assurance Summary: PCB assurance actives are informed by risk in context of the Project. Lessons are being applied across Projects for continuous improvements. Newer component technologies, smaller/high pitch devices: tighter and more demanding PCB designs: Identifying new research areas. New materials, designs, structures and test methods.

  5. R D software quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    Hood, F.C.

    1991-10-01

    Research software quality assurance (QA) requirements must be adequate to strengthen development or modification objectives, but flexible enough not to restrict creativity. Application guidelines are needed for the different kinds of research and development (R D) software activities to assure project objectives are achieved.

  6. Dry Well Storage Facility conceptual design study

    International Nuclear Information System (INIS)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included

  7. Dry Well Storage Facility conceptual design study

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included.

  8. Quality assurance inspections for shipping and storage containers

    Energy Technology Data Exchange (ETDEWEB)

    Stromberg, H.M.; Roberts, G.D.; Bryce, J.H. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1996-04-01

    This is a guide for conducting quality assurance inspections of transportation packaging and dry spent fuel storage system suppliers. (Suppliers are defined as designers, fabricators, distributors, users or owners of those packaging and storage systems.) This guide may be used during inspection to determine regulatory compliance with 10 CFR, Part 71, Subpart H; 10 CFR, Part 72, Subpart G; 10 CFR, Part 21; and supplier`s quality assurance program commitments. It was developed to provide a structured, consistent approach to inspections. The guidance therein provides a framework for evaluation of transportation packaging and dry spent fuel storage systems quality assurance programs. Inspectors are provided with the flexibility to adapt the methods and concepts to meet inspection requirements for the particular facility. The method used in the guide treats each activity at a facility as a separate performance element and combines the activities within the framework of an ``inspection tree.``The method separates each performance element into several areas for inspection and identifies guidelines, based on regulatory requirements, to qualitatively evaluate each area. This guide also serves as a field manual to facilitate quality assurance inspection activities. This guide replaces an earlier one, NUREG/CR-5717 (Packing Supplier Inspection Guide). This replacement guide enhances the inspection activities for transportation packagings and adds the dry spent fuel storage system quality assurance inspection activities.

  9. Quality assurance inspections for shipping and storage containers

    International Nuclear Information System (INIS)

    Stromberg, H.M.; Roberts, G.D.; Bryce, J.H.

    1996-04-01

    This is a guide for conducting quality assurance inspections of transportation packaging and dry spent fuel storage system suppliers. (Suppliers are defined as designers, fabricators, distributors, users or owners of those packaging and storage systems.) This guide may be used during inspection to determine regulatory compliance with 10 CFR, Part 71, Subpart H; 10 CFR, Part 72, Subpart G; 10 CFR, Part 21; and supplier's quality assurance program commitments. It was developed to provide a structured, consistent approach to inspections. The guidance therein provides a framework for evaluation of transportation packaging and dry spent fuel storage systems quality assurance programs. Inspectors are provided with the flexibility to adapt the methods and concepts to meet inspection requirements for the particular facility. The method used in the guide treats each activity at a facility as a separate performance element and combines the activities within the framework of an ''inspection tree.''The method separates each performance element into several areas for inspection and identifies guidelines, based on regulatory requirements, to qualitatively evaluate each area. This guide also serves as a field manual to facilitate quality assurance inspection activities. This guide replaces an earlier one, NUREG/CR-5717 (Packing Supplier Inspection Guide). This replacement guide enhances the inspection activities for transportation packagings and adds the dry spent fuel storage system quality assurance inspection activities

  10. Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of safety-related structures, and components of nuclear power plants. Criterion XVIII, Audits, of Appendix B establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of quality assurance program audit personnel for nuclear power plants

  11. Software quality assurance | News

    Science.gov (United States)

    Financial Officer Finance Section Office of the Chief Operating Officer Facilities Engineering Services Accelerator Division Accelerator Physics Center Office of the Chief Safety Officer Environment, Safety, Health and Quality Section Office of the Chief Project Officer Office of Project Support Services Office of

  12. Nevada Nuclear Waste Storage Investigations: Quality Assurance Plan

    International Nuclear Information System (INIS)

    1980-08-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) were established by DOE/NV to evaluate the geohydrologic setting and underground rock masses of the Nevada Test Site (NTS) and contiguous areas to determine whether a suitable site exists for constructing a repository for isolating highly radioactive solid wastes. Since the results of these evaluations will impact possible risks to public health and safety, a quality assurance program which conforms to the criteria given in the Code of Federal Regulations is needed to control the quality aspects of the work. This Quality Assurance Plan (QAP) describes the general quality assurance program for the overall NNWSI project under which the quality assurance programs of the individual participating organizations and support contractors are to operate. The details of how each of these groups will meet the criteria will differ among participating organizations and support contractors, and those details are given in the QAPP's listed in Appendix A. It is the purpose of this plan to show the commonality of quality assurance programs in effect within the project and to define how each element fits into the entire picture to give total quality assurance coverage for the NNWSI Project

  13. Software Quality Assurance for Nuclear Safety Systems

    International Nuclear Information System (INIS)

    Sparkman, D R; Lagdon, R

    2004-01-01

    The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: (sm b ullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (sm b ullet) Considers the larger system that uses the software and its impacts (sm b ullet) Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

  14. Development of an evaluation method for seismic isolation systems of nuclear power facilities. Seismic design analysis methods for crossover piping system

    International Nuclear Information System (INIS)

    Tai, Koichi; Sasajima, Keisuke; Fukushima, Shunsuke; Takamura, Noriyuki; Onishi, Shigenobu

    2014-01-01

    This paper provides seismic design analysis methods suitable for crossover piping system, which connects between seismic isolated building and non-isolated building in the seismic isolated nuclear power plant. Through the numerical study focused on the main steam crossover piping system, seismic response spectrum analysis applying ISM (Independent Support Motion) method with SRSS combination or CCFS (Cross-oscillator, Cross-Floor response Spectrum) method has found to be quite effective for the seismic design of multiply supported crossover piping system. (author)

  15. Quality assurance program plan for cesium legacy project

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Cesium Legacy Project. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of cask transportation, project related operations within the 324 Building, and waste management as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations, Central Waste Complex Operations, etc.) are covered in other appropriate QAPPs. The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents

  16. Methods of Software Quality Assurance under a Nuclear Quality Assurance Program

    International Nuclear Information System (INIS)

    Kim, Jang Yeol; Lee, Young Jun; Cha, Kyung Ho; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon

    2005-01-01

    This paper addresses a substantial implementation of a software quality assurance under a nuclear quality assurance program. The relationship of the responsibility between a top-level nuclear quality assurance program such as ASME/NQA-1 and its lower level software quality assurance is described. Software quality assurance activities and software quality assurance procedures during the software development life cycle are also described

  17. Assuring the availability of funds for decommissioning nuclear reactors

    International Nuclear Information System (INIS)

    1990-08-01

    The general requirements for applications for license termination and decommissioning nuclear power, research, and test reactors are contained in 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities.'' On June 27, 1988, the Commission published amendments to 10 CFR Part 50 (53 FR 24018) concerning specific criteria for decommissioning nuclear facilities. Amended 10 CFR 50.33(k), 50.75, and 50.82(b) require operating license applicants and existing licensees to submit information on how reasonable assurance will be provided that funds are available to decommission the facility. Amended section 50.75 establishes requirements for indicating how this assurance will be provided, namely the amount of funds that must provided, including updates, and the methods to be used for assuring funds. This regulatory guide has been developed in conjunction with the rule amendments and was published for public comment in May 1989. This version incorporates, where appropriate, the public comments received. Its purpose is to provide guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the NRC staff for complying with requirements in the amended rule regarding the amount of funds for decommissioning. It also provides guidance on the content and form of the financial assurance mechanisms indicated in the rule amendments. 9 refs

  18. Environmental restoration remedial action quality assurance requirements document

    International Nuclear Information System (INIS)

    Cote, R.F.

    1991-01-01

    The environmental Restoration Remedial Action Quality Assurance Requirements Document (DOE/RL 90-28) defines the quality assurance program requirements for the US Department of Energy-Richland Field Office Environmental Restoration Remedial Action Program at the Hanford Site, Richland, Washington. This paper describes the objectives outlined in DOE/RL 90-28. The Environmental Restoration Remedial Action Program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency

  19. Development of a quality assurance system for radiotherapy

    International Nuclear Information System (INIS)

    Vroome, I.H. de; Leer, J.W.H.; Corver, R.

    1997-01-01

    Due to 1996 legislation in the Netherlands, every health care facility should have a quality assurance program. Because it is difficult to measure the quality of the product of care, a choice is made to focus on the process of care. For this purpose PACE was founded. (PACE is a Dutch acronym for Project ACcreditation) with as founding members: Public Health Insurance Council, TNO health research, 4 university hospitals and 4 large general hospitals. For in total 19 services and disciplines quality assurance standards where developed by groups in six of the hospitals. (author)

  20. Quality assurance during site construction

    International Nuclear Information System (INIS)

    Dommke, J.; Jurgutat, H.

    1980-01-01

    During the time of planing and construction of a nuclear power plant, the following proceeding is approved: - the deliverer of a nuclear power plant provides the reports fixing the quality assurance program, it means that he is responsible to write the safety analysis report, the specifications for the erection of the components, the working manuals and specifications for testing (eg nondestr. testing) - the manufacturing of components or systems will be controlled by an own independent quality assurance group, provided that this group was checked by the quality assurance group of the applicant - the TUeV with its independent assessors will fix the requirements relating to quality assurance in its assessment. On this basis the examination of the applicants specifications, working manuals, testing specifications will be done. The efficiency of quality assurance at the manufacturer and at the applicant will be checked by the TUeV specialists by considering specifications of modifications, repairs or tolerances. A mean point of the quality assurance in Germany is the dynamic adjustment, of an action on the latest state of engineering or science. If there exists a change of rules or guidelines, the quality assurance requirements have to be fit on this state in so far as it is feasible from the technical point of view. (orig./RW)

  1. Ballistic quality assurance

    International Nuclear Information System (INIS)

    Cassol, E.; Bonnet, J.; Porcheron, D.; Mazeron, J.J.; Peiffert, D.; Alapetite, C.

    2012-01-01

    This review describes the ballistic quality assurance for stereotactic intracranial irradiation treatments delivered with Gamma Knife R either dedicated or adapted medical linear accelerators. Specific and periodic controls should be performed in order to check the mechanical stability for both irradiation and collimation systems. If this step remains under the responsibility of the medical physicist, it should be done in agreement with the manufacturer's technical support. At this time, there are no recent published guidelines. With technological developments, both frequency and accuracy should be assessed in each institution according to the treatment mode: single versus hypo-fractionated dose, circular collimator versus micro-multi-leaf collimators. In addition, 'end-to-end' techniques are mandatory to find the origin of potential discrepancies and to estimate the global ballistic accuracy of the delivered treatment. Indeed, they include frames, non-invasive immobilization devices, localizers, multimodal imaging for delineation and in-room positioning imaging systems. The final precision that could be reasonably achieved is more or less 1 mm. (authors)

  2. Quality assurance and accreditation.

    Science.gov (United States)

    1997-01-01

    In 1996, the Joint Commission International (JCI), which is a partnership between the Joint Commission on Accreditation of Healthcare Organizations and Quality Healthcare Resources, Inc., became one of the contractors of the Quality Assurance Project (QAP). JCI recognizes the link between accreditation and quality, and uses a collaborative approach to help a country develop national quality standards that will improve patient care, satisfy patient-centered objectives, and serve the interest of all affected parties. The implementation of good standards provides support for the good performance of professionals, introduces new ideas for improvement, enhances the quality of patient care, reduces costs, increases efficiency, strengthens public confidence, improves management, and enhances the involvement of the medical staff. Such good standards are objective and measurable; achievable with current resources; adaptable to different institutions and cultures; and demonstrate autonomy, flexibility, and creativity. The QAP offers the opportunity to approach accreditation through research efforts, training programs, and regulatory processes. QAP work in the area of accreditation has been targeted for Zambia, where the goal is to provide equal access to cost-effective, quality health care; Jordan, where a consensus process for the development of standards, guidelines, and policies has been initiated; and Ecuador, where JCI has been asked to help plan an approach to the evaluation and monitoring of the health care delivery system.

  3. A quality assurance programme for reload fuel for light-water reactors

    International Nuclear Information System (INIS)

    Nilson, R.

    1976-01-01

    The Exxon Nuclear quality assurance programme for the design and fabrication of reload fuel for light-water reactors is described. The programme is based on the 18 quality assurance criteria used for the design and construction of nuclear facilities in the United States of America, but is broadened considerably to reflect other inputs and experiences unique to nuclear fuel production. The government and utility interfaces with the fuel supplier in the area of quality assurance, and future trends, for example, the development of topical quality assurance reports, are also discussed. Quality assurance is discussed in terms of three fundamental categories: management control, engineering assurance and quality control. Examples of specific design, processing and inspection considerations which relate to known fuel failure mechanisms are discussed. The results of irradiated fuel examinations to date have shown that certain fuel failure mechanisms can be alleviated by the considerations described and that fuel of the requisite quality can be consistently produced. (author)

  4. Environmental Test Facility (ETF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Environmental Test Facility (ETF) provides non-isolated shock testing for stand-alone equipment and full size cabinets under MIL-S-901D specifications. The ETF...

  5. Managerial attitude toward quality assurance

    International Nuclear Information System (INIS)

    Kirschenmann, H.J.

    1983-01-01

    This paper will present what relationships exist between the attitude toward quality assurance and the variables of training and experience on the part of managers within the nuclear power industry. Managerial attitude toward quality assurance was measured via questionnaires submitted to managers within architect-engineering, nuclear steam supplier, and constructor firms throughout the United States. The data from the completed questionnaires were statistically analyzed using the chi-square test and conclusions were drawn. Additional study results related to major factors for positive and negative attitudes toward quality assurance will be presented

  6. Quality assurance of polymer concrete

    International Nuclear Information System (INIS)

    Schulz, H.

    1984-01-01

    With polymer concrete, a whole range of organisational and functional measures have to be met in order to assure the required quality with an economic expenditure. Quality assurance begins in the design and does not end in the production, rather includes all fields of the enterprise. The following deals with a particular range of the total complex, the inspection methods for assuring the quality of machine components of polymer concrete, particularly machine tool bases, this being through the control of the raw material, the production and the finished product. (orig.) [de

  7. Review of SKB's Quality Assurance Programme

    International Nuclear Information System (INIS)

    Baldwin, Tamara D.; Hicks, Timothy W.

