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Sample records for assurance requirements documents

  1. 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

  2. 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

  3. 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

  4. Quality Assurance Source Requirements Traceability Database

    International Nuclear Information System (INIS)

    MURTHY, R.; NAYDENOVA, A.; DEKLEVER, R.; BOONE, A.

    2006-01-01

    At the Yucca Mountain Project the Project Requirements Processing System assists in the management of relationships between regulatory and national/industry standards source criteria, and Quality Assurance Requirements and Description document (DOE/R W-0333P) requirements to create compliance matrices representing respective relationships. The matrices are submitted to the U.S. Nuclear Regulatory Commission to assist in the commission's review, interpretation, and concurrence with the Yucca Mountain Project QA program document. The tool is highly customized to meet the needs of the Office of Civilian Radioactive Waste Management Office of Quality Assurance

  5. 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

  6. Hanford analytical services quality assurance requirements documents. Volume 1: Administrative Requirements

    International Nuclear Information System (INIS)

    Hyatt, J.E.

    1997-01-01

    Hanford Analytical Services Quality Assurance Requirements Document (HASQARD) is issued by the Analytical Services, Program of the Waste Management Division, US Department of Energy (US DOE), Richland Operations Office (DOE-RL). The HASQARD establishes quality requirements in response to DOE Order 5700.6C (DOE 1991b). The HASQARD is designed to meet the needs of DOE-RL for maintaining a consistent level of quality for sampling and field and laboratory analytical services provided by contractor and commercial field and laboratory analytical operations. The HASQARD serves as the quality basis for all sampling and field/laboratory analytical services provided to DOE-RL through the Analytical Services Program of the Waste Management Division in support of Hanford Site environmental cleanup efforts. This includes work performed by contractor and commercial laboratories and covers radiological and nonradiological analyses. The HASQARD applies to field sampling, field analysis, and research and development activities that support work conducted under the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement and regulatory permit applications and applicable permit requirements described in subsections of this volume. The HASQARD applies to work done to support process chemistry analysis (e.g., ongoing site waste treatment and characterization operations) and research and development projects related to Hanford Site environmental cleanup activities. This ensures a uniform quality umbrella to analytical site activities predicated on the concepts contained in the HASQARD. Using HASQARD will ensure data of known quality and technical defensibility of the methods used to obtain that data. The HASQARD is made up of four volumes: Volume 1, Administrative Requirements; Volume 2, Sampling Technical Requirements; Volume 3, Field Analytical Technical Requirements; and Volume 4, Laboratory Technical Requirements. Volume 1 describes the administrative requirements

  7. 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

  8. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1993-01-01

    This Mined Geologic Disposal System Requirements document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) and commercial and defense high level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The development and control of the MGDS-RD is quality-affecting work and is subject to the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Quality Assurance Requirements Document (QARD). As part of the technical requirements baseline, it is also subject to Baseline Management Plan controls. The MGDS-RD and the other program-level requirements documents have been prepared and managed in accordance with the Technical Document Preparation Plan (TDPP) for the Preparation of System Requirements Documents

  9. Quality assurance program preparation - review of requirements and plant systems - selection of program levels

    International Nuclear Information System (INIS)

    Asmuss, G.

    1980-01-01

    The establishment and implementation for a practicable quality assurance program for a nuclear power plant demands a detailed background in the field of engineering, manufacturing, organization and quality assurance. It will be demonstrated with examples to define and control the achievement of quality related activities during the phases of design, procurement, manufactoring, commissioning and operation. In general the quality assurance program applies to all items, processes and services important to safety of nuclear power plant. The classification for safety related and non-safety related items and services demonstrate the levels of quality assurance requirements. The lecture gives an introduction of QA Program preparation under the following topics: -Basic criteria and international requirements - Interaction of QA activities - Modular and product oriented QA programs - Structuring of organization for the QA program - Identification of the main quality assurance functions and required actions - Quality Assurance Program documentation - Documentation of planning of activities - Control of program documents - Definitions. (orig./RW)

  10. 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

  11. 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)

  12. 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.)

  13. Quality assurance requirements and methods for high level waste package acceptability

    International Nuclear Information System (INIS)

    1992-12-01

    This document should serve as guidance for assigning the necessary items to control the conditioning process in such a way that waste packages are produced in compliance with the waste acceptance requirements. It is also provided to promote the exchange of information on quality assurance requirements and on the application of quality assurance methods associated with the production of high level waste packages, to ensure that these waste packages comply with the requirements for transportation, interim storage and waste disposal in deep geological formations. The document is intended to assist both the operators of conditioning facilities and repositories as well as national authorities and regulatory bodies, involved in the licensing of the conditioning of high level radioactive wastes or in the development of deep underground disposal systems. The document recommends the quality assurance requirements and methods which are necessary to generate data for these parameters identified in IAEA-TECDOC-560 on qualitative acceptance criteria, and indicates where and when the control methods can be applied, e.g. in the operation or commissioning of a process or in the development of a waste package design. Emphasis is on the control of the process and little reliance is placed on non-destructive or destructive testing. Qualitative criteria, relevant to disposal of high level waste, are repository dependent and are not addressed here. 37 refs, 3 figs, 2 tabs

  14. Functional requirements document for measuring emissions of airborne radioactive materials

    International Nuclear Information System (INIS)

    Glissmeyer, J.A.; Alvarez, J.L.; Hoover, M.D.; Newton, G.C.; McFarland, A.R.; Rodgers, J.C.

    1994-11-01

    This document states the general functional requirements for systems and procedures for measuring emissions of airborne radioactive materials from facilities administered by the Westinghouse Hanford Company (WHC). The following issues are addressed in this document: lg-bullet definition of the program objectives lg-bullet selection of the overall approach to collecting the samples lg-bullet sampling equipment design lg-bullet sampling equipment maintenance and quality assurance issues. The following issues are not addressed in this document: lg-bullet air sampling in work areas or containments lg-bullet selection of specific on-line sample monitoring instrumentation lg-bullet analyzing collected samples lg-bullet reporting and interpreting results. The document provides equipment design guidance that is performance based rather than prescriptive. Locations from which samples are obtained should exhibit mixing of the contaminants with the airstream and acceptable air flow characteristics. Sample collection equipment and effluent and sample flow elements should meet defined performance standards. Quality control and assurance requirements specific to sample collection, equipment inspection, and calibration are presented. Key sample collection performance requirements are summarized in Section 5.4. The intent of this document is to assist WHC in demonstrating a high quality of air emission measurements with verified system performance based on documented system design, testing, inspection, and maintenance

  15. Quality assurance when documenting chemical hazards to health and environment

    International Nuclear Information System (INIS)

    Guttormsen, R.; Modahl, S.I.; Tufto, P.A.; Buset, H.

    1991-01-01

    In a joint project between The Norwegian Petroleum Directorate (NPD), the State Pollution Control Agency (SFT) and Conoco Norway Inc. (CNI) we have evaluated the use of quality assurance principles in connection with development and distribution of information about chemicals. Assuring quality of the documentation is first of all depending on: the work in international organizations; the content of national and international guidelines and criteria documents; the use of product registers; activities in manufacturers' organizations; the role of importers and agents. These are aspects which have been evaluated. Recommendations are given in this paper concerning: definition of responsibilities in regulations, standards and guidelines; feedback of experience and coordination through international work; application of quality assurance principles in the use of information technology in international organizations and in manufacturers' organizations; use of quality assurance principles in validation of data

  16. General review of quality assurance system requirements. The utility or customer requirement

    International Nuclear Information System (INIS)

    Fowler, J.L.

    1976-01-01

    What are the customer's Quality Assurance requirements and how does he convey these to his contractor, or apply them to himself. Many documents have been prepared mostly by countries with high technology availability and it is significant to note that many of the documents, particularly those of the United States of America, were prepared for nuclear safety related plant, but the logic of these documents equally applied to heavy engineering projects that are cost effective, and this is the current thinking and practice within the CEGB (Central Electricity Generating Board). Some documents have legislative backing, others rely on contractual disciplines, but they all appear to repeat the same basic requirements, so why does one continue to write more documents. The basic problem is that customers have to satisfy differing national legislative, economic and commercial requirements and, like all discerning customers, wish to reserve the right to satisfy their own needs, which are very often highly specialized. The CEGB are aware of this problem and are actively co-operating with most of the national and international authorities who are leading in this field, with a view to obtaining compatibility of requirements, but now there still remains the problem of satisfying national custom and practice. (author)

  17. Quality assurance requirements for the computer software and safety analyses

    International Nuclear Information System (INIS)

    Husarecek, J.

    1992-01-01

    The requirements are given as placed on the development, procurement, maintenance, and application of software for the creation or processing of data during the design, construction, operation, repair, maintenance and safety-related upgrading of nuclear power plants. The verification and validation processes are highlighted, and the requirements put on the software documentation are outlined. The general quality assurance principles applied to safety analyses are characterized. (J.B.). 1 ref

  18. Guidance and Control Software Project Data - Volume 4: Configuration Management and Quality Assurance Documents

    Science.gov (United States)

    Hayhurst, Kelly J. (Editor)

    2008-01-01

    The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes configuration management and quality assurance documents from the GCS project. Volume 4 contains six appendices: A. Software Accomplishment Summary for the Guidance and Control Software Project; B. Software Configuration Index for the Guidance and Control Software Project; C. Configuration Management Records for the Guidance and Control Software Project; D. Software Quality Assurance Records for the Guidance and Control Software Project; E. Problem Report for the Pluto Implementation of the Guidance and Control Software Project; and F. Support Documentation Change Reports for the Guidance and Control Software Project.

  19. 44 CFR 19.115 - Assurance required.

    Science.gov (United States)

    2010-10-01

    ... RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 19.115 Assurance required. (a) General. Either at the... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Assurance required. 19.115 Section 19.115 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF...

  20. 222-S Laboratory Quality Assurance Plan. Revision 1

    International Nuclear Information System (INIS)

    Meznarich, H.K.

    1995-01-01

    This Quality Assurance Plan provides,quality assurance (QA) guidance, regulatory QA requirements (e.g., 10 CFR 830.120), and quality control (QC) specifications for analytical service. This document follows the U.S Department of Energy (DOE) issued Hanford Analytical Services Quality Assurance Plan (HASQAP). In addition, this document meets the objectives of the Quality Assurance Program provided in the WHC-CM-4-2, Section 2.1. Quality assurance elements required in the Guidelines and Specifications for Preparing Quality Assurance Program Plans (QAMS-004) and Interim Guidelines and Specifications for Preparing Quality Assurance Project Plans (QAMS-005) from the US Environmental Protection Agency (EPA) are covered throughout this document. A quality assurance index is provided in the Appendix A. This document also provides and/or identifies the procedural information that governs laboratory operations. The personnel of the 222-S Laboratory and the Standards Laboratory including managers, analysts, QA/QC staff, auditors, and support staff shall use this document as guidance and instructions for their operational and quality assurance activities. Other organizations that conduct activities described in this document for the 222-S Laboratory shall follow this QA/QC document

  1. Bruce Power's nuclear pressure boundary quality assurance program requirements, implementation and transition

    International Nuclear Information System (INIS)

    Krane, J.C.

    2009-01-01

    The development of a full scope nuclear pressure boundary quality assurance program in Canada requires extensive knowledge of the structure and detailed requirements of codes and standards published by the Canadian Standards Association (CSA) and American Society of Mechanical Engineers (ASME). Incorporation into company governance documents and implementation of these requirements while managing the transition to more recent revisions of these codes and standards represents a significant challenge for Bruce Power, Canada's largest independent nuclear operator. This paper explores the key developments and innovative changes that are used to ensure successful regulatory compliance and effective implementation of the Bruce Power Pressure Boundary Quality Assurance Program. Challenges and mitigating strategies to sustain this large compliance based program at Bruce Power's 8 unit nuclear power plant site will also be detailed. (author)

  2. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    International Nuclear Information System (INIS)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years

  3. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Quality Assurance Functional Area Requirements Identification Document (RID), addresses the programmatic requirements that ensure risks and environmental impacts are minimized, ensure safety, reliability, and performance are maximized through the application of effective management systems commensurate with the risks posed by the Tank Farm Facility and its operation. This RID incorporates guidance intended to provide Tank Farms management with the necessary requirements information to develop, upgrade, or assess the effectiveness of a Quality Assurance Program in the performance of organizational and functional activities. Quality Assurance is defined as all those planned and systematic actions necessary to provide adequate confidence that a facility, structure, system, or component will perform satisfactorily and safely in service. This document will provide the specific requirements to meet DNFSB recommendations and the guidance provided in DOE Order 5700.6C, utilizing industry codes, standards, regulatory guidelines, and industry good practices that have proven to be essential elements for an effective and efficient Quality Assurance Program as the nuclear industry has matured over the last thirty years.

  4. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction

  5. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

  6. 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

  7. NASA software documentation standard software engineering program

    Science.gov (United States)

    1991-01-01

    The NASA Software Documentation Standard (hereinafter referred to as Standard) can be applied to the documentation of all NASA software. This Standard is limited to documentation format and content requirements. It does not mandate specific management, engineering, or assurance standards or techniques. This Standard defines the format and content of documentation for software acquisition, development, and sustaining engineering. Format requirements address where information shall be recorded and content requirements address what information shall be recorded. This Standard provides a framework to allow consistency of documentation across NASA and visibility into the completeness of project documentation. This basic framework consists of four major sections (or volumes). The Management Plan contains all planning and business aspects of a software project, including engineering and assurance planning. The Product Specification contains all technical engineering information, including software requirements and design. The Assurance and Test Procedures contains all technical assurance information, including Test, Quality Assurance (QA), and Verification and Validation (V&V). The Management, Engineering, and Assurance Reports is the library and/or listing of all project reports.

  8. Operational excellence (six sigma) philosophy: Application to software quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    Lackner, M.

    1997-11-01

    This report contains viewgraphs on operational excellence philosophy of six sigma applied to software quality assurance. This report outlines the following: goal of six sigma; six sigma tools; manufacturing vs administrative processes; Software quality assurance document inspections; map software quality assurance requirements document; failure mode effects analysis for requirements document; measuring the right response variables; and questions.

  9. 45 CFR 86.4 - Assurance required.

    Science.gov (United States)

    2010-10-01

    ... SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 86.4 Assurance required. (a) General. Every application for Federal financial assistance for any education... Director of such assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance...

  10. 10 CFR 1042.115 - Assurance required.

    Science.gov (United States)

    2010-01-01

    ... ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 1042.115 Assurance required. (a) General... applications for Federal financial assistance or awards of Federal financial assistance contain, be accompanied... assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance extended to provide...

  11. Future CANDU nuclear power plant design requirements document executive summary

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; S. A. Usmani

    1996-03-01

    The future CANDU Requirements Document (FCRED) describes a clear and complete statement of utility requirements for the next generation of CANDU nuclear power plants including those in Korea. The requirements are based on proven technology of PHWR experience and are intended to be consistent with those specified in the current international requirement documents. Furthermore, these integrated set of design requirements, incorporate utility input to the extent currently available and assure a simple, robust and more forgiving design that enhances the performance and safety. The FCRED addresses the entire plant, including the nuclear steam supply system and the balance of the plant, up to the interface with the utility grid at the distribution side of the circuit breakers which connect the switchyard to the transmission lines. Requirements for processing of low level radioactive waste at the plant site and spent fuel storage requirements are included in the FCRED. Off-site waste disposal is beyond the scope of the FCRED. 2 tabs., 1 fig. (Author) .new

  12. 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.)

  13. 22 CFR 146.115 - Assurance required.

    Science.gov (United States)

    2010-04-01

    ... PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 146.115 Assurance required. (a... applications for Federal financial assistance or awards of Federal financial assistance contain, be accompanied... assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance extended to provide...

  14. 49 CFR 25.115 - Assurance required.

    Science.gov (United States)

    2010-10-01

    ... PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 25.115 Assurance required. (a... applications for Federal financial assistance or awards of Federal financial assistance contain, be accompanied... assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance extended to provide...

  15. 22 CFR 229.115 - Assurance required.

    Science.gov (United States)

    2010-04-01

    ... PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 229.115 Assurance required. (a... applications for Federal financial assistance or awards of Federal financial assistance contain, be accompanied... assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance extended to provide...

  16. 45 CFR 605.5 - Assurances required.

    Science.gov (United States)

    2010-10-01

    ... ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE General Provisions § 605.5 Assurances required. (a) Assurances. Recipients of Federal financial assistance to which... purpose for which Federal financial assistance is extended or for another purpose involving the provision...

  17. 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

  18. 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

  19. 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

  20. Manpower requirements for quality assurance during operation

    International Nuclear Information System (INIS)

    Pratt, J.M.; Sollenberger, L.G.

    1982-01-01

    As a result of the Three Mile Island accident and the findings presented in various investigatory reports, some fundamental changes are taking place in the role and scope of quality assurance. Recent changes to United States national codes, guides and standards are analysed in order to identify the principles involved. This analysis shows that the scope of the programme is being extended beyond the equipment designated 'nuclear safety related' and greater emphasis is being placed upon the independent verification of the satisfactory performance of activities affecting safety. Such fundamental changes could lead to a significant increase in the number of quality assurance personnel required to support an operating nuclear power plant. The evolving quality assurance organization at Three Mile Island is used to illustrate how these fundamental changes could affect the quality assurance organization and manpower requirements. (author)

  1. U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.

  2. 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

  3. 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.

  4. 41 CFR 101-4.115 - Assurance required.

    Science.gov (United States)

    2010-07-01

    ... EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 101-4.115 Assurance... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Assurance required. 101-4.115 Section 101-4.115 Public Contracts and Property Management Federal Property Management Regulations...

  5. Development of quality assurance requirements - an international comparison

    Energy Technology Data Exchange (ETDEWEB)

    Link, M [Siemens AG, Bereich Energieerzeugung (KWU), Erlangen (Germany); Mertz, W [Siemens AG, Bereich Energieerzeugung (KWU), Offenbach am Main (Germany)

    1993-12-01

    Total quality management strategy and the worldwide introduction of the DIN/ISO 9000 (EN 29 000) series of standards have given new impetus to traditional quality assurance. The most important change must surely be seen in the holistic approach of total quality management and its strict orientation towards customer requirements and satisfaction. International codes and standards for the nuclear industry will also have to be brought into line as part of the process of harmonizing quality assurance system standards. One possible approach is simply to specify a supplementary 'delta' of nuclear-specific requirements to be appended to the broad range of conventional requirements. It is a particular feature of quality-assured procedures in Germany that product and/or component related quality requirements and quality verifications are defined in the specifications of the architect engineer so that full implementation of the requirements from the design phase through to the manufacturing phase is assured. Looking at the development of the European Pressurized Water Reactor (EPR) and the elaboration of 'Common Rules', it is to be anticipated that a major step will be made toward international harmonization of safety criteria. (orig.)

  6. Development of quality assurance requirements - an international comparison

    International Nuclear Information System (INIS)

    Link, M.; Mertz, W.

    1993-01-01

    Total quality management strategy and the worldwide introduction of the DIN/ISO 9000 (EN 29 000) series of standards have given new impetus to traditional quality assurance. The most important change must surely be seen in the holistic approach of total quality management and its strict orientation towards customer requirements and satisfaction. International codes and standards for the nuclear industry will also have to be brought into line as part of the process of harmonizing quality assurance system standards. One possible approach is simply to specify a supplementary 'delta' of nuclear-specific requirements to be appended to the broad range of conventional requirements. It is a particular feature of quality-assured procedures in Germany that product and/or component related quality requirements and quality verifications are defined in the specifications of the architect engineer so that full implementation of the requirements from the design phase through to the manufacturing phase is assured. Looking at the development of the European Pressurized Water Reactor (EPR) and the elaboration of 'Common Rules', it is to be anticipated that a major step will be made toward international harmonization of safety criteria. (orig.) [de

  7. Quality assurance requirements in various codes and standards

    International Nuclear Information System (INIS)

    Shaaban, H.I.; EL-Sayed, A.; Aly, A.E.

    1987-01-01

    The quality assurance requirements in various countries and according to various international codes and standards are presented, compared and critically discussed. Cases of developing countries are also discussed, and the use of IAEA code of practice and other codes for quality assurance in these countries is reviewed. Recommendations are made regarding the quality assurance system to be applied for Egypt's nuclear power plants

  8. 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

  9. Transportation System Requirements Document

    International Nuclear Information System (INIS)

    1993-09-01

    This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification

  10. 49 CFR 27.9 - Assurance required.

    Science.gov (United States)

    2010-10-01

    ... OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE General § 27.9 Assurance required. (a) General... requirements of this part for so long as the property is used for the purpose for which the Federal financial assistance was provided or for a similar purpose. (2) When Federal financial assistance is used by a...

  11. TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT

    International Nuclear Information System (INIS)

    2004-01-01

    This document establishes the Transportation system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are derived from the Civilian Radioactive Waste Management System Requirements Document (CRD). The Transportation System Requirements Document (TSRD) was developed in accordance with LP-3.1Q-OCRWM, Preparation, Review, and Approval of Office of National Transportation Level-2 Baseline Requirements. As illustrated in Figure 1, the TSRD forms a part of the DOE Office of Civilian Radioactive Waste Management (OCRWM) Technical Baseline

  12. Analysis of compatibility of current Czech initial documentation in the area of technical assurance of nuclear safety with the requirements of the EUR document

    International Nuclear Information System (INIS)

    Zdebor, J.; Zdebor, R.; Kratochvil, L.

    2001-11-01

    The publication is structured as follows: Description of existing documentation. General requirements, goals, principles and design principles: Documents being compared; Method of comparison; Results and partial evaluation of comparison of requirements between EUR and Czech regulations (basic goals and safety philosophy; quantitative safety objectives; basic design requirements; extended design requirements; external and internal threats; technical requirements; site conditions); Summary of the comparison of safety requirements. Comparison of requirements for the systems: Requirements for the nuclear reactor unit systems; Barrier systems (fuel system; reactor cooling system; containment system); Remaining systems (control systems; protection systems; coolant makeup and purification system; residual heat removal system; emergency cooling system; power systems); Common technical requirements for systems (technical requirements for systems; internal and external events). (P.A.)

  13. H2FIRST Hydrogen Contaminant Detector Task: Requirements Document and Market Survey

    Energy Technology Data Exchange (ETDEWEB)

    Terlip, Danny [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Ainscough, Chris [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Buttner, William [National Renewable Energy Laboratory (NREL), Golden, CO (United States); McWhorter, Scott [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-04-20

    The rollout of hydrogen fueling stations, and the fuel cell electric vehicles (FCEV) they support, requires the assurance of high quality hydrogen at the dispensing point. Automotive fuel cells are sensitive to a number of chemicals that can be introduced into the dispensed fuel at multiple points. Quality assurance and quality control methods are employed by the industry to ensure product quality, but they are not completely comprehensive and can fail at various points in the hydrogen pathway from production to dispensing. This reality leaves open the possibility of a station unknowingly dispensing harmful contaminants to a FCEV which, depending on the contaminant, may not be discovered until the FCEV is irreparably damaged. This situation is unacceptable. A hydrogen contaminant detector (HCD), defined as a combination of a gas analyzer and the components necessary for fuel stream integration, installed at hydrogen stations is one method for preventing poor quality gas from reaching an FCEV. This document identifies the characteristics required of such a device by industry and compares those requirements with the current state of commercially available gas analysis technology.

  14. Instructions for submittal and control of FFTF design documents and design related documentation

    International Nuclear Information System (INIS)

    Grush, R.E.

    1976-10-01

    This document provides the system and requirements for management of FFTF technical data prepared by Westinghouse Hanford (HEDL), and design contractors, the construction contractor and lower tier equipment suppliers. Included in this document are provisions for the review, approval, release, change control, and accounting of FFTF design disclosure and base documentation. Also included are provisions for submittal of other design related documents for review and approval consistent with applicable requirements of RDT-Standard F 2-2, ''Quality Assurance Program Requirements.''

  15. 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

  16. 40 CFR 75.21 - Quality assurance and quality control requirements.

    Science.gov (United States)

    2010-07-01

    ... quality assurance audit or any other audit, the system is out-of-control. The owner or operator shall... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Quality assurance and quality control... assurance and quality control requirements. (a) Continuous emission monitoring systems. The owner or...