    2009-06-01

    SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that there is a satisfactory level of assurance that experiments have been carried of with sufficient quality, so that results can be considered to be reliable within the context of their use in safety assessment. SSM has initiated a series of reviews of SKB's methods of quality assurance and their implementation. This project includes reviews of the quality assurance (QA) procedures and instructions that have been prepared for the SR-Site assessment as well as reviews of QA implementation at the canister and buffer/backfill laboratories in Oskarshamn, Sweden. The purpose of this project is to assess SKB's quality assurance with the view of providing a good basis for subsequent quality reviews in the context of future licensing. This has been achieved by examination of a number of SKB experiments using a check list, visits to the relevant facilities, and meetings with contractors and a few members of the SKB staff. Overall, the reviewed set of QA documents and instructions do provide reasonably comprehensive coverage of quality-affecting issues relating to the SR-Site safety assessment and, if implemented correctly, will generate confidence in the reliability of the safety assessment results. The results show that the efforts involving quality assurance are increasing within the SKB programme and in general appear to be satisfactory for ongoing experiments and measurements. However, progress in development of the QA documents and instructions has been relatively recent and it may be difficult for these to be fully implemented in the short period remaining before the planned licence

  8. Radiation shielding quality assurance

    Science.gov (United States)

    Um, Dallsun

    For the radiation shielding quality assurance, the validity and reliability of the neutron transport code MCNP, which is now one of the most widely used radiation shielding analysis codes, were checked with lot of benchmark experiments. And also as a practical example, follows were performed in this thesis. One integral neutron transport experiment to measure the effect of neutron streaming in iron and void was performed with Dog-Legged Void Assembly in Knolls Atomic Power Laboratory in 1991. Neutron flux was measured six different places with the methane detectors and a BF-3 detector. The main purpose of the measurements was to provide benchmark against which various neutron transport calculation tools could be compared. Those data were used in verification of Monte Carlo Neutron & Photon Transport Code, MCNP, with the modeling for that. Experimental results and calculation results were compared in both ways, as the total integrated value of neutron fluxes along neutron energy range from 10 KeV to 2 MeV and as the neutron spectrum along with neutron energy range. Both results are well matched with the statistical error +/-20%. MCNP results were also compared with those of TORT, a three dimensional discrete ordinates code which was developed by Oak Ridge National Laboratory. MCNP results are superior to the TORT results at all detector places except one. This means that MCNP is proved as a very powerful tool for the analysis of neutron transport through iron & air and further it could be used as a powerful tool for the radiation shielding analysis. For one application of the analysis of variance (ANOVA) to neutron and gamma transport problems, uncertainties for the calculated values of critical K were evaluated as in the ANOVA on statistical data.

  9. An overview of quality assurance

    International Nuclear Information System (INIS)

    Morris, I.T.

    1983-01-01

    A good quality assurance program seeks to minimise radiation exposure and maximise image quality. Factors considered are equipment performance, films and screens, film processing, viewing conditions and film repeats

  10. BUILDING "BRIDGES" WITH QUALITY ASSURANCE

    Science.gov (United States)

    The papr describes how, rather than building "bridges" across centuries, quality assurance (QA) personnel have the opportunity to build bridges across technical disciplines, between public and private organizations, and between different QA groups. As reviewers and auditors of a...

  11. QANU - Quality Assurance Netherlands Universities

    DEFF Research Database (Denmark)

    Jensen, Henrik Toft; Maria E., Weber; Vyt, André

    The Quality Assurance Netherlands Universities (QANU) underwent an ENQA-coordinated external review in 2016. The review was chaired by Henrik Toft Jensen, Research fellow at Roskilde University (RUC), Denmark....

  12. Quality assurance in nuclear medicine

    International Nuclear Information System (INIS)

    Kaul, A.

    1986-01-01

    'Quality Assurance in Nuclear Medicine' is the title of the English language original that has been translated into German. The manual very extensively deals with quality control of nuclear medical equipment. Tests are explained for checking radioactivity measuring devices, manual and automatic in-vitro sample measuring systems, in-vivo measuring systems with single or multiple detectors, rectlinear scanners, and gamma cameras, including the phantoms required for the methods. Other chapters discuss the quality control of radiopharmaceuticals, or the quality assurance in data recording and evaluation of results. Helpful comments on the organisation of quality assurance programms are given. The book is intended as a practical guide for introducing quality assurance principles in nuclear medicine in the Federal Republic of Germany. With 13 figs., 22 tabs [de

  13. System management and quality assurance

    International Nuclear Information System (INIS)

    Sastry, A.M.

    1989-01-01

    This paper describes the principles of system management and shows the relationship to quality assurance. It discusses the need for balanced attention to all the project management controls required for project success

  14. Quality Assurance Training Tracking (QATTS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This is metadata documentation for the Quality Assurance Training Tracking System (QATTS) which tracks Quality Assurace training given by R7 QA staff to in-house...

  15. The Italian compliance assurance programme

    International Nuclear Information System (INIS)

    Trivelloni, S.

    1999-01-01

    An overview is given of the compliance assurance programme that is applied in Italy and the role of the different competent authorities that have responsibilities for the transport of radioactive materials is described. (author)

  16. Material quality assurance risk assessment.

    Science.gov (United States)

    2013-01-01

    Over the past two decades the role of SHA has shifted from quality control (QC) of materials and : placement techniques to quality assurance (QA) and acceptance. The role of the Office of Materials : Technology (OMT) has been shifting towards assuran...

  17. Quality assurance within regulatory bodies

    International Nuclear Information System (INIS)

    1999-06-01

    The IAEA directed extensive efforts during the years 1991 to 1995 to the integral revision of all NUSS quality assurance publications, which were approved and issued as Safety Series No.50-C/SG-Q, Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations (1996). When these quality assurance publications were developed, their prime focus was on requirements against which work performed by the licensees could be measured and assessed by the regulatory bodies. In this way, they only helped to facilitate the functions of regulators. No requirements or recommendations were provided on how the regulators should ensure the effective implementation of their own activities. The present publication is a first attempt to collect, integrate and offer available experience to directly support performance of regulatory activities. It presents a comprehensive compilation on the application of quality assurance principles and methods by regulatory bodies to their activities. The aim is consistent good performance of regulatory activities through a systematic approach

  18. Hanford analytical services quality assurance plan. Revision 1

    International Nuclear Information System (INIS)

    1995-02-01

    This document, the Hanford Analytical Services Quality Assurance Plan (HASQAP), is issued by the U.S. Department of Energy, Richland Operations Office (RL). The HASQAP establishes quality requirements in response to U.S. Department of Energy (DOE) Order 5700.6C, Quality Assurance (10 CFR 830.120, open-quotes Quality Assurance Requirementsclose quotes). The HASQAP is designed to meet the needs of the RL for controlling the of analytical chemistry services provided by laboratory operations. The HASQAP is issued through the Analytical Services Branch of the Waste Management Division. The Analytical Services Branch is designated by the RL as having the responsibility for oversight management of laboratory operations under the Waste Management Division. The laboratories conduct sample analyses under several regulatory statutes, such as the Clean Air Act and the Clean Water Act. Sample analysis in support of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) is a major role of the laboratory operations

  19. Quality assurance considerations for nuclear power system selection

    International Nuclear Information System (INIS)

    Bender, M.

    1977-01-01

    The key quality assurance principle to be applied in nuclear system selection is to establish that the technological basis is understood and used properly. Knowledgeable and capable personnel with experience in the application are needed, and they must have access to appropriate engineering, laboratory, and manufacturing facilities. A suitable balance must be maintained between the responsibilities of the seller-supplier and the purchaser-owner to assure an even-handed treatment of the implementation program. Safety and reliability must be inherent to the regulatory framework. There must be flexibility in the purchaser-owner resources to overcome unanticipated adversity. Given these quality assurance elements, the nuclear system selection process should result in a high probability that the performance objectives will be satisfied

  20. Quality assurance and accreditation of engineering education in Jordan

    Science.gov (United States)

    Aqlan, Faisal; Al-Araidah, Omar; Al-Hawari, Tarek

    2010-06-01

    This paper provides a study of the quality assurance and accreditation in the Jordanian higher education sector and focuses mainly on engineering education. It presents engineering education, accreditation and quality assurance in Jordan and considers the Jordan University of Science and Technology (JUST) for a case study. The study highlights the efforts undertaken by the faculty of engineering at JUST concerning quality assurance and accreditation. Three engineering departments were accorded substantial equivalency status by the Accreditation Board of Engineering and Technology in 2009. Various measures of quality improvement, including curricula development, laboratories improvement, computer facilities, e-learning, and other supporting services are also discussed. Further assessment of the current situation is made through two surveys, targeting engineering instructors and students. Finally, the paper draws conclusions and proposes recommendations to enhance the quality of engineering education at JUST and other Jordanian educational institutions.

  1. Quality assurance in plant engineering

    International Nuclear Information System (INIS)

    Ohsumi, Morimichi

    1977-01-01

    Quality assurance is defined as the intentional and systematic activity carried out to obtain such reliability that the functions of nuclear power generating plants are demonstrated during the plant operation, and the section in charge has the role to organize, adjust and communicate so that the related sections can work smoothly. There are many documents concerning the quality assurance, such as quality assurance basic program, quality assurance manual, quality control plan and its manual and many specifications, etc. The content of the quality assurance is different for every step of plant planning such as at inquiry and order receiving, and prior to manufacturing, for example, inspection specification being decided for the material and the welded parts of classified pipings at the step of order receiving. Document management, engineering schedule and the custody of quality records are also quality assurance activities. Design management is controlled step by step; plant planning including safety analysis, overall layout plan, conceptual design of buildings, aseismatic design guide, heat balance and so on, system design mainly with system description, piping design including piping specification, standard dimensions of edge preparation, piping and valve lists, inspection manual, etc., detailed design, standardization of piping and design review, etc. are explained. The management of the intermediate between soft and hard parts consists of the quality check for material manufacturers and shipment inspection, etc. (Nakai, Y.)

  2. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  3. Optimization of single plate-serial dilution spotting (SP-SDS) with sample anchoring as an assured method for bacterial and yeast cfu enumeration and single colony isolation from diverse samples.

    Science.gov (United States)

    Thomas, Pious; Sekhar, Aparna C; Upreti, Reshmi; Mujawar, Mohammad M; Pasha, Sadiq S

    2015-12-01

    We propose a simple technique for bacterial and yeast cfu estimations from diverse samples with no prior idea of viable counts, designated as single plate-serial dilution spotting (SP-SDS) with the prime recommendation of sample anchoring (10 0 stocks). For pure cultures, serial dilutions were prepared from 0.1 OD (10 0 ) stock and 20 μl aliquots of six dilutions (10 1 -10 6 ) were applied as 10-15 micro-drops in six sectors over agar-gelled medium in 9-cm plates. For liquid samples 10 0 -10 5 dilutions, and for colloidal suspensions and solid samples (10% w/v), 10 1 -10 6 dilutions were used. Following incubation, at least one dilution level yielded 6-60 cfu per sector comparable to the standard method involving 100 μl samples. Tested on diverse bacteria, composite samples and Saccharomyces cerevisiae , SP-SDS offered wider applicability over alternative methods like drop-plating and track-dilution for cfu estimation, single colony isolation and culture purity testing, particularly suiting low resource settings.

  4. Waste Isolation Pilot Plant Safety Analysis Report

    International Nuclear Information System (INIS)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

  5. Waste Isolation Pilot Plant Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  6. Measurement quality assurance for radioassay laboratories

    International Nuclear Information System (INIS)

    McCurdy, D.E.

    1993-01-01

    Until recently, the quality of U.S. radioassay laboratory services has been evaluated by a limited number of governmental measurement assurance programs (MAPs). The major programs have been limited to the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA) and the U.S. Nuclear Regulatory Commission (NRC). In 1988, an industry MAP was established for the nuclear power utility industry through the U.S. Council for Energy Awareness/National Institute of Standards and Technology (USCEA/NIST). This program functions as both a MAP for utility laboratories and/or their commercial contractor laboratories, and as a traceability program for the U.S. radioactive source manufacturers and the utility laboratories. Each of these generic MAPs has been initiated and is maintained to serve the specific needs of the sponsoring agency or organization. As a result, there is diversification in their approach, scope, requirements, and degree of traceability to NIST. In 1987, a writing committee was formed under the American National Standards Institute (ANSI) N42.2 committee to develop a standard to serve as the basis document for the creation of a national measurement quality assurance (MQA) program for radioassay laboratories in the U.S. The standard is entitled, open-quotes Measurement Quality Assurance For Radioassay Laboratories.open-quotes The document was developed to serve as a guide for MQA programs maintained for the specialized sectors of the radioassay community, such as bioassay, routine environmental monitoring, environmental restoration and waste management, radiopharmaceuticals, and nuclear facilities. It was the intent of the writing committee to develop a guidance document that could be utilized to establish a laboratory's specific data quality objectives (DQOs) that govern the operational requirements of the radioassay process, including mandated protocols and recommendations

  7. Measurement quality assurance for radioassay laboratories

    Energy Technology Data Exchange (ETDEWEB)

    McCurdy, D.E. [Yankee Atomic Environmental Laboratory, Boston, MA (United States)

    1993-12-31

    Until recently, the quality of U.S. radioassay laboratory services has been evaluated by a limited number of governmental measurement assurance programs (MAPs). The major programs have been limited to the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA) and the U.S. Nuclear Regulatory Commission (NRC). In 1988, an industry MAP was established for the nuclear power utility industry through the U.S. Council for Energy Awareness/National Institute of Standards and Technology (USCEA/NIST). This program functions as both a MAP for utility laboratories and/or their commercial contractor laboratories, and as a traceability program for the U.S. radioactive source manufacturers and the utility laboratories. Each of these generic MAPs has been initiated and is maintained to serve the specific needs of the sponsoring agency or organization. As a result, there is diversification in their approach, scope, requirements, and degree of traceability to NIST. In 1987, a writing committee was formed under the American National Standards Institute (ANSI) N42.2 committee to develop a standard to serve as the basis document for the creation of a national measurement quality assurance (MQA) program for radioassay laboratories in the U.S. The standard is entitled, {open_quotes}Measurement Quality Assurance For Radioassay Laboratories.{open_quotes} The document was developed to serve as a guide for MQA programs maintained for the specialized sectors of the radioassay community, such as bioassay, routine environmental monitoring, environmental restoration and waste management, radiopharmaceuticals, and nuclear facilities. It was the intent of the writing committee to develop a guidance document that could be utilized to establish a laboratory`s specific data quality objectives (DQOs) that govern the operational requirements of the radioassay process, including mandated protocols and recommendations.

  8. Thoughts on Internal and External Quality Assurance

    Science.gov (United States)

    Zhang, Jianxin

    2012-01-01

    Quality assurance of higher education is made up of two parts: internal quality assurance (IQA) and external quality assurance (EQA). Both belong to a union of the coexistence and balance of yin and yang. But in reality there exists a paradox of "confusion of quality assurance (QA) subject consciousness, singularity of social QA and lack of QA…

  9. 10 CFR 71.37 - Quality assurance.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance. 71.37 Section 71.37 Energy NUCLEAR... Package Approval § 71.37 Quality assurance. (a) The applicant shall describe the quality assurance program... quality assurance program that are applicable to the particular package design under consideration...

  10. Health equity monitoring for healthcare quality assurance.

    Science.gov (United States)

    Cookson, R; Asaria, M; Ali, S; Shaw, R; Doran, T; Goldblatt, P

    2018-02-01

    Population-wide health equity monitoring remains isolated from mainstream healthcare quality assurance. As a result, healthcare organizations remain ill-informed about the health equity impacts of their decisions - despite becoming increasingly well-informed about quality of care for the average patient. We present a new and improved analytical approach to integrating health equity into mainstream healthcare quality assurance, illustrate how this approach has been applied in the English National Health Service, and discuss how it could be applied in other countries. We illustrate the approach using a key quality indicator that is widely used to assess how well healthcare is co-ordinated between primary, community and acute settings: emergency inpatient hospital admissions for ambulatory care sensitive chronic conditions ("potentially avoidable emergency admissions", for short). Whole-population data for 2015 on potentially avoidable emergency admissions in England were linked with neighborhood deprivation indices. Inequality within the populations served by 209 clinical commissioning groups (CCGs: care purchasing organizations with mean population 272,000) was compared against two benchmarks - national inequality and inequality within ten similar populations - using neighborhood-level models to simulate the gap in indirectly standardized admissions between most and least deprived neighborhoods. The modelled inequality gap for England was 927 potentially avoidable emergency admissions per 100,000 people, implying 263,894 excess hospitalizations associated with inequality. Against this national benchmark, 17% of CCGs had significantly worse-than-benchmark equity, and 23% significantly better. The corresponding figures were 11% and 12% respectively against the similar populations benchmark. Deprivation-related inequality in potentially avoidable emergency admissions varies substantially between English CCGs serving similar populations, beyond expected statistical

  11. Code on the safety of nuclear power plants: Quality assurance

    International Nuclear Information System (INIS)

    1988-01-01

    This revised Code provides the principles and objectives for the establishment and implementation of quality assurance programmes applied to both the overall and each of the constituent activities associated with a nuclear power plant project. The quality assurance principles enumerated in the present Code can be usefully applied to nuclear facilities other than nuclear power plants. The quality assurance programme encompasses: (1) the activities that are necessary to achieve the appropriate quality of the respective item or service; and (2) the activities that are necessary for verifying that the required quality is achieved and that objective evidence is produced to that effect. Quality assurance is an essential aspect of good management and the quality assurance programme is the main management tool for a disciplined approach to all activities affecting quality, including, where appropriate, verification that each task has been satisfactorily performed and that necessary corrective actions have been implemented. The principles and objectives provided by the Code are applicable by all those responsible for the nuclear power plant, by plant designers, suppliers, architect-engineers, plant constructors, plant operators and other organizations participating in activities affecting quality. The Code is a revision of the previous Code of Practice (1978) on the same subject of interest to regulatory bodies and experts in quality assurance for design, siting and operation of nuclear power plants. Contents: Definitions; 1. Introduction; 2. Quality assurance programmes; 3. Organization; 4. Document control; 5. Design control; 6. Procurement control; 7. Control of items; 8. Process control; 9. Inspection and test control; 10. Non-conformance control; 11. Corrective actions; 12, Records; 13. Audits

  12. NIF Projects Controls and Information Systems Software Quality Assurance Plan

    Energy Technology Data Exchange (ETDEWEB)

    Fishler, B

    2011-03-18

    Quality achievement for the National Ignition Facility (NIF) and the National Ignition Campaign (NIC) is the responsibility of the NIF Projects line organization as described in the NIF and Photon Science Directorate Quality Assurance Plan (NIF QA Plan). This Software Quality Assurance Plan (SQAP) is subordinate to the NIF QA Plan and establishes quality assurance (QA) activities for the software subsystems within Controls and Information Systems (CIS). This SQAP implements an activity level software quality assurance plan for NIF Projects as required by the LLNL Institutional Software Quality Assurance Program (ISQAP). Planned QA activities help achieve, assess, and maintain appropriate quality of software developed and/or acquired for control systems, shot data systems, laser performance modeling systems, business applications, industrial control and safety systems, and information technology systems. The objective of this SQAP is to ensure that appropriate controls are developed and implemented for management planning, work execution, and quality assessment of the CIS organization's software activities. The CIS line organization places special QA emphasis on rigorous configuration control, change management, testing, and issue tracking to help achieve its quality goals.

  13. Mixed Waste Integrated Program Quality Assurance requirements plan

    International Nuclear Information System (INIS)

    1994-01-01

    Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities

  14. Implementation guide for Hanford Analytical Services Quality Assurance Plan

    International Nuclear Information System (INIS)

    1994-09-01

    This implementation guide for the Hanford Analytical Services Quality Assurance Plan (HASQAP) was developed by the US Department of Energy, Richland Operations Office (RL) Waste Management Division, Analytical Services Branch. This plan formally presents RL's direction for Hanford Sitewide implementation of the HASQAP. The HASQAP establishes a uniform standard for quality requirements to meet US Department of Energy Order 5700.6C, Quality Assurance (10 CFR 830.120, ''Quality Assurance Requirements''), and is intended to satisfy the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) requirements for ''Guidance on Preparation of Laboratory Quality Assurance Plans''. The quality assurance criteria specified in the HASQAP shall serve as a baseline for implementing quality management systems for the laboratories that provide analytical services, for data requesters and users, and for oversight organizations that monitor the data-generation process. Affected organizations shall implement the HASQAP requirements that are applicable to their work scope. Full implementation of the HASQAP is scheduled to occur by August 1995. RL will work with the US Environmental Protection Agency (EPA) and Washington State Department of Ecology (Ecology) to have the HASQAP document incorporated into Appendix F of the Tri-Party Agreement by early Fiscal Year 1996

  15. Mixed Waste Integrated Program Quality Assurance requirements plan

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-15

    Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities.

  16. NIF Projects Controls and Information Systems Software Quality Assurance Plan

    International Nuclear Information System (INIS)

    Fishler, B.

    2011-01-01

    Quality achievement for the National Ignition Facility (NIF) and the National Ignition Campaign (NIC) is the responsibility of the NIF Projects line organization as described in the NIF and Photon Science Directorate Quality Assurance Plan (NIF QA Plan). This Software Quality Assurance Plan (SQAP) is subordinate to the NIF QA Plan and establishes quality assurance (QA) activities for the software subsystems within Controls and Information Systems (CIS). This SQAP implements an activity level software quality assurance plan for NIF Projects as required by the LLNL Institutional Software Quality Assurance Program (ISQAP). Planned QA activities help achieve, assess, and maintain appropriate quality of software developed and/or acquired for control systems, shot data systems, laser performance modeling systems, business applications, industrial control and safety systems, and information technology systems. The objective of this SQAP is to ensure that appropriate controls are developed and implemented for management planning, work execution, and quality assessment of the CIS organization's software activities. The CIS line organization places special QA emphasis on rigorous configuration control, change management, testing, and issue tracking to help achieve its quality goals.

  17. DOE's Assurance Program for Remedial Action (APRA)

    International Nuclear Information System (INIS)

    Denham, D.H.; Stenner, R.D.; Welty, C.G. Jr.; Needels, T.S.

    1985-01-01

    The US Department of Energy's (DOE) Office of Operational Safety (OOS) is presently developing and implementing the Assurance Program for Remedial Action (APRA) to overview DOE's Remedial Action programs. APRA's objective is to ensure the adequacy of environmental, safety and health (ES and H) protection practices within the four DOE Remedial Action programs: Grand Junction Remedial Action Program (GJRAP), Uranium Mill Tailings Remedial Action Program (UMTRAP), Formerly Utilized Sites Remedial Action Program (FUSRAP), and Surplus Facilities Management Program (SFMP). APRA encompasses all ES and H practices of DOE and its contractors/subcontractors within the four Remedial Action programs. Specific activities of APRA include document reviews, selected site visits, and program office appraisals. Technical support and assistance to OOS is being provided by APRA contractors in the evaluation of radiological standards and criteria, quality assurance measures, radiation measurements, and risk assessment practices. This paper provides an overview of these activities and discusses program to date, including the roles of OOS and the respective contractors. The contractors involved in providing technical support and assistance to OOS are Aerospace Corporation, Oak Ridge Associated Universities, and Pacific Northwest Laboratory

  18. DOE's Assurance Program for Remedial Action (APRA)

    International Nuclear Information System (INIS)

    Denham, D.H.; Stenner, R.D.; Welty, C.G. Jr.; Needels, T.S.

    1984-10-01

    The US Department of Energy's (DOE) Office of Operational Safety (OOS) is presently developing and implementing the Assurance Program for Remedial Action (APRA) to overview DOE's Remedial Action programs. APRA's objective is to ensure the adequacy of environmental, safety and health (ES and H) protection practices within the four DOE Remedial Action programs: Grand Junction Remedial Action Program (GJRAP), Uranium Mill Tailings Remedial Action Program (UMTRAP), Formerly Utilized Sites Remedial Action Program (FUSRAP), and Surplus Facilities Management Program (SFMP). APRA encompasses all ES and H practices of DOE and its contractors/subcontractors within the four Remedial Action programs. Specific activities of APRA include document reviews, selected site visits, and program office appraisals. Technical support and assistance to OOS is being provided by APRA contractors in the evaluation of radiological standards and criteria, quality assurance measures, radiation measurements, and risk assessment practices. This paper provides an overview of these activities and discusses progress to date, including the roles of OOS and the respective contractors. The contractors involved in providing technical support and assistance to OOS are Aerospace Corporation, Oak Ridge Associated Universities, and Pacific Northwest Laboratory

  19. General rules applicable to quality assurance

    International Nuclear Information System (INIS)

    1981-11-01

    RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this rule is to define a series of measures to meet these general regulatory equipments. By applying this rule, the quality assurance code of practice for nuclear power plant safety, established by the International Atomic Energy Agency (I.A.E.A.), is considered to be observed

  20. Management services, quality assurance, and safety

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Broad technical and administrative support for the programmatic research and development activities of the Fusion Energy Division is provided by the Management Services Section and by the division's quality assurance (QA) and safety programs. Support is provided through effective communication with division programmatic staff and through the coordination of resources from disciplines outside the division. The QA activity in the division emphasizes the development and documentation of a QA program that conforms to national standards, the review and approval of engineering documents, supplier surveillance, identification and documentation of nonconforming items, audits, and QA assessments/plans. The division's safety activities include a formal safety program, emergency planning activities, and environmental protection services. Efforts devoted to the removal of hazardous wastes from division facilities were expanded during 1986

  1. 242-A Evaporator quality assurance plan. Revision 2

    International Nuclear Information System (INIS)

    Basra, T.S.

    1995-01-01

    The purpose of this quality assurance project plan (Plan) is to provide requirements for activities pertaining to sampling, shipping, and analyses associated with candidate feed tank samples for the 242-A Evaporator project. The purpose of the 242-A Evaporator project is to reduce the volume of aqueous waste in the Double Shell Tank (DST) System and will result in considerable savings to the disposal of mixed waste. The 242-A Evaporator feed stream originates from DSTs identified as candidate feed tanks. The 242-A Evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending the condensate (called process condensate) to the Liquid Effluent Retention Facility (LEPF) storage basin where it is stored prior to treatment in the Effluent Treatment Facility (ETF). The objective of this quality assurance project plan is to provide the planning, implementation, and assessment of sample collection and analysis, data issuance, and validation activities for the candidate feed tanks

  2. Quality assurance handbook for measurement laboratories

    International Nuclear Information System (INIS)

    Delvin, W.L.

    1984-10-01

    This handbook provides guidance in the application of quality assurance to measurement activities. It is intended to help those persons making measurements in applying quality assurance to their work activities by showing how laboratory practices and quality assurance requirements are integrated to provide control within those activities. The use of the guidance found in this handbook should help provide consistency in the interpretation of quality assurance requirements across all types of measurement laboratories. This handbook also can assist quality assurance personnel in understanding the relationships between laboratory practices and quality assurance requirements. The handbook is composed of three chapters and several appendices. Basic guidance is provided by the three chapters. In Chapter 1, the role of quality assurance in obtaining quality data and the importance of such data are discussed. Chapter 2 presents the elements of laboratory quality assurance in terms of practices that can be used in controlling work activities to assure the acquisition of quality data. Chapter 3 discusses the implementation of laboratory quality assurance. The appendices provide supplemental information to give the users a better understanding of the following: what is quality assurance; why quality assurance is required; where quality assurance requirements come from; how those requirements are interpreted for application to laboratory operations; how the elements of laboratory quality assurance relate to various laboratory activities; and how a quality assurance program can be developed

  3. Concepts of nuclear quality assurance

    International Nuclear Information System (INIS)

    Randers, G.; Morris, P.A.; Pomeroy, D.

    1976-01-01

    While the safety record of the nuclear industry continues to be excellent, the forced outage rates for recent years continue to be 15% or more. Quality assurance, therefore, needs to be applied not only to nuclear safety matters, but to the goals of increased productivity and reduced construction and operating costs. Broadening the application of the general concept of quality assurance in this way leads to the introduction of reliability technology. The total activity might better be called reliability assurance. That effective quality assurance systems do pay off is described by examples from the utility industry, from a manufacturer of instruments and systems and from the experience of Westinghouse Electric Company's manufacturing divisions. The special situation of applying quality assurance to nuclear fuel is discussed. Problems include the lack of a fully developed regulatory policy in this area, incomplete understanding of the mechanism for pellet-clad interaction failures, incomplete access to manufacturers design and process information, inability to make desirable changes on a timely basis and inadequate feedback of irradiation experience. (author)

  4. Qualtity assurance in nuclear technology

    International Nuclear Information System (INIS)

    Roesler, U.

    1977-01-01

    The demand for safety in nuclear power plants is rooted in the Atomic Energy Act of the Federal Republic of Germany, under which 'preplanned safety' is a licensing condition. Moreover, the safety of nuclear power plants is outlined in more precise terms in the guidelines of the German Advisory Committee for Reactor Safeguards (Reaktorsicherheitskommission). The usual approach taken in this country, i.e., to establish quality assurance for each specific product, with supplementary quality assurance measures geared to systems requirements being implemented by industry, has proved to work satisfactorily. Product-based quality assurance mainly stems from the classical quality control concept, whereas systems-based quality assurance primarily is to ensure that both manufacturers and systems suppliers take all measures in advance which are needed for the satisfactory processing of an order and to achieve the quality level required. The special features and the advantages of the joint action of manufacturers, systems suppliers and experts, which are characteristic of the German approach, very clearly emerge from a comparison with practices in the United States. In the further refinement of the quality assurance concept as practised in Germany, qhich will have a particularly great impact on costs and schedules because of the manpower requirement involved, it should be carefully weighed where there are exaggerations and unnecessary complications which can no longer be justified by the demand for more safety. (orig.) [de

  5. Waste Management Quality Assurance Plan

    International Nuclear Information System (INIS)

    1993-01-01

    Lawrence Berkeley Laboratory's Environment Department addresses its responsibilities through activities in a variety of areas. The need for a comprehensive management control system for these activities has been identified by the Department of Energy (DOE). The WM QA (Waste Management Quality Assurance) Plan is an integral part of a management system that provides controls necessary to ensure that the department's activities are planned, performed, documented, and verified. This WM QA Plan defines the requirements of the WM QA program. These requirements are derived from DOE Order 5700.6C, Quality Assurance, the LBL Operating and Assurance Program Plan (OAP, LBL PUB-3111), and other environmental compliance documents applicable to WM activities. The requirements presented herein, as well as the procedures and methodologies that direct the implementation of these requirements, will undergo review and revisions as necessary. The provisions of this QA Plan and its implementing documents apply to quality-affecting activities performed by and for WM. It is also applicable to WM contractors, vendors, and other LBL organizations associated with WM activities, except where such contractors, vendors, or organizations are governed by their own WM-approved QA programs. References used in the preparation of this document are (1) ASME NQA-1-1989, (2) ANSI/ASQC E4 (Draft), (3) Waste Management Quality Assurance Implementing Management Plan (LBL PUB-5352, Rev. 1), (4) LBL Operating and Assurance Program Plan (OAP), LBL PUB-3111, 2/3/93. A list of terms and definitions used throughout this document is included as Appendix A

  6. A Test Setup for Quality Assurance of Front End Hybrids

    CERN Document Server

    Axer, Markus; Camps, Clemens; Commichau, Volker; Flügge, Günter; Franke, Torsten; Hangarter, Klaus; Ilgin, Can; Mnich, Joachim; Niehusmann, Jan; Poettgens, Michael; Schorn, Peter; Schulte, Reiner; Struczinski, Wolfgang

    2001-01-01

    The APV Readout Control (ARC) Test Setup is a compact, cost efficient test and diagnostic tool which is suited for full operation and characterisation of FE hybrids and Si-Detector modules. This note gives an overview of the construction and the features of the test facility. Based on the ARC setup and the experience gained with one prototype FE hybrid, possible quality assurance scenarios for short and long term tests of FE hybrids are also presented.