  17. Framework for the quality assurance of 'omics technologies considering GLP requirements.

    Science.gov (United States)

    Kauffmann, Hans-Martin; Kamp, Hennicke; Fuchs, Regine; Chorley, Brian N; Deferme, Lize; Ebbels, Timothy; Hackermüller, Jörg; Perdichizzi, Stefania; Poole, Alan; Sauer, Ursula G; Tollefsen, Knut E; Tralau, Tewes; Yauk, Carole; van Ravenzwaay, Ben

    2017-12-01

    'Omics technologies are gaining importance to support regulatory toxicity studies. Prerequisites for performing 'omics studies considering GLP principles were discussed at the European Centre for Ecotoxicology and Toxicology of Chemicals (ECETOC) Workshop Applying 'omics technologies in Chemical Risk Assessment. A GLP environment comprises a standard operating procedure system, proper pre-planning and documentation, and inspections of independent quality assurance staff. To prevent uncontrolled data changes, the raw data obtained in the respective 'omics data recording systems have to be specifically defined. Further requirements include transparent and reproducible data processing steps, and safe data storage and archiving procedures. The software for data recording and processing should be validated, and data changes should be traceable or disabled. GLP-compliant quality assurance of 'omics technologies appears feasible for many GLP requirements. However, challenges include (i) defining, storing, and archiving the raw data; (ii) transparent descriptions of data processing steps; (iii) software validation; and (iv) ensuring complete reproducibility of final results with respect to raw data. Nevertheless, 'omics studies can be supported by quality measures (e.g., GLP principles) to ensure quality control, reproducibility and traceability of experiments. This enables regulators to use 'omics data in a fit-for-purpose context, which enhances their applicability for risk assessment. Copyright © 2017 Elsevier Inc. All rights reserved.

  18. 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.'

  19. 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

  20. Quality assurance requirements for dedication process in Angra 1

    Energy Technology Data Exchange (ETDEWEB)

    Baliza, Ana Rosa, E-mail: baliza@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento GQO.G; Morghi, Youssef, E-mail: ymo@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

  1. Quality assurance requirements for dedication process in Angra 1

    International Nuclear Information System (INIS)

    Baliza, Ana Rosa

    2015-01-01

    In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

  2. 10 CFR 5.115 - Assurance required.

    Science.gov (United States)

    2010-01-01

    ... FEDERAL FINANCIAL ASSISTANCE Introduction § 5.115 Assurance required. (a) General. Either at the application stage or the award stage, Federal agencies must ensure that applications for Federal financial assistance or awards of Federal financial assistance contain, be accompanied by, or be covered by a...

  3. Waste management system requirements document

    International Nuclear Information System (INIS)

    1991-02-01

    This volume defines the top level requirements for the Mined Geologic Disposal System (MGDS). It is designed to be used in conjunction with Volume 1 of the WMSR, General System Requirements. It provides a functional description expanding the requirements allocated to the MGDS in Volume 1 and elaborates on each requirement by providing associated performance criteria as appropriate. Volumes 1 and 4 of the WMSR provide a minimum set of requirements that must be satisfied by the final MGDS design. This document sets forth specific requirements that must be fulfilled. It is not the intent or purpose of this top level document to describe how each requirement is to be satisfied in the final MGDS design. Each subsequent level of the technical document hierarchy must provide further guidance and definition as to how each of these requirements is to be implemented in the design. It is expected that each subsequent level of requirements will be significantly more detailed. Section 2 of this volume provides a functional description of the MGDS. Each function is addressed in terms of requirements, and performance criteria. Section 3 provides a list of controlling documents. Each document cited in a requirement of Chapter 2 is included in this list and is incorporated into this document as a requirement on the final system. The WMSR addresses only federal requirements (i.e., laws, regulations and DOE orders). State and local requirements are not addressed. However, it will be specifically noted at the potentially affected WMSR requirements that there could be additional or more stringent regulations imposed by a state or local requirements or administering agency over the cited federal requirements

  4. The Groundwater Performance Assessment Project Quality Assurance Plan

    International Nuclear Information System (INIS)

    Luttrell, Stuart P.

    2006-01-01

    U.S. Department of Energy (DOE) has monitored groundwater on the Hanford Site since the 1940s to help determine what chemical and radiological contaminants have made their way into the groundwater. As regulatory requirements for monitoring increased in the 1980s, there began to be some overlap between various programs. DOE established the Groundwater Performance Assessment Project (groundwater project) in 1996 to ensure protection of the public and the environment while improving the efficiency of monitoring activities. The groundwater project is designed to support all groundwater monitoring needs at the site, eliminate redundant sampling and analysis, and establish a cost-effective hierarchy for groundwater monitoring activities. This document provides the quality assurance guidelines that will be followed by the groundwater project. This QA Plan is based on the QA requirements of DOE Order 414.1C, Quality Assurance, and 10 CFR 830, Subpart A--General Provisions/Quality Assurance Requirements as delineated in Pacific Northwest National Laboratory's Standards-Based Management System. In addition, the groundwater project is subject to the Environmental Protection Agency (EPA) Requirements for Quality Assurance Project Plans (EPA/240/B-01/003, QA/R-5). The groundwater project has determined that the Hanford Analytical Services Quality Assurance Requirements Documents (HASQARD, DOE/RL-96-68) apply to portions of this project and to the subcontractors. HASQARD requirements are discussed within applicable sections of this plan

  5. 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

  6. Regulatory requirements and quality assurance of radiation monitoring instruments

    International Nuclear Information System (INIS)

    Narasimharao, K.L.; Sharma, Ranjit

    2005-01-01

    The successful utilisation of radiation sources in the fields of medicine and industry requires the accurate measurement of activity, exposure rate and dose. Many varieties of instruments are in use for measurement of these parameters and new ones are being developed. The criteria for the design of the radiation monitoring instrument include the type and intensity of the radiation, purpose of measurement and ruggedness of the instrument. Quality and reliability of radiation monitoring instruments ensure that individuals are adequately protected. Accuracy, response time and ruggedness are required to be as per the approved/ prescribed guidelines. Regulatory authorities outline the design and performance criteria for radiation monitoring instruments and prescribe the recommendations of international agencies such as IAEA, ICRU and ISO for radiological measurement assurance programme. National Standards Laboratories all over the world prescribe procedures for calibration of various radiation monitoring instruments. The instruments should be calibrated as per these guidelines and should be traceable to national standards. The calibration traceable to national/ international standards and documentation as well as limits stipulated by the competent authority ensures the expected performance of the instrument. (author)

  7. How does one develop the right quality assurance program for waste management projects?

    International Nuclear Information System (INIS)

    Hedges, D.

    1988-01-01

    The quality assurance requirements in use today for radioactive waste facilities, geologic repositories and hazardous waste projects were developed initially for the nuclear power plant industry, and their intent is being applied to regulations and guidance documents to radioactive and hazardous waste programs. The wording of the Nuclear Regulatory Commission (NRC) quality assurance (QA) requirements in Appendix B of 10CFR50, the related guidance documents and the industry's ANSI/ASME NQA-1 were developed over a period of several years to address quality assurance for the design and construction of the complex and interactive systems to produce electrical power using nuclear fuel. Now, those same documents are the basis for the quality assurance requirements and guidance for waste management facilities and repositories. The intent of Appendix B of 10CFR50 and NQA-1 can easily be applied to waste projects providing one understands and uses the intent of the requirements. This paper describes the intent of existing QA requirements as they apply to radioactive and hazardous waste programs. Methods of ensuring that the quality assurance program design will be acceptable to DOE and regulatory agencies are illustrated

  8. How does one develop the right quality assurance program for waste management projects?

    International Nuclear Information System (INIS)

    Hedges, D.

    1988-01-01

    The quality assurance requirements in use today for radioactive waste facilities, geologic repositories and hazardous waste projects were developed initially for the nuclear power plant industry, and their intent is being applied by regulations and guidance documents to radioactive and hazardous waste programs. The wording of the NRC quality assurance requirements in Appendix B of 10CFR50, the related guidance documents and the industry's ANSI/ASME NQA-1 were developed over a period of several years to address quality assurance for the design and construction of the complex and interactive systems to produce electrical power using nuclear fuel. Now, those same documents are the basis for the quality assurance requirements and guidance for waste management facilities and repositories. The intent of Appendix B of 10CFR50 and NQA-1 can easily be applied to waste projects, providing one understands and uses the intent of the requirements. This paper describes the intent of existing QA requirements as they apply to radioactive and hazardous waste programs. Methods of ensuring that the quality assurance program design will be acceptable to DOE and regulatory agencies are illustrated

  9. 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

  10. 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

  11. Legacy Management CERCLA Sites. Quality Assurance Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Riddle, Donna L.

    2007-05-03

    S.M. Stoller Corporation is the contractor for the Technical Assistance Contract (TAC) for the U.S. Department of Energy (DOE) Office of Legacy Management (LM) operations. Stoller employs a management system that applies to all programs, projects, and business management systems funded through DOE-LM task orders. The management system incorporates the philosophy, policies, and requirements of health and safety, environmental compliance, and quality assurance (QA) in all aspects of project planning and implementation. Health and safety requirements are documented in the Health and Safety Manual (STO 2), the Radiological Control Manual (STO 3), the Integrated Safety Management System Description (STO 10), and the Drilling Health and Safety Requirements (STO 14). Environmental compliance policy and requirements are documented in the Environmental Management Program Implementation Manual (STO 11). The QA Program is documented in the Quality Assurance Manual (STO 1). The QA Manual (STO 1) implements the specific requirements and philosophy of DOE Order 414.1C, Quality Assurance. This manual also includes the requirements of other standards that are regularly imposed by customers, regulators, or other DOE orders. Title 10 Code of Federal Regulations Part 830, “Quality Assurance Requirements,” ANSI/ASQC E4-2004, “Quality Systems for Environmental Data and Technology Programs – Requirements with Guidance for Use,” and ISO 14001-2004, “Environmental Management Systems,” have been included. These standards are similar in content. The intent of the QA Manual (STO 1) is to provide a QA management system that incorporates the requirements and philosophy of DOE and other customers within the QA Manual. Criterion 1, “Quality Assurance Program,” identifies the fundamental requirements for establishing and implementing the QA management system; QA Instruction (QAI) 1.1, “QA Program Implementation,” identifies the TAC organizations that have responsibility for

  12. Legacy Management CERCLA Sites. Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    2007-01-01

    S.M. Stoller Corporation is the contractor for the Technical Assistance Contract (TAC) for the U.S. Department of Energy (DOE) Office of Legacy Management (LM) operations. Stoller employs a management system that applies to all programs, projects, and business management systems funded through DOE-LM task orders. The management system incorporates the philosophy, policies, and requirements of health and safety, environmental compliance, and quality assurance (QA) in all aspects of project planning and implementation. Health and safety requirements are documented in the Health and Safety Manual (STO 2), the Radiological Control Manual (STO 3), the Integrated Safety Management System Description (STO 10), and the Drilling Health and Safety Requirements (STO 14). Environmental compliance policy and requirements are documented in the Environmental Management Program Implementation Manual (STO 11). The QA Program is documented in the Quality Assurance Manual (STO 1). The QA Manual (STO 1) implements the specific requirements and philosophy of DOE Order 414.1C, Quality Assurance. This manual also includes the requirements of other standards that are regularly imposed by customers, regulators, or other DOE orders. Title 10 Code of Federal Regulations Part 830, 'Quality Assurance Requirements', ANSI/ASQC E4-2004, 'Quality Systems for Environmental Data and Technology Programs - Requirements with Guidance for Use', and ISO 14001-2004, 'Environmental Management Systems', have been included. These standards are similar in content. The intent of the QA Manual (STO 1) is to provide a QA management system that incorporates the requirements and philosophy of DOE and other customers within the QA Manual. Criterion 1, 'Quality Assurance Program', identifies the fundamental requirements for establishing and implementing the QA management system; QA Instruction (QAI) 1.1, 'QA Program Implementation', identifies the TAC organizations that have responsibility for implementing the QA

  13. 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.)

  14. Quality assurance - not only for engineers

    International Nuclear Information System (INIS)

    Treffner, F.W.

    1984-01-01

    The actual purpose of quality assurance is the definition of effective processes, ways and means of planning, fabricating and obtaining the required characteristics determining the quality of components, subsystems and their fabrication techniques at any place and any time. Service companies can contribute quality assurance, quality control and documentation work do cost-benefit analyses and act as expert consultants. (orig.) [de

  15. UMTRA project technical assistance contractor quality assurance implementation plan

    International Nuclear Information System (INIS)

    1994-03-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance contractor (TAC) Quality Assurance Implementation Plan (QAIP) outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QAIP is subordinate to the latest issue of the UMTRA Project TAC Quality Assurance Program Plan (QAPP) (DOE, 1993a), which was developed using US Department of Energy (DOE) Order 5700.6C quality assurance (QA) criteria. The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. All QA issues in the QAIP shall comply with requirements contained in the TAC QAPP (DOE, 1933a). Because industry standards for data acquisition and data control are not addressed in DOE Order 5700.6C, the QAIP has been formatted to the 14 US Environmental Protection Agency (EPA) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) QA requirements. DOE Order 5700.6C criteria that are not contained in the CERCLA requirements are added to the QAIP as additional requirements in Sections 15.0 through 18.0. Project documents that contain CERCLA requirements and 5700.6 criteria shall be referenced in this document to avoid duplication. Referenced documents are not included in this QAIP but are available through the UMTRA Project Document Control Center

  16. Revision of Krsko NPP Quality Assurance Plan

    International Nuclear Information System (INIS)

    Biscan, R.; Fifnja, I.; Kavsek, D.

    2012-01-01

    International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

  17. Civilian Radioactive Waste Management System Requirements Document

    International Nuclear Information System (INIS)

    1992-12-01

    This document specifies the top-level requirements for the Civilian Radioactive Waste Management System (CRWMS). The document is referred to herein as the CRD, for CRWMS Requirements document. The OCRWM System Engineering Management Plan (SEMP) establishes the technical document hierarchy (hierarchy of technical requirements and configuration baseline documents) for the CRWMS program. The CRD is the top-level document in this hierarchy. The immediate subordinate documents are the System Requirements Documents (SRDS) for the four elements of the CRWMS and the Interface Specification (IFS). The four elements of the CRWMS are the Waste Acceptance System, the Transportation System, the Monitored Retrievable Storage (MRS) System and the Mined Geologic Disposal System (MGDS). The Interface Specification describes the six inter-element interfaces between the four elements. This hierarchy establishes the requirements to be addressed by the design of the system elements. Many of the technical requirements for the CRWMS are documented in a variety of Federal regulations, DOE directives and other Government documentation. It is the purpose of the CRD to establish the technical requirements for the entire program. In doing so, the CRD summarizes source documentation for requirements that must be addressed by the program, specifies particular requirements, and documents derived requirements that are not covered in regulatory and other Government documentation, but are necessary to accomplish the mission of the CRWMS. The CRD defines the CRWMS by identifying the top-level functions the elements must perform (These top-level functions were derived using functional analysis initially documented in the Physical System Requirements (PSR) documents). The CRD also defines the top-level physical architecture of the system and allocates the functions and requirements to the architectural elements of the system

  18. The Columbia River Protection Supplemental Technologies Quality Assurance Project Plan

    International Nuclear Information System (INIS)

    Fix, Anne

    2007-01-01

    The U.S. Department of Energy (DOE) has conducted interim groundwater remedial activities on the Hanford Site since the mid-1990s for several groundwater contamination plumes. DOE established the Columbia River Protection Supplemental Technologies Project (Technologies Project) in 2006 to evaluate alternative treatment technologies. The objectives for the technology project are as follows: develop a 300 Area polyphosphate treatability test to immobilize uranium, design and test infiltration of a phosphate/apatite technology for Sr-90 at 100-N, perform carbon tetrachloride and chloroform attenuation parameter studies, perform vadose zone chromium characterization and geochemistry studies, perform in situ biostimulation of chromium studies for a reducing barrier at 100-D, and perform a treatability test for phytoremediation for Sr-90 at 100-N. This document provides the quality assurance guidelines that will be followed by the Technologies Project. This Quality Assurance Project Plan is based on the quality assurance requirements of DOE Order 414.1C, Quality Assurance, and 10 CFR 830, Subpart A--Quality Assurance Requirements as delineated in Pacific Northwest National Laboratory?s Standards-Based Management System. In addition, the technology project is subject to the Environmental Protection Agency (EPA) Requirements for Quality Assurance Project Plans (EPA/240/B-01/003, QA/R-5). The Hanford Analytical Services Quality Assurance Requirements Documents (HASQARD, DOE/RL-96-68) apply to portions of this project and to the subcontractors. HASQARD requirements are discussed within applicable sections of this plan.

  19. Quality assurance requirements for packaging and transportation of radioactive materials

    International Nuclear Information System (INIS)

    Barker, R.F.; MacDonald, C.E.; Doda, R.J.

    1978-01-01

    This paper discusses the new quality assurance regulations of the Nuclear Regulatory Commission (NRC) for packaging and transportation of radioactive materials. These regulations became effective on October 18, 1977. Background information concerning these regulations and packaging and transportation history is included. The quality assurance program is described with indications of how it is composed of general (administrative) provisions which must meet the 18 quality assurance criteria and be approved by the NRC; specific provisions which appear in the DOT and NRC regulations and in the individual package design approval; and other specific procedures which are not required by regulations but which are necessary for the proper control of quality. The quality assurance program is to be developed using a graded approach for the application of pertinent criteria and optimizing the required degree of safety and control efforts involved in achieving this level of safety. The licensee-user is responsible for all phases of quality assurance for packaging activities including: design, manufacture, test, use, maintenance and repair. The package design phase is considered to be particularly important in producing adequate safety in operational activities concerning packaging and transportation of radioactive materials

  20. 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)

  1. 7 CFR 15a.4 - Assurance required.

    Science.gov (United States)

    2010-01-01

    ... FEDERAL FINANCIAL ASSISTANCE Introduction § 15a.4 Assurance required. (a) General. Every application for Federal financial assistance for any education program or activity shall as condition of its approval... Federal financial assistance to a transferee which operates any education program or activity, and the...

  2. 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

  3. LASL computerized quality assurance record-keeping system for analytical chemistry

    International Nuclear Information System (INIS)

    Dahlby, J.W.; Phillips, J.R.

    1976-06-01

    Research programs requiring quality assurance surveillance, certification procedures, and associated record keeping have increased markedly at the Los Alamos Scientific Laboratory. A computer-based system, accessible through time-sharing terminals, performs many routine operations, including continued records updating for equipment calibration, personnel certification, quality assurance procedure listings, and controlled-document distribution lists. The system described has operated successfully for more than a year, resulting in a significant savings in man-hours required to keep quality assurance records

  4. Requirements for, and training and certification of, quality assurance technicians for nuclear power plants

    International Nuclear Information System (INIS)

    Saiz, A.; Mir, A.; Serrano, J.

    1982-01-01

    The paper examines the requirements for, and training and certification of, technicians working in a quality assurance department at periods when the site, the main supplier and the engineering firm are being selected for construction, commissioning and operation of a light-water nuclear power plant with an output of approximately 1000 MW(e). In determining the system to be applied for the present work, account is taken of the special fields of engineering, supply, commissioning and operation. To this end, an analysis is made of the necessary organization, pointing out the number of technicians in each of the phases mentioned, and the necessary experience and knowledge required for discharging the functions indicated and for obtaining the appropriate certification. The second generation of Spanish nuclear power stations - about 7500MW(e) - demonstrated the need for quality assurance technicians. The Spanish Atomic Forum, a member of Foratom, is the first Spanish body to deal with the problem of training of such technicians at the national level through holding of seminars. This led to the appearance (in April 1974) of the first publication in Spanish on these techniques, a document which is still being used for teaching purposes. Later, it was the university and the professional associations which, with the support of the State Administration, undertook to provide this instruction. The paper also analyses Spanish experience in the teaching of quality assurance techniques during the period 1975-80, describing the programmes and contents of the courses

  5. The quality assurance practice in Spain

    International Nuclear Information System (INIS)

    Mugica, A.P.

    1980-01-01

    Even when the basic requirements for a Quality Assurance Program are delineated in documents such as the Code of Federal Regulations or Standards like ANSI N 45. 2, the way in which these requirements are put into practice is very dependent on the organization to which they are applied. So, in order to approach accurately the Quality Assurance practice and experience in Spain, the legal and industrial scenario must be considered. We are trying to present an outlook of the Spanish Energy Plan, Regulations and Nuclear Industry. (orig.)

  6. Quality assurance during site construction. Pt. 1

    International Nuclear Information System (INIS)

    Mueller, J.

    1980-01-01

    The first part of the lecture deals with the Quality Assurance system on the construction site in general. Basic site-related problems during contract implementation and the QA system requirements resulting from them are presented. The compilation of these requirements in a QA program and its inclusion in the site manual in written form are explained. Site organization, personnel qualification and procedures are referred to. Whereas the first part shows what is to be done, the second part shows how it can be put into practice on the site. All the essential points for the assurance of quality are addressed. They include, e.g., review of documents, incoming goods control, in-process surveillance, store controls, identification of components and systems, dealing with changes and deviations, documentation control and audits. By means of examples taken form practice the necessity of a well-functioning QA system, and the importance of quality-assuring measures on the site are pointed out. (orig.)

  7. Software requirements elicitation to support internal monitoring of quality assurance system for higher education in Indonesia

    Science.gov (United States)

    Amalia, A.; Gunawan, D.; Hardi, S. M.; Rachmawati, D.

    2018-02-01

    The Internal Quality Assurance System (in Indonesian: SPMI (Sistem Penjaminan Mutu Internal) is a systemic activity of quality assurance of higher education in Indonesia. SPMI should be done by all higher education or universities in Indonesia based on the Regulation of the Minister of Research, Technology and Higher Education of the Republic of Indonesia Number 62 of 2016. Implementation of SPMI must refer to the principle of SPMI that is independent, standardize, accurate, well planned and sustainable, documented and systematic. To assist the SPMI cycle properly, universities need a supporting software to monitor all the activities of SPMI. But in reality, many universities are not optimal in building this SPMI monitoring system. One of the obstacles is the determination of system requirements in support of SPMI principles is difficult to achieve. In this paper, we observe the initial phase of the engineering requirements elicitation. Unlike other methods that collect system requirements from users and stakeholders, we find the system requirements of the SPMI principles from SPMI guideline book. The result of this paper can be used as a choice in determining SPMI software requirements. This paper can also be used by developers and users to understand the scenario of SPMI so that could overcome the problems of understanding between this two parties.

  8. Supplementary quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel during the construction phase of nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    This standard sets forth the supplementary quality assurance requirements for installation, inspection, and testing of structural concrete and structural steel for nuclear power plant construction. The requirements may also be extended to other appropriate parts of nuclear power plants when specified in contract documents. This standard is intended to be used in conjunction with ANSI N45.2

  9. Office of Geologic Repositories quality assurance plan for high-level radioactive waste repositories

    International Nuclear Information System (INIS)

    1986-08-01

    This document sets forth geologic repository program-wide quality assurance program requirements and defines management's quality assurance responsibilities for the Office of Geologic Repositories and its projects. (LM)

  10. 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

  11. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    International Nuclear Information System (INIS)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard

    2013-01-01

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  12. Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282

    Energy Technology Data Exchange (ETDEWEB)

    Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

    2013-07-01

    The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

  13. Software quality assurance documentation for the release of NUFT 2.0 for HP platforms

    International Nuclear Information System (INIS)

    Fernandez, M.W.; Preckshot, G.G.; Johnson, G.L.

    1998-01-01

    section 1.1 above, to meet the applicable requirements of 033-YMP-QP 3.2, and to establish a Version 2.0 baseline for subsequent qualifications of NUFT for additional problems or for use on additional platforms. The detailed requirements applicable to the class of problems for which this release is applicable will be defined in the NUFT 2.0 Requirements Document. The scope of this ISP is limited to NUFT. Auxiliary software such as the post-processing tool XTOOL, YMESH, -and RADPRO, which are often used in conjunction with NUFT, will be addressed separately as needed. Version 2.0 is the first quality controlled release for the NUFT software. Additional releases are anticipated. NUFT Version 2.0 is acquired software, as defined by 033- YMP-QP 3.2. Version 1 .O was released in February 1998, but that certification is being withdrawn based upon the quality assurance surveillance findings described in LLNL-98- D-065

  14. Office of Storage and Transportation Systems quality assurance directive

    International Nuclear Information System (INIS)

    1986-10-01

    This Directive provides policy guidance, defines organizational authorities and responsibilities for quality assurance (QA) and establishes minimum acceptable requirements for assuring the quality of all programs under the overall direction of the OSTS. This directive provides guidance for preparation of subordinate QA documents (e.g., QA plans, procedures) for the major Office of Storage and Transportation Systems programs that support DOE licensing and/or certification objectives. In turn, those highly specific QA documents will amplify the general guidance presented in this Directive

  15. SWiFT Software Quality Assurance Plan.

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Jonathan Charles [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    This document describes the software development practice areas and processes which contribute to the ability of SWiFT software developers to provide quality software. These processes are designed to satisfy the requirements set forth by the Sandia Software Quality Assurance Program (SSQAP). APPROVALS SWiFT Software Quality Assurance Plan (SAND2016-0765) approved by: Department Manager SWiFT Site Lead Dave Minster (6121) Date Jonathan White (6121) Date SWiFT Controls Engineer Jonathan Berg (6121) Date CHANGE HISTORY Issue Date Originator(s) Description A 2016/01/27 Jon Berg (06121) Initial release of the SWiFT Software Quality Assurance Plan

  16. 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

  17. 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).