  7. Quality assurance in nuclear medicine

    International Nuclear Information System (INIS)

    Paras, P.

    1978-01-01

    Quality assurance practices must be followed throughout the entire nuclear medicine process, from the initial decision to perform a particular procedure, through the interpretation and reporting of the results. The various parameters that can be defined and measured in each area must be monitored by quality control tests to assure the excellence of the total nuclear medicine process. The presentation will discuss each of the major areas of nuclear medicine quality control and their interaction as a part of the entire system. Quality control testing results and recommendations for measurements of radioactivity distribution will be described with emphasis on imaging equipment and dose calibrating instrumentation. The role of the health physicist in a quality assurance program will be stressed. (author)

  8. Modernization of software quality assurance

    Science.gov (United States)

    Bhaumik, Gokul

    1988-01-01

    The customers satisfaction depends not only on functional performance, it also depends on the quality characteristics of the software products. An examination of this quality aspect of software products will provide a clear, well defined framework for quality assurance functions, which improve the life-cycle activities of software development. Software developers must be aware of the following aspects which have been expressed by many quality experts: quality cannot be added on; the level of quality built into a program is a function of the quality attributes employed during the development process; and finally, quality must be managed. These concepts have guided our development of the following definition for a Software Quality Assurance function: Software Quality Assurance is a formal, planned approach of actions designed to evaluate the degree of an identifiable set of quality attributes present in all software systems and their products. This paper is an explanation of how this definition was developed and how it is used.

  9. Grading of quality assurance requirements

    International Nuclear Information System (INIS)

    1991-01-01

    The present Manual provides guidance and illustrative examples for applying a method by which graded quality assurance requirements may be determined and adapted to the items and services of a nuclear power plant in conformance with the requirements of the IAEA Nuclear Safety Standards (NUSS) Code and Safety Guides on quality assurance. The Manual replaces the previous publication IAEA-TECDOC-303 on the same subject. Various methods of grading quality assurance are available in a number of Member States. During the development of the present Manual it was not considered practical to attempt to resolve the differences between those methods and it was preferred to identify and benefit from the good practices available in all the methods. The method presented in this Manual deals with the aspects of management, documentation, control, verification and administration which affect quality. 1 fig., 4 tabs

  10. Balancing compliance and cost when implementing a Quality Assurance program

    International Nuclear Information System (INIS)

    Pickering, S.Y.

    1997-12-01

    When implementing a Quality Assurance (QA) program, compliance and cost must be balanced. A QA program must be developed that hits the mark in terms of adequate control and documentation, but does not unnecessarily expand resources. As the Waste Isolation Pilot Plant (WIPP) has moved towards certification, Sandia National Laboratories has learned much about balancing compliance and costs. Some of these lessons are summarized here

  11. Quality assurance programs at the PNL calibrations laboratory

    International Nuclear Information System (INIS)

    Piper, R.K.; McDonald, J.C.; Fox, R.A.; Eichner, F.N.

    1993-03-01

    The calibrations laboratory at Pacific Northwest Laboratory (PNL) serves as a radiological standardization facility for personnel and environmental dosimetry and radiological survey instruments. As part of this function, the calibrations laboratory must maintain radiological reference fields with calibrations traceable to the National Institute of Standards and Technology (NIST). This task is accomplished by a combination of (1) sources or reference instruments calibrated at or by NIST, (2) measurement quality assurance (MQA) interactions with NIST, and (3) rigorous internal annual and quarterly calibration verifications. This paper describes a representative sample of the facilities, sources, and actions used to maintain accurate and traceable fields

  12. Quality assurance in medical laboratories

    International Nuclear Information System (INIS)

    Boroviczeny, K.G. von; Merten, R.; Merten, U.P.

    1987-01-01

    The book presents a comprehensive and specified survey of the quality assurance measures and methods applied in medical laboratories in the pre-analytical phase and in the analytical and post-analytical phases. It also gives information on computer-aided procedures, cost-benefit analyses in this field, and on official requirements and standards in the fields of clinical chemistry, hematology, immunology and microbiology, and equipment testing and inspection. One chapter of the book particularly deals with quality assurance for radioimmunological in-vitro analyses. With 112 figs., 337 tabs [de

  13. Quality assurance in radiation processing

    International Nuclear Information System (INIS)

    Noriah Mod Ali

    2002-01-01

    The growth of the radiation processing industries in Malaysia has presented the SSDL-MINT a new set of parameter for the Quality Assurance (QA) programs. The large massive doses of radiation required for commercial application of sterilization, cross-linking etc needs measurement method outside the scope of familiar radiation detection instruments. This requires establishment of proper calibration procedure and selection of appropriate transfer system/technique to assure adequate traceability to an international radiation standard. The benefit of accurate in-plant dosimetry for the operator, approving authority and purchaser are balanced against the extra dosimetric efforts required for good QA is presented. (Author)

  14. The challenge of quality assurance

    International Nuclear Information System (INIS)

    Simon, R.; Krischer, W.; Price, M.S.T.

    1986-01-01

    The paper presents the aims of quality assurance in the design and production of radioactive waste packages. It lists the most relevant acceptance criteria and regulatory requirements, investigates the institutional and technical problems of carrying out Quality Assurance and presents suggestions for establishing suitable organisational structures and technical programmes to provide adequate confidence in the safe nature and the performance of waste packages. The Commission of European Communities has laid emphasis on the development of appropriate test methods in its last research and development programme. First results of the work are reviewed in the context of international progress in this field. (author)

  15. Quality assurance of qualitative analysis

    DEFF Research Database (Denmark)

    Ríos, Ángel; Barceló, Damiá; Buydens, Lutgarde

    2003-01-01

    The European Commission has supported the G6MA-CT-2000-01012 project on "Metrology of Qualitative Chemical Analysis" (MEQUALAN), which was developed during 2000-2002. The final result is a document produced by a group of scientists with expertise in different areas of chemical analysis, metrology...... and quality assurance. One important part of this document deals, therefore, with aspects involved in analytical quality assurance of qualitative analysis. This article shows the main conclusions reported in the document referring to the implementation of quality principles in qualitative analysis...

  16. Review of the ISOL Method

    CERN Document Server

    Lindroos, M

    2004-01-01

    The ISOL technique was invented in Copenhagen over 50 years ago and eventually migrated to CERN where a suitable proton drive beam was available at the Syncho-Cyclotron. The quick spread of the technique from CERN to many other laboratories has resulted in a large user community, which has assured the continued development of the method, physics in the front-line of fundamental research and the application of the method to many applied sciences. The technique is today established as one of the main techniques for on-line isotope production of high intensity and high quality beams. The thick targets used allows the production of unmatched high intensity radioactive beams. The fact that the ions are produced at rest makes it ideally suitable for low energy experiments and for post acceleration using well established accelerator techniques. The many different versions of the technique will be discussed and the many facilities spread all over the world will be reviewed. The major developments at the existing faci...

  17. Revision of the ASME nuclear quality assurance standard and its historical background

    International Nuclear Information System (INIS)

    Suzuki, Tetsuya

    2009-01-01

    ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

  18. Quality Assurance 1992-2012

    Science.gov (United States)

    Brown, Roger

    2012-01-01

    As the author's contribution to a series marking the Golden Jubilee of the Association of University Administrators, he reflects on changes in quality assurance over the past twenty years and speculates on what the future may hold for quality as the association moves into a new and very different competitive regime. He begins by discussing the…

  19. Redefining and expanding quality assurance.

    Science.gov (United States)

    Robins, J L

    1992-12-01

    To meet the current standards of excellence necessary for blood establishments, we have learned from industry that a movement toward organization-wide quality assurance/total quality management must be made. Everyone in the organization must accept responsibility for participating in providing the highest quality products and services. Quality must be built into processes and design systems to support these quality processes. Quality assurance has been redefined to include a quality planning function described as the most effective way of designing quality into processes. A formalized quality planning process must be part of quality assurance. Continuous quality improvement has been identified as the strategy every blood establishment must support while striving for error-free processing as the long-term objective. The auditing process has been realigned to support and facilitate this same objective. Implementing organization-wide quality assurance/total quality management is one proven plan for guaranteeing the quality of the 20 million products that are transfused into 4 million patients each year and for moving toward the new order.

  20. Quality assurance during site construction

    International Nuclear Information System (INIS)

    Eymess, K.J.; Haas, R.; Wellnitz, G.

    1980-01-01

    Quality Assurance for Nuclear Power Plants under consideration of pipe assembling. Flow of Quality Requirements during: - Desing - Construction - Procurement - Prefabrication - Site. Organizational Requirements and Measurements during Erection: - Incoming Control - Material Storage - Surveillance of Tools - Weld Surveillance - Nondestructive Testing - Cleaning - Final Documentation. Qualification and Training of QA Personnel. (orig.)

  1. Quality assurance issues and PACS

    NARCIS (Netherlands)

    Banta, H.D.

    1992-01-01

    Quality assessment and assurance is a growing concern in all areas of health care. The concern is fueled by a body of evidence that indicates that quality of care is not optimal, and in many instances, is unacceptably low. Although different standards for quality have been proposed, health outcome

  2. [Quality assurance in interventional cardiology].

    Science.gov (United States)

    Gülker, H

    2009-10-01

    Quality assurance in clinical studies aiming at approval of pharmaceutical products is submitted to strict rules, controls and auditing regulations. Comparative instruments to ensure quality in diagnostic and therapeutic procedures are not available in interventional cardiology, likewise in other fields of cardiovascular medicine. Quality assurance simply consists of "quality registers" with basic data not externally controlled. Based on the experiences of clinical studies and their long history of standardization it is assumed that these data may be severely flawed thus being inappropriate to set standards for diagnostic and therapeutic strategies. The precondition for quality assurance are quality data. In invasive coronary angiography and intervention medical indications, the decision making process interventional versus surgical revascularization, technical performance and after - care are essential aspects affecting quality of diagnostics and therapy. Quality data are externally controlled data. To collect quality data an appropriate infrastructure is a necessary precondition which is not existent. For an appropriate infrastructure investments have to be done both to build up as well as to sustain the necessary preconditions. As long as there are no infrastructure and no investments there will be no "quality data". There exist simply registers of data which are not proved to be a basis for significant assurance and enhancement in quality in interventional coronary cardiology. Georg Thieme Verlag KG Stuttgart, New York.

  3. NRC assessment of the high-level waste repository quality assurance program

    International Nuclear Information System (INIS)

    Kennedy, J.E.

    1987-01-01

    As part of its licensing responsibilities, the NRC is independently reviewing the DOE quality assurance program applied to the site characterization phase activities. Data collected and other information generated during this phase of the program will ultimately be used in a license application to demonstrate the suitability of one site for long-term isolation of waste. They must therefore fall under the quality assurance program to provide confidence in their adequacy. This NRC review consists of three main activities: development of staff guidance on quality assurance measures appropriate for site characterization activities; review of DOE QA plans and procedures; and audits and other reviews of the implementation of the program

  4. Characteristics quality system assurance of university programs

    Directory of Open Access Journals (Sweden)

    Lucian Ion Medar

    2011-03-01

    Full Text Available Quality assurance program of study requires time, dedication, effort, innovative thinking and creativity. Competitive research programs monitored by quality assurance system to create the desired results on the relationship between learning and teaching methods and assessment.

  5. Has quality assurance outlived its usefulness

    International Nuclear Information System (INIS)

    Goldenberg, N.

    1989-01-01

    This paper explores the impact that better management and increased productivity will have on the need for, and role of, quality assurance in the future. The author discusses criticisms of existing quality assurance programs

  6. Material quality assurance risk assessment : [summary].

    Science.gov (United States)

    2013-01-01

    With the shift from quality control (QC) of materials and placement techniques : to quality assurance (QA) and acceptance over the years, the role of the Office : of Materials Technology (OMT) has been shifting towards assurance of : material quality...

  7. Nova laser assurance-management system

    International Nuclear Information System (INIS)

    Levy, A.J.

    1983-01-01

    In a well managed project, Quality Assurance is an integral part of the management activities performed on a daily basis. Management assures successful performance within budget and on schedule by using all the good business, scientific, engineering, quality assurance, and safety practices available. Quality assurance and safety practices employed on Nova are put in perspective by integrating them into the overall function of good project management. The Nova assurance management system was developed using the quality assurance (QA) approach first implemented at LLNL in early 1978. The LLNL QA program is described as an introduction to the Nova assurance management system. The Nova system is described pictorially through the Nova configuration, subsystems and major components, interjecting the QA techniques which are being pragmatically used to assure the successful completion of the project

  8. Quality assurance - how to involve the employees

    DEFF Research Database (Denmark)

    Jørgensen, Michael Søgaard

    1996-01-01

    An overview of strategies for involvement of employees in quality assurance developement and implementation.......An overview of strategies for involvement of employees in quality assurance developement and implementation....

  9. On the isolation of elemental carbon (EC) for micro-molar 14C accelerator mass spectrometry: development of a hybrid reference material for 14C-EC accuracy assurance, and a critical evaluation of the thermal optical kinetic (TOK) EC isolation procedure

    Science.gov (United States)

    Currie, L. A.; Kessler, J. D.

    2005-10-01

    The primary objective of the research reported here has been the development of a hybrid reference material (RM) to serve as a test of accuracy for elemental carbon (EC) isotopic (14C) speciation measurements. Such measurements are vital for the quantitative apportionment of fossil and biomass sources of "soot" (EC), the tracer of fire that has profound effects on health, atmospheric visibility, and climate. Previous studies of 14C-EC measurement quality, carried out with NIST SRM 1649a (Urban Dust), showed a range of results, but since the "truth" was not known for this natural matrix RM, one had to rely on isotopic-chemical consistency evidence (14C in PAH, EC) of measurement validity (Currie et al., 2002). Components of the new Hybrid RM (DiesApple), however, have known 14C and EC composition, and they are nearly orthogonal (isotopically and chemically). NIST SRM 2975 (Forklift Diesel Soot) has little or no 14C, and its major compositional component is EC; SRM 1515 (Apple Leaves) has the 14C content of biomass-C, and it has little or no EC. Thus, the Hybrid RM can serve as an absolute isotopic test for the absence of EC-mimicking pyrolysis-C (char) from SRM 1515 in the EC isolate of the Hybrid RM, as well as a test for conservation of its dominant soot fraction throughout the isolation procedure. The secondary objective was to employ the Hybrid RM for the comparative evaluation of the thermal optical kinetic (TOK) and thermal optical transmission (TOT) methods for the isolation of EC for micro-molar carbon accelerator mass spectrometry (AMS). As part of this process, the relatively new TOK method was subjected to a critical evaluation and significant development. Key findings of our study are: (1) both methods exhibited biomass-C "leakage"; for TOT, the EC fraction isolated for AMS contained about 8% of the original biomass-C; for TOK, the refractory carbon (RC) isolated contained about 3% of the original biomass-C.; (2) the initial isothermal oxidation stage of

  10. On the isolation of elemental carbon (EC for micro-molar 14C accelerator mass spectrometry: development of a hybrid reference material for 14C-EC accuracy assurance, and a critical evaluation of the thermal optical kinetic (TOK EC isolation procedure

    Directory of Open Access Journals (Sweden)

    L. A. Currie

    2005-01-01

    Full Text Available The primary objective of the research reported here has been the development of a hybrid reference material (RM to serve as a test of accuracy for elemental carbon (EC isotopic (14C speciation measurements. Such measurements are vital for the quantitative apportionment of fossil and biomass sources of 'soot' (EC, the tracer of fire that has profound effects on health, atmospheric visibility, and climate. Previous studies of 14C-EC measurement quality, carried out with NIST SRM 1649a (Urban Dust, showed a range of results, but since the 'truth' was not known for this natural matrix RM, one had to rely on isotopic-chemical consistency evidence (14C in PAH, EC of measurement validity (Currie et al., 2002. Components of the new Hybrid RM (DiesApple, however, have known 14C and EC composition, and they are nearly orthogonal (isotopically and chemically. NIST SRM 2975 (Forklift Diesel Soot has little or no 14C, and its major compositional component is EC; SRM 1515 (Apple Leaves has the 14C content of biomass-C, and it has little or no EC. Thus, the Hybrid RM can serve as an absolute isotopic test for the absence of EC-mimicking pyrolysis-C (char from SRM 1515 in the EC isolate of the Hybrid RM, as well as a test for conservation of its dominant soot fraction throughout the isolation procedure. The secondary objective was to employ the Hybrid RM for the comparative evaluation of the thermal optical kinetic (TOK and thermal optical transmission (TOT methods for the isolation of EC for micro-molar carbon accelerator mass spectrometry (AMS. As part of this process, the relatively new TOK method was subjected to a critical evaluation and significant development. Key findings of our study are: (1 both methods exhibited biomass-C 'leakage'; for TOT, the EC fraction isolated for AMS contained about 8% of the original biomass-C; for TOK, the refractory carbon (RC isolated contained about 3% of the original biomass-C.; (2 the initial isothermal oxidation stage

  11. A strategy to develop and implement Canadian standards for quality assurance in radiation therapy

    International Nuclear Information System (INIS)

    1999-05-01

    In Canada, the Atomic Energy Control Board (AECB) regulates the limits of radiation exposure to the public and to workers in industry. In 1993, it discussed the fact that the safety of radiation therapy patients who receive medical exposures is not regulated [AE93]. The Group of Medical Advisors (GMA) to the AECB initiated a research contract to review quality assurance in Canadian radiation oncology centres and nuclear medicine departments. The review [MA95] revealed that the level of quality assurance in radiation therapy facilities varied across the country. As a result, the GMA undertook its own review of quality assurance in radiation therapy centres and made recommendations on how to achieve a uniform national system [MA98]. In response to the GMA report, the President of the AECB formed a Joint Working Group (JWG-11) to propose how Canadian Standards for Quality Assurance in Radiation Therapy could be developed and implemented. These national standards for quality assurance will serve as a common basis for establishing and evaluating quality assurance programs at individual radiation therapy centres. These standards should address the structure of quality assurance programs and quality assurance for radiation therapy equipment, personnel, and procedures. (author)

  12. Assuring Competency in Nuclear Power Plants: Regulatory Policy and Practice

    International Nuclear Information System (INIS)

    Durbin, Nancy E.; Melber, Barbara

    2004-06-01

    This report provides descriptive and comparative information on competency regulation and oversight in selected countries and identifies issues concerning competency. Interviews with competency experts in five countries: Sweden, Finland, Spain, Canada, and the United Kingdom were conducted and analyzed. The report provides a summary and comparison of the regulations used in these five countries. Regulations and policies in four areas are discussed: Licensing, certification and approvals; Educational qualifications; Training; Experience. Methods and tools used by regulators in the five countries are discussed with regard to how regulators: Assure that licensees determine the competencies needed for the safe operation of nuclear facilities and fill positions with competent staff; Oversee training and examinations in the areas of operations, engineering and maintenance; Assure competence of contractors; Oversee work group performance; Assure competency of managers; Assure competency of other personnel; Assure competency when modifications and other changes occur. Competency experts identified the following as the biggest challenges in regulating competency: The continued availability of qualified personnel; Determining appropriate criteria for competency and assuring those criteria are met. Determining whether licensees have adequately identified and met training needs, especially evaluating systematic approaches to training (SAT); Overseeing contractors. The following issues related to competency are discussed in the report: The sufficiency of qualified personnel; The evaluation of personnel requirements (determining appropriate criteria for competency and assuring those criteria are met); The effects of major organizational changes, including downsizing; Assurance of competency of contractors; International competency issues; The historical and current focus on technical and hardware issues over human factors issues; Selected examples illustrate regulatory

  13. U.S. comments on co-chairmen WG.2/15, chapter 7-A assurance of supply

    International Nuclear Information System (INIS)

    1979-05-01

    The U.S. delegation proposes revision in chapter 7 regarding assurance of supply, to reflect that alternative suppliers now exist to provide an assured supply, and that for most countries national enrichment facilities would not be practical or economic. The paper also argues that the spread of national facilities could increase proliferation risks. The revised text also argues that, because enrichment is highly capital-intensive, consumers should not expect significant surplus capacity at any given time, and should not interpret the absence of surplus capacity as an indication of lack of assurance in supply. Options which increase a consumer's flexibility in meeting enrichment needs are reviewed

  14. Integrating quality assurance and research and development

    International Nuclear Information System (INIS)

    Dronkers, J.J.

    1985-01-01

    Quality assurance programs cannot be transferred from one organization to another without attention to existing cultures and traditions. Introduction of quality assurance programs constitutes a significant change and represents a significant impact on the organizational structure and operational mode. Quality assurance professionals are change agents, but do not know how to be effective ones. Quality assurance as a body of knowledge and experience can only become accepted when its practitioners become familiar with their role as change agents. 8 references

  15. 2. Product quality control and assurance system

    International Nuclear Information System (INIS)

    1990-01-01

    Product quality control and assurance are dealt with in relation to reliability in nuclear power engineering. The topics treated include product quality control in nuclear power engineering, product quality assurance of nuclear power plant equipment, quality assurance programs, classification of selected nuclear power equipment, and standards relating to quality control and assurance and to nuclear power engineering. Particular attention is paid to Czechoslovak and CMEA standards. (P.A.). 2 figs., 1 tab., 12 refs

  16. Environmental Restoration Remedial Action quality assurance requirements document

    International Nuclear Information System (INIS)

    1991-01-01

    This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this document will be applied to activities affecting quality, using a graded approach based on the importance of the item, service, or activity to the program objectives. The Quality Assurance Program that will be established using this document as the basis, together with other program and technical documents, form an integrated management control system for conducting the Environmental Restoration Remedial Action program activities in a manner that provides safety and protects the environment and public health

  17. Measurement assurance program for LSC analyses of tritium samples

    International Nuclear Information System (INIS)

    Levi, G.D. Jr.; Clark, J.P.

    1997-01-01

    Liquid Scintillation Counting (LSC) for Tritium is done on 600 to 800 samples daily as part of a contamination control program at the Savannah River Site's Tritium Facilities. The tritium results from the LSCs are used: to release items as radiologically clean; to establish radiological control measures for workers; and to characterize waste. The following is a list of the sample matrices that are analyzed for tritium: filter paper smears, aqueous, oil, oily rags, ethylene glycol, ethyl alcohol, freon and mercury. Routine and special causes of variation in standards, counting equipment, environment, operators, counting times, samples, activity levels, etc. produce uncertainty in the LSC measurements. A comprehensive analytical process measurement assurance program such as JTIPMAP trademark has been implemented. The process measurement assurance program is being used to quantify and control many of the sources of variation and provide accurate estimates of the overall measurement uncertainty associated with the LSC measurements. The paper will describe LSC operations, process improvements, quality control and quality assurance programs along with future improvements associated with the implementation of the process measurement assurance program

  18. Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

    International Nuclear Information System (INIS)

    1992-01-01

    This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

  19. Quality assurance in the nuclear industry

    International Nuclear Information System (INIS)

    Knoedler, D.

    1978-01-01

    Quality assurance is the sum of all activities systematically planned, practiced, and controlled with the aim to assure the quality of deliveries and performances. This assurance today covers all phases of activities, from the planning (including a determination of the required and necessary quality characteristics) to the start-up of a plant. (orig./RW) [de

  20. Quality assurance management policies and requirements

    International Nuclear Information System (INIS)

    1985-10-01

    The purpose of this document is to: set forth overall, integrated quality assurance management policies and requirements for the entire Civilian Radioactive Waste Management Program; define management responsibilities for assuring quality; and provide a general framework for the development of more detailed quality assurance management policies and requirements by program, project, and contractor organizations

  1. 40 CFR 31.45 - Quality assurance.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Quality assurance. 31.45 Section 31.45... Requirements Reports, Records, Retention, and Enforcement § 31.45 Quality assurance. If the grantee's project... quality assurance practices consisting of policies, procedures, specifications, standards, and...

  2. 7 CFR 652.7 - Quality assurance.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Quality assurance. 652.7 Section 652.7 Agriculture... assurance. (a) NRCS will review, in consultation with the Farm Service Agency, as appropriate, the quality... information obtained through its quality assurance process, documentation submitted by the technical service...

  3. 30 CFR 74.9 - Quality assurance.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Quality assurance. 74.9 Section 74.9 Mineral... DUST SAMPLING DEVICES Requirements for Continuous Personal Dust Monitors § 74.9 Quality assurance. (a) General requirements. The applicant shall establish and maintain a quality control system that assures...

  4. 40 CFR 30.54 - Quality assurance.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Quality assurance. 30.54 Section 30.54... NON-PROFIT ORGANIZATIONS Post-Award Requirements Reports and Records § 30.54 Quality assurance. If the... data generation, the grantee shall develop and implement quality assurance practices consisting of...

  5. 10 CFR 76.93 - Quality assurance.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance. 76.93 Section 76.93 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safety § 76.93 Quality assurance. The Corporation shall establish, maintain, and execute a quality assurance program satisfying each of...

  6. An approach to total quality assurance

    International Nuclear Information System (INIS)

    Archer, L.G.

    1976-01-01

    Total Quality Assurance must be based on amalgamating three quality functions: effective quality control, competent inspection, and regularly audited Quality Assurance programmes. In applying these functions the fuel supplier must regard each of his sub-contractors as part of his own works and ensure a common policy of motivated Quality Assurance throughout his own works and those of his suppliers. (author)

  7. Assuring nuclear competence in the Netherlands

    International Nuclear Information System (INIS)

    Van Santen, R.J.

    2000-01-01

    The nuclear sphere of activity in the Netherlands is characterised by the size of nuclear programme: small nuclear programme (1 PWR operating, 1 BWR in decommissioning, 3 research reactors, 1 enrichment plant, 1 longer term waste storage facility and 1 nuclear laboratory); small nuclear regulatory authority, connected to 2-4 ministries (Nuclear Safety Department (KFD) ca. 12 experts, 4 inspectors and in total ca. 22 people); scale of nuclear supporting industry also small. A complicating factor in the near future is the closure of the only operating nuclear power plant. The Parliament has decided to permanently close down in end 2003. The early closing down decision was taken not for technical reasons, but because of the political/social situation as a matter of fact right after the end of the large end and complex modification project. The policy of assuring competence of the RA and the Licensees in the near future is based on considerations as: both are explicit responsible for maintaining the necessary competence for their own existing staff, and the RA watches over the effort of the Licensees; incorrect assessments are not tolerated, because of the political sensitivity towards every thing that relates to nuclear; sufficient budget should be available for foreign assistance. Important parts of the assessing of the assurance of the competence are the international contacts and working programmes within the western world. Besides the reason for international or European contacts, the exchange of knowledge and practices because of their contacts are an essential complement to reaching the necessary nuclear competence levels of nuclear safety. (N.C.)

  8. Quality assurance for hammer forgings

    International Nuclear Information System (INIS)

    Potthast, E.

    1984-01-01

    The quality assurance program introduced by Arbed Saarstahl and laid down in a quality assurance manual is described. A particular attention is attached thereby both to quality practice proper and to a reliable flow of information amongst all the persons involved. The production and test sequence schedules of the hammer forging plant are illustrated by the example of a forged valve housing for nuclear power plants. These schedules specify not only the forging process in the individual production stages but also the workpiece contour after each working operation, the heat treatment, the furnace charging, and the inspection of finished parts. The formalization of the tests is designed both to promote the customer's trust towards the supplier and to prevent the formal operations involved from hindering further technical development. (orig.) [de

  9. Information Assurance in Wireless Networks

    Science.gov (United States)

    Kabara, Joseph; Krishnamurthy, Prashant; Tipper, David

    2001-09-01

    Emerging wireless networks will contain a hybrid infrastructure based on fixed, mobile and ad hoc topologies and technologies. In such a dynamic architecture, we define information assurance as the provisions for both information security and information availability. The implications of this definition are that the wireless network architecture must (a) provide sufficient security measures, (b) be survivable under node or link attack or failure and (c) be designed such that sufficient capacity remains for all critical services (and preferably most other services) in the event of attack or component failure. We have begun a research project to investigate the provision of information assurance for wireless networks viz. survivability, security and availability and here discuss the issues and challenges therein.

  10. New techniques in quality assurance

    International Nuclear Information System (INIS)

    Fornicola, J.C.

    1987-01-01

    GPU Nuclear Corp. has a multifaceted quality assurance (QA) program. This program includes a comprehensive QA organization to help ensure its implementation. The QA organization employs various techniques in assuring quality at GPU Nuclear. These techniques not only include the typical QA/quality-control verification activities, i.e., QA engineering, quality control, and audits, but also include some new innovative techniques. Several new techniques have been developed for verifying activities. These techniques include monitoring and functional audits of safety systems. Several new techniques for assessing performance and adequacy and effectiveness of plant and QA programs, such as plant assessments and QA systems engineering evaluations, have also been developed. This paper provides an overview of these and other new techniques being employed by GPU Nuclear's QA organization

  11. Quality assurance in the design

    International Nuclear Information System (INIS)

    Edelmann, J.

    1980-01-01

    System- and product-related quality assurance measures are completing one another. Certainly it is possible to detect a lot of defects in the single technical document by well controlled product related quality inspections and to avoid the consequences of these defects; but also a not unimportant part of defects and deviations has its origin in system linked deficiencies. The latter can be detected more easily and more securely by means of system related reviews (System audit, Product audit). But also the sole implementation of system related quality assurance measures keeps the danger to get stuck only in formality and to loose all references to the specific characteristics of the product. (orig./RW)

  12. Assuring quality in narrative analysis.

    Science.gov (United States)

    Bailey, P H

    1996-04-01

    Many nurse-researchers using qualitative strategies have been concerned with assuring quality in their work. The early literature reveals that the concepts of validity and reliability, as understood from the positivist perspective, are somehow inappropriate and inadequate when applied to interpretive research. More recent literature suggests that because of the positivist and interpretive paradigms are epistemologically divergent, the transfer of quality criteria from one perspective to the other is not automatic or even reasonable. The purpose of this article, therefore, is to clarify what the terms quality, trustworthiness, credibility, authenticity, and goodness mean in qualitative research findings. The process of assuring quality, validation, in qualitative research will be discussed within the context of the interpretive method, narrative analysis. A brief review of quality in narrative analysis nursing research will also be presented.

  13. Quality management and quality assurance

    International Nuclear Information System (INIS)

    Pieroni, N.

    1991-01-01

    The main common difficulties are presented found in the implementation of effective Quality Management and Quality Assurance Programmes, based on the recommendations of the IAEA International Nuclear Safety Advisory Group, the information collected by the IAEA experts participating in its meetings, and the results of the IAEA Operational Safety Review Team missions. The difficulties were identified in several areas. The most relevant root causes can be characterized as lack of understanding of quality principles and difficulty in implementation by the responsible management. The IAEA programme is described attempting to provide advice and support in the implementation of an effective quality programme through a number of activities including: preparation of practical guidelines, training programmes for management personnel, assistance in building up qualified manpower, and promoting the quest for excellence through the exchange of experience in the implementation of effective Quality Management and Quality Assurance Programmes in nuclear power plants with good performance records. (Z.S.)