  18. 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)

  19. Waste Management System Requirement document

    International Nuclear Information System (INIS)

    1990-04-01

    This volume defines the top level technical requirements for the Monitored Retrievable Storage (MRS) facility. It is designed to be used in conjunction with Volume 1, General System Requirements. Volume 3 provides a functional description expanding the requirements allocated to the MRS facility in Volume 1 and, when appropriate, elaborates on requirements by providing associated performance criteria. Volumes 1 and 3 together convey a minimum set of requirements that must be satisfied by the final MRS facility design without unduly constraining individual design efforts. The requirements are derived from the Nuclear Waste Policy Act of 1982 (NWPA), the Nuclear Waste Policy Amendments Act of 1987 (NWPAA), the Environmental Protection Agency's (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel (40 CFR 191), NRC Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste (10 CFR 72), and other federal statutory and regulatory requirements, and major program policy decisions. This document sets forth specific requirements that will be fulfilled. Each subsequent level of the technical document hierarchy will be significantly more detailed and provide further guidance and definition as to how each of these requirements will be implemented in the design. Requirements appearing in Volume 3 are traceable into the MRS Design Requirements Document. Section 2 of this volume provides a functional breakdown for the MRS facility. 1 tab

  20. TWRS configuration management requirement source document

    International Nuclear Information System (INIS)

    Vann, J.M.

    1997-01-01

    The TWRS Configuration Management (CM) Requirement Source document prescribes CM as a basic product life-cycle function by which work and activities are conducted or accomplished. This document serves as the requirements basis for the TWRS CM program. The objective of the TWRS CM program is to establish consistency among requirements, physical/functional configuration, information, and documentation for TWRS and TWRS products, and to maintain this consistency throughout the life-cycle of TWRS and the product, particularly as changes are being made

  1. 222-S laboratory quality assurance plan

    International Nuclear Information System (INIS)

    Meznarich, H.K.

    1995-01-01

    This document provides quality assurance guidelines and quality control requirements for analytical services. This document is designed on the basis of Hanford Analytical Services Quality Assurance Plan (HASQAP) technical guidelines and is used for governing 222-S and 222-SA analytical and quality control activities. The 222-S Laboratory provides analytical services to various clients including, but not limited to, waste characterization for the Tank Waste Remediation Systems (TWRS), waste characterization for regulatory waste treatment, storage, and disposal (TSD), regulatory compliance samples, radiation screening, process samples, and TPA samples. A graded approach is applied on the level of sample custody, QC, data verification, and data reporting to meet the specific needs of the client

  2. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS

  3. Waste Acceptance System Requirements document (WASRD)

    International Nuclear Information System (INIS)

    1993-01-01

    This Waste Acceptance System Requirements document (WA-SRD) describes the functions to be performed and the technical requirements for a Waste Acceptance System for accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) into the Civilian Radioactive Waste Management System (CRWMS). This revision of the WA-SRD addresses the requirements for the acceptance of HLW. This revision has been developed as a top priority document to permit DOE's Office of Environmental Restoration and Waste Management (EM) to commence waste qualification runs at the Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) in a timely manner. Additionally, this revision of the WA-SRD includes the requirements from the Physical System Requirements -- Accept Waste document for the acceptance of SNF. A subsequent revision will fully address requirements relative to the acceptance of SNF

  4. The IAEA Code of Practice on quality assurance, and quality assurance requirements and practices in Member States

    International Nuclear Information System (INIS)

    Raisic, N.

    1982-01-01

    The IAEA Code of Practice on Quality Assurance for Safety in Nuclear Power Plants and the corresponding Safety Guides are reviewed and compared with quality assurance (QA) practices in the IAEA Member States. The QA requirements stipulated by the Code place on the nuclear power plant owner the responsibility to establish an overall QA programme for the plant. In selecting the QA programme level for specific activities, the Code allows of a flexible approach but does not specify gradation in programme requirements. The Code is placing the burden of quality-achieving and quality-assuring functions on the task-performing organizations, namely the designers, manufacturers, constructors and plant operators. The plant owner provides for the management of the overall QA programme, surveillance of activities and verifications of the effectiveness of the constituent programmes of all project participants through programme audits and evaluations. The Code and the supporting Safety Guides are consistent with existing QA practices in Member States. However, certain differences exist, which are mainly expressed in the different QA functions assigned to the various organizations participating in the overall QA programme. Also, some Member States place more emphasis on redundant verification activities than on quality-achieving functions. Tendencies are also identified to grade the QA requirements in respect of items and activities, in accordance with some pre-established criteria. In an annex to the paper, QA practices in Member States participating in the Agency's Technical Review Committee on Quality Assurance (TRC-QA) are reviewed, indicating their similarities to and differences from the Code

  5. Quality assurance plan for the Objective Supply Capability Adaptive Redesign (OSCAR) project

    Energy Technology Data Exchange (ETDEWEB)

    Stewart, K.A.; Rasch, K.A.; Reid, R.W.

    1996-11-01

    This document establishes the Quality Assurance Plan (QAP) for the National Guard Bureau Objective Supply Capability Adaptive Redesign (OSCAR) project activities under the Oak Ridge National Laboratory (ORNL) management. It defines the requirements and assigns responsibilities for ensuring, with a high degree of confidence, that project objectives will be achieved as planned. The QAP outlined herein is responsive to and meets the Quality Assurance Program standards for the U.S. Department of Energy (DOE), Lockheed Martin Energy Research Corporation and ORNL and the ORNL Computing, Robotics, and Education Directorate (CRE). This document is intended to be in compliance with DOE Order 5700.6C, Quality Assurance Program, and the ORNL Standard Practice Procedure, SPP X-QA-8, Quality Assurance for ORNL Computing Software. This standard allows individual organizations to apply the stated requirements in a flexible manner suitable to the type of activity involved. Section I of this document provides an introduction to the OSCAR project QAP; Sections 2 and 3 describe the specific aspects of quality assurance as applicable to the OSCAR project. Section 4 describes the project approach to risk management. The Risk Management Matrix given in Appendix A is a tool to assess, prioritize, and prevent problems before they occur. Therefore, the matrix will be reviewed and revised on a periodic basis.

  6. Tank waste remediation system functions and requirements document

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, K.E

    1996-10-03

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle.

  7. Tank waste remediation system functions and requirements document

    International Nuclear Information System (INIS)

    Carpenter, K.E

    1996-01-01

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle

  8. The Role Of Quality Assurance Program For Safety Operation Of Nuclear Installations

    International Nuclear Information System (INIS)

    Harjanto, N.T.; Purwadi, K.P.; Boru, D.S.; Farida; Suharni

    2000-01-01

    Nuclear installations expose potential hazard of radiation, therefore in their construction, operation and maintenance, it is necessary to consider safety aspect, in which the safety requirements which has been determined must be met. One of the requirements that is absolutely needed is quality assurance, which covers arrangement of quality assurance program, organization and administration of the implementation of quality assurance, and supervision. Quality Assurance program is a guideline containing quality policies and basic determination on the realization of activities that effect the quality of equipment's and items used in the operation of nuclear installations in order that the operation of nuclear installation can run safety and in accordance with their design aims and operation limits. Quality Assurance Program includes document control, design control, supply control, control of equipment s and items, operation/process control, inspection and control of equipment test, and control of nonconformance and corrections. General system of nuclear installation operation is equipped with safety and supporting systems. These systems must apply the quality assurance program that cover control of activities in the systems. In the implementation of the quality assurance program, it is necessary to establish procedures, work guidelines/instructions, and quality recording that constitutes documents of quality system 2 nd , 3 th , and 4 th level after the quality assurance program. To ensure the effectivity and to prove whether the realization of the program has been pursuant to the determined requirements, an internal audit must be conducted accordingly

  9. ERD UMTRA Project quality assurance program plan, Revision 7

    International Nuclear Information System (INIS)

    1995-09-01

    This document is the revised Quality Assurance Program Plan (QAPP) dated September, 1995 for the Environmental Restoration Division (ERD) Uranium Mill Tailings Remedial Action Project (UMTRA). Quality Assurance requirements for the ERD UMTRA Project are based on the criteria outlined in DOE Order 5700.6C or applicable sections of 10 CFR 830.120. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the ERD UMTRA Project and its contractors

  10. Technical position on items and activities in the high-level waste geologic repository program subject to quality assurance requirements

    International Nuclear Information System (INIS)

    Duncan, A.B.; Bilhorn, S.G.; Kennedy, J.E.

    1988-04-01

    This document provides guidance on how to identify items and activities subject to Quality Assurance in the high-level nuclear waste repository program for pre-closure and post-closure phases of the repository. In the pre-closure phase, structures, systems and components essential to the prevention or mitigation of an accident that could result in an off-site radiation dose of 0.5rem or greater are termed ''important to safety''. In the post-closure phase, the barriers which are relied on to meet the containment and isolation requirements are defined as ''important to waste isolation''. These structures, systems, components, and barriers, and the activities related to their characterization, design, construction, and operation are required to meet quality assurance (QA) criteria to provide confidence in the performance of the geologic repository. The list of structures, systems, and components important to safety and engineered barriers important to waste isolation is referred to as the ''Q-List'' and lies within the scope of the QA program. 10 refs

  11. 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

  12. Quality assurance programme for screen film mammography

    International Nuclear Information System (INIS)

    2009-01-01

    The application of radiation in human health, for both the diagnosis and treatment of disease, is an important component of the work of the IAEA. In the area of diagnostic radiology, this work is focused on quality assurance methods to both the promotion of the effective use of radiation for diagnostic outcome, through achieving and maintaining appropriate image quality, and also on dose determination to allow the monitoring and reduction of dose to the patient. In response to heightened awareness of the importance of patient dose contributed by radiology procedures, the IAEA published Dosimetry in Diagnostic Radiology: An International Code of Practice (Technical Reports Series No. 457) in 2007, to form a basis for patient dose determination for the Member States. Further to this, it is recognized that for complex diagnostic procedures, such as mammography, a detailed guidance document is required to give the professionals in the clinical centre the knowledge necessary to assess the patient dose, as well as to ensure that the procedure gives the maximal patient benefit possible. It is well documented that without the implementation of a quality culture and a systematic quality assurance programme with appropriate education, the detection of breast cancer cannot be made at an early enough stage to allow effective curative treatment to be undertaken. Currently there are a number of established quality assurance protocols in mammography from national and regional institutions, however, many of these protocols are distinctive and so a harmonized approach is required. This will allow the Member States to facilitate quality assurance in mammography in a standardized way which will also facilitate the introduction of national quality assurance programmes that are needed to underpin effective population screening programmes for breast cancer. Development of a quality assurance document for screen film mammography was started in 2005 with the appointment of a drafting

  13. Quality assurance manual for the development of digital systems

    International Nuclear Information System (INIS)

    Lee, Cheol Kwon; Kwon, Kee Choon; You, Young Eun; Kim, Kwan Hyun; Park, Jung Woo; Park, Chan Seok

    2001-12-01

    A digital safety system is being developed by three companies under the Korea Nuclear I and C System R and D Program. This Quality Assurance Manual (QAM) is written to ensure the safety and reliability of the system and to meet the regulatory requirements associated with quality assurance. This QAM describes eighteen elements of quality assurance criteria required for the development of the system, which are coincident with the criteria specified in Nuclear Energy Laws and Enforcement Regulations of Nuclear Energy Laws and 10CFR50 Appendix B. This QAM is submitted to the regulatory body with other documents related to the quality assurance activities performed during the system development. And its safety, validity and fulfillment are reviewed and audited in the review process of topical report of the digital safety system

  14. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1976-01-01

    The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

  15. Quality assurance in the procurement, design and manufacture of nuclear fuel assemblies

    International Nuclear Information System (INIS)

    1983-01-01

    This Safety Guide provides requirements and recommendations for quality assurance programmes that are relevant for the unique features of the procurement, design, manufacture, inspection, testing, packaging, shipping, storage, and receiving inspection of fuel assemblies for nuclear power plants. The generic quality assurance requirements of the Code and related Safety Guides are referred to where applicable, and are duplicated in this document where increased emphasis is desirable

  16. Implementation of quality assurance with respect to product quality and scheduling

    International Nuclear Information System (INIS)

    Schleimer, W.F.

    1986-04-01

    Quality assurance means the whole range of actions which are necessary to meet the client's requirements for the product and the test methods. Audits: The preconditions for fabrication must be fulfilled by approval of the manufacturer's quality assurance system, the staff's qualification, his procedures and his equipments. This is done by means of a system audit at KWU or an equivalent organisation. Specifications: For quality assurance the requirements for the components are fixed in specifications. There are material specifications, process/procedure specifications, components specifications. Approval of Component Design and Manufacture (Scheduling): The approval procedure of a structurally welded part is described as an example of the approval of component design and manufacture, thus representing one small piece of a mechanical equipment. In-Process Surveillance (Product Audit): At KWU the in-process surveillance is regulated by a KQ- or product audit concept. In this concept we have K- and KQ-steps. The list of KQ-steps will be presented. Documentation: All test or examination steps are documented with certificates, lists, and stamps for the final documentation. 19 figs

  17. Monitored Retrievable Storage System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design

  18. 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.

  19. Regulatory viewpoint on nuclear fuel quality assurance

    International Nuclear Information System (INIS)

    Tripp, L.E.

    1976-01-01

    Considerations of the importance of fuel quality and performance to nuclear safety, ''as low reasonably achievable'' release of radioactive materials in reactor effluents, and past fuel performance problems demonstrate the need for strong regulatory input, review and inspection of nuclear fuel quality assurance programs at all levels. Such a regulatory program is being applied in the United States of America by the US Nuclear Regulatory Commission. Quality assurance requirements are contained within government regulations. Guidance on acceptable methods of implementing portions of the quality assurance program is contained within Regulatory Guides and other NRC documents. Fuel supplier quality assurance program descriptions are reviewed as a part of the reactor licensing process. Inspections of reactor licensee control of their fuel vendors as well as direct inspections of fuel vendor quality assurance programs are conducted on a regularly scheduled basis. (author)

  20. 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

  1. 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).

  2. 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)

  3. 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

  4. Quality assurance program plan for the Reactor Research Experiment Programs (RREP)

    International Nuclear Information System (INIS)

    Pipher, D.G.

    1982-05-01

    This document describes the Quality Assurance Program plans which will be applied to tasks on Reactor Research Experiments performed on Sandia National Laboratories' reactors. The program provides for individual project or experiment quality plan development and allows for reasonable plan flexibility and maximum plan visibility. Various controls and requirements in this program plan are considered mandatory on all features which are identified as important to public health and safety (Level I). It is the intent of this document that the Quality Assurance program comprise those elements which will provide adequate assurance that all components, equipment, and systems of the experiments will perform as designed, and hence prevent delays and costs due to rejections or failures

  5. 22 CFR 40.71 - Documentation requirements for immigrants.

    Science.gov (United States)

    2010-04-01

    ... 22 Foreign Relations 1 2010-04-01 2010-04-01 false Documentation requirements for immigrants. 40... NONIMMIGRANTS AND IMMIGRANTS UNDER THE IMMIGRATION AND NATIONALITY ACT, AS AMENDED Documentation Requirements § 40.71 Documentation requirements for immigrants. INA 212(a)(7)(A) is not applicable at the time of...

  6. Reliability assurance programme guidebook for advanced light water reactors

    International Nuclear Information System (INIS)

    2001-12-01

    To facilitate the implementation of reliability assurance programmes (RAP) within future advanced reactor programmes and to ensure that the next generation of commercial nuclear reactors achieves the very high levels of safety, reliability and economy which are expected of them, in 1996, the International Atomic Energy Agency (IAEA) established a task to develop a guidebook for reliability assurance programmes. The draft RAP guidebook was prepared by an expert consultant and was reviewed/modified at an Advisory Group meeting (7-10 April 1997) and at a consults meeting (7-10 October 1997). The programme for the RAP guidebook was reported to and guided by the Technical Working Group on Advanced Technologies for Light Water Reactors (TWG-LWR). This guidebook will demonstrate how the designers and operators of future commercial nuclear plants can exploit the risk, reliability and availability engineering methods and techniques developed over the past two decades to augment existing design and operational nuclear plant decision-making capabilities. This guidebook is intended to provide the necessary understanding, insights and examples of RAP management systems and processes from which a future user can derive his own plant specific reliability assurance programmes. The RAP guidebook is intended to augment, not replace, specific reliability assurance requirements defined by the utility requirements documents and by individual nuclear steam supply system (NSSS) designers. This guidebook draws from utility experience gained during implementation of reliability and availability improvement and risk based management programmes to provide both written and diagrammatic 'how to' guidance which can be followed to assure conformance with the specific requirements outlined by utility requirements documents and in the development of a practical and effective plant specific RAP in any IAEA Member State

  7. Guide for reviewing safety analysis reports for packaging: Review of quality assurance requirements

    International Nuclear Information System (INIS)

    Moon, D.W.

    1988-10-01

    This review section describes quality assurance requirements applying to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging which are important to safety. The design effort, operation's plans, and quality assurance requirements should be integrated to achieve a system in which the independent QA program is not overly stringent and the application of QA requirements is commensurate with safety significance. The reviewer must verify that the applicant's QA section in the SARP contains package-specific QA information required by DOE Orders and federal regulations that demonstrate compliance. 8 refs

  8. Impact of proposed financial assurance requirements on nuclear materials licensees

    International Nuclear Information System (INIS)

    Hendrickson, P.L.; Scott, M.J.; Mullen, M.F.; Nicholls, A.K.; Smith, S.A.

    1987-09-01

    The NRC is considering a possible rulemaking that would require certain nuclear materials licensees to demonstrate financial ability to clean up accidental releases of radioactive materials. The rulemaking would potentially affect approximately 16,350 NRC and Agreement State licensees. This report was prepared for NRC by the Pacific Northwest Laboratory to provide background information and analysis for the potential rulemaking. Specific topics examined in the report include: (1) characteristics of potentially affected licensees, (2) the availability and cost of various financial assurance mechanisms, (3) the financial impacts for licensees (including licensees classified as small businesses) of providing $2M of assurance per licensee and a sliding amount of assurance tied to risk, (4) the cost of administering a financial assurance rule, and (5) overall benefits and costs. Tabular information on past material licensee accidents and cleanup efforts is also included. The financial occurrence mechanism that appears to be most suitable for providing the desired financial assurance is one or more newly formed captive insurance companies. Potential benefits of the rulemaking include reduced need for taxpayer-funded cleanup of accidental releases, reduces administrative time to secure such funds, and the possibility of more cleanup with correspondingly reduced occupational and public exposure to radioactive materials

  9. Quality assurance in production and use of special form radioactive material - focal points in BAM approvals

    International Nuclear Information System (INIS)

    Rolle, A.; Buhlemann, L.

    2004-01-01

    BAM as the competent authority for approval of special form radioactive material attaches great importance to a detailed audit of the required quality assurance programs for design, manufacture, testing, documentation, use, maintenance and inspection. Applicants have to submit, together with application documentation information on general arrangements for quality assurance, as well as on quality assurance in production and in operation. Fields where BAM has often found deficiencies are leak test methods, weld seam quality and the safety level after use

  10. Quality assurance application in the documentation of nuclear research reactor

    International Nuclear Information System (INIS)

    Nababan, N.

    1999-01-01

    For each nuclear research reactor a document control system should be established and should be provide for preparation, review, approval, issuance, distribution, revision and validation (where appropriate) of documents essential to the management, performance and verification of work. In the document control system the responsibilities for each participating organization or individual should be defined in writing. The types of document include, but are not limited to document comprising the QA program, safety requirements, maintenance and operating procedures, inspection instructions, inspection and test reports, assessment reports, drawings, data files, calculations, specifications, computer codes, purchase orders and related documents, vendor supplied documents and work instruction. Management should identify the need for documents and should provide guidance to the organizations and people preparing them. The guidance should cover the status, scope and contents and the policies, standards and codes witch apply. It should also explain the need for feedback of experience. Plant modification or the results of assessments could also give rise to the need for a new document

  11. 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.

  12. 10 CFR 74.59 - Quality assurance and accounting requirements.

    Science.gov (United States)

    2010-01-01

    ... measurement system in question must not be used for material control and accounting purposes until it has been... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance and accounting requirements. 74.59 Section 74.59 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

  13. The simplification of quality assurance programmes to suit developing countries

    International Nuclear Information System (INIS)

    French, F.J.

    1978-01-01

    Whilst the need to produce and maintain documentation covering the supply and operation of Nuclear Steam Supply Systems is appreciated, it is felt that there is now a tendency to regard such documentation as more important than the plant itself. This tendency must be corrected if the safety and reliability of nuclear plants is to be maintained. The following paper proposes actions which will bring documentation into its proper perspective and make it more easily understood internationally. In addition, it is proposed that a common international Quality Assurance Programme Standard should be adopted by countries importing and exporting NSSS in order to make the requirements more understandable to all concerned. The proposals cover Quality Assurance Systems Specifications and the training of quality engineers and evaluators, and discuss Quality Assurance Programmes and Quality Plans. Specifically, the paper suggests the actions which could be undertaken now and proposes the bodies which should be responsible for such actions. (author)

  14. Monitoring of performance management using Quality Assurance Indicators and ISO requirement

    Directory of Open Access Journals (Sweden)

    Dargahi H

    2007-06-01

    Full Text Available Background: Quality assurance is a prevention-oriented system that can be used to improve the quality of care, increase productivity and monitor the performance management in clinical laboratories. ISO 9001: 2000 requirements are a collection of management and technical systems designed to implement quality assurance and monitor performance management in organizations. Methods: A checklist was prepared to monitor the preanalytical, analytical and postanalytical stages of laboratory performance management in 16 areas and all laboratory activities in 14 of the clinical laboratories of the Tehran University of Medical Sciences (TUMS hospitals. Collected data were stored and statistically analyzed using SPSS software. Results: The best performance, in which 77.73% of quality assurance indicators were observed, was found in Sina Hospital. However, only 57.56% of these indicators were fulfilled at Farabi Hospital, with the lowest-level performance among the clinical laboratories of TUMS hospitals. The highest level of compliance with quality assurance indicators was in the hematology departments and for facility demands in management areas. Overall, quality assurance indicators were appropriately followed in only 7% of the clinical laboratories. Conclusion: The average quality assurance observation rate in the clinical laboratories studied was 67.22%, which is insufficient and must be remedied with stricter enforcement of the ISO 9001: 2000 regulations.

  15. 40 CFR 5.115 - Assurance required.

    Science.gov (United States)

    2010-07-01

    ... EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 5.115 Assurance... that applications for Federal financial assistance or awards of Federal financial assistance contain... official of such assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance...

  16. 28 CFR 54.115 - Assurance required.

    Science.gov (United States)

    2010-07-01

    ... EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 54.115 Assurance... that applications for Federal financial assistance or awards of Federal financial assistance contain... official of such assurance. (b) Duration of obligation. (1) In the case of Federal financial assistance...

  17. Technical requirements document for the waste flow analysis

    International Nuclear Information System (INIS)

    Shropshire, D.E.