  14. 40 CFR 792.31 - Testing facility management.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Testing facility management. 792.31... facility management. For each study, testing facility management shall: (a) Designate a study director as... appropriately tested for identity, strength, purity, stability, and uniformity, as applicable. (e) Assure that...

  15. Quality assurance in diagnostic radiology

    International Nuclear Information System (INIS)

    1982-01-01

    The present guide endeavours to provide an outline of the type of quality assurance programme to be recommended for (1) routine implementation by those performing radiodiagnostic procedures (medical radiology technicians, medical physicists, and radiologists), (2) for application by the responsible national authorities, and (3) for use by international bodies such as the International Society of Radiology (ISR), the International Commission on Radiological Protection (ICRP), and the International Commission on Radiation Units and Measurements (ICRU)

  16. Quality Assurance in Higher Education

    OpenAIRE

    Nurdin, Nurdin

    2009-01-01

    Kualitas telah menjadi isu kritis dalam persaingan modern dewasa ini, dan hal itu telah menjadi beban tugas bagi para manager menengah. Dalam tataran abstrak kualitas telah didefinisikan oleh dua pakar penting bidang kualitas yaitu Joseph Juran dan Edward Deming. Mereka berdua telah berhasil menjadikan kualitas sebagai mindset yang berkembang terus dalam kajian managemen, khususnya managemen kualitas. Ouality assurance dalam dunia pendidikan adalah suatu keniscayaan seiring dengan terjadinya ...

  17. Quality Assurance In Radioactivity Measurements

    International Nuclear Information System (INIS)

    Riekstina, D.; Veveris, O.; Smilskalne, G.

    2007-01-01

    The credibility of obtained results is ensured by the quality assurance and control. The main requisitions involved in the quality assurance of the laboratory according to the requirements of LVS EN ISO/IEC 17025:2005 are: 1) the use of calibrated equipment only; 2) the regular and long-time use of reference materials in the control of equipment; 3) the estimation of uncertainty sources and determination of uncertainties within the given interval of credibility; 4) the validation and verification. The very important requirement is regular participation in the interlaboratory intercomparison exercises that makes it possible to estimate and find possible error sources and carry out the corrective actions. The measurements of the radioactivity of Cs-137, Co-60, H-3, the natural radioactive nuclides as well as other radionuclides in different environmental (soil, precipitation, different types of water, needles, et al.) samples, and in various radioactive polluted objects are carried out in the Laboratory of Radiation physics. The quality assurance system was implemented in our laboratory in 2000. Since 1999 laboratory is regular participant in the interlaboratory intercomparison exercises, organized by the RISO National Laboratory (Denmark) and IAEA (Vienna). The paper shows the laboratory's system of quality assurance and its implementation. We have the internal quality audit program that takes into account the requirements of LVS EN ISO/IEC 17025: 2005, but the main attention is paid to the intercomparison of the results of analyses of laboratories, their evaluation and interpretation. Only credible and justified results can be the basis for further use in any field, thus making it possible to make legitimate decisions. (Authors)

  18. Quality assurance of ageing components

    International Nuclear Information System (INIS)

    Novak, W.

    1992-01-01

    Comprehensive and permanent quality assurance on existing plants places very high requirements on measurement and evaluation technology. The necessary preconditions are often not met, however. By means of stocktaking using an external data registration and evaluation system may provide the basis for the assessment of the object and the existing power station instrumentation. After defining the desired scope and standards for the evaluation process, a specific solution may be produced. 5 figs

  19. Investigation of the performances of an ECR charge breeder at ISOLDE: a study of the 1$^{+}\\to$n$^{+}$ scenario for the next generation ISOL facilities.

    CERN Document Server

    MARIE-JEANNE, M; Delahaye, P

    2009-01-01

    The work described here was performed at ISOLDE, CERN. It aimed at giving an objective report of the current performances of Electron Cyclotron Resonance (ECR) ion sources used as charge breeders, with both stable and radioactive ion beams. As a prerequisite, some technical developments were undertaken during the PhD thesis to improve the setup and to lead the tests with optimal conditions. A major part of these developments concerns beam purity, and is detailed in this thesis. Then, measurements of the charge breeding efficiencies of various isotopes were completed with different charge breeding modes. Results of these experiments are analyzed and compared to the current performances of other types of charge breeding methods. At the end, some conclusions are drawn from this investigation in perspective of the choices to make for future ISOL postaccelerators. The discussion is extended to the immediate application of ECR charge bred radioactive ion beams to physics experiments.

  20. Quality assurance in tube manufacture

    International Nuclear Information System (INIS)

    Depken, H.

    1976-01-01

    Reliability in service essential for many high-technology products fabricated today. This is particularly the case within the nuclear industry. Here defective materials or components may have diastrous consequences to the safety of human beings and the environment. A new concept - Quality Assurance - originates from this industry. The concept implies that all contractors, fabricators and material manufactures involved must prove that the quality control system used, fulfits particular requirements at all manufacturing, inspection and testing stages. These requirement are laid down in two standards issued by the U.S. Atomic Energy Commission and the American Society of Mechanical Engineers. These standards are discussed in the paper. As a manufacturer of steel products for nuclear applications Sandvik has been forced to establish a quality assurance system according to these principles. The Sandvik approach is briefly described with regard to organisation and other major quality assurance activities. Further the education and training of operators and technicians is touched upon. Finally some viewpoints regarding audits performed by customers of steel manufacturers are expressed. (author)

  1. Quality Assurance for Clinical Trials

    Science.gov (United States)

    Ibbott, Geoffrey S.; Haworth, Annette; Followill, David S.

    2013-01-01

    Cooperative groups, of which the Radiation Therapy Oncology Group is one example, conduct national clinical trials that often involve the use of radiation therapy. In preparation for such a trial, the cooperative group prepares a protocol to define the goals of the trial, the rationale for its design, and the details of the treatment procedure to be followed. The Radiological Physics Center (RPC) is one of several quality assurance (QA) offices that is charged with assuring that participating institutions deliver doses that are clinically consistent and comparable. The RPC does this by conducting a variety of independent audits and credentialing processes. The RPC has compiled data showing that credentialing can help institutions comply with the requirements of a cooperative group clinical protocol. Phantom irradiations have been demonstrated to exercise an institution’s procedures for planning and delivering advanced external beam techniques (1–3). Similarly, RPC data indicate that a rapid review of patient treatment records or planning procedures can improve compliance with clinical trials (4). The experiences of the RPC are presented as examples of the contributions that a national clinical trials QA center can make to cooperative group trials. These experiences illustrate the critical need for comprehensive QA to assure that clinical trials are successful and cost-effective. The RPC is supported by grants CA 10953 and CA 81647 from the National Cancer Institute, NIH, DHHS. PMID:24392352

  2. Quality assurance and quality control

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The practice of nuclear diagnostic imaging requires an appropriate quality assurance program to attain high standards of efficiency and reliability. The International Atomic Energy Agency defines the term quality assurance as ''the closeness with which the outcome of a given procedure approaches some ideal, free from all errors and artifacts.'' The term quality control is used in reference to the specific measures taken to ensure that one particular aspect of the procedure is satisfactory. Therefore, quality assurance is a hospital-wide concept that should involve all aspects of clinical practice. Quality control is concerned with the submission of requests for procedures; the scheduling of patients; the preparation and dispensing of radiopharmaceuticals; the protection of patients, staff, and the general public against radiation hazards and accidents caused by radioactive materials or by faulty equipment; the setting up, use, and maintenance of electronic instruments; the methodology of the actual procedures; the analysis and interpretation of data; the reporting of results; and, finally, the keeping of records. The chapter discusses each of these areas

  3. Filters in nuclear facilities

    International Nuclear Information System (INIS)

    Berg, K.H.; Wilhelm, J.G.

    1985-01-01

    The topics of the nine papers given include the behavior of HEPA filters during exposure to air flows of high humidity as well as of high differential pressure, the development of steel-fiber filters suitable for extreme operating conditions, and the occurrence of various radioactive iodine species in the exhaust air from boiling water reactors. In an introductory presentation the German view of the performance requirements to be met by filters in nuclear facilities as well as the present status of filter quality assurance are discussed. (orig.) [de

  4. Joint CDRH (Center for Devices and Radiological Health) and state quality-assurance surveys in nuclear medicine: Phase 2 - radiopharmaceuticals

    International Nuclear Information System (INIS)

    Hamilton, D.R.; Evans, C.D.

    1986-08-01

    The report discusses survey results on aspects of the quality assurance of radio-pharmaceuticals from 180 nuclear-medicine facilities in the United States. Data were collected from facilities in 8 states. Demographic information about nuclear-medicine operations and quality-assurance programs was gathered by state radiation-control-program personnel. The data collected from the survey show an incomplete acceptance of quality-assurance practices for radiopharmaceuticals. Most of the facilities in the survey indicated that, because an inferior radiopharmaceutical was prepared so infrequently, they did not believe it was cost-effective to perform extensive quality-assurance testing. The Center for Devices and Radiological Health hopes that the information from the survey will stimulate nuclear-medicine professionals and their organizations to encourage appropriate testing of all radiopharmaceuticals

  5. Quality assurance in processing radioactive waste for land disposal

    International Nuclear Information System (INIS)

    1984-01-01

    To provide the appropriate assurances as to the quality of processed radioactive waste it is necessary to consider the complete range of activities involved in the formation and operation of a radioactive waste processing facility. To this end, an outline has been given to the individual elements which should be addressed in quality assurance proposals to the authorising Departments. In general terms, the quality checks on product material should be aimed at demonstrating that the radioactive waste product is what was agreed at the time of process approval. In addition, at the discretion of the authorising Departments, the waste processor will be required to confirm that the product meets any specific acceptance criteria such as the capability to retain the immobilised radionuclides when in contact with water. (author)

  6. Technical Evaluation of Oak Ridge Filter Test Facility

    CERN Document Server

    Kriskovich, J R

    2002-01-01

    Two evaluations of the Oak Ridge Department of Energy (DOE) Filter Test Facility (FTF) were performed on December 11 and 12, 2001, and consisted of a quality assurance and a technical evaluation. This report documents results of the technical evaluation.

  7. Quality Assurance Program Plan Waste Management Federal Services of Hanford, Inc

    International Nuclear Information System (INIS)

    VOLKMAN, D.D.

    1999-01-01

    This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program

  8. Safety analysis report for the National Low-Temperature Neutron Irradiation Facility (NLTNIF) at the ORNL Bulk Shielding Reactor (BSR)

    International Nuclear Information System (INIS)

    Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Richardson, S.A.

    1986-06-01

    This report provides information concerning: the experiment facility; experiment assembly; instrumentation and controls; materials; radioactivity; shielding; thermodynamics; estimated or measured reactivity effects; procedures; hazards; and quality assurance

  9. The 18 basic requirement of quality assurance for American design NPP

    International Nuclear Information System (INIS)

    Baliza, Ana Rosa

    2013-01-01

    On April 17th, 1969, the Atomic Energy Commission (AEC) published in the U.S. Federal Register (FR), Volume 34, Number 73, a proposed amendment to 10CFR50 to insert Appendix B - 'Quality assurance criteria for Nuclear Power Plant'. This Appendix was officially approved on June 27th, 1970 and published in the FR, volume 35, number 125. Appendix B is the Quality Assurance document for U.S. nuclear facilities. This document establishes eighteen basic requirements (BR) to design, construction, manufacture and operation of structures, systems and components (SSC) related to safety. The 18 BR describe 'what' shall be done, but not 'how' to do. In order to standardize the actions of nuclear facilities during 10 CFR 50 App B implementation, the industry has developed some documents, the main ones are: ASME NQA-1 (Quality Assurance Requirements for Nuclear Facility Applications) and the series ANSI N 45.2 (Quality Assurance Program Requirements for Nuclear Facilities). Both documents are approved by the NRC (Nuclear Regulatory Commission). The NRC is the licensing body of U.S. nuclear facilities. In Brazil, the licensing body is CNEN (Comissao Nacional de Energia Nuclear). This paper describes the 18 BR for American Designed Nuclear Power Plant (NPP), applicable to Angra-1 NPP. (author)

  10. Investigation of the performances of an ECR charge breeder at ISOLDE: a study of the 1+ → n+ scenario for the next generation ISOL facilities

    International Nuclear Information System (INIS)

    Marie-Jeanne, M.

    2009-02-01

    The work I describe here was performed at ISOLDE, CERN. It aimed at giving an objective report of the current performances of Electron Cyclotron Resonance (ECR) ion sources used as charge breeders, with both stable and radioactive ion beams. As a prerequisite, some technical developments were undertaken to improve the setup and to lead the tests with optimal conditions. A major part of these developments concerns beam purity, and is detailed in this thesis. Then, the program of measurements of the charge breeding efficiencies of various isotopes was completed with different charge breeding modes. I analyzed the results of these experiments and compared them to the current performances of other types of charge breeding methods. At the end, some conclusions are drawn from this investigation in perspective of the choices to make for future ISOL post-accelerators. The discussion is extended to the immediate application of ECR charge bred radioactive ion beams to physics experiments, for which I proposed and performed additional tests. (author)

  11. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  12. Quality assurance requirements and description for the Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    1992-01-01

    The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through application for an operating license; (5) the high-level-waste form from production through acceptance. Section 2.0 defines in greater detail criteria for determining work subject to QARD requirements. The QARD is organized into sections, supplements, appendices, and a glossary. The sections contain requirements that are common to all Program elements. The supplements contain requirements for specialized activities. The appendices contain requirements that are specific to an individual Program element. The glossary establishes a common vocabulary for the Quality Assurance Program

  13. Quality assurance plan: Prepared for the state of Florida, Department of Health and rehabilitative Services, Office of Laboratory Services, Water Certification Program

    International Nuclear Information System (INIS)

    1992-02-01

    This quality assurance plan is for use in ongoing operations in the General Electric Neutron Devices Department. General Electric operates the Department of Energy (DOE) facility in Largo, Florida. All work covered by this quality assurance plan is in support of the operations of the wastewater pretreatment facility operated by GENDD at the DOE facility in Largo, Florida. As a Florida State certified laboratory we will follow Health and Rehabilitation Services (HRS) or HRS approved standard methods, successfully participate in HRS or HRS approved performance evaluation studies, and will maintain Quality Assurance Documentation as outlined in this plan or its subsequent revisions

  14. Biochemistry Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

  15. Quality Assurance Review of SKB's Copper Corrosion Experiments

    International Nuclear Information System (INIS)

    Baldwin, Tamara D.; Hicks, Timothy W.