    1996-05-01

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

  18. Underground Test Area Activity Quality Assurance Plan Nevada National Security Site, Nevada. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Krenzien, Susan [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States); Farnham, Irene [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2015-06-01

    This Quality Assurance Plan (QAP) provides the overall quality assurance (QA) requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) Underground Test Area (UGTA) activities. The requirements in this QAP are consistent with DOE Order 414.1D, Change 1, Quality Assurance (DOE, 2013a); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). If a participant’s requirement document differs from this QAP, the stricter requirement will take precedence. NNSA/NFO, or designee, must review this QAP every two years. Changes that do not affect the overall scope or requirements will not require an immediate QAP revision but will be incorporated into the next revision cycle after identification. Section 1.0 describes UGTA objectives, participant responsibilities, and administrative and management quality requirements (i.e., training, records, procurement). Section 1.0 also details data management and computer software requirements. Section 2.0 establishes the requirements to ensure newly collected data are valid, existing data uses are appropriate, and environmental-modeling methods are reliable. Section 3.0 provides feedback loops through assessments and reports to management. Section 4.0 provides the framework for corrective actions. Section 5.0 provides references for this document.

  19. Fiscal year 1999 waste information requirements document

    International Nuclear Information System (INIS)

    Adams, M.R.

    1998-01-01

    The Waste Information Requirements Document (WIRD) has the following purposes: To describe the overall drivers that require characterization information and to document their source; To define how characterization is going to satisfy the drivers, close issues, and measure and report progress; and To describe deliverables and acceptance criteria for characterization. Characterization information is required to maintain regulatory compliance, perform operations and maintenance, resolve safety issues, and prepare for disposal of waste. Commitments addressing these requirements are derived from the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement; the Recommendation 93-5 Implementation Plan (DOE-RL 1996a) to the Defense Nuclear Facilities Safety Board (DNFSB); and other requirement sources listed in Section 2.0. The Waste Information Requirements Document replaces the tank waste analysis plans and the tank characterization plan previously required by the Tri-Party Agreement, Milestone M-44-01 and M-44-02 series

  20. 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

  1. Progress in France of the standardization of multi-level quality assurance

    International Nuclear Information System (INIS)

    Debout, E.

    1982-01-01

    Quality assurance has evolved in a steady but somewhat haphazard manner in various industries, each of which has drawn up its own standards. Examples of this are the armaments industry under the auspices of NATO, nuclear energy (IAEA guides), the French aerospace industries and the Industrial Monitoring Service for Armaments in France. For the sake of both the supplier companies and the customers, these differing and sometimes incompatible requirements should be brought into line. At the instigation of the French Association for Industrial Quality Control (AFCIQ), the French Association for Standardization (AFNOR) is therefore in the process of publishing a series of documents on quality management and assurance. For its part, the International Organization for Standardization (ISO) has set up a committee (TC 176) to standardize quality assurance. The different documents provide for various levels of quality assurance, the compatibility of which will have to be closely monitored. (author)

  2. 22 CFR 141.4 - Assurances required.

    Science.gov (United States)

    2010-04-01

    ... of the United States for the desegregation of such school or school system, and provides an assurance... other participants. Any such assurance shall include provisions which give the United States a right to... system which the responsible official of the Department of Health, Education, and Welfare determines is...

  3. Study on quality assurance for high-level radioactive waste disposal project

    International Nuclear Information System (INIS)

    Takada, Susumu

    2005-01-01

    The U.S. Department of Energy (DOE) has developed comparatively detailed quality assurance requirements for the high-level radioactive waste disposal systems. Quality assurance is recognized as a key issue for confidence building and smooth implementation of the HLW program in Japan, and Japan is at an initial phase of repository development. Then the quality assurance requirements at site research and site selection, site characterization, and site suitability analysis used in the Yucca Mountain project were examined in detail and comprehensive descriptions were developed using flow charts. Additionally, the applicability to the Japan high-level radioactive waste disposal project was studied. The examination and study were performed for the following QA requirements: The requirements that have the relative importance at site research and site selection, site characterization, and site suitability analysis (such as planning and performing scientific investigations, sample control, data control, model development and use, technical report review, software control, and control of the electric management of data). The requirements that have the relative importance at the whole repository phases (such as quality assurance program, document control, and control of quality assurance records). (author)

  4. AVLIS Production Plant Preliminary Quality Assurance Plan and Assessment

    International Nuclear Information System (INIS)

    1984-01-01

    This preliminary Quality Assurance Plan and Assessment establishes the Quality Assurance requirements for the AVLIS Production Plant Project. The Quality Assurance Plan defines the management approach, organization, interfaces, and controls that will be used in order to provide adequate confidence that the AVLIS Production Plant design, procurement, construction, fabrication, installation, start-up, and operation are accomplished within established goals and objectives. The Quality Assurance Program defined in this document includes a system for assessing those elements of the project whose failure would have a significant impact on safety, environment, schedule, cost, or overall plant objectives. As elements of the project are assessed, classifications are provided to establish and assure that special actions are defined which will eliminate or reduce the probability of occurrence or control the consequences of failure. 8 figures, 18 tables

  5. Documentation requirements for radiation sterilization

    DEFF Research Database (Denmark)

    Miller, A.

    1995-01-01

    Several standards are recently approved or are under development by the standard organizations ISO and CEN in the field of radiation sterilization. Particularly in Europe these standards define new requirements on some issues and on other issues they emphasize the necessary documentation for appr......Several standards are recently approved or are under development by the standard organizations ISO and CEN in the field of radiation sterilization. Particularly in Europe these standards define new requirements on some issues and on other issues they emphasize the necessary documentation...... for approval of radiation sterilized products. The impact of these standards on the radiation sterilization is discussed, with special attention given to a few special issues, mainly traceability and uncertainty of measurement results....

  6. XML: Solution for the integration of nuclear power plant data and technical documents

    International Nuclear Information System (INIS)

    Gordillo, F.

    2000-01-01

    Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

  7. Assessment Report Sandia National Laboratories Fuel Cycle Technologies Quality Assurance Evaluation of FY15 SNL FCT M2 Milestone Deliverables

    International Nuclear Information System (INIS)

    Appel, Gordon John

    2016-01-01

    Sandia National Laboratories (SNL) Fuel Cycle Technologies (FCT) program activities are conducted in accordance with FCT Quality Assurance Program Document (FCT-QAPD) requirements. The FCT-QAPD interfaces with SNL approved Quality Assurance Program Description (SNL-QAPD) as explained in the Sandia National Laboratories QA Program Interface Document for FCT Activities (Interface Document). This plan describes SNL's FY16 assessment of SNL's FY15 FCT M2 milestone deliverable's compliance with program QA requirements, including SNL R&A requirements. The assessment is intended to confirm that SNL's FY15 milestone deliverables contain the appropriate authenticated review documentation and that there is a copy marked with SNL R&A numbers.

  8. Assessment Report Sandia National Laboratories Fuel Cycle Technologies Quality Assurance Evaluation of FY15 SNL FCT M2 Milestone Deliverables

    Energy Technology Data Exchange (ETDEWEB)

    Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-05-01

    Sandia National Laboratories (SNL) Fuel Cycle Technologies (FCT) program activities are conducted in accordance with FCT Quality Assurance Program Document (FCT-QAPD) requirements. The FCT-QAPD interfaces with SNL approved Quality Assurance Program Description (SNL-QAPD) as explained in the Sandia National Laboratories QA Program Interface Document for FCT Activities (Interface Document). This plan describes SNL's FY16 assessment of SNL's FY15 FCT M2 milestone deliverable's compliance with program QA requirements, including SNL R&A requirements. The assessment is intended to confirm that SNL's FY15 milestone deliverables contain the appropriate authenticated review documentation and that there is a copy marked with SNL R&A numbers.

  9. The grading management of the quality assurance

    International Nuclear Information System (INIS)

    Ma Xiaozheng; Han Shufang; Yu Bei; Tian Xuehang

    2009-01-01

    This paper introduces the quality assurance grading management of the items, services and technology process on nuclear power plants (nuclear island, conventional island, BOP), such as the requirements and aim in the related code, guide, technical document, the requirements for the related units, the grading principle and grading, the considering method for the differences of QA requirements of the each QA grand, as well as the status and propositions in the QA grading management in China. (authors)

  10. quality assurance systems in nuclear fuel procurement and manufacturing

    International Nuclear Information System (INIS)

    Can, S.

    1997-01-01

    Quality is the totality of features and characteristics of a product or service that bear on its ability to satisfy stated or implied needs. Quality control is activities and techniques used to fulfill the requirements of quality. Quality assurance is a system and its main components are requirements. QA program, organization and responsibilities, design and verification, material and its control, manufacturing and process control, inspections, audits and documents: manuals, specifications, instructions. Quality assurance systems are largely based on ISO 9000 series of the International Standards Organization. ISO 9000 series has been adopted and published by Turkish Standards Institute as TS-ISO 9000. International Atomic Energy Agency also published a guide (50-SG-QA11) ''Quality Assurance in the Procurement, Design and Manufacture of Nuclear Fuel Assemblies'' in the safety guide series. In this study the role of quality control in quality assurance systems, inspection and test plans and acceptance and nonconformance quality levels will be explained in relation to nuclear fuel production. Examples of applications in quality assurance systems based on ISO 9000 will be given

  11. Quality assurance: Importance of systems and standard operating procedures.

    Science.gov (United States)

    Manghani, Kishu

    2011-01-01

    It is mandatory for sponsors of clinical trials and contract research organizations alike to establish, manage and monitor their quality control and quality assurance systems and their integral standard operating procedures and other quality documents to provide high-quality products and services to fully satisfy customer needs and expectations. Quality control and quality assurance systems together constitute the key quality systems. Quality control and quality assurance are parts of quality management. Quality control is focused on fulfilling quality requirements, whereas quality assurance is focused on providing confidence that quality requirements are fulfilled. The quality systems must be commensurate with the Company business objectives and business model. Top management commitment and its active involvement are critical in order to ensure at all times the adequacy, suitability, effectiveness and efficiency of the quality systems. Effective and efficient quality systems can promote timely registration of drugs by eliminating waste and the need for rework with overall financial and social benefits to the Company.

  12. Quality assurance: Importance of systems and standard operating procedures

    Directory of Open Access Journals (Sweden)

    Kishu Manghani

    2011-01-01

    Full Text Available It is mandatory for sponsors of clinical trials and contract research organizations alike to establish, manage and monitor their quality control and quality assurance systems and their integral standard operating procedures and other quality documents to provide high-quality products and services to fully satisfy customer needs and expectations. Quality control and quality assurance systems together constitute the key quality systems. Quality control and quality assurance are parts of quality management. Quality control is focused on fulfilling quality requirements, whereas quality assurance is focused on providing confidence that quality requirements are fulfilled. The quality systems must be commensurate with the Company business objectives and business model. Top management commitment and its active involvement are critical in order to ensure at all times the adequacy, suitability, effectiveness and efficiency of the quality systems. Effective and efficient quality systems can promote timely registration of drugs by eliminating waste and the need for rework with overall financial and social benefits to the Company.

  13. Assessment report for Hanford analytical services quality assurance plan

    International Nuclear Information System (INIS)

    Taylor, L.H.

    1994-11-01

    This report documents the assessment results of DOE/RL-94-55, Hanford Analytical Services Quality Assurance Plan. The assessment was conducted using the Requirement and Self-Assessment Database (RSAD), which contains mandatory and nonmandatory DOE Order statements for the relevant DOE orders

  14. 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.

  15. 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

  16. Guidance for implementing an environmental, safety, and health-assurance program. Volume 15. A model plan for line organization environmental, safety, and health-assurance programs

    Energy Technology Data Exchange (ETDEWEB)

    Ellingson, A.C.; Trauth, C.A. Jr.

    1982-01-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This particular document presents a model operational-level ES and H Assurance Program that may be used as a guide by an operational-level organization in developing its own plan. The model presented here reflects the guidance given in the total series of 15 documents.

  17. Plutonium immobilization project development and testing quality assurance program description - February 1999

    International Nuclear Information System (INIS)

    MacLean, L. M.; Ziemba, J.

    1999-01-01

    Lawrence Livermore National Laboratory Immobilization Development and Testing organization (LLNL ID and T) is a Participant in the Plutonium Immobilization Project (PIP). The LLNL D and T has lead responsibilities for form characterization and qualification, ceramic form development, process/equipment development with plutonium, and process systems testing and validation for both conversion and immobilization. This work must be performed in accordance with the graded approach of a Quality Assurance (QA) Program. A QA Program has been developed at LLNL to meet the requirements of the DOE/MD Quality Assurance Requirements. The LLNL QA Program consists of a Quality Assurance Program Description (QAPD) and Quality Implementing Procedures. These documents interface and are a subset of the overall PIP QA Program Documents. The PIP QA Program is described in the PIP ID and T QA Plan, PIP QAPD, and QA Procedures. Other Participant Organizations also must document and describe their PIP compliant QA Programs in a QAPD and implementing procedures. The purpose of this LLNL QAPD is to describe the organization, management processes, QA Controls for Grading, functional responsibilities, levels of authority, and interfaces for those managing, performing, and assessing the adequacy of work

  18. Idaho National Laboratory Emergency Readiness Assurance Plan - Fiscal Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Carl J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    Department of Energy Order 151.1C, Comprehensive Emergency Management System requires that each Department of Energy field element documents readiness assurance activities, addressing emergency response planning and preparedness. Battelle Energy Alliance, LLC, as prime contractor at the Idaho National Laboratory (INL), has compiled this Emergency Readiness Assurance Plan to provide this assurance to the Department of Energy Idaho Operations Office. Stated emergency capabilities at the INL are sufficient to implement emergency plans. Summary tables augment descriptive paragraphs to provide easy access to data. Additionally, the plan furnishes budgeting, personnel, and planning forecasts for the next 5 years.

  19. Flow assurance : complex phase behavior and complex work requires confidence and vigilance

    Energy Technology Data Exchange (ETDEWEB)

    Brown, L.D. [ConocoPhillips, Major Projects, Advanced Integrated Simulation, Houston, TX (United States)

    2008-07-01

    Petroleum exploration and development projects and operations increasingly rely on flow assurance definition. Flow assurance is an integrating discipline as it follows the fluid from the reservoir to the market. Flow assurance works across complex technical and non-technical interfaces, including the reservoir, well completions, operation processes, project management, physical/organic chemistry, fluid mechanics, chemical engineering, mechanical engineering and corrosion. The phase behaviour in real fluids also has complex interfaces. The understanding and management of flow assurance of complex phase behaviour must be well communicated in order to enable proper selection, execution, and operation of development concepts designed to manage successful production within the fluid's phase behaviour. Simulation tools facilitate the translation of science into engineering. Academic, industrial, and field research is the core of these tools. The author cautioned that vigilance is required to assist and identify the right time to move innovation into the core tools.

  20. Quality Assurance Program Plan for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    1992-01-01

    The United States Department of Energy (USDOE) has initiated the Environmental Restoration Program (ERP) in an effort to manage, control and remediate existing hazardous, toxic and radioactive wastes generated at the Portsmouth Gaseous Diffusion Plant (PORTS). This ERP Quality Assurance Program Plan (QAPP) is responsive to the PORTS ESH Division QAPP and the ES Environmental Restoration Division (ERD) QAPP. This QAPP establishes the policies, requirements and responsibilities by which an appropriate level of QA shall be implemented within the PORTS-ERP. All PORTS-ERP activities shall be conducted in accordance with the requirements of this document and/or of a project level document which is derivative of this document

  1. Quality assurance program plan for the Site Physical and Electrical Calibration Services Lab. Revision 1

    International Nuclear Information System (INIS)

    Carpenter, C.A.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) is organized to address WHC's implementation of quality assurance requirements as they are presented as interpretive guidance endorsed by the Department of Energy (DOE) Field Office, Richland DOE Order 5700.6C Quality Assurance. The quality assurance requirements presented in this plan will assure Measuring and Test Equipment (M and TE) are in conformance with prescribed technical requirements and that data provided by testing, inspection, or maintenance are valid. This QAPP covers all activities and work elements that are variously called QA, quality control, and quality engineering regardless of the organization performing the work. This QAPP identifies the QA requirements for planning, control, and documentation of operations, modifications, and maintenance of the WHC Site Physical and Electrical Calibration Services Laboratory. The primary function of the WHC Site Physical and Electrical Calibration Services Laboratory is providing calibration, standardization, or repair service of M and TE

  2. Fluor Daniel Hanford contract standards/requirements identification document

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, G.L.

    1997-04-24

    This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment.

  3. Fluor Daniel Hanford company standards requirements identification document

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1997-01-01

    This document, the Standards/Requirements Identification Document (S/RID) for the Fluor Daniel Hanford Contract, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment

  4. The Algorithm Theoretical Basis Document for Level 1A Processing

    Science.gov (United States)

    Jester, Peggy L.; Hancock, David W., III

    2012-01-01

    The first process of the Geoscience Laser Altimeter System (GLAS) Science Algorithm Software converts the Level 0 data into the Level 1A Data Products. The Level 1A Data Products are the time ordered instrument data converted from counts to engineering units. This document defines the equations that convert the raw instrument data into engineering units. Required scale factors, bias values, and coefficients are defined in this document. Additionally, required quality assurance and browse products are defined in this document.

  5. Transportation system requirements document. Revision 1 DCN01. Supplement

    International Nuclear Information System (INIS)

    1995-05-01

    The original Transportation System Requirements Document described the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of that document was to define the system-level requirements. These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presented an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. This revision of the document contains only the pages that have been modified

  6. 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.

  7. 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

  8. HPV testing for primary cervical screening: Laboratory issues and evolving requirements for robust quality assurance.

    Science.gov (United States)

    Carozzi, Francesca Maria; Del Mistro, Annarosa; Cuschieri, Kate; Frayle, Helena; Sani, Cristina; Burroni, Elena

    2016-03-01

    This review aims to highlight the importance of Quality Assurance for Laboratories performing HPV test for Cervical Cancer Screening. An HPV test, to be used as primary screening test, must be validated according to international criteria, based on comparison of its clinical accuracy to HC2 or GP5+/6+ PCR-EIA tests. The number of validated platforms is increasing and appropriate Quality Assurance Programs (QAPs) which can interrogate longitudinal robustness and quality are paramount. This document describes the following topics: (1) the characteristics of an HPV laboratory and the personnel training needs, to ensure an elevated quality of the entire process and the optimal use of the resources; (2) the Quality Assurance, as both internal (IQA) and external quality assessment (EQA) systems, to be implemented and performed, and the description of the existing EQAs, including limitations; (3) general considerations for an optimal EQA program for hrHPV primary screening Due to the importance of Quality Assurance for this field, international efforts are necessary to improve QA International Collaboration. Copyright © 2015 Elsevier B.V. All rights reserved.

  9. European Guidelines for Quality Assurance in Cervical Cancer Screening. Second edition--summary document.

    Science.gov (United States)

    Arbyn, M; Anttila, A; Jordan, J; Ronco, G; Schenck, U; Segnan, N; Wiener, H; Herbert, A; von Karsa, L

    2010-03-01

    European Guidelines for Quality Assurance in Cervical Cancer Screening have been initiated in the Europe Against Cancer Programme. The first edition established the principles of organised population-based screening and stimulated numerous pilot projects. The second multidisciplinary edition was published in 2008 and comprises approximately 250 pages divided into seven chapters prepared by 48 authors and contributors. Considerable attention has been devoted to organised, population-based programme policies which minimise adverse effects and maximise benefits of screening. It is hoped that this expanded guidelines edition will have a greater impact on countries in which screening programmes are still lacking and in which opportunistic screening has been preferred in the past. Other methodological aspects such as future prospects of human papillomavirus testing and vaccination in cervical cancer control have also been examined in the second edition; recommendations for integration of the latter technologies into European guidelines are currently under development in a related project supported by the European Union Health Programme. An overview of the fundamental points and principles that should support any quality-assured screening programme and key performance indicators are presented here in a summary document of the second guidelines edition in order to make these principles and standards known to a wider scientific community.

  10. 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...

  11. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Safeguards and Security (S&S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S&S laws and regulations. Numerous S&S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S&S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces.

  12. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 3

    International Nuclear Information System (INIS)

    1994-04-01

    The Safeguards and Security (S ampersand S) Functional Area address the programmatic and technical requirements, controls, and standards which assure compliance with applicable S ampersand S laws and regulations. Numerous S ampersand S responsibilities are performed on behalf of the Tank Farm Facility by site level organizations. Certain other responsibilities are shared, and the remainder are the sole responsibility of the Tank Farm Facility. This Requirements Identification Document describes a complete functional Safeguards and Security Program that is presumed to be the responsibility of the Tank Farm Facility. The following list identifies the programmatic elements in the S ampersand S Functional Area: Program Management, Protection Program Scope and Evaluation, Personnel Security, Physical Security Systems, Protection Program Operations, Material Control and Accountability, Information Security, and Key Program Interfaces

  13. 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.

  14. 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

  15. B and W NPGD quality assurance program for nuclear equipment. Revision 1

    International Nuclear Information System (INIS)

    1975-03-01

    B and W's Quality Assurance Program (QAP) is described. The program is implemented through the Nuclear Power Generation Division (NPGD) and includes design, procurement, and manufacturing activities of NPGD and all its suppliers furnishing items in the B and W scope of supply including other Divisions/ Subsidiaries of B and W. These activities are controlled by including applicable quality assurance requirements, as described, in NPGD procurement documents imposed on its suppliers. Each supplier must then establish and/or maintain a documented QA Program to meet the requirements imposed by the procurement documents. Implementation of the suppliers' NPGD-approved QA Program is verified by NPGD through Audit and QC Surveillance activities. The position and relationships of the NPGD within the Company's corporate structure are described. An overview of the QAP describing its implementation, its operation, the controls imposed on all suppliers (both corporate and vendor) and site consulting activities is presented. (U.S.)

  16. Spectrum analysis on quality requirements consideration in software design documents.

    Science.gov (United States)

    Kaiya, Haruhiko; Umemura, Masahiro; Ogata, Shinpei; Kaijiri, Kenji

    2013-12-01

    Software quality requirements defined in the requirements analysis stage should be implemented in the final products, such as source codes and system deployment. To guarantee this meta-requirement, quality requirements should be considered in the intermediate stages, such as the design stage or the architectural definition stage. We propose a novel method for checking whether quality requirements are considered in the design stage. In this method, a technique called "spectrum analysis for quality requirements" is applied not only to requirements specifications but also to design documents. The technique enables us to derive the spectrum of a document, and quality requirements considerations in the document are numerically represented in the spectrum. We can thus objectively identify whether the considerations of quality requirements in a requirements document are adapted to its design document. To validate the method, we applied it to commercial software systems with the help of a supporting tool, and we confirmed that the method worked well.

  17. Managing Requirements-Documents to Data

    Science.gov (United States)

    Orr, Kevin; Hudson, Abe

    2017-01-01

    Managing Requirements on long term projects like International Space Station (ISS) can go thru many phases, from initial product development to almost over 20 years of operations and sustainment. Over that time many authorized changes have been made to the requirement set, that apply to any new systems that would visit the ISS today, like commercial cargo/crew vehicles or payloads. Explore the benefits of managing requirements in a database while satisfying traditional documents needs for contracts and stakeholder/user consumption that are not tied into the database.

  18. Quality assurance requirements for the operation of Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1983-09-01

    An adaption of NRC's 10 CFR 50, Appendis B (Quality Assurance Criteria for Nuclear Power and Fuel Reprocessing Plants) to Swedish conditions is presented. No references are given to regulations standards etc that influence the requirements and their adaption to local conditions. (Aa)

  19. The role of the EPA radiation quality assurance program in the measurement quality assurance accreditation program for radioassay laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Grady, T.M. [Environmental Monitoring Systems Laboratory, Las Vegas, NV (United States)

    1993-12-31

    As the nature and extent of radiological contamination becomes better documented and more public, radioanalytical laboratories are faced with a constantly expanding variety of new and difficult analytical requirements. Concurrent with those requirements is the responsibility to provide customers, regulatory officials, or the public with defensible data produced in an environment of verifiable, controlled quality. To meet that need, a quality assurance accreditation program for radioassay laboratories has been proposed by the American National Standards Institute (ANSI). The standard will provide the organizational framework and functional requirements needed to assure the quality of laboratory outputs. Under the proposed program, the U.S. Environmental Protection Agency`s (EPA`s) Laboratory Intercomparison Program plays a key role as a reference laboratory. The current and proposed roles of the EPA Intercomparison Program are discussed, as are the functional relationships between EPA, the accreditating organization, and the service and monitoring laboratories.

  20. 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...

  1. 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

  2. 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)

  3. Manpower requirements of quality assurance personnel for the nuclear power plants

    International Nuclear Information System (INIS)

    Aly, A.E.; El-sayed, A.A.; Shabaan, I.H.