    2010-06-01

    SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that there is a satisfactory level of assurance that experiments have been carried out with sufficient quality, so that results can be considered to be reliable within the context of their use in safety assessment. The former named authority, SKI, has initiated a series of reviews of SKB's methods of quality assurance and their implementation. This quality assurance review is focused on the work of copper corrosion being conducted in at SKB's Hard Rock Laboratory (HRL) in Aespoe, LOT and Miniature canister (Minican) experiments. In order for the reviewers to get a broad understanding of the issue of copper corrosion both SKB reports as well as the viewpoint of MKG was collected prior to commencement of the actual review task. The purpose of this project is to assess SKB's quality assurance with the view of providing input for the preparation of the SR-Site safety assessment. This has been achieved by examination of the corrosion part of the LOT and Minican experiments using a check list, visits to the relevant facilities, and meetings with contractors and a few members of the SKB staff. The same approach for quality assurance reviews has been used earlier in similar review tasks. During the quality review of the selected projects, several QA- related issues of different degree of severity was noted by the reviewers. The most significant finding was that SKB has chosen to present only selected real-time corrosion monitoring data in TR-09-20. This was surprising and SSM expect that SKB will analyse the reason for this thoroughly. The reviewers also made other observations which can be

  16. Status of RIB facilities in Asia

    International Nuclear Information System (INIS)

    Tanihata, Isao

    1998-01-01

    Radioactive Ion Beam Facilities in Asia are presented. In China, in-flight separation type facilities are in operation at the Institute of Modern Physics in Lanzhou and the other at Tandem facility in China Institute of Atomic Energy in Beijing. The storage-ring facility is proposed and approved in Lanzhou. In India, the Variable Energy Cyclotron Facility in Calcutta start to construct an ISOL-type facility. In Japan, in-flight separation type facilities are working at Research Center for Nuclear Physics in Osaka, and at RIKEN. Also a separator start its operation in medical facility in Chiba. In RIKEN, the construction of RI Beam Factory has been started. An ISOL-type facility is proposed in the Japan Hadron Facility in KEK. Table I summarize these facilities

  17. Quality assurance program plan for 324 Building B-Cell safety cleanout project (BCCP)

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the 324 Building B-Cell Safety Cleanout Project (BCCP). This QAPP is responsive to the Westinghouse Hanford Company Quality Assurance Program and Implementation Plan, WHC-SP-1131, for 10 CFR 830.120, Nuclear Safety Management, Quality Assurance Requirements; and DOE Order 5700.6C, Quality Assurance. This QAPP supersedes PNNL PNL-MA-70 QAP Quality Assurance Plan No. WTC-050 Rev. 2, issue date May 3, 1996. This QAPP has been developed specifically for the BCCP. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of decontaminating B-Cell and project related operations within the 324 Building as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations) are covered in the Building 324 QAPP. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping, and HSRCM-1, Hanford Site Radiological Control Manual, The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing, PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to 10 CFR 83 0.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be

  18. Auditing of quality assurance programs for nuclear power plants - September 1980 - (Rev.1)

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of structures, systems, and components of nuclear power plants important to safety. Criterion XVIII, Audits, of Appendix B to 10 CFR Part 50 establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to auditing of quality assurance programs for nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  19. Digital radiography for quality assurance

    International Nuclear Information System (INIS)

    Thiele, H.; Friemel, H.J.

    2001-01-01

    The digital radiographic system AMICA-401 is described. It is a mobile system originally developed for wall thickness and diameter measurements of insulated and non-insulated pipes which is also suited for quality assurance in fabrication and maintenance. Its advantages are immediate evaluation of images, very short exposure times with reduced radiation loads, and an efficient integrated image processing software. Further, no chemical substances are required for film processing. The system can be used both in mobile and in stationary applications. Practical examples are presented and discussed. (orig.) [de

  20. Quality assurance of nuclear fuel

    International Nuclear Information System (INIS)

    1994-01-01

    The guide presents the quality assurance requirements to be completed with in the procurement, design, manufacture, transport, handling and operation of the nuclear fuel. The guide also applies to the procurement of the control rods and the shield elements to be placed in the reactor. The guide is mainly aimed for the licensee responsible for the procurement and operation of fuel, for the fuel designer and manufacturer and for other organizations whose activities affect fuel quality, the safety of fuel transport, storage and operation. (2 refs.)

  1. Performance assurance for IT systems

    CERN Document Server

    King, Brian

    2004-01-01

    INDIVIDUAL AREAS OF INTERESTPreparing for the ChallengeAbstractIntroductionIn the BeginningThe Need to Address New ApplicationsDefinition of PerformanceThe Required SkillsPerformance Assurance Within a Project LifecycleSummaryCaveat Emptor (Let the Buyer Beware)AbstractSoftware Product LifecycleHardware Product LifecycleMarketingTechnical Reviews of ProductsLies, Damned Lies and BenchmarksAbstractIntroductionIndustry BenchmarksVendor BenchmarksIndependent BenchmarkingIn-House Benchmarking""Tricks of the Trade""Using Benchmarks Non-Functional Requirements and SolutionsAbstractIntroductionThe Pr

  2. Quality assurance in digital radiography

    International Nuclear Information System (INIS)

    Busch, H.P.; Lehmann, K.J.

    1989-01-01

    At present, there is no standard way of evaluating performance characteristics of digital radiography systems. Continuous measurements of performance parameters are necessary in order to obtain images of high quality. Parameters of quality assurance in digital radiography, which can be evaluated with simple, quick methods, are spatial resolution, low-contrast detectability, dynamic range and exposure dose. Spatial resolution was determined by a lead bar pattern, whereas the other parameters were measured by commercially available phantoms. Performance measurements of 10 digital subtraction angiography (DSA) units and one digital radiography system for unsubtracted digital radiography were assessed. From these results, recommendations for performance parameter levels will be discussed. (author)

  3. Radiation Dosimetry Management: Quality Assurance and Investigations

    International Nuclear Information System (INIS)

    Perle, S.

    2001-01-01

    Full text: In a litigation-prone society, it is prudent for any business to evaluate its potential exposure to legal action, initiated by either an employee or a member of the general public. This potential is exacerbated when the phobia of radiation exposure and radioactive materials is interjected into the equation. This phobia is fuelled by the perceived risks of radiation exposure, be they fact or fantasy. With the current cancer incidence rate being approximately 1 in every 2.5 individuals (for all types of cancer), it is imperative that all facilities take a proactive look at their business vulnerability. When radiation exposure is the issue, records documentation is a critical factor, and a significant amount of effort should be expended to implement a comprehensive records management system. A comprehensive Radiation Dosimetry Management Program is essential if a business is going to mitigate any regulatory or legal intervention. This lecture will address appropriate Records Quality Assurance, and, the appropriate requirements for investigations of dosimetry results. (author)

  4. Geomechanical monitoring system at the Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Francke, J.L.; Carrasco, R.C.

    1992-01-01

    This paper describes in detail the geomechanical instrumentation system and the database that has been established from the geomechanical monitoring program. In addition, it describes the quality assurance and control measures that are in place to ensure that the data from the underground is accurate, traceable, and defensible. The system is installed at the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This facility is being developed for the disposal of transuranic nuclear wastes in underground excavations in salt 655 meters below the surface. The purpose of the instrumentation system, is to monitor the deformations and stress changes that are occurring in the rock with time. This information is needed to routinely assess conditions in the facility and to ensure that safe operating conditions are maintained. The geomechanical monitoring system has provided data collection, quality control, and database maintenance, all of which are of vital importance to monitoring the geomechanical performance of underground excavations

  5. Geomechanical monitoring system at the Waste Isolation Pilot Plant, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    Francke, J.L.; Cook, R.F.; Carrasco, R.C.

    1993-01-01

    This paper describes in detail the geomechanical instrumentation system and the data base that has been established from the geomechanical monitoring program. In addition, it describes the quality assurance and control measures that are in place to ensure that the data from the underground is accurate, traceable, and defensible. The system is installed at the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This facility is being developed for the disposal of transuranic nuclear wastes in underground excavations in salt 2150 feet below the surface. The purpose of the instrumentation system is to monitor the deformations and stress changes that are occurring in the rock with time. This information is needed to routinely assess conditions in the facility and to ensure that safe operating conditions are maintained

  6. Quality assurance considerations in nuclear waste management

    International Nuclear Information System (INIS)

    Delvin, W.L.

    1982-01-01

    Proper use of quality assurance will provide the basis for an effective management control system for nuclear waste management programs. Control is essential for achieving successful programs free from costly losses and failures and for assuring the public and regulators that the environment and health and safety are being protected. The essence of quality assurance is the conscientious use of planned and systematic actions, based on selecting and applying appropriate requirements from an established quality assurance standard. Developing a quality assurance program consists of using knowledge of the technical and managerial aspects of a project to identify and evaluate risks of loss and failure and then to select appropriate quality assurance requirements that will minimize the risks. Those requirements are integrated into the project planning documents and are carried out as specific actions during the life of the project

  7. Approach to assurance of reliability of linear accelerator operation observations

    International Nuclear Information System (INIS)

    Bakov, S.M.; Borovikov, A.A.; Kavkun, S.L.

    1994-01-01

    The system approach to solving the task of assuring reliability of observations over the linear accelerator operation is proposed. The basic principles of this method consist in application of dependences between the facility parameters, decrease in the number of the system apparatus channels for data acquisition without replacement of failed channel by reserve one. The signal commutation unit, the introduction whereof into the data acquisition system essentially increases the reliability of the measurement system on the account of active reserve, is considered detail. 8 refs. 6 figs

  8. Dance Facilities.

    Science.gov (United States)

    Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

    This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

  9. Quality assurance for gamma knives

    International Nuclear Information System (INIS)

    Jones, E.D.; Banks, W.W.; Fischer, L.E.

    1995-09-01

    This report describes and summarizes the results of a quality assurance (QA) study of the Gamma Knife, a nuclear medical device used for the gamma irradiation of intracranial lesions. Focus was on the physical aspects of QA and did not address issues that are essentially medical, such as patient selection or prescription of dose. A risk-based QA assessment approach was used. Sample programs for quality control and assurance are included. The use of the Gamma Knife was found to conform to existing standards and guidelines concerning radiation safety and quality control of external beam therapies (shielding, safety reviews, radiation surveys, interlock systems, exposure monitoring, good medical physics practices, etc.) and to be compliant with NRC teletherapy regulations. There are, however, current practices for the Gamma Knife not covered by existing, formalized regulations, standards, or guidelines. These practices have been adopted by Gamma Knife users and continue to be developed with further experience. Some of these have appeared in publications or presentations and are slowly finding their way into recommendations of professional organizations

  10. The challenge of Quality Assurance

    International Nuclear Information System (INIS)

    Simon, R.; Price, M.S.T.; Krischer, W.

    1985-01-01

    The safe terminal containment of hazardous wastes cannot only rely upon the geographic remoteness and the arid climates of the repository sites. Radioactive and permanently toxic chemical wastes must by prevented from returning to the human environment by natural and engineered barriers. The long-term integrity of these barriers and the safety of waste emplacement operation will be controlled by systematic actions under the common objective of Quality Assurance (QA). The following paper presents the aims of QA in the design and production of waste packages. It lists the most relevant acceptance criteria and regulatory requirements, investigates the institutional and technical problems of carrying out Quality Assurance and presents suggestions for establishing suitable organizational structures and technical programmes to provide adequate confidence in the safe nature and the performance of waste packages. In view of the technical difficulties of verifying the compliance of industrially produced waste forms with the acceptance criteria, the CEC has laid emphasis on the development of appropriate test methods in its last R and D programme. First results of the work are reviewed in the context of international progress in this field

  11. Quality assurance for gamma knives

    Energy Technology Data Exchange (ETDEWEB)

    Jones, E.D.; Banks, W.W.; Fischer, L.E. [Lawrence Livermore National Lab., CA (United States)

    1995-09-01

    This report describes and summarizes the results of a quality assurance (QA) study of the Gamma Knife, a nuclear medical device used for the gamma irradiation of intracranial lesions. Focus was on the physical aspects of QA and did not address issues that are essentially medical, such as patient selection or prescription of dose. A risk-based QA assessment approach was used. Sample programs for quality control and assurance are included. The use of the Gamma Knife was found to conform to existing standards and guidelines concerning radiation safety and quality control of external beam therapies (shielding, safety reviews, radiation surveys, interlock systems, exposure monitoring, good medical physics practices, etc.) and to be compliant with NRC teletherapy regulations. There are, however, current practices for the Gamma Knife not covered by existing, formalized regulations, standards, or guidelines. These practices have been adopted by Gamma Knife users and continue to be developed with further experience. Some of these have appeared in publications or presentations and are slowly finding their way into recommendations of professional organizations.

  12. Quality assurance programme and responsibility

    International Nuclear Information System (INIS)

    Lee Peter

    2004-01-01

    The contents of this chapter are follows - Quality Control of Equipment and Facilities, Monitoring and Analysis of Film Reject Rate, Continuous Medical Education (CME), Audit of X-Ray Radiographs, General Principles, Good Image Criteria

  13. Waste Isolation Pilot Plant Safety Analysis Report. Volume 5

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  14. Waste Isolation Pilot Plant Safety Analysis Report. Volume 1

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection: Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating control and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  15. Waste Isolation Pilot Plant Safety Analysis Report. Volume 4

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  16. Waste Isolation Pilot Plant Safety Analysis Report. Volume 2

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  17. GSFC Safety and Mission Assurance Organization

    Science.gov (United States)

    Kelly, Michael P.

    2010-01-01

    This viewgraph presentation reviews NASA Goddard Space Flight Center's approach to safety and mission assurance. The contents include: 1) NASA GSFC Background; 2) Safety and Mission Assurance Directorate; 3) The Role of SMA-D and the Technical Authority; 4) GSFC Mission assurance Requirements; 5) GSFC Systems Review Office (SRO); 6) GSFC Supply Chain Management Program; and 7) GSFC ISO9001/AS9100 Status Brief.

  18. Quality assurance and nuclear power plant safety

    International Nuclear Information System (INIS)

    Mullan, J.V.

    1983-01-01

    Quality assurance in the nuclear industry was born in the late 1960s. Atomic Energy Control Board staff began its regulatory practice on quality assurance during that period. In this presentation the author traces the circumstances that first led to the establishment of Canadian nuclear power plant quality assurance programmes, summarizes progress over the last decade and a half, and outlines the current regulatory approach and what has been learned so far

  19. Software quality assurance - seven years experience

    International Nuclear Information System (INIS)

    Malsbury, J.A.

    1987-01-01

    This paper describes seven years experience with software quality assurance at PPPL. It covers the early attempts of 1980 and 1981 to establish software quality assurance; the first attempt of 1982 to develop a complete software quality assurance plan; the significant modifications of this plan in 1985; and the future. In addition, the paper describes the role of the Quality Assurance organization within each plan. The scope of this paper is limited to discussions of the software development procedures used in the seven year period. Other software quality topics, such as configuration control or problem identification and resolution, are not discussed

  20. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-02-01

    The Topical Report presented establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of the report

  1. Quality assurance program for nuclear power plants

    International Nuclear Information System (INIS)

    Gamon, T.H.

    1976-06-01

    This topical report establishes and provides the basis for the Brown and Root Quality Assurance Program for Nuclear Power Plants from which the Brown and Root Quality Assurance Manual is prepared and implemented. The Quality Assurance Program is implemented by the Brown and Root Power Division during the design, procurement, and construction phases of nuclear power plants. The Brown and Root Quality Assurance Program conforms to the requirements of Nuclear Regulatory Commission Regulation 10 CFR 50, Appendix B; to approved industry standards such as ANSI N45.2 and ''Daughter Standards''; or to equivalent alternatives as indicated in the appropriate sections of this report

  2. Example of the contribution of text processing by machine for establishing quality assurance report dossiers

    International Nuclear Information System (INIS)

    Didierlaurent, Maryvonne; Meurgues, J.P.

    1981-03-01

    When safety requirements are imposed, quality assurance report dossiers (term consecrated by the IAEA in Vienna) must be established for all realizations and, in particular, for mechanical realizations connected with nuclear facilities. Supply dossiers are envisaged in the context of these dossiers. This present text treats the material aspects of the constitution of these dossiers [fr

  3. Mammography in public hospitals at Rio de Janeiro: a quality assurance program

    International Nuclear Information System (INIS)

    Briquet, C.; Coutinho, C.M.C.; Mota, H.C.; Tavares, E.