    1987-01-01

    Basic principles for structuring and staffing of the quality assurance (Q.A.)organisation in the nuclear power plant (NPP) are presented. the manpower requirements of the Q.A.organisation in the NPP during both construction and operational stages are determined. the manpower requirements for Q.A./Q.C. functions in a NPP are found to be proportional to the number of craft workers needed to perform the required level of the construction. The Q.A./Q.C. personnel are about 15% of the total number of the craft workers required during construction

  4. Overall quality assurance program requirements for nuclear power plants

    International Nuclear Information System (INIS)

    1992-09-01

    This standard contains the requirements for the owner's overall quality assurance program for a nuclear power plant. This program encompasses all phases of a nuclear power plant life cycle, including site evaluation, design, procurement, manufacturing, construction and installation, commissioning, operation, and decommissioning. It covers the activities associated with specifying, directing, and administering the work to be done during these phases, and the evaluation and integrated of the activities and programs of participants

  5. 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

  6. Monitored Retrievable Storage System Requirements Document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design.

  7. 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

  8. High level waste storage tanks 242-A evaporator standards/requirement identification document

    International Nuclear Information System (INIS)

    Biebesheimer, E.

    1996-01-01

    This document, the Standards/Requirements Identification Document (S/RIDS) for the subject facility, represents the necessary and sufficient requirements to provide an adequate level of protection of the worker, public health and safety, and the environment. It lists those source documents from which requirements were extracted, and those requirements documents considered, but from which no requirements where taken. Documents considered as source documents included State and Federal Regulations, DOE Orders, and DOE Standards

  9. 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.

  10. Technical Document on Control of Nitrogen Oxides From Municipal Waste Combustors

    Science.gov (United States)

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  11. Requirements for auditing of quality assurance programs for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Requirements and guidance are provided for establishing and implementing a system of internal and external audits of quality assurance programs for nuclear power plants, including the preparation, performance, reporting and follow-up of audits by both the auditing and the audited organizations. This standard is to be used in conjunction with ANSI N45.2

  12. IAEA's role in achieving and assuring safety in the transport of radioactive materials

    International Nuclear Information System (INIS)

    White, M.C.

    1983-01-01

    The results of the radiological impact studies, the data on shipments and the feedback from compliance assurance actions will help identify any shortcomings or weaknesses in the Regulations. The Advisory Material and the Explanatory Material, by amplifying the various requirements and elaborating the purpose and reason(s) for them, will help users understand the Regulations. These documents may also help motivate users. Quality Assurance will help prevent problems in the implementation process. Compliance Assurance will detect and lead to the rectification of failures in the implementation process. The data transfer on Certificates will aid in stopping the use of unsafe packages. 17 references

  13. Simplifying documentation while approaching site closure: integrated health and safety plans as documented safety analysis

    International Nuclear Information System (INIS)

    Brown, Tulanda

    2003-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D and D I-HASP as an example

  14. 10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-25

    Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)

  15. Implementation of quality assurance in the nuclear industry of Republic of Korea

    International Nuclear Information System (INIS)

    Voin, V.

    1985-10-01

    This paper describes the assistance supplied by FRAMEX to achieve establishment and implementation of Quality Assurance Program by Korean Manufacturers. But to assure that equipment purchased in KOREA complies with the procurement documents, technical assistance has been provided to transfer proven, reliable know-how and technology. At this stage of the project, we can say that the total support which is available for the Korean manufacturers is efficient. We have the adequate confidence that the quality of the equipment conforms to predetermined requirements and that it will perform satisfactorily in service. Experienced and qualified personnel in Quality Assurance is now available in KOREA for the development of Korean nuclear program

  16. 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

  17. 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)

  18. Supplemental design requirements document, Project W026

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1993-01-01

    This document supplements and extends the Functional Design Criteria, SP-W026-FDC-001, for the Waste Receiving and Processing Facility (WRAP), Module 1. It provides additional detailed requirements, summarizes key Westinghouse Hanford Company design guidance, and establishes baseline technical agreements to be used in definitive design of the WRAP-1 facility. Revision 3 of the Supplemental Design Requirements Document has been assigned an Impact Level of 3ESQ based on the content of the entire revision. The actual changes made from Revision 2 have an Impact Level of 3S and the basis for these changes was previously reviewed and approved per WHC correspondence No. 9355770

  19. 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

  20. 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

  1. Fiscal year 1997-1998 waste information requirements document

    International Nuclear Information System (INIS)

    Poppiti, J.A.

    1997-01-01

    The Waste Information Requirements Document describes the activities of the Tank Waste Remediation System (TWRS) Characterization Project that provide characterization information on Hanford Site waste tanks. The characterization information is required to perform operations and meet the commitments of TWRS end users. These commitments are derived from the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement; the Recommendation 93-5 Implementation Plan to the Defense Nuclear Facilities Safety Board (DNFSB); and other directives as listed in Section 4.0. This Waste Information Requirement Document applies to Fiscal Years 1997 and 1998 activities. Its contents are based on the best information available in August 1997. The format and content are based on the directions of DOE-RL (Sieracki, 1997) and Fluor Daniel Hanford Incorporated (Umek, 1997). Activities, such as the revision of the Tank Characterization Technical Sampling Basis (Brown et al. 1997), the revision of the data quality objectives (DQOs), issue closures, discussions with Ecology, and management decisions may cause subsequent updates to the Waste Information Requirements Document

  2. Quality assured technical documentation for nuclear power generation

    International Nuclear Information System (INIS)

    Ault, M.P.

    1992-01-01

    Present day large scale industry in general is made up of highly complex technology subjected to many rigorous external controls and constraints. This is particularly so in the nuclear power industry where it is essential that materials and services provided during the phases of construction, commissioning and operations, conform precisely to requirements as specified. Failure to do this could lead to unit shut-down and loss of income. For over 25 years, a central unit within the Central Electricity Generating Board (CEGB) developed an enviable reputation for the production of high class technical documentation essential during power station commissioning and operations phases. Following privatization of the electricity supply industry in 1991 the unit became a stand-alone organization and since 1989 has been known as Technical Publications Management Services (TPMS). TPMS with its many years of experience now offers its services to industry in general as well as to the electricity supply industry. Work currently being undertaken by TPMS is described here. Recent contracts obtained for work at Sizewell and for Severn Trent Water indicate the continuing and expanding need for specialist documentation services. (author)

  3. 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.)

  4. Delivery of completed irradiation vehicles and the quality assurance document to the High Flux Isotope Reactor for irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Petrie, Christian M. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); McDuffee, Joel Lee [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Katoh, Yutai [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    This report details the initial fabrication and delivery of two Fuel Cycle Research and Development (FCRD) irradiation capsules (ATFSC01 and ATFSC02), with associated quality assurance documentation, to the High Flux Isotope Reactor (HFIR). The capsules and documentation were delivered by September 30, 2015, thus meeting the deadline for milestone M3FT-15OR0202268. These irradiation experiments are testing silicon carbide composite tubes in order to obtain experimental validation of thermo-mechanical models of stress states in SiC cladding irradiated under a prototypic high heat flux. This document contains a copy of the completed capsule fabrication request sheets, which detail all constituent components, pertinent drawings, etc., along with a detailed summary of the capsule assembly process performed by the Thermal Hydraulics and Irradiation Engineering Group (THIEG) in the Reactor and Nuclear Systems Division (RNSD). A complete fabrication package record is maintained by the THIEG and is available upon request.

  5. Spent Nuclear Fuel Project document control and Records Management Program Description

    International Nuclear Information System (INIS)

    MARTIN, B.M.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document

  6. Impact of extreme load requirements and quality assurance on nuclear power plant costs

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1993-01-01

    Definitive costs, applicable to nuclear power plant concrete structures, as a function of National Regulatory Requirements, standardization, the effect of extreme load design associated with both design basis accidents and extreme external events and quality assurance are difficult to develop since such effects are interrelated and not only differ widely from country to country, project to project but also vary in time. Table 1 shows an estimate of the of the overall plant cost effects of external event extreme load design on nuclear power plant design for the U.S -and selected foreign countries for which experience with LWRs exist- Germany is the most expensive primarily due to a military aircraft crash resistance. However, the German requirement for 4 safeguards trains rather than 2 and the containment design requirement to consider one Steam Generator blowdown concurrent with a RCS blowdown. This presentation will concentrate on the direct current impact extreme load design and quality assurance have on concrete structures, systems and components for nuclear plants. This presentation is considered timely due to the increased interest in the c potential backfit of Eastern European nuclear power stations of the WWER 440 and WWER 1000 types which typically did not consider the extreme loads identified in Table 1 and accident loads in Table 3 and quality assurance in Table 5 in their original design. Concrete structures in particular are highlighted because they typically form the last barrier to radioactive release from the containment and other Safety Related Structures

  7. Maintenance of the electrical and electronic components and quality assurance

    International Nuclear Information System (INIS)

    Foletto, A.

    1992-01-01

    Quality assurance in the area of maintenance must satisfy certain requirements which concern the materials to be replaced, the working and requalification documentation and the qualifications of the persons carrying out the work. The test systems described in the last section of this article have a dual aim - quality of the work and reduced duration. tabs

  8. ISS Crew Transportation and Services Requirements Document

    Science.gov (United States)

    Bayt, Robert L. (Compiler); Lueders, Kathryn L. (Compiler)

    2016-01-01

    The ISS Crew Transportation and Services Requirements Document (CCT-REQ-1130) contains all technical, safety, and crew health medical requirements that are mandatory for achieving a Crew Transportation System Certification that will allow for International Space Station delivery and return of NASA crew and limited cargo. Previously approved on TN23183.

  9. Underground Test Area Activity Quality Assurance Plan Nevada National Security Site, Nevada. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Farnham, Irene [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States); Krenzien, Susan [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2012-10-01

    This Quality Assurance Plan (QAP) provides the overall quality assurance (QA) requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) activities. The requirements in this QAP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). NNSA/NSO, or designee, must review this QAP every two years. Changes that do not affect the overall scope or requirements will not require an immediate QAP revision but will be incorporated into the next revision cycle after identification. Section 1.0 describes UGTA objectives, participant responsibilities, and administrative and management quality requirements (i.e., training, records, procurement). Section 1.0 also details data management and computer software requirements. Section 2.0 establishes the requirements to ensure newly collected data are valid, existing data uses are appropriate, and environmental-modeling methods are reliable. Section 3.0 provides feedback loops through assessments and reports to management. Section 4.0 provides the framework for corrective actions. Section 5.0 provides references for this document.

  10. Comparative analysis of quality assurance requirements for selected LMFBR components of classes 1, 2 and 3

    International Nuclear Information System (INIS)

    Kleinert, K.P.

    1992-01-01

    The study analyses and compares German, French, British and Italian practices and procedures applied for various LMFBR projects both related to the quality assurance system and related to the particular type of class of component:Class 1: primary reactor vessel; Class 2: Secondary sodium pump; Class 3: Primary cold trap. Various areas of analysis and comparison were selected to identify the underlying concepts of grading of requirements and measures, to identify the similarities and differences, and to give recommendations for further actions concerning quality assurance requirements 60 refs., 21 tabs., 6 figs

  11. Quality assurance programme for the LVR-15 nuclear research reactor

    International Nuclear Information System (INIS)

    1995-03-01

    The document specifies all aspects of the quality assurance programme for the LVR-15 nuclear research reactor. The programme addresses the organization and responsibilities, basic quality assurance activities, and identification of management, planning, and working documents necessary to implement the programme. (P.A.)

  12. Quality assurance on the Idaho National Engineering Laboratory Buried Waste Program

    International Nuclear Information System (INIS)

    Rasmussen, T.L.

    1989-01-01

    This paper discusses the clean-up of an Idaho National Engineering Laboratory (INEL) site utilized for disposal of transuranic contaminated waste from 1954 until 1970. The author presents requirements of the environmental protection statutes that have generated quality assurance requirements in addition to those historically implemented as a part of facility design, construction and operation. A hierarchy of program guidance quality documentation and procedures is discussed. Data qualification and computer database management are identified as requirements

  13. ENHANCED CHARACTERIZATION OF THE REPOSITORY BLOCK REQUIREMENTS DOCUMENT (ECRB-RD)

    International Nuclear Information System (INIS)

    G.M. Teraoka

    1998-01-01

    This Enhanced Characterization of the Repository Block Requirements Document (ECRB-RD) provides applicable design and construction requirements for the Enhanced Characterization of the Repository Block (ECRB) East-West Drift and its associated equipment. This document also identifies the applicable requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) Document (YMPICM-00 19, Revision 2, ICN- 1) for design and construction of the ECRB East-West Drift, ground support, constructor support utilities and components. These requirements have been tailored specifically for the ECRB East-West Drift design and construction. The allocated requirements for the ECRB East-West Drift are in Sections III through VI. The requirements in sections III through VI contain requirement numbers from the ESFDR, Rev 2, ICN-1 for reference back to the ESFDR. Each requirement in the ECRB-RD also identifies a trace to the Site Design and Test Requirements Document (YMP/CM-0021, Rev. 2, ICN-1) and 10CFR60 similar to the style used in the ESFDR. These traces to 10CFR60 are consistent with the 1995 version of 10CFR60 used by the SD and TRD and the ESFDR. Those ESFDR requirements statements that were technically modified are identified as such and those that were derived as part of this allocation are also identified. An activity evaluation has been performed in accordance with QAP-2-0 and has determined that the QA program is applicable to this document. Therefore, the development of this document was performed in compliance with QAP-3-5, Revision 7, Development of Technical Documents and checked and reviewed in compliance with Section 5.3. This is consistent with the IOC from R. Stambaugh to M. Lugo on the subject of ECRB-RD, Revision 1, TDPP Applicability (LV.SEI.,RMS.03/98-0 12, Dated 3/12/98). The ECRB East-West Drift includes those excavated underground openings to support enhanced characterization testing activities for the repository block and provides potential

  14. Quality assurance standards: comparison between IAEA 50-C/SG-Q and ISO 9001:1994

    International Nuclear Information System (INIS)

    2000-11-01

    The International Atomic Energy Agency (IAEA) and the International Organization for Standardization (ISO) agreement regarding the scope and coverage of documents published by both organizations points out that the standards of safety developed by the IAEA are recommendations for use by its Member States in the framework of national regulations for the safe utilization of nuclear energy. Such standards should be considered as nuclear safety regulatory documents. The standards developed by the ISO are complementary technical documents emphasizing industrial application and contractual aspects. Regarding the quality assurance topic, the IAEA standards 50-C/SG-Q are mostly used directly or indirectly to establish the nuclear safety requirements at the utility-regulatory interface. The industrial ISO 9001 standards have progressively been used to implement the quality assurance requirements at the interface utility-supplier. The relationship between both standards is growing in significance owing to the impact upon the owners/operators of nuclear facilities and their contractors/suppliers. The relationship between the IAEA and ISO standards is considered critical, in particular regarding suppliers with a small range of nuclear supplies. These organizations are not always willing to prepare special quality assurance programmes based on nuclear safety standards. On the other hand, these organizations may be qualified on the basis of the ISO quality assurance standards. In any case, for delivering nuclear items and services the quality assurance programme must comply with the requirements established in the nuclear safety regulatory standards. This implies that the utility-supplier will have to demonstrate that the acceptable degree of quality assurance in relation to nuclear safety is accomplished. This may be achieved by imposing additional requirements on the supplier over and above those contained within the ISO. In order to provide a description of the differences

  15. UMTRA Project Office quality assurance program plan. Revision 6

    International Nuclear Information System (INIS)

    1994-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites. The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. Because these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the UMTRA Project Office and its contractors

  16. Tank waste remediation system privatization phase I infrastructure, project W-519, Quality Assurance implementation plan

    International Nuclear Information System (INIS)

    HUSTON, J.J.

    1999-01-01

    This document has been prepared to identify the quality requirements for all products/activities developed by or for Project W-519. This plan is responsive to the Numatec Hanford Corporation, Quality Assurance Program Plan, NHC-MP-001

  17. Documentation of medical findings in radiation workers in the GDR to meet the requirements of ICRP publication 26

    International Nuclear Information System (INIS)

    Wolff, H.R.; Neumeister, K.

    1979-01-01

    Based on ICRP Publication 26, the future organization of the medical surveillance system for radiation workers in the GDR is considered in this paper. These radiation workers will also in future be medically supervised by means of pre-employment and routine examinations. It is considered necessary to have as extensive a registration as possible of information on medical examinations, working place analyses and incidents. Such data have to be collected and stored to be compared with other national and international projects (e.g. in the field of occupational health). In addition, they should permit epidemiological studies to be internationally co-ordinated. For this purpose, a documentation system has been prepared in the German Democratic Republic which is based on GDR experiences and makes it possible to specify the requirements of ICRP Publication 26. This system forms a new basis for mass examinations of occupationally exposed persons. Uniform examination methods tailored to meet the task of assuring occupational health in the GDR will be introduced. The documentation cards are meant to be used as clear-text cards suited for automatic reading by optical character recognition. The examination form consists of ten parts and comprises all details from working place situation to medical findings to laboratory results. It is felt that this new documentation system permits registration of all relevant data required for the effective radiation protection of man. On the basis of this documentation of findings, participation is scheduled in the respective international IAEA programmes and the studies proposed by the ICRP for problems of radiation-induced carcinogenesis and radiogenetics

  18. 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

  19. Quality assurance technical cooperation and training

    International Nuclear Information System (INIS)

    Chen, C.K.

    1993-01-01

    An IAEA Manual (TRS 340) which provides guidance for establishing training programme covering Quality Assurance principles and practices was published in 1992. The document is mainly based on the experience and material collected through the performance of some 50 interregional, regional and national training courses, seminars and workshops on Quality Assurance organized by the IAEA in about 20 countries. The purpose of this document is to provide a systematic approach for use by the responsible management in developing an overall QA training programme and lecture material for all personnel of a nuclear power plant. The document can be suitably adjusted for various management levels and adapted to the national variables and needs

  20. 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

  1. Concept document of the repository-based software engineering program: A constructive appraisal

    Science.gov (United States)

    1992-01-01

    A constructive appraisal of the Concept Document of the Repository-Based Software Engineering Program is provided. The Concept Document is designed to provide an overview of the Repository-Based Software Engineering (RBSE) Program. The Document should be brief and provide the context for reading subsequent requirements and product specifications. That is, all requirements to be developed should be traceable to the Concept Document. Applied Expertise's analysis of the Document was directed toward assuring that: (1) the Executive Summary provides a clear, concise, and comprehensive overview of the Concept (rewrite as necessary); (2) the sections of the Document make best use of the NASA 'Data Item Description' for concept documents; (3) the information contained in the Document provides a foundation for subsequent requirements; and (4) the document adequately: identifies the problem being addressed; articulates RBSE's specific role; specifies the unique aspects of the program; and identifies the nature and extent of the program's users.

  2. Development of quality assurance programme for prescribed ionizing radiation source testing. Recommendations

    International Nuclear Information System (INIS)

    1999-01-01

    The document gives guidance to those applying for licence to perform ionizing radiation source acceptance tests and long-term stability tests and provides information which should be known when introducing quality assurance systems in compliance with legislative requirements. It is envisaged that this document ('Recommendations') will form a basis for final Safety Guides to be issued by the State Office for Nuclear Safety, the Czech nuclear regulatory authority. The setup of the publication is as follows. Part I gives a glossary of basic terms in quality systems. Part 2 explains quality system principles, paying special attention to radiation safety issues, and describes the structure and scope of quality system documentation. Part 3 explains the individual elements of the quality system and gives practical examples. Part 4 deals with the quality assurance programme; using instructions and practical examples, this part shows how the quality system elements should be applied to long-time stability testing and acceptance testing. A model structure of 2nd degree documentation (guidelines) and a model testing protocol are given in annexes. (P.A.)

  3. 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.

  4. 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

  5. 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.

  6. 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

  7. Sequence Coding and Search System Backfit Quality Assurance Program Plan

    International Nuclear Information System (INIS)

    Lovell, C.J.; Stepina, P.L.

    1985-03-01

    The Sequence Coding and Search System is a computer-based encoding system for events described in Licensee Event Reports. This data system contains LERs from 1981 to present. Backfit of the data system to include LERs prior to 1981 is required. This report documents the Quality Assurance Program Plan that EG and G Idaho, Inc. will follow while encoding 1980 LERs

  8. Quality Assurance in Higher Education: Proposals for Consultation.

    Science.gov (United States)

    Higher Education Funding Council for England, Bristol.

    This document sets out for consultation proposals for a revised method for quality assurance of teaching and learning in higher education. The proposals cover: (1) the objectives and principles of quality assurance; (2) an approach to quality assurance based on external audit principles; (3) the collection and publication of information; (4)…

  9. Project W-441 cold vacuum drying facility design requirements document

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage

  10. A Functional Model of Quality Assurance for Psychiatric Hospitals and Corresponding Staffing Requirements.

    Science.gov (United States)

    Kamis-Gould, Edna; And Others

    1991-01-01

    A model for quality assurance (QA) in psychiatric hospitals is described. Its functions (general QA, utilization review, clinical records, evaluation, management information systems, risk management, and infection control), subfunctions, and corresponding staffing requirements are reviewed. This model was designed to foster standardization in QA…

  11. Development and implementation of an analytical quality assurance plan at the Hanford site

    International Nuclear Information System (INIS)

    Kuhl-Klinger, K.J.; Taylor, C.D.; Kawabata, K.K.

    1995-08-01

    The Hanford Analytical Services Quality Assurance Plan (HASQAP) provides a uniform standard for onsite and offsite laboratories performing analytical work in support of Hanford Site environmental cleanup initiatives. The Hanford Site is a nuclear site that originated during World War 11 and has a legacy of environmental clean up issues. In early 1993, the need for and feasibility of developing a quality assurance plan to direct all analytical activities performed to support environmental cleanup initiatives set forth in the Hanford Federal Facility Agreement and Consent Order were discussed. Several group discussions were held and from them came the HASQAP. This document will become the quality assurance guidance document in a Federal Facility Agreement and Consent Order. This paper presents the mechanics involved in developing a quality assurance plan for this scope of activity, including the approach taken to resolve the variability of quality control requirements driven by numerous regulations. It further describes the consensus building process and how the goal of uniting onsite and offsite laboratories as well as inorganic, organic, and radioanalytic disciplines under a common understanding of basic quality control concepts was achieved

  12. 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.

  13. Documentation and verification required for type A packaging use

    Energy Technology Data Exchange (ETDEWEB)

    O`Brien, J.H.

    1997-07-30

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ``Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.`` This guidance document uses a checklist to show compliance.

  14. Documentation and verification required for type A packaging use

    International Nuclear Information System (INIS)

    O'Brien, J.H.

    1997-01-01

    This document furnishes knowledge and methods for verifying compliance with the U.S. Department of Transportation (DOT) packaging requirements for shipping Type A quantities of radioactive material. The primary emphasis is on the requirements identified in 49 CFR 173.415(a), which states, ''Each offeror of a Specification 7A package must maintain on file for at least one year after the shipment, and shall provide to DOT on request, complete documentation of tests and an engineering evaluation of comparative data showing that the construction methods, packaging design, and materials of construction comply with that specification.'' This guidance document uses a checklist to show compliance

  15. From document to database: modernizing requirements management

    International Nuclear Information System (INIS)

    Giajnorio, J.; Hamilton, S.

    2007-01-01

    The creation, communication, and management of design requirements are central to the successful completion of any large engineering project, both technically and commercially. Design requirements in the Canadian nuclear industry are typically numbered lists in multiple documents created using word processing software. As an alternative, GE Nuclear Products implemented a central requirements management database for a major project at Bruce Power. The database configured the off-the-shelf software product, Telelogic Doors, to GE's requirements structure. This paper describes the advantages realized by this scheme. Examples include traceability from customer requirements through to test procedures, concurrent engineering, and automated change history. (author)

  16. Quality assurance experience in the manufacture of PFBR reactor vessel during technology development work

    International Nuclear Information System (INIS)

    Shanmugam, K.; Chandramohan, R.; Ramamurthy, M.K.

    1996-01-01

    An efficient and proper implementation of quality assurance in the technology development works of Prototype Fast Breeder Reactor (PFBR) main vessel was undertaken to achieve the desired quality and dimensional accuracy of main vessel. In this paper an attempt has been made to bring out the methods and procedures adopted to implement the quality assurance programme on important activities including approval of documents, material, general requirements for manufacture of SS components, inspection procedures, forming and welding of petals, non-destructive testing etc. (author)

  17. 6 CFR 17.115 - Assurance required.

    Science.gov (United States)

    2010-01-01

    ... OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 17... agencies must ensure that applications for Federal financial assistance or awards of Federal financial... financial assistance extended to provide real property or structures thereon, such assurance shall obligate...

  18. 14 CFR 1253.115 - Assurance required.

    Science.gov (United States)

    2010-01-01

    ... OF SEX IN EDUCATION PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Introduction § 1253... agencies must ensure that applications for Federal financial assistance or awards of Federal financial... financial assistance extended to provide real property or structures thereon, such assurance shall obligate...

  19. CAED Document Repository

    Data.gov (United States)

    U.S. Environmental Protection Agency — Compliance Assurance and Enforcement Division Document Repository (CAEDDOCRESP) provides internal and external access of Inspection Records, Enforcement Actions, and...

  20. Implementation guide for use with suspect/counterfeit items: Requirements of DOE O 440.1, worker protection management; 10 CFR 830.120; and DOE 5700.6C, quality assurance

    International Nuclear Information System (INIS)

    1997-06-01

    Department of Energy (DOE) Order (O) 440.1, Worker Protection Management For DOE Federal and Contractors Employees, [7] sets forth requirements for DOE and its contractors to implement suspect and counterfeit items (S/CI) controls as part of the quality assurance (QA) programs required by 10 Code of Federal Regulations (CFR) 830.120 [8] or DOE 5700.6C, Quality Assurance [9]. DOE G-830.120, Implementation Guide for Use with 10 CFR Part 830.120, Quality Assurance, [10] provides additional guidance on establishing and implementing effective QA processes to control S/CIs. DOE O 232.1, Occurrence Reporting and Processing of Operations, [11] specifies requirements for reporting S/CIs under the DOE Occurrence Reporting and Processing System (ORPS). DOE promulgated the requirements and guidance to control or eliminate the hazards posed by S/CIs, which can lead to unexpected equipment failures and undue risks to the DOE mission, the environment, and personnel. This Guide is a compendium of information contained in the referenced DOE directives and other documents concerning S/CI controls. It incorporates, updates, and supersedes earlier guidance issued in Plan for the Suspect/Counterfeit Products Issue in the Department of Energy, dated October 1993, [4] and in memoranda issued by Defense Programs (DP) [12-16] and other DOE program offices. This guidance was developed to strengthen the procurement process, identify and eliminate S/CIs, and improve the reporting of S/CIs. The information in this Guide, when implemented by DOE and its contractors, will satisfy the S/CI requirements contained in the referenced DOE directives

  1. Implementation guide for use with suspect/counterfeit items: Requirements of DOE O 440.1, worker protection management; 10 CFR 830.120; and DOE 5700.6C, quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    Department of Energy (DOE) Order (O) 440.1, Worker Protection Management For DOE Federal and Contractors Employees, [7] sets forth requirements for DOE and its contractors to implement suspect and counterfeit items (S/CI) controls as part of the quality assurance (QA) programs required by 10 Code of Federal Regulations (CFR) 830.120 [8] or DOE 5700.6C, Quality Assurance [9]. DOE G-830.120, Implementation Guide for Use with 10 CFR Part 830.120, Quality Assurance, [10] provides additional guidance on establishing and implementing effective QA processes to control S/CIs. DOE O 232.1, Occurrence Reporting and Processing of Operations, [11] specifies requirements for reporting S/CIs under the DOE Occurrence Reporting and Processing System (ORPS). DOE promulgated the requirements and guidance to control or eliminate the hazards posed by S/CIs, which can lead to unexpected equipment failures and undue risks to the DOE mission, the environment, and personnel. This Guide is a compendium of information contained in the referenced DOE directives and other documents concerning S/CI controls. It incorporates, updates, and supersedes earlier guidance issued in Plan for the Suspect/Counterfeit Products Issue in the Department of Energy, dated October 1993, [4] and in memoranda issued by Defense Programs (DP) [12-16] and other DOE program offices. This guidance was developed to strengthen the procurement process, identify and eliminate S/CIs, and improve the reporting of S/CIs. The information in this Guide, when implemented by DOE and its contractors, will satisfy the S/CI requirements contained in the referenced DOE directives.

  2. EUR, an European utility requirements documents for future LWR power stations

    International Nuclear Information System (INIS)

    Berbey, Pierre; Lienard, Michel; Redon, Ramon; Essmann, Juergen; Taylor, David T.

    2004-01-01

    A group of the major European utilities are developing a common requirement document which will be used for the LWR nuclear power plants to be built in Europe from the beginning of the next century. This document provides harmonised policies and technical requirements that will allow the implementation of a design developed in one country into another one. The objectives and contents of the document, the organisation set up for its production and the main requirements are summarised in the paper. (author)

  3. 45 CFR 84.5 - Assurances required.

    Science.gov (United States)

    2010-10-01

    ... benefits. (2) In the case of Federal financial assistance extended to provide personal property, the... effecting or recording this transfer shall contain a covenant running with the land to assure... benefits. (2) Where no transfer of property is involved but property is purchased or improved with Federal...

  4. 22 CFR 217.5 - Assurances required.

    Science.gov (United States)

    2010-04-01

    ... benefits. (2) In the case of Federal financial assistance extended to provide personal property, the... or recording this transfer shall contain a covenant running with the land to assure nondiscrimination... services or benefits. (2) Where no transfer of property is involved but property is purchased or improved...

  5. Quality Assurance Program Plan for TRUPACT-II Gas Generation Test Program

    International Nuclear Information System (INIS)

    2002-01-01

    The Gas Generation Test Program (GGTP), referred to as the Program, is designed to establish the concentration of flammable gases and/or gas generation rates in a test category waste container intended for shipment in the Transuranic Package Transporter-II (TRUPACT-II). The phrase 'gas generationtesting' shall refer to any activity that establishes the flammable gas concentration or the flammable gas generation rate. This includes, but is not limited to, measurements performed directly on waste containers or during tests performed on waste containers. This Quality Assurance Program Plan (QAPP) documents the quality assurance (QA) and quality control (QC) requirements that apply to the Program. The TRUPACT-II requirements and technical bases for allowable flammable gas concentration and gas generation rates are described in the TRUPACT-II Authorized Methods for Payload Control (TRAMPAC).

  6. Quality assurance for the IAEA International Database on Irradiated Nuclear Graphite Properties

    International Nuclear Information System (INIS)

    Wickham, A.J.; Humbert, D.

    2006-06-01

    Consideration has been given to the process of Quality Assurance applied to data entered into current versions of the IAEA International Database on Irradiated Nuclear Graphite Properties. Originally conceived simply as a means of collecting and preserving data on irradiation experiments and reactor operation, the data are increasingly being utilised for the preparation of safety arguments and in the design of new graphites for forthcoming generations of graphite-moderated plant. Under these circumstances, regulatory agencies require assurances that the data are of appropriate accuracy and correctly transcribed, that obvious errors in the original documentation are either highlighted or corrected, etc., before they are prepared to accept analyses built upon these data. The processes employed in the data transcription are described in this document, and proposals are made for the categorisation of data and for error reporting by Database users. (author)

  7. B plant standards/requirements identification document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the B Plant. This S/RID is applicable to the appropriate life cycle phases of design, construction,operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  8. 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...

  9. Environmental Restoration Program quality system requirements for the Hanford Site

    International Nuclear Information System (INIS)

    Cote, R.F.

    1993-11-01

    This document defines the quality system requirements for the US Department of Energy, Richland Operations Office, Environmental Restoration Program at the Hanford Site. The Quality System Requirements (OSR) for the Hanford Site integrates quality assurance requirements from the US Department of Energy Orders, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), and applicable industry standards into a single source document for the development of quality systems applicable to the Environmental Restoration Program activities. This document, based on fifteen criteria and divided intro three parts, provides user organizations with the flexibility to incorporate only those criteria and parts applicable to their specific scopes of work. The requirements of this document shall be applied to activities that affect quality based on a graded approach that takes into consideration the risk inherent in, as well as the importance of, specific items, services, and activities in terms of meeting ER Program objectives and customer expectations. The individual quality systems developed in accordance with this document are intended to provide an integrated management control system that assures the conduct of ER Program activities in a manner that protects human health and the environment

  10. Functions and requirements document for interim store solidified high-level and transuranic waste

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Fewell, M.A., Westinghouse Hanford

    1996-05-17

    The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

  11. Quality Assurance Tracking System - R7 (QATS-R7)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This is metadata documentation for the Quality Assurance Tracking System - R7, an EPA Region 7 resource that tracks information on quality assurance reviews. Also...

  12. Using simulation and virtual machines to identify information assurance requirements

    Science.gov (United States)

    Banks, Sheila B.; Stytz, Martin R.

    2010-04-01

    The US military is changing its philosophy, approach, and technologies used for warfare. In the process of achieving this vision for high-speed, highly mobile warfare, there are a number of issues that must be addressed and solved; issues that are not addressed by commercial systems because Department of Defense (DoD) Information Technology (IT) systems operate in an environment different from the commercial world. The differences arise from the differences in the scope and skill used in attacks upon DoD systems, the interdependencies between DoD software systems used for network centric warfare (NCW), and the need to rely upon commercial software components in virtually every DoD system. As a result, while NCW promises more effective and efficient means for employing DoD resources, it also increases the vulnerability and allure of DoD systems to cyber attack. A further challenge arises due to the rapid changes in software and information assurance (IA) requirements and technologies over the course of a project. Therefore, the four challenges that must be addressed are determining how to specify the information assurance requirements for a DoD system, minimizing changes to commercial software, incorporation of new system and IA requirements in a timely manner with minimal impact, and insuring that the interdependencies between systems do not result in cyber attack vulnerabilities. In this paper, we address all four issues. In addition to addressing the four challenges outlined above, the interdependencies and interconnections between systems indicate that the IA requirements for a system must consider two important facets of a system's IA defensive capabilities. The facets are the types of IA attacks that the system must repel and the ability of a system to insure that any IA attack that penetrates the system is contained within the system and does not spread. The IA requirements should be derived from threat assessments for the system as well as for the need to

  13. 24 CFR 8.50 - Assurances required.

    Science.gov (United States)

    2010-04-01

    ... another purpose involving the provision of similar services or benefits. (2) In the case of Federal... contain a covenant running with the land to assure nondiscrimination for the period during which the real... purpose involving the provision of similar services or benefits. (2) Where no transfer of property is...

  14. 34 CFR 104.5 - Assurances required.

    Science.gov (United States)

    2010-07-01

    ... involving the provision of similar services or benefits. (2) In the case of Federal financial assistance... running with the land to assure nondiscrimination for the period during which the real property is used... the provision of similar services or benefits. (2) Where no transfer of property is involved but...

  15. Requirements for the data transfer during the examination of design documentation

    Directory of Open Access Journals (Sweden)

    Karakozova Irina

    2017-01-01

    Full Text Available When you transfer the design documents to the examination office, number of incompatible electronic documents increases dramatically. The article discusses the way to solve the problem of transferring of the text and graphic data of design documentation for state and non-state expertise, as well as verification of estimates and requirement management. The methods for the recognition of the system elements and requirements for the transferring of text and graphic design documents are provided. The need to use the classification and coding of various elements of information systems (structures, objects, resources, requirements, contracts, etc. in data transferring systems is indicated separately. The authors have developed a sequence of document processing and transmission of data during the examination, and propose a language for describing the construction of the facility, taking into account the classification criteria of the structures and construction works.

  16. The European Utility Requirement Document

    International Nuclear Information System (INIS)

    Roche, I.I.

    1999-01-01

    The major European electricity producers work on a common requirement document for future LWR plants since 1992. They aim at requirements acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Such a standardisation promotes an improvement of generation costs and of safety : public and authorities acceptance should be improved as well ; significant savings are expected in development and construction costs. Since the early stages of the project, the EUR group has grown significantly. It now includes utilities from nine European countries. Utilities from two other European countries are joining the group. Specific cooperation agreements are also in progress with a few extra-European partners

  17. 45 CFR 1170.51 - Assurances required.

    Science.gov (United States)

    2010-10-01

    ... extended or for another purpose involving the provision of similar services or benefits. (2) In the case of... transfer shall contain a covenant running with the land to assure nondiscrimination for the period during... for another purpose involving the provision of similar services or benefits. (2) Where no transfer of...

  18. Quality assurance for health and environmental chemistry: 1986

    International Nuclear Information System (INIS)

    Gautier, M.A.; Gladney, E.S.; Moss, W.D.; Phillips, M.B.; O'Malley, B.T.

    1987-11-01

    This report documents the continuing quality assurance efforts of the Health and Environmental Chemistry Group at the Los Alamos National Laboratory. The philosophy, methodology, and computing resources used by the quality assurance program to encompass the diversity of analytical chemistry practiced in the group are described. Included in the report are all quality assurance reference materials used, along with their certified or consensus concentrations, and all analytical chemistry quality assurance measurements made by HSE-9 during 1986. 27 refs., 3 figs

  19. Quality assurance program manual for nuclear power plants. Volume I. Policies

    International Nuclear Information System (INIS)

    1975-01-01

    Policies and procedures are presented which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumers Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary

  20. 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...

  1. High-level waste tank farm set point document

    International Nuclear Information System (INIS)

    Anthony, J.A. III.

    1995-01-01

    Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope

  2. High-level waste tank farm set point document

    Energy Technology Data Exchange (ETDEWEB)

    Anthony, J.A. III

    1995-01-15

    Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.

  3. MDEP VICWG-02 Technical Report - Survey on quality assurance program requirements

    International Nuclear Information System (INIS)

    2011-01-01

    The survey was prepared using the requirements of Appendix B to 10 CFR Part 50, 'Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants'. These requirements form the basis upon which the U.S. NRC oversees the activities of vendors providing parts and services to the commercial U.S. nuclear power industry. As discussed and agreed to at the October 2008 Vendor Inspection Cooperation Working Group meeting in Dijon, France, the survey that follows was developed using these requirements. The survey is divided into the 18 basic criteria of Appendix B to 10 CFR Part 50. Within each criteria there are individual requirements that have been identified as separate and distinct elements that are covered during the inspection of vendor activities. In addition to the requirements of Appendix B to 10 CFR Part 50, the requirements of 10 CFR Part 21, 'Reporting of Defects and Non-compliance', have been listed at the end of the survey as an example of 'Other Requirements Related To Vendor Inspections', for the NRC. (authors)

  4. Internal Audits and Quality Assurance Surveillance in NPP Krsko

    International Nuclear Information System (INIS)

    Cavajda, M.; Bracic, I.

    1996-01-01

    This paper is describing establishment of the requirements for the development and execution of the Internal Audit and Quality Assurance Surveillance Program in the NPP Krsko, to identify relevant regulatory commitment and other documents, and to exhibit different functional areas, levels and work categories and factors that impact selecting and scheduling an audit or surveillance. It is not intention of this paper to explain how and by whom an audit or surveillance has to be done. (author)

  5. System requirements specification for waste information and control system

    International Nuclear Information System (INIS)

    Harris, R.R.

    1994-09-01

    This document defines the requirements for the Waste Information and Control System (WICS). The document defines the functions, constraints, and objectives that pertain to WICS. This shall serve as the baseline document to ensure the needs of the Hazardous Material Control group (HMC) at 222-S Laboratory are met with regard to assurance of accuracy and quality of data taken with WICS

  6. 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...

  7. Standard review plan for the review of environmental restoration remedial action quality assurance program plans

    International Nuclear Information System (INIS)

    1991-09-01

    This plan establishes both the scope of the review and the acceptance criteria to be utilized for the review of Quality Assurance Program Plans (QAPPs) developed in accordance with the requirements of DOE/RL-90-28. DOE/RL-90-28, the Environmental Restoration Remedial Action Quality Assurance Requirements Document (QARD) defines all quality assurance (QA) requirements governing activities that affect the quality of the Environmental Restoration Remedial Action (ERRA) program at the Hanford Site. These requirements are defined in three parts, Part 1 of Quality Management and Administration tasks, Part 2 for Environmental Data Operations, and Part 3 of the Design and Construction of items, systems, and facilities. The purpose of this document is to identify the scope of the review by the DOE Field Office, Richland staff, and establish the acceptance criteria (Parts 1, 2, and 3) that the DOE Field Office, Richland staff will utilize to evaluate the participant QAPPs. Use of the standard review plan will (1) help ensure that participant QAPPs contain the information required by DOE/RL-90-28, (2) aid program participant and DOE Field Office, Richland staff is ensuring that the information describing the participant's QAPP is complete, (3) help persons regarding DOE/RL- 90-28 to locate information, and (4) contribute to decreasing the time needed for the review process. In addition, the Standard Review Plan (SRP) ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate compliance of participant quality programs against DOE/RL-90-28

  8. Preliminary design requirements document (DRD) for Project W-236B, ''Initial Pretreatment Module''

    International Nuclear Information System (INIS)

    Swanson, L.M.

    1995-01-01

    The scope of this Design Requirements Document (DRD) is to identify and define the functions, with associated requirements, which must be performed to separate Hanford Site tank waste supernatants into low-level and high-level fractions. This documents sets forth function requirements, performance requirements, and design constraints necessary to begin conceptual design for the Initial Pretreatment Module (IPM). System and physical interfaces between the IPM project and the Tank Waste Remediation System (TWRS) are identified. The constraints, performance requirements, and transfer of information and data across a technical interface will be documented in an Interface Control Document. Supplemental DRDs will be prepared to provide more detailed requirements specific to systems described in the DRD

  9. Performance assurance of the re-applying project documentation

    Science.gov (United States)

    Kozlova, Olga

    2017-10-01

    Usage of the re-applying project documentation is cost effective measure. Saving of budgetary funds for purchases for development of new project documentation occurs by means of it. It also becomes possible to consider better decisions and prevent the repetition of mistakes. Nowadays, state authorities in construction management are forming separate institute for re-applying project documentation. The article shows the main tasks of such events and the issues to be solved for achievement of a high positive result.

  10. Functions and requirements for the INEL light duty utility arm gripper end effector

    International Nuclear Information System (INIS)

    Pace, D.P.; Barnes, G.E.

    1995-02-01

    This gripper end effector system functions and requirements document defines the system functions that the end effector must perform as well as the requirements the design must meet. Safety, quality assurance, operations, environmental conditions, and regulatory requirements have been considered. The main purpose of this document is to provide a basis for the end effector engineering, design, and fabrication activities. The document shall be the living reference document to initiate the development activities and will be updated as system technologies are finalized

  11. Functions and requirements for the INEL light duty utility arm sampler end effector

    International Nuclear Information System (INIS)

    Pace, D.P.; Barnes, G.E.

    1995-02-01

    This sampler end effector system functions and requirements document defines the system functions that the end effector must perform as well as the requirements the design must meet. Safety, quality assurance, operations, environmental conditions, and regulatory requirements have been considered. The main purpose of this document is to provide a basis for the end effector engineering, design, and fabrication activities. The document shall be the living reference document to initiate the development activities and will be updated as system technologies are finalized

  12. Current quality assurance concepts and considerations for quality control of in-clinic biochemistry testing.

    Science.gov (United States)

    Lester, Sally; Harr, K E; Rishniw, Mark; Pion, Paul

    2013-01-15

    Quality assurance is an implied concept inherent in every consumer's purchase of a product or service. In laboratory testing, quality assurance encompasses preanalytic (sampling, transport, and handling prior to testing), analytic (measurement), and postanalytic (reporting and interpretation) factors. Quality-assurance programs require that procedures are in place to detect errors in all 3 components and that the procedures are characterized by both documentation and correction of errors. There are regulatory bodies that provide mandatory standards for and regulation of human medical laboratories. No such regulations exist for veterinary laboratory testing. The American Society for Veterinary Clinical Pathology (ASVCP) Quality Assurance and Laboratory Standards Committee was formed in 1996 in response to concerns of ASVCP members about quality assurance and quality control in laboratories performing veterinary testing. Guidelines for veterinary laboratory testing have been developed by the ASVCP. The purpose of this report was to provide an overview of selected quality-assurance concepts and to provide recommendations for quality control for in-clinic biochemistry testing in general veterinary practice.

  13. Traceability and retrievability: Documentation, the bridge from science to compliance

    International Nuclear Information System (INIS)

    Warner, P.J.

    1997-01-01

    In this day of regulatory compliance, the fact that good science was practiced and documented is, in and of itself, not enough to assure a successful licensing or permitting result. A new level of documentation, that clearly walks a non-project reviewer through the traceability of all activities and decisions is required for successful acceptance of scientific results. Compliance reviewers (whether the Nuclear Regulatory Commission (NRC), Environmental Protection Agency (EPA), etc.) expect to verify the results of the scientific and program activities without the physical presence of the person or persons that conducted the activity. Traceability of activities and associated decisions through the retrieval of all associated records is a must. This presentation is based on lessons learned from the various quality assurance (QA) audits and program reviews of Sandia National Laboratories, Nuclear Waste Management Programs Center, scientific and programmatic documentation. The authors build a bridge from science to compliance from lessons learned. Here now is a somewhat fictional rendition of actual scientific testing and compliance support activities

  14. Hanford Tanks Initiative requirements and document management process guide

    International Nuclear Information System (INIS)

    Schaus, P.S.

    1998-01-01

    This revision of the guide provides updated references to project management level Program Management and Assessment Configuration Management activities, and provides working level directions for submitting requirements and project documentation related to the Hanford Tanks Initiative (HTI) project. This includes documents and information created by HTI, as well as non-HTI generated materials submitted to the project

  15. Quality assurance for health and environmental chemistry: 1989

    International Nuclear Information System (INIS)

    Gautier, M.A.; Gladney, E.S.; Koski, N.L.; Jones, E.A.; Phillips, M.B.; O'Malley, B.T.

    1990-12-01

    This report documents the continuing quality assurance efforts of the Health and Environmental Chemistry Group (HSE-9) at the Los Alamos National Laboratory. The philosophy, methodology, computing resources, and laboratory information management system used by the quality assurance program to encompass the diversity of analytical chemistry practiced in the group are described. Included in the report are all quality assurance reference materials used, along with their certified or consensus concentrations, and all analytical chemistry quality assurance measurements made by HSE-9 during 1989. 38 refs., 8 figs., 3 tabs

  16. Position paper: recommendations for a digital mammography quality assurance program V4.0.

    Science.gov (United States)

    Heggie, J C P; Barnes, P; Cartwright, L; Diffey, J; Tse, J; Herley, J; McLean, I D; Thomson, F J; Grewal, R K; Collins, L T

    2017-09-01

    In 2001 the ACPSEM published a position paper on quality assurance in screen film mammography which was subsequently adopted as a basis for the quality assurance programs of both the Royal Australian and New Zealand College of Radiologists (RANZCR) and of BreastScreen Australia. Since then the clinical implementation of digital mammography has been realised and it has become evident that existing screen-film protocols were not appropriate to assure the required image quality needed for reliable diagnosis or to address the new dose implications resulting from digital technology. In addition, the advantages and responsibilities inherent in teleradiology are most critical in mammography and also need to be addressed. The current document is the result of a review of current overseas practice and local experience in these areas. At this time the technology of digital imaging is undergoing significant development and there is still a lack of full international consensus about some of the detailed quality control (QC) tests that should be included in quality assurance (QA) programs. This document describes the current status in digital mammography QA and recommends test procedures that may be suitable in the Australasian environment. For completeness, this document also includes a review of the QA programs required for the various types of digital biopsy units used in mammography. In the future, international harmonisation of digital quality assurance in mammography and changes in the technology may require a review of this document. Version 2.0 represented the first of these updates and key changes related to image quality evaluation, ghost image evaluation and interpretation of signal to noise ratio measurements. In Version 3.0 some significant changes, made in light of further experience gained in testing digital mammography equipment were introduced. In Version 4.0, further changes have been made, most notably digital breast tomosynthesis (DBT) testing and QC have

  17. Project Quality Assurance Plan for research and development services provided by Oak Ridge National Laboratory in support of the Westinghouse Materials Company of Ohio Operable Unit 1 Stabilization Development and Treatability Studies Program

    Energy Technology Data Exchange (ETDEWEB)

    Gilliam, T.M.