    1998-01-01

    This paper presents the preliminary results and the methodology followed by the implementation of a Quality Assurance Program in public hospitals at Rio de Janeiro. We observed that the main problems of image are due to the processing. None facility has a dedicated processor and the processor daily quality control is a concern not yet adopted. (Author)

  4. Large hadron collider (LHC) project quality assurance plan

    Energy Technology Data Exchange (ETDEWEB)

    Gullo, Lisa; Karpenko, Victor; Robinson, Kem; Turner, William; Wong, Otis

    2002-09-30

    The LHC Quality Assurance Plan is a set of operating principles, requirements, and practices used to support Berkeley Lab's participation in the Large Hadron Collider Project. The LHC/QAP is intended to achieve reliable, safe, and quality performance in the LHC project activities. The LHC/QAP is also designed to fulfill the following objectives: (1) The LHC/QAP is Berkeley Lab's QA program document that describes the elements necessary to integrate quality assurance, safety management, and conduct of operations into the Berkeley Lab's portion of the LHC operations. (2) The LHC/QAP provides the framework for Berkeley Lab LHC Project administrators, managers, supervisors, and staff to plan, manage, perform, and assess their Laboratory work. (3) The LHC/QAP is the compliance document that conforms to the requirements of the Laboratory's Work Smart Standards for quality assurance (DOE O 414.1, 10 CFR 830.120), facility operations (DOE O 5480.19), and safety management (DOE P 450.4).

  5. The quality assurance program at K ampersand S

    International Nuclear Information System (INIS)

    Slowey, T.W.

    1993-01-01

    K ampersand S operates the largest and one of the most comprehensive Accredited Dosimetry Calibration Laboratories (ADCLs) in the American Association of Physicists in Medicine (AAPM) secondary laboratory system. It offers calibrations covering energies from Grenz-Ray (0.03-mm Al) to cesium-137 and cobalt-60, brachytherapy source and well chamber calibrations for low-activity sources, and, recently, high-dose-rate iridium-192. The present Quality Assurance (QA) program at K ampersand S began with the AAPM Guidelines for Accreditation (Task Group No. 22 and No. 3, 1989) and grew over the past 10 years to include all aspects of providing a private, self-supporting calibration service from a free-standing independent facility. Some aspects of the QA program were prompted by the requirements of the nuclear power industry while other parts were from national consensus standards or the experiences of staff. Redundancy and teamwork are the most important characteristics of this QA program. K ampersand S has participated in a National Institute of Standards and Technology (NIST) measurement quality assurance (MQA) program since 1982, and, in recent years, an ADCL intralaboratory intercomparison was conducted by Task Group 3 of the Radiation Therapy Committee of the AAPM. One measure of the credibility of a QA program is consistent performance on the MQA program and the ADCL intercomparisons over the past 10 years. An equally important measure of the ability of a program to assure quality results is the frequency of reported errors

  6. Large hadron collider (LHC) project quality assurance plan

    International Nuclear Information System (INIS)

    Gullo, Lisa; Karpenko, Victor; Robinson, Kem; Turner, William; Wong, Otis

    2002-01-01

    The LHC Quality Assurance Plan is a set of operating principles, requirements, and practices used to support Berkeley Lab's participation in the Large Hadron Collider Project. The LHC/QAP is intended to achieve reliable, safe, and quality performance in the LHC project activities. The LHC/QAP is also designed to fulfill the following objectives: (1) The LHC/QAP is Berkeley Lab's QA program document that describes the elements necessary to integrate quality assurance, safety management, and conduct of operations into the Berkeley Lab's portion of the LHC operations. (2) The LHC/QAP provides the framework for Berkeley Lab LHC Project administrators, managers, supervisors, and staff to plan, manage, perform, and assess their Laboratory work. (3) The LHC/QAP is the compliance document that conforms to the requirements of the Laboratory's Work Smart Standards for quality assurance (DOE O 414.1, 10 CFR 830.120), facility operations (DOE O 5480.19), and safety management (DOE P 450.4)

  7. Rapid assessment of antimicrobial resistance prevalence using a Lot Quality Assurance sampling approach

    NARCIS (Netherlands)

    van Leth, Frank; den Heijer, Casper; Beerepoot, Marielle; Stobberingh, Ellen; Geerlings, Suzanne; Schultsz, Constance

    2017-01-01

    Increasing antimicrobial resistance (AMR) requires rapid surveillance tools, such as Lot Quality Assurance Sampling (LQAS). LQAS classifies AMR as high or low based on set parameters. We compared classifications with the underlying true AMR prevalence using data on 1335 Escherichia coli isolates

  8. Nuclear power plants - Quality assurance

    International Nuclear Information System (INIS)

    1980-01-01

    This International Standard defines principles for the establishment and implementation of quality assurance programmes during all phases of design, procurement, fabrication, construction, commissioning, operation, maintenance and decommissioning of structures, systems and components of nuclear power plants. These principles apply to activities affecting the quality of items, such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling and modifying and eventually decommissioning. The manner in which the principles described in this document will be implemented in different organizations involved in a specific nuclear power project will depend on regulatory and contractual requirements, the form of management applied to a nuclear power project, and the nature and scope of the work to be performed by different organizations

  9. Grid Technology and Quality Assurance

    International Nuclear Information System (INIS)

    Rippa, A.; Manieri, A.; Begin, M.E.; Di Meglio, A.

    2007-01-01

    Grid is one of the potential architectures of the coming years to support both the research and the commercial environment. Quality assurance techniques need both to adapt to these new architectures and exploit them to improve its effectiveness. Software quality is a key issue in the Digital Era: Industries as well as Public Administrations devote time to check and verify the quality of ICT products and services supplied. The definition of automatic measurement of quality metrics is a key point for implementing effective QA methods. In this paper we propose a quality certification model, named Grid-based Quality Certification Model (GQCM), that uses automatically calculable metrics to asses the quality of software applications; this model has been developed within the ETICS SSA4 activities and exploit grid technology for full automation of metrics calculation. It is however designed to be generic enough such that it can be implemented using any automatic build and test tool. (Author)

  10. Quality assurance and product quality

    International Nuclear Information System (INIS)

    Lacroix, D.; Bastiani, P. de

    2004-01-01

    The basic quality assurance requirements have to be completed by means that are oriented towards the quality of products; in COGEMA LOGISTICS our approach is based on four principles: 1) an integrated management system: Quality, health and safety, environment 2) an organization based on the responsibility of all actors, trust and transparency 3) a methodical approach to continuously improve the methods that are employed to achieve quality: -process management -corrective and preventive actions -self assessments and various surveys 4) but at the same time strong procedures for control and monitoring of all activities: -technical and quality audits (external and internal) -at source inspections -engineering activities inspections This performance-based approach is necessary to guaranty the effectiveness of the traditional formal QA means

  11. Quality assurance in radionuclide laboratories

    International Nuclear Information System (INIS)

    Otto, R.; Voelkle, H.; Wershofen, H.; Wilhelm, C.

    2003-01-01

    The authors are members of an ad-hoc working group preparing a contribution to the procedures manual (''Loseblattsammlung'') dealing with quality assurance and quality control in radionuclide laboratories. The Loseblattsammlung is edited by the working group ''Environmental Monitoring'' of the German-Swiss Radiological Protection Association. The intention of the manual under preparation is not to give a procedure on how to establish a quality management system allowing for an accreditation in accordance with the international standard DIN EN ISO/IEC 17025:2000 04 (''ISO 17025'') [1] but to compile routine quality control procedures necessary for reliable measurements and to give tips to the practitioner on how to keep both the extent and the frequency of procedures on a reasonable level. A short version of the Loseblatt is presented here. (orig.)

  12. Quality assurance and statistical control

    DEFF Research Database (Denmark)

    Heydorn, K.

    1991-01-01

    In scientific research laboratories it is rarely possible to use quality assurance schemes, developed for large-scale analysis. Instead methods have been developed to control the quality of modest numbers of analytical results by relying on statistical control: Analysis of precision serves...... to detect analytical errors by comparing the a priori precision of the analytical results with the actual variability observed among replicates or duplicates. The method relies on the chi-square distribution to detect excess variability and is quite sensitive even for 5-10 results. Interference control...... serves to detect analytical bias by comparing results obtained by two different analytical methods, each relying on a different detection principle and therefore exhibiting different influence from matrix elements; only 5-10 sets of results are required to establish whether a regression line passes...

  13. Security assurances and regional stability

    International Nuclear Information System (INIS)

    Sanders, B.

    1995-01-01

    This paper discusses whether and how security assurances affect political stability in geographic regions. Before embarking on what is necessarily a limited analysis of a complex subject, I point out that the subject is by no means new. For centuries, vast areas of the world have been affected by forces used against them by more powerful States, which at one time or another incorporated large parts of them into overseas colonies or contiguous empires. The new factors are the emancipation of those areas into independent regions, made up of States that play their own parts in international affairs, and the possession by a handful of Powers, outside or on the edge of those regions, of a specific form of superior force: nuclear weapons. (author)

  14. Is quality assurance really necessary

    International Nuclear Information System (INIS)

    Elwen, L.

    1983-01-01

    The modern concept of quality assurance began to take root in the 50's in Japan. In the rest of the world the demand for quality of products and services might well have arisen through the demise of the craftsman, concurrent with a change in emphasis from quality and workmanship towards economy and output. In the beginning this metamorphosis had its virtues, when rationalisation of production methods benefited both producer and consumer. However, the increasing pressure on production in virtually all sectors of commerce and industry inevitably lead to a trend towards cutting corners, a philosophy not conducive to increasing the standards of quality. The shortage of skilled manpower began to make itself felt at about the same time. The civil construction industry did not remain unscathed

  15. Is quality assurance really necessary

    Energy Technology Data Exchange (ETDEWEB)

    Elwen, L

    1983-03-01

    The modern concept of quality assurance began to take root in the 50's in Japan. In the rest of the world the demand for quality of products and services might well have arisen through the demise of the craftsman, concurrent with a change in emphasis from quality and workmanship towards economy and output. In the beginning this metamorphosis had its virtues, when rationalisation of production methods benefited both producer and consumer. However, the increasing pressure on production in virtually all sectors of commerce and industry inevitably lead to a trend towards cutting corners, a philosophy not conducive to increasing the standards of quality. The shortage of skilled manpower began to make itself felt at about the same time. The civil construction industry did not remain unscathed.

  16. Islay development flow assurance challenges

    Energy Technology Data Exchange (ETDEWEB)

    Helingoe, Mark; Greder, Hugues

    2010-07-01

    The Islay field is located in the Northern North Sea UK sector in the vicinity of the Alwyn Platforms. This gas condensate Brent structure is planned to be developed subsea with first gas in 2011. The main development challenge for this HPHT field comes from the early expected formation water production which is the source of major hydrate related flow assurance issues. As continuous inhibition is not feasible, Total has progressed a development scenario based on seabed conditioning prior to pipe laying so that water can be collected and temporarily inhibited at specific low points after a shut-down. It is also intended to heat trace the pipeline as a back-up solution to avoid hydrate formation. Heat tracing has so far never been implemented in Subsea developments. The Islay pilot could open the path to a new hydrate management philosophy for future developments. (Author)

  17. Quality assurance and quality control

    International Nuclear Information System (INIS)

    Kaden, W.

    1986-01-01

    General preconditions and methods for QA work in the nuclear field are analysed. The application of general QA principles to actual situations is illustrated by examples in the fields of engineering and of the manufacturing of mechanical and electrical components. All QA measures must be fitted to the complexity and relevance of the work steps, which are under consideration. The key to good product quality is the control of working processes. The term 'controlled process' is discussed in detail and examples of feed back systems are given. The main QA measures for the operation of nuclear power plants include the establishment of a Quality Assurance Program, training and qualification of personnel, procurement control, inspection and tests, reviews and audits. These activities are discussed. (orig.)

  18. Statistical methods for quality assurance

    International Nuclear Information System (INIS)

    Rinne, H.; Mittag, H.J.

    1989-01-01

    This is the first German-language textbook on quality assurance and the fundamental statistical methods that is suitable for private study. The material for this book has been developed from a course of Hagen Open University and is characterized by a particularly careful didactical design which is achieved and supported by numerous illustrations and photographs, more than 100 exercises with complete problem solutions, many fully displayed calculation examples, surveys fostering a comprehensive approach, bibliography with comments. The textbook has an eye to practice and applications, and great care has been taken by the authors to avoid abstraction wherever appropriate, to explain the proper conditions of application of the testing methods described, and to give guidance for suitable interpretation of results. The testing methods explained also include latest developments and research results in order to foster their adoption in practice. (orig.) [de

  19. Basic principles of quality assurance

    International Nuclear Information System (INIS)

    Stauffer, M.

    1977-01-01

    After a brief review of the origin of the 'quality concept' and the historical development of quality assurance, questions such as 'what is QA' and 'why is QA so important in nuclear technology' as well as definitions and main requirements of relevant QA codes and standards are presented and discussed. By means of a project realization schematic, tasks, duties, responsibilities, and possible QA organigrammes as well as QA programme and manual requirements are explained and compared. From a QA point of view, it is shown that no basic difference exists between design and production or construction control activities. Special emphasis is layed upon active owner's participation in the implementation of QA programmes for NPP and the advantages offered are described and illustrated by typical examples. (RW) [de

  20. Comparative Prevalence of Immune Evasion Complex Genes Associated with β-Hemolysin Converting Bacteriophages in MRSA ST5 Isolates from Swine, Swine Facilities, Humans with Swine Contact, and Humans with No Swine Contact.

    Directory of Open Access Journals (Sweden)

    Samantha J Hau

    Full Text Available Livestock associated methicillin-resistant Staphylococcus aureus (LA-MRSA draws concern from the public health community because in some countries these organisms may represent the largest reservoir of MRSA outside hospital settings. Recent studies indicate LA-MRSA strains from swine are more genetically diverse than the first reported sequence type ST398. In the US, a diverse population of LA-MRSA is found including organisms of the ST398, ST9, and ST5 lineages. Occurrence of ST5 MRSA in swine is of particular concern since ST5 is among the most prevalent lineages causing clinical infections in humans. The prominence of ST5 in clinical disease is believed to result from acquisition of bacteriophages containing virulence or host-adapted genes including the immune-evasion cluster (IEC genes carried by β-hemolysin converting bacteriophages, whose absence in LA-MRSA ST398 is thought to contribute to reduced rates of human infection and transmission associated with this lineage. The goal of this study was to investigate the prevalence of IEC genes associated with β-hemolysin converting bacteriophages in MRSA ST5 isolates obtained from agricultural sources, including swine, swine facilities, and humans with short- or long-term swine exposure. To gain a broader perspective, the prevalence of these genes in LA-MRSA ST5 strains was compared to the prevalence in clinical MRSA ST5 strains from humans with no known exposure to swine. IEC genes were not present in any of the tested MRSA ST5 strains from agricultural sources and the β-hemolysin gene was intact in these strains, indicating the bacteriophage's absence. In contrast, the prevalence of the β-hemolysin converting bacteriophage in MRSA ST5 strains from humans with no exposure to swine was 90.4%. The absence of β-hemolysin converting bacteriophage in LA-MRSA ST5 isolates is consistent with previous reports evaluating ST398 strains and provides genetic evidence indicating LA-MRSA ST5 isolates