    1991-05-01

    This Project Quality Assurance Plan (PQAP) sets forth the quality assurance (QA) requirements that are applied to those elements of the Westinghouse Materials Company of Ohio (WMCO) Operable Unit 1 support at Oak Ridge National Laboratory (ORNL) project that involve research and development (R D) performed at ORNL. This is in compliance with the applicable criteria of 10 CFR Part 50, Appendix B, ANSI/ASME NQA-1, as specified by Department of Energy (DOE) Oak Ridge Operations (ORO) Order 5700.6B. For this application, NQA-1 is the core QA Program requirements document. QA policy, normally found in the requirements document, is contained herein. The requirements of this PQAP apply to project activities that affect the quality and reliability/credibility of research, development, and investigative data and documentation. These activities include the functions of attaining quality objectives and assuring that an appropriate QA program scope is established. The scope of activities affecting quality includes organization; personnel training and qualifications; design control; procurement; material handling and storage; operating procedures; testing, surveillance, and auditing; R D investigative activities and documentation; deficiencies; corrective actions; and QA record keeping. 12 figs.

  18. The Marshall Islands radioassay quality assurance program. An overview

    International Nuclear Information System (INIS)

    Hamilton, T.F.; Robison, W.L.; Kehl, S.; Stoker, A.C.; Conrado, C.L.

    2000-01-01

    An extensive quality assurance program to provide high quality data and assessments in support of the Marshall Islands Dose Assessment and Radioecology Program has been developed the Lawrence Livermore National Laboratory. Quality assurance objectives begin with the premise of providing integrated and cost-effective program support (to meet wide-ranging programmatic needs, scientific peer review, and build public confidence) and continue through from design and implementation of large-scale field programs, sampling and sample preparation, radiometric and chemical analyses, documentation of quality assurance/quality control practices, exposure assessments, and dose/risk assessments until publication. The basic structure of the radioassay quality assurance/quality control program can be divided into four essential elements: (1) sample and data integrity control, (2) instrument validation and calibration, (3) method performance testing, validation, development and documentation, and (4) periodic peer review and on-site assessments. While the quality assurance objectives are tailored towards a single research program and the evaluation of major exposure pathways/critical radionuclides pertinent to the Marshall Islands, quality assurance practices that are consistent with proposed criteria designed for laboratory accreditation were attempted to be developed. (author)

  19. Advanced light water reactor utility requirements document: Volume 1--ALWR policy and summary of top-tier requirements

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The U.S. utilities are leading an industry wide effort to establish the technical foundation for the design of the Advanced Light Water Reactor (ALWR). This effort, the ALWR Program, is being managed for the U.S. electric utility industry by the Electric Power Research Institute (EPRI) and includes participation and sponsorship of several international utility companies and close cooperation with the U.S. Department of Energy (DOE). The cornerstone of the ALWR Program is a set of utility design requirements which are contained in the ALWR Requirements Document. The purpose of the Requirement Document is to present a clear, complete statement of utility desires for their next generation of nuclear plants. The Requirements Document covers the entire plant up to the grid interface. It therefore is the basis for an integrated plant design, i.e., nuclear steam supply system and balance of plant, and it emphasizes those areas which are most important to the objective of achieving an ALWR which is excellent with respect to safety, performance, constructibility, and economics. The document applies to both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). The Requirements Document is organized in three volumes. Volume 1 summarizes AlWR Program policy statements and top-tier requirements. The top-tier design requirements are categorized by major functions, including safety and investment protection, performance, and design process and constructibility. There is also a set of general design requirements, such as simplification and proven technology, which apply broadly to the ALWR design, and a set of economic goals for the ALWR program. The top-tier design requirements are described further in Volume 1 and are formally invoked as requirements in Volumes 2 and 3

  20. Quality assurance guidance for TRUPACT-II [Transuranic Package Transporter-II] payload control

    International Nuclear Information System (INIS)

    1989-10-01

    The Transuranic Package Transporter-II (TRUPACT-II) Safety Analysis Report for Packaging (SARP) approved by the Nuclear Regulatory Commission (NRC), discusses authorized methods for payload control in Appendix 1.3.7 and the Quality Assurance (QA) requirements in Section 9.3. Subsection 9.3.2.1 covers maintenance and use of the TRUPACT-II and the specific QA requirements are given in DOE/WIPP 89-012. Subsection 9.3.2.2 covers payload compliance, for which this document was written. 6 refs

  1. Quality assurance plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1994-01-01

    This Quality Assurance Plan (QAP) is concerned with design and construction (Sect. 2) and characterization and monitoring (Sect. 3). The basis for Sect. 2 is the Quality Assurance Plan for the Design and Construction of Waste Area Grouping 6 Closure at Oak Ridge National Laboratory, Oak Ridge, Tennessee, and the basis for Sect. 3 is the Environmental Restoration Quality Program Plan. Combining the two areas into one plan gives a single, overall document that explains the requirements and from which the individual QAPs and quality assurance project plans can be written. The Waste Area Grouping (WAG) 6 QAP establishes the procedures and requirements to be implemented for control of quality-related activities for the WAG 6 project. Quality Assurance (QA) activities are subject to requirements detailed in the Martin Marietta Energy Systems, Inc. (Energy Systems), QA Program and the Environmental Restoration (ER) QA Program, as well as to other quality requirements. These activities may be performed by Energy Systems organizations, subcontractors to Energy Systems, and architect-engineer (A-E) under prime contract to the US Department of Energy (DOE), or a construction manager under prime contract to DOE. This plan specifies the overall Energy Systems quality requirements for the project. The WAG 6 QAP will be supplemented by subproject QAPs that will identify additional requirements pertaining to each subproject

  2. Roles of the operator and the safety services in nuclear power plant quality assurance

    International Nuclear Information System (INIS)

    Widmer, M.; Perrot, J.

    1985-01-01

    With regard to the operation of nuclear power plants, Electricite de France formally recognized in 1973 that it was necessary for safety reasons and economically acceptable to adopt organizational principles of quality assurance that would be applicable both to its own activities and to those of its suppliers. Generally speaking, the form and spirit of the quality assurance programme chosen is based largely on the Code of Practice No. 50-C-QA. In particular, the programme focuses on the flexible character of quality assurance requirements and stresses that in the final analysis product quality depends above all on those to whom the project has been assigned, because it is they who are responsible for meeting the quality objectives set. Ten years of experience with the suppliers of Electricite de France has shown that these suppliers, after some initial difficulty, have been able to adapt the application of quality assurance so as to achieve satisfactory quality as regards both safety and availability. In the case of the French standard nuclear power plants, quality assurance is particularly important thanks to the traceability which it affords and to the allowance for corrective measures which it demands. The safety services normally take action related to quality assurance in three ways: through regulation, the analysis of measures to assure plant safety, and plant supervision. As regards regulation, an order has just been published relating to design, construction and operational quality in base-load nuclear power plants. The requirements laid down in this document incorporate the recommendations of the IAEA Code on quality assurance. (author)

  3. 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.

  4. Current status of quality assurance of treatment planning systems

    International Nuclear Information System (INIS)

    Mijnheer, B.J.

    1997-01-01

    A review is given of the current status of quality assurance of treatment planning systems. At this moment only one comprehensive report is available. In order to review national activities a questionnaire has been distributed amongst national societies of medical physicists. From the 23 responding countries, 8 indicated that only limited efforts are underway, 8 answered that a working group is evaluating their specific national requirements while in 5 countries a document is drafted. The highlights of these reports have been summarized. (author)

  5. Documentation Service

    International Nuclear Information System (INIS)

    Charnay, J.; Chosson, L.; Croize, M.; Ducloux, A.; Flores, S.; Jarroux, D.; Melka, J.; Morgue, D.; Mottin, C.

    1998-01-01

    This service assures the treatment and diffusion of the scientific information and the management of the scientific production of the institute as well as the secretariat operation for the groups and services of the institute. The report on documentation-library section mentions: the management of the documentation funds, search in international databases (INIS, Current Contents, Inspects), Pret-Inter service which allows accessing documents through DEMOCRITE network of IN2P3. As realizations also mentioned are: the setup of a video, photo database, the Web home page of the institute's library, follow-up of digitizing the document funds by integrating the CD-ROMs and diskettes, electronic archiving of the scientific production, etc

  6. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    International Nuclear Information System (INIS)

    Burbank, D.A.

    1998-01-01

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

  7. E-nursing documentation as a tool for quality assurance.

    Science.gov (United States)

    Rajkovic, Vladislav; Sustersic, Olga; Rajkovic, Uros

    2006-01-01

    The article presents the results of a project with which we describe the reengineering of nursing documentation. Documentation in nursing is an efficient tool for ensuring quality health care and consequently quality patient treatment along the whole clinical path. We have taken into account the nursing process and patient treatment based on Henderson theoretical model of nursing that consists of 14 basic living activities. The model of new documentation enables tracing, transparency, selectivity, monitoring and analyses. All these factors lead to improvements of a health system as well as to improved safety of patients and members of nursing teams. Thus the documentation was developed for three health care segments: secondary and tertiary level, dispensaries and community health care. The new quality introduced to the documentation process by information and communication technology is presented by a database model and a software prototype for managing documentation.

  8. Preliminary Design Requirements Document for Project W-314

    Energy Technology Data Exchange (ETDEWEB)

    MCGREW, D.L.

    2000-04-27

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1.

  9. Preliminary Design Requirements Document for Project W-314

    International Nuclear Information System (INIS)

    MCGREW, D.L.

    2000-01-01

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1

  10. 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

  11. 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

  12. 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

  13. 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

  14. Detector Control System for an LHC experiment - User Requirements Document

    CERN Document Server

    CERN. Geneva

    1997-01-01

    The purpose of this document is to provide the user requirements for a detector control system kernel for the LHC experiments following the ESA standard PSS-05 [1]. The first issue will be used to provide the basis for an evaluation of possible development philosophies for a kernel DCS. As such it will cover all the major functionality but only to a level of detail sufficient for such an evaluation to be performed. Many of the requirements are therefore intentionally high level and generic, and are meant to outline the functionality that would be required of the kernel DCS, but not yet to the level of the detail required for implementation. The document is also written in a generic fashion in order not to rule out any implementation technology.

  15. 7 CFR 15b.5 - Assurances required.

    Science.gov (United States)

    2010-01-01

    ... assistance is extended or for another purpose involving the provision of similar services or benefits. (2) In... recording this transfer shall contain a covenant running with the land to assure nondiscrimination for the... is extended or for another purpose involving the provision of similar services or benefits. (2) Where...

  16. Plutonium immobilization project development and testing technical project office quality assurance program description

    International Nuclear Information System (INIS)

    Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

    1999-01-01

    The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

  17. Quality assurance and reference material requirements and considerations for environmental sample analysis in nuclear forensics

    International Nuclear Information System (INIS)

    Swindle, D.W. Jr.; Perrin, R.E.; Goldberg, S.A.; Cappis, J.

    2002-01-01

    Full text: High-sensitivity nuclear environmental sampling and analysis techniques have been proven in their ability to verify declared nuclear activities, as well as to assist in the detection of undeclared nuclear activities and facilities. Following the Gulf War, the capability and revealing power of environmental sampling and analysis techniques to support international safeguards was demonstrated and subsequently adopted by the International Atomic Energy Agency (IAEA) as routine safeguards measures in safeguards inspections and verifications. In addition to having been proved useful in international safeguards, environmental sampling and analysis techniques have demonstrated their utility in identifying the origins of 'orphaned' nuclear material, as well as the origin of intercepted smuggled nuclear material. Today, environmental sampling and analysis techniques are now being applied in six broad areas to support nonproliferation, disarmament treaty verification, national and international nuclear security, and environmental stewardship of weapons production activities. Consequently, more and more laboratories around the world are establishing capabilities or expanding capabilities to meet these growing applications, and as such requirements for quality assurance and control are increasing. The six areas are: 1) Nuclear safeguards; 2) Nuclear forensics/illicit trafficking; 3) Ongoing monitoring and verification (OMV); 4) Comprehensive Test Ban Treaty (CTBT); 5) Weapons dismantlement/materials disposition; and 6) Research and development (R and D)/environmental stewardship/safety. Application of environmental sampling and analysis techniques and resources to illicit nuclear material trafficking, while embodying the same basic techniques and resources, does have unique requirements for sample management, handling, protocols, chain of custody, archiving, and data interpretation. These requirements are derived from needs of how data from nuclear forensics

  18. Technical basis document for internal dosimetry

    International Nuclear Information System (INIS)

    Hickman, D.P.

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

  19. Requirements for an ES and H assurance program at the working levels of organization

    International Nuclear Information System (INIS)

    Tierney, M.S.; Ellingson, A.C.

    1979-07-01

    Means by which the disciplines of quality assurance (QA), reliability (R), and human factors (HF) might be used to the advantage of Environment, Safety, and Health (ES and H) programs are being investigated. A generalized model assurance program, based on QA, R, and HF principles but specifically tailored to ES and H program needs, has been developed. Current studies address implementation of the model assurance program at the working levels of organization. It appears that the only way practicability at the working level can be determined is by the case study method. The present study represents a first step in the application of such a procedure. An attempt was made to approach the question of practicability by first constructing a generic ES and H assurance plan for working-level organizations that is based upon the more widely-applied model plan and studies mentioned earlier. Then the elements of this generic working-level plan were compared with the practices of an existing R and D organization at Sandia Laboratories, Albuquerque. Some of the necessary steps were taken to convert these practices to those required by the generic plan in order to gain a measure of the feasibility, cost, and some of the possible benefits of such a conversion. Partial results of one case study are presented, and some generalizations that emerge regarding the structure of an idealized working-level ES and H plan are made

  20. Quality assurance program plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Boom, R.J.

    1995-03-01

    This Quality Assurance Program Plan identifies quality assurance program requirements and addresses the various Westinghouse Hanford Company organizations and their particular responsibilities in regards to sample and data handling of airborne emissions. The Hanford Site radioactive airborne emissions requirements are defined in National Emissions Standards for Hazardous Air Pollutants (NESHAP), Code of Federal Regulations, Title 40, Part 61, Subpart H (EPA 1991a). Reporting of the emissions to the US Department of Energy is performed in compliance with requirements of US Department of Energy, Richland Operations Office Order 5400.1, General Environmental Protection Program (DOE-RL 1988). This Quality Assurance Program Plan is prepared in accordance with and to the requirements of QAMS-004/80, Guidelines and Specifications for Preparing Quality Assurance Program Plans (EPA 1983). Title 40 CFR Part 61, Appendix B, Method 114, Quality Assurance Methods (EPA 1991b) specifies the quality assurance requirements and that a program plan should be prepared to meet the requirements of this regulation. This Quality Assurance Program Plan identifies NESHAP responsibilities and how the Westinghouse Hanford Company Environmental, Safety, Health, and Quality Assurance Division will verify that the methods are properly implemented

  1. 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

  2. Basic national requirements for safe design, construction and operation

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1980-01-01

    Nuclear power plants have to be save. Vendors and utilities operating such plants, are convinced that their plants meet this requirement. Who, however, is establishing the safety requirements to be met by those manufacturing and operating nuclear power plants. What are the mechanisms to control whether the features provided assure the required safety level. Who controls whether the required and planned safety features are really provided. Who is eventually responsible for assuring safety after commissioning of a nuclear power plant. These fundamental questions being raised in many discussions on safety and environmental protection are dealt with in the following sections: (1) Fundamental safety requirements on nuclear power plants, in which such items as risk, legal bases and licensing procedure are discussed, (2) Surveillance during construction, in which safety analysis report, siting, safety evaluation, document examination, quality assurance, and commissioning testing are dealt with, (3) Operating tests and conditions in which recurrent inspections, environmental protection during operation, investigation of abnormal occurences and backfitting requirements as reviewed, and (4) Safety philosophy and safety policy to conclude this presentation. The German approach to nuclear safety serves as an example for an effective way of assuring safe nuclear power. (orig.)

  3. Lawrence Livermore National Laboratory Emergency Response Capability Baseline Needs Assessment Requirement Document

    Energy Technology Data Exchange (ETDEWEB)

    Sharry, J A

    2009-12-30

    This revision of the LLNL Fire Protection Baseline Needs Assessment (BNA) was prepared by John A. Sharry, LLNL Fire Marshal and LLNL Division Leader for Fire Protection and reviewed by Martin Gresho, Sandia/CA Fire Marshal. The document follows and expands upon the format and contents of the DOE Model Fire Protection Baseline Capabilities Assessment document contained on the DOE Fire Protection Web Site, but only address emergency response. The original LLNL BNA was created on April 23, 1997 as a means of collecting all requirements concerning emergency response capabilities at LLNL (including response to emergencies at Sandia/CA) into one BNA document. The original BNA documented the basis for emergency response, emergency personnel staffing, and emergency response equipment over the years. The BNA has been updated and reissued five times since in 1998, 1999, 2000, 2002, and 2004. A significant format change was performed in the 2004 update of the BNA in that it was 'zero based.' Starting with the requirement documents, the 2004 BNA evaluated the requirements, and determined minimum needs without regard to previous evaluations. This 2010 update maintains the same basic format and requirements as the 2004 BNA. In this 2010 BNA, as in the previous BNA, the document has been intentionally divided into two separate documents - the needs assessment (1) and the compliance assessment (2). The needs assessment will be referred to as the BNA and the compliance assessment will be referred to as the BNA Compliance Assessment. The primary driver for separation is that the needs assessment identifies the detailed applicable regulations (primarily NFPA Standards) for emergency response capabilities based on the hazards present at LLNL and Sandia/CA and the geographical location of the facilities. The needs assessment also identifies areas where the modification of the requirements in the applicable NFPA standards is appropriate, due to the improved fire protection

  4. Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

    International Nuclear Information System (INIS)

    Caplinger, W.H.

    1990-12-01

    This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

  5. 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

  6. Civilian Radioactive Waste Management System Requirements Document (CRP)

    International Nuclear Information System (INIS)

    C.A. Kouts

    2006-01-01

    The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further

  7. Underground Test Area Fiscal Year 2013 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Krenzien, Susan [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States); Marutzky, Sam [Navarro-Intera, LLC (N-I), Las Vegas, NV (United States)

    2014-01-01

    This report is required by the Underground Test Area (UGTA) Quality Assurance Plan (QAP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2013. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2013. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, and publishing documents. In addition, integrated UGTA required reading and corrective action tracking was instituted.

  8. 7 CFR 1488.8 - Documents required after delivery.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Documents required after delivery. 1488.8 Section... delivery. (a) CCC will purchase an exporter's account receivable only if the Treasurer, Commodity Credit... or Assistant Treasurer, CCC, after date of delivery of commodities exported or to be exported under...

  9. 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...

  10. 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

  11. Westinghouse Hanford Company (WHC) standards/requirements identification document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, G.L.

    1996-03-15

    This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES&H) standards/requirements for Westinghouse Hanford Company Level Programs, where implementation and compliance is the responsibility of these organizations. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  12. Manual on quality assurance for computer software related to the safety of nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

  13. National waste terminal storage repository in a bedded salt formation for spent unreprocessed fuel. Quality assurance program for licensing

    International Nuclear Information System (INIS)

    1978-12-01

    A National Waste Terminal Storage Repository, in bedded salt, for spent unreprocessed fuel is the subject of a conceptual design project which began in January 1977. This volume presents a preliminary quality assurance program to guide the license applicant in developing a detailed program that will be compatible with anticipated National Waste Terminal Storage (NWTSR2) contracting arrangements and provide the documentation required by regulatory bodies. This QA program is designed to provide confidence that the quality-related activities pertaining to safety-related structures, systems, and components will be identified and controlled. Specific responsibilities for quality-related activities are documented and assigned to personnel and organizations for the major phases of facility design and construction. These responsibilities encompass a broad range of activities and are addressed in this preliminary program. The quality assurance program elements are organized and discussed herein as follows: (1) quality assurance during design and construction; (2) the applicant (DOE); (3) siting contractor; (4) architect/engineer; (5) project field management; and (6) operations contractor

  14. IDC Re-Engineering Phase 2 System Requirements Document V1.3.

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data but includes requirements for the dissemination of radionuclide data and products.

  15. IDC Re-Engineering Phase 2 System Requirements Document Version 1.4

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-01-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data, but includes requirements for the dissemination of radionuclide data and products.

  16. 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)

  17. Quality assurance in digital dental radiography--justification and dose reduction in dental and maxillofacial radiology.

    Science.gov (United States)

    Hellstern, F; Geibel, M-A

    2012-01-01

    To evaluate the implementation of quality assurance requirements for digital dental radiography in routine clinical practice. The results should be discussed by radiation protection authorities in the context of the relevant legal requirements and current debates on radiation protection. Two hundred digital dental radiographs were randomly selected from the digital database of the Department of Dentistry's Dental and Maxillofacial Surgery Clinic, Ulm University, and evaluated for various aspects of image quality and compliance with radiographic documentation requirements. The dental films were prepared by different radiology assistants (RAs) using one of two digital intraoral radiographic systems: Sirona Heliodent DS, 60 kV, focal spot size: 0.7 mm (group A) or KaVo Gendex 765 DC, 65 kV, focal spot size: 0.4 mm (group B). Radiographic justification was documented in 70.5% of cases, and the radiographic findings in 76.5%. Both variables were documented in the patient records as well as in the software in 14% of cases. Clinical documentation of the required information (name of the responsible dentist and radiology assistant, date, patient name, department, tube voltage, tube current, exposure time, type of radiograph, film size, department and serial number of the dental radiograph) was 100% complete in all cases. Moreover, the department certified according to DIN ISO 9001:2008 specifications demonstrated complete clinical documentation of radiographic justifications and radiographic findings. The entire dentition was visible on 83% of the digital films. The visible area corresponded to the target region on 85.7% of the digital dental radiographs. Seven to 8.5% of the images were classified as "hypometric" or "hypermetric". This study indicates that improvements in radiology training and continuing education fordentists and dental staff performing x-ray examinations are needed to ensure consistent high quality of digital dental radiography. Implementation of

  18. Technical and quality assurance specifications for dosimetry services

    International Nuclear Information System (INIS)

    1989-01-01

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

  19. Quality assurance in the transport and packaging of radioactive material

    International Nuclear Information System (INIS)

    Hale, J.

    1995-01-01

    Quality Assurance (QA) is a requirement of the International Atomic Energy Agency (IAEA) Safety Series No. 6 ''Regulations for Safe Transport of Radioactive Materials.'' It is also, increasingly, a customer requirement. British Nuclear Fuels plc (BNFL) Transport Division has established an integrated management system (including quality and safety) which is being extended to cover environmental aspects. The management system covers the design, procurement, manufacture, testing, documentation, use, maintenance, inspection and decommissioning of all packages used for the transport of radioactive materials and for interim storage. It also covers planning, programming and transport operations. These arrangements cover all modes of transport by road, rail, sea and air. The QA arrangements developed enable Transport Division to demonstrate to Competent Authorities, customers and the general public that the systems in place meet all regulatory requirements. This paper discusses what quality assurance is, why QA arrangements should be introduced and how they were established within Transport Division. Finally, the further developments in the Division's quality arrangements using the tools and techniques of Total Quality Management (TQM) and the European Foundation for Quality Management Model for Self Assessment are described

  20. 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

  1. Westinghouse Hanford Company (WHC) standards/requirements identification document (S/RID)

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES ampersand amp;H) standards/requirements for Westinghouse Hanford Company Level Programs, where implementation and compliance is the responsibility of these organizations. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

  2. Maintenance quality assurance peer exchange 2.

    Science.gov (United States)

    2009-04-01

    This report documents a comprehensive study of twenty three maintenance quality assurance : (MQA) programs throughout the United States and Canada. The policies and standards of : each program were synthesized to create a general assessment on the co...

  3. 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...

  4. Project W-236A, work plan for preparation of a design requirements document

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    This work plan outlines the tasks necessary, and defines the organizational responsibilities for preparing a Design Requirements Document (DRD) for project W-236A, Multi-Function Waste Tank Facility (MWTF). A DRD is a Systems Engineering document which bounds, at a high level, the requirements of a discrete system element of the Tank Waste Remediation System (TWRS) Program. This system element is usually assigned to a specific project, in this case the MWTF. The DRD is the document that connects the TWRS program requirements with the highest level projects requirements and provides the project's link to the overall TWRS mission. The MWTF DRD effort is somewhat unique in that the project is already in detailed design, whereas a DRO is normally prepared prior to preliminary design. The MWTF design effort was initiated with a Functional Design Criteria (FDC) and a Supplemental Design Requirements Document (SDRD) bounding the high level requirements. Another unique aspect of this effort is that some of the TWRS program requirements are still in development. Because of these unique aspects of the MWTF DRD development, the MWTF will be developed from existing TWRS Program requirements and project specific requirements contained in the FDC and SDRD. The following list describes the objectives of the MWTF DRD: determine the primary functions of the tanks through a functional decomposition of the TWRS Program high level functions; allocate the primary functions to a sub-system architecture for the tanks; define the fundamental design features in terms of performance requirements for the system and subsystems; identify system interfaces and design constraints; and document the results in a DRD

  5. 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

  6. 40 CFR 194.22 - Quality assurance.

    Science.gov (United States)

    2010-07-01

    ... General Requirements § 194.22 Quality assurance. (a)(1) As soon as practicable after April 9, 1996, the Department shall adhere to a quality assurance program that implements the requirements of ASME NQA-1-1989... elicitation used to support applications for certification or re-certification of compliance; (vi) Design of...

  7. An approach to applying quality assurance to nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Cooper, R.B.; Abel, R.

    1996-12-01

    An approach to developing and applying a quality assurance program for a nuclear fuel waste disposal facility is described. The proposed program would be based on N286-series standards used for quality assurance programs in nuclear power plants, and would cover all aspects of work across all stages of the project, from initial feasibility studies to final closure of the vault. A quality assurance manual describing the overall quality assurance program and its elements would be prepared at the outset. Planning requirements of the quality assurance program would be addressed in a comprehensive plan for the project. Like the QA manual, this plan would be prepared at the outset of the project and updated at each stage. Particular attention would be given to incorporating the observational approach in procedures for underground engineering, where the ability to adapt designs and mining techniques to changing ground conditions would be essential. Quality verification requirements would be addressed through design reviews, peer reviews, inspections and surveillance, equipment calibration and laboratory analysis checks, and testing programs. Regular audits and program reviews would help to assess the state of implementation, degree of conformance to standards, and effectiveness of the quality assurance program. Audits would be particularly useful in assessing the quality systems of contractors and suppliers, and in verifying the completion of work at the end of stages. Since a nuclear fuel waste disposal project would span a period of about 90 years, a key function of the quality assurance program would be to ensure the continuity of knowledge and the transfer of experience from one stage to another This would be achieved by maintaining a records management system throughout the life of the project, by ensuring that work procedures were documented and kept current with new technologies and practices, and by instituting training programs that made use of experience gained

  8. 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

  9. CH2M Hill Hanford Group, Inc., Standards and Requirements Identification Document (SRID) Requirements Management System and Requirements Specification

    International Nuclear Information System (INIS)

    JOHNSON, A.L.

    2000-01-01

    The current Tank Farm Contractor (TFC) for the U. S. Department of Energy, Office of River Protection (ORP), River Protection Project (RPP), CH2M Hill Hanford Group, Inc. (CHG), will use a computer based requirements management system. The system will serve as a tool to assist in identifying, capturing, and maintaining the Standards/Requirements Identification Document (S/RID) requirements and links to implementing procedures and other documents. By managing requirements as one integrated set, CHG will be able to carry out its mission more efficiently and effectively. CHG has chosen the Dynamic Object Oriented Requirements System (DOORS(trademark)) as the preferred computer based requirements management system. Accordingly, the S/RID program will use DOORS(trademark). DOORS(trademark) will replace the Environmental Requirements Management Interface (ERMI) system as the tool for S/RID data management. The DOORS(trademark) S/RID test project currently resides on the DOORSTM test server. The S/RID project will be migrated to the DOORS(trademark) production server. After the migration the S/RID project will be considered a production project and will no longer reside on the test server

  10. Quality assurance requirements in the testing of packages to be used for safe transportation of RAM

    International Nuclear Information System (INIS)

    Vieru, Gheorghe; Nistor, Viorica; Mihaiu, Ramona

    2010-01-01

    The quality of the Type A, B or C packages used for transport and storage of Radioactive Material (RAM) has to be proved by performing qualification tests in accordance with the Transport Regulations, within the Reliability and Testing Laboratory, Institute for Nuclear Research (INR) Pitesti, where has designed and developed a new Romanian Testing Facility. The qualifications testing are performed under a strict quality assurance programme based on the specific procedures prior approved by the Romanian Nuclear Regulatory Body CNCAN (National Commission for Nuclear Activity Control). This paper describe the quality assurance programme in accordance with the quality management system developed in order to meet the requirements provided by the national regulations as well as to the requirements of the IAEA's safety standard TS-R-1 related to testing of packages to be used for transport of RAM and also provides an overview of the new Romanian Testing Facilities for RAM Packages, developed by the INR's Reliability and Testing Laboratory within an Excellence Scientific Contract. (authors)

  11. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  12. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    Maddox, B.S.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

  13. 17 CFR 4.31 - Required delivery of Disclosure Document to prospective clients.

    Science.gov (United States)

    2010-04-01

    ... Disclosure Document to prospective clients. 4.31 Section 4.31 Commodity and Securities Exchanges COMMODITY... Advisors § 4.31 Required delivery of Disclosure Document to prospective clients. (a) Each commodity trading... prospective client a Disclosure Document containing the information set forth in §§ 4.34 and 4.35 for the...

  14. Design requirements document for project W-520, immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Ashworth, S.C.

    1998-01-01

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

  15. Design requirements document for project W-520, immobilized low-activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  16. Guidelines for comprehensive quality assurance in brachytherapy

    International Nuclear Information System (INIS)

    Goldson, A.L.; Nibhanupudy, J.R.

    1984-01-01

    Brachytherapy treatment techniques can provide significant improvement in local control and overall survival, but only when quality assurance can be guaranteed. To establish brachytherapy quality assurance, basic requirements for three predetermined subdivisions of clinical institutions will be forwarded. These are: (1) centers having minimum requirements to provide brachytherapy, (2) intermediate centers such as regional or community hospitals, and (3) optimal centers such as university hospital and cancer centers. This presentation will highlight personnel needs, equipment requirements, academic activities, clinical experience with these systems and proposed quality assurance guidelines

  17. Commissioning quality assurance for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-09-01

    This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig.

  18. Commissioning quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    1986-09-01

    This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig

  19. Software quality assurance for safety analysis and risk management at the Savannah River Site

    International Nuclear Information System (INIS)

    Ades, M.J.; Toffer, H.; Crowe, R.D.

    1991-01-01

    As part of its Reactor Operations Improvement Program at the Savannah River Site (SRS), Westinghouse Savannah River Company (WSRC), in cooperation with the Westinghouse Hanford Company, has developed and implemented quality assurance for safety-related software for technical programs essential to the safety and reliability of reactor operations. More specifically, the quality assurance process involved the development and implementation of quality standards and attendant procedures based on industry software quality standards. These procedures were then applied to computer codes in reactor safety and probabilistic risk assessment analyses. This paper provides a review of the major aspects of the WSRC safety-related software quality assurance. In particular, quality assurance procedures are described for the different life cycle phases of the software that include the Requirements, Software Design and Implementation, Testing and Installation, Operation and Maintenance, and Retirement Phases. For each phase, specific provisions are made to categorize the range of activities, the level of responsibilities, and the documentation needed to assure the control of the software. The software quality assurance procedures developed and implemented are evolutionary in nature, and thus, prone to further refinements. These procedures, nevertheless, represent an effective controlling tool for the development, production, and operation of safety-related software applicable to reactor safety and probabilistic risk assessment analyses

  20. Quality-assurance plan for groundwater activities, U.S. Geological Survey, Washington Water Science Center

    Science.gov (United States)

    Kozar, Mark D.; Kahle, Sue C.

    2013-01-01

    This report documents the standard procedures, policies, and field methods used by the U.S. Geological Survey’s (USGS) Washington Water Science Center staff for activities related to the collection, processing, analysis, storage, and publication of groundwater data. This groundwater quality-assurance plan changes through time to accommodate new methods and requirements developed by the Washington Water Science Center and the USGS Office of Groundwater. The plan is based largely on requirements and guidelines provided by the USGS Office of Groundwater, or the USGS Water Mission Area. Regular updates to this plan represent an integral part of the quality-assurance process. Because numerous policy memoranda have been issued by the Office of Groundwater since the previous groundwater quality assurance plan was written, this report is a substantial revision of the previous report, supplants it, and contains significant additional policies not covered in the previous report. This updated plan includes information related to the organization and responsibilities of USGS Washington Water Science Center staff, training, safety, project proposal development, project review procedures, data collection activities, data processing activities, report review procedures, and archiving of field data and interpretative information pertaining to groundwater flow models, borehole aquifer tests, and aquifer tests. Important updates from the previous groundwater quality assurance plan include: (1) procedures for documenting and archiving of groundwater flow models; (2) revisions to procedures and policies for the creation of sites in the Groundwater Site Inventory database; (3) adoption of new water-level forms to be used within the USGS Washington Water Science Center; (4) procedures for future creation of borehole geophysics, surface geophysics, and aquifer-test archives; and (5) use of the USGS Multi Optional Network Key Entry System software for entry of routine water-level data

  1. 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

  2. Westinghouse Water Reactor Divisions quality assurance plan

    International Nuclear Information System (INIS)

    1977-09-01

    The Quality Assurance Program used by Westinghouse Water Reactor Divisions is described. The purpose of the program is to assure that the design, materials, and workmanship on Nuclear Steam Supply System (NSSS) equipment meet applicable safety requirements, fulfill the requirements of the contracts with the applicants, and satisfy the applicable codes, standards, and regulatory requirements. This program satisfies the NRC Quality Assurance Criteria, 10CFR50 Appendix B, to the extent that these criteria apply to safety related NSSS equipment. Also, it follows the regulatory position provided in NRC regulatory guides and the requirements of ANSI Standard N45.2.12 as identified in this Topical Report

  3. 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

  4. 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

  5. Issues and Experiences on Radioactive Waste Quality Control / Quality Assurance with Regard to Future Disposal

    International Nuclear Information System (INIS)

    Beckmerhagen, I.; Brennecke, P.; Steyer, S.; Bandt, G.

    2006-01-01

    In the Federal Republic of Germany all types of radioactive waste (short-lived, long-lived) are to be disposed of in deep geological formations. Thus, the safe management of radioactive waste presupposes an appropriate conditioning of primary waste-to-waste packages suitable for emplacement in a repository as well as the documentation of pre-treatment, processing and packaging steps and the waste package characteristics being relevant for disposal. Due to the operation, decommissioning and dismantling of nuclear facilities as well as the application of radioisotopes in industry, medicine and research and development radioactive waste continuously arises in Germany. In order to manage this waste different measures and procedures regarding its conditioning and quality control/quality assurance were introduced and since many years successfully applied. Waste conditioning is especially characterized by a flexible application of the Konrad waste acceptance requirements. The rationale for this approach is due to the present non-availability of a repository in Germany. Several examples of a 'tailor-made' application of the waste acceptance requirements in treatment, conditioning and documentation processes as well as the quality assurance/quality control processes illustrate the current German approach. (authors)

  6. Quality assurance systems at SKODA JS

    International Nuclear Information System (INIS)

    Janecek, P.

    2000-01-01

    In addition to technical requirements put upon the design, manufacture, installation and commissioning of equipment for nuclear power plants, emphasis is laid upon quality assurance of such activities so as to secure nuclear safety of installations over the world. As the technical level of nuclear safety assurance is being enhanced continuously, the requirements are becoming more and more stringent, which is mirrored by the relevant standards and legislation. SKODA JS has always been pursuing the quality goal and has been contributing to this aspect markedly. The quality assurance system at SKODA JS helps the company to satisfy all the appropriate requirements of its customers as well as the applicable standards and regulations. (author)

  7. Homogenization of independent inspection criteria of Quality Assurance in the maintenance activities

    International Nuclear Information System (INIS)

    Gomez Cardinanos, R.

    2012-01-01

    Among the official documents governing the operation of Spanish nuclear power plants is the Quality Manual and Quality Assurance. This manual gives a formal answer to the requirements of the regulations and the Nuclear Safety Council. To monitor the compliance of its requirements, the plants are controlled by independent organizations. Since 2007, in nuclear Sta. Maria de Garona is developed a project to improve the performance of the QA inspectors during maintenance activities. Results of the project have been edited data sheets on specific activities of maintenance. The project aims to incorporate sheets that help QA inspectors in their daily inspection.

  8. Quality assurance program plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Boom, R.J.

    1995-12-01

    This Quality Assurance Program Plan identifies quality assurance program requirements and addresses the various Westinghouse Hanford Company organizations and their particular responsibilities in regards to sample and data handling of radiological airborne emissions. This Quality Assurance Program Plan is prepared in accordance with and to written requirements

  9. Standard format and content of financial assurance mechanisms required for decommissioning under 10 CFR parts 30, 40, 70, and 72

    International Nuclear Information System (INIS)

    1990-06-01

    The purpose of this regulatory guide, ''Standard Format and Content of Financial Assurance Mechanisms Required for Decommissioning Under 10 CFR Parts 30, 40, 70, and 72,'' is to provide guidance acceptable to the NRC staff on the information to be provided for establishing financial assurance for decommissioning and to establish a standard format for presenting the information. Use of the standard format will help ensure that the financial instruments contain the information required by 10 CFR Parts 30, 40, 70, and 72; aid the applicant and NRC staff in ensuring that the information is complete; and help persons reading the financial instruments to locate information. This guide address financial assurance for decommissioning of facilities under materials licenses granted under Parts 30, 40, 70, and 72. These parts include licensees in the following categories: Part 30, Byproduct Material; Part 40, Source Material; Part 70, Special Nuclear Material; and Part 72, Independent Spent Fuel Storage Installations

  10. Quality assurance plan, Westinghouse Water Reactor Divisions

    Energy Technology Data Exchange (ETDEWEB)

    1976-03-01

    The Quality Assurance Program used by Westinghouse Nuclear Energy Systems Water Reactor Divisions is described. The purpose of the program is to assure that the design, materials, and workmanship on Nuclear Steam Supply System (NSSS) equipment meet applicable safety requirements, fulfill the requirements of the contracts with the applicants, and satisfy the applicable codes, standards, and regulatory requirements.

  11. Quality assurance during preoperational testing and during startup operation

    International Nuclear Information System (INIS)

    Eisele, H.; Meyer, F.A.

    1980-01-01

    Rules and guidelines for the quality assurance. Quality assurance in the course of preoperational testing and the startup period: preoperational testing; hot functional test I; hot functional test II; initial making critical and zero power physics testing; power range testing. Startup documents: startup program; startup instructions; startup data sheet; startup sequence outlines; final startup reports. Advisory safety committee for nuclear startup. (orig./RW)

  12. 50 CFR 23.19 - What CITES documents are required to export Appendix-I plants?

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false What CITES documents are required to... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Prohibitions, Exemptions, and Requirements § 23.19 What CITES documents are required to export Appendix-I plants? Answer the questions in the following decision...

  13. 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

  14. 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.

  15. 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

  16. 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.)

  17. 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)

  18. Multinationals' accountability on sustainability: the evolution of third-party assurance of sustainability reports

    OpenAIRE

    Perego, P.; Kolk, A.

    2012-01-01

    In this article we explore how multinational corporations (MNCs) adopt assurance practices to develop and sustain organizational accountability for sustainability. Using a panel of Fortune Global 250 firms over a period of 10 years, we document the diffusion patterns of third-party assurance of sustainability reports. We specifically investigate how evolving auditing practices, namely diversity of assurance standards and type of assurance providers, shape the quality of sustainability assuran...

  19. 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

  20. The evolving story of information assurance at the DoD.

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, Philip LaRoche

    2007-01-01

    This document is a review of five documents on information assurance from the Department of Defense (DoD), namely 5200.40, 8510.1-M, 8500.1, 8500.2, and an ''interim'' document on DIACAP [9]. The five documents divide into three sets: (1) 5200.40 & 8510.1-M, (2) 8500.1 & 8500.2, and (3) the interim DIACAP document. The first two sets describe the certification and accreditation process known as ''DITSCAP''; the last two sets describe the certification and accreditation process known as ''DIACAP'' (the second set applies to both processes). Each set of documents describes (1) a process, (2) a systems classification, and (3) a measurement standard. Appendices in this report (a) list the Phases, Activities, and Tasks of DITSCAP, (b) note the discrepancies between 5200.40 and 8510.1-M concerning DITSCAP Tasks and the System Security Authorization Agreement (SSAA), (c) analyze the DIACAP constraints on role fusion and on reporting, (d) map terms shared across the documents, and (e) review three additional documents on information assurance, namely DCID 6/3, NIST 800-37, and COBIT{reg_sign}.

  1. Assessment of LANL solid low-level waste management documentation

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1991-04-01

    DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section's capabilities regarding preparation and maintenance of appropriate criteria, plans and procedures and identify particular areas where these documents are not presently in existence or being fully implemented. DOE Order 5820.2A, Radioactive Waste Management, Chapter III sets forth the requirements and guidelines for preparation and implementation of criteria, plans and procedures to be utilized in the management of solid low-level waste. The documents being assessed in this report are: Solid Low-Level Waste Acceptance Criteria, Solid Low-Level Waste Characterization Plan, Solid Low-Level Waste Certification Plan, Solid Low-Level Waste Acceptance Procedures, Solid Low-Level Waste Characterization Procedures, Solid Low-Level Waste Certification Procedures, Solid Low-Level Waste Training Procedures, and Solid Low-Level Waste Recordkeeping Procedures. Suggested outlines for these documents are presented as Appendix A

  2. 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

  3. Regulatory inspection of the implementation of quality assurance programmes

    International Nuclear Information System (INIS)

    1989-01-01

    This Manual provides guidance to Member States in the organization and performance of their regulatory inspection functions regarding the implementation of nuclear power plant quality assurance programmes. It addresses the interface between, and is consistent with, the IAEA Nuclear Safety Standards (NUSS programme) documents on quality assurance and governmental organization. The Manual offers a practical model and examples for performing regulatory inspections to ensure that the quality assurance programme is operating satisfactorily in the siting, design, manufacturing, construction, commissioning, operation and decommissioning of nuclear power plants. The primary objective is to confirm that the licensee has the capability to manage and control the effective performance of all quality assurance responsibilities during all phases of a nuclear power project. The guidance provided through this Manual for proper establishment and execution of the regulatory inspections helps to enforce the effective implementation of the quality assurance programme as a management control system that the nuclear industry should establish and use in attaining the safety and reliability objectives for nuclear installations. This enforcement action by national regulatory bodies and the emphasis on the purposes and advantages of quality assurance as an important management tool integrated within the total project task have been recommended by the IAEA International Nuclear Safety Advisory Group (INSAG). The primary intended users of this Manual are the management personnel and high level staff from regulatory bodies but it will also be helpful to management personnel from nuclear utilities and vendors. They all are inevitable partners in a nuclear power project and this document offers all of them valuable information on the better accomplishment of quality assurance activities to ensure the common objective of safe and reliable nuclear power production

  4. Solid Waste Information and Tracking System (SWITS) Software Requirements Specification

    International Nuclear Information System (INIS)

    MAY, D.L.

    2000-01-01

    This document is the primary document establishing requirements for the Solid Waste Information and Tracking System (SWITS) as it is converted to a client-server architecture. The purpose is to provide the customer and the performing organizations with the requirements for the SWITS in the new environment. This Software Requirement Specification (SRS) describes the system requirements for the SWITS Project, and follows the PHMC Engineering Requirements, HNF-PRO-1819, and Computer Software Qualify Assurance Requirements, HNF-PRO-309, policies. This SRS includes sections on general description, specific requirements, references, appendices, and index. The SWITS system defined in this document stores information about the solid waste inventory on the Hanford site. Waste is tracked as it is generated, analyzed, shipped, stored, and treated. In addition to inventory reports a number of reports for regulatory agencies are produced

  5. Solid Waste Information and Tracking System (SWITS) Software Requirements Specification

    Energy Technology Data Exchange (ETDEWEB)

    MAY, D.L.

    2000-03-22

    This document is the primary document establishing requirements for the Solid Waste Information and Tracking System (SWITS) as it is converted to a client-server architecture. The purpose is to provide the customer and the performing organizations with the requirements for the SWITS in the new environment. This Software Requirement Specification (SRS) describes the system requirements for the SWITS Project, and follows the PHMC Engineering Requirements, HNF-PRO-1819, and Computer Software Qualify Assurance Requirements, HNF-PRO-309, policies. This SRS includes sections on general description, specific requirements, references, appendices, and index. The SWITS system defined in this document stores information about the solid waste inventory on the Hanford site. Waste is tracked as it is generated, analyzed, shipped, stored, and treated. In addition to inventory reports a number of reports for regulatory agencies are produced.

  6. Manufacture of heavy reactor components with particular considerations to quality assurance

    International Nuclear Information System (INIS)

    Kreppel, H.; Clausmeyer, H.

    1980-01-01

    The use of adequate quality assurance measures is one of the most important prerequisites for the manufacture of reactor components. Nature and extent of the quality assurance system at present adopted in the Federal Republic of Germany are illustrated, using the manufacture of a reactor pressure vessel as an example. The system comprises quality organization, planning of all quality assurance measures, quality surveillance through all stages of manufacture and documentation of quality attained. (orig.)

  7. Manufacture of heavy reactor components with particular consideration to quality assurance

    International Nuclear Information System (INIS)

    Clausmeyer, H.; Kreppel, H.

    1977-01-01

    The use of adequate quality assurance measures is one of the most important prerequisites for the manufacture of reactor components. Nature and extent of the quality assurance system at present adopted in the Federal Republic of Germany are illustrated, using the manufacture of a reactor pressure vessel as an example. The system comprises quality organization, planning of all quality assurance measures, quality surveillance through all stages of manufacture and documentation of quality attained. (orig.) [de

  8. Manufacture of heavy reactor components with particular consideration to quality assurance

    International Nuclear Information System (INIS)

    Kreppel, H.; Clausmeyer, H.

    1981-01-01

    The use of adequate quality assurance measures is one of the most important prerequisites for the manufacture of reactor components. Nature and extent of the quality assurance system at present adopted in the Federal Republic of Germany are illustrated, using the manufacture of a reactor pressure vessel as an example. The system comprises quality organization, planning of all quality assurance measures, quality surveillance through all stages of manufacture and documentation of quality attained. (orig.)

  9. System requirements and design description for the document basis database interface (DocBasis)

    International Nuclear Information System (INIS)

    Lehman, W.J.

    1997-01-01

    This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)

  10. UMTRA technical assistance contractor Quality Assurance Program Plan

    International Nuclear Information System (INIS)

    Pehrson, P.

    1993-01-01

    This Quality Assurance Program Plan (QAPP) provides the primary requirements for the integration of quality functions into all Technical Assistance Contractor (TAC) Project organization activities. The QAPP is the written directive authorized by the TAC Program Manager to accomplish this task and to implement procedures that provide the controls and sound management practices needed to ensure TAC contractual obligations are met. The QA program is designed to use monitoring, audit, and surveillance functions as management tools to ensure that all Project organization functions are executed in a manner that will protect public health and safety, promote the success of the Project, and meet or exceed contract requirements. The key to ensuring compliance with this directive is a two-step professional approach: utilize the quality system in all areas of activity, and generate a personal commitment from all personnel to provide quality service. The quality staff will be experienced, trained professionals capable of providing maximum flexibility to Project goal attainment. Such flexibility will enable the staff to be more cost effective and to further improve communication and coordination. To provide control details, this QAPP will be supplemented by approved standard operating procedures that provide requirements for performing the various TAC quality-related activities. These procedures shall describe applicable design input and document control activities and documentation

  11. 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)

  12. 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.

  13. 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

  14. Early Engagement of Safety and Mission Assurance Expertise Using Systems Engineering Tools: A Risk-Based Approach to Early Identification of Safety and Assurance Requirements

    Science.gov (United States)

    Darpel, Scott; Beckman, Sean

    2016-01-01

    Decades of systems engineering practice have demonstrated that the earlier the identification of requirements occurs, the lower the chance that costly redesigns will needed later in the project life cycle. A better understanding of all requirements can also improve the likelihood of a design's success. Significant effort has been put into developing tools and practices that facilitate requirements determination, including those that are part of the model-based systems engineering (MBSE) paradigm. These efforts have yielded improvements in requirements definition, but have thus far focused on a design's performance needs. The identification of safety & mission assurance (S&MA) related requirements, in comparison, can occur after preliminary designs are already established, yielding forced redesigns. Engaging S&MA expertise at an earlier stage, facilitated by the use of MBSE tools, and focused on actual project risk, can yield the same type of design life cycle improvements that have been realized in technical and performance requirements.

  15. The quality assurance topical report - International co-operation for manufacturing of nuclear packages

    International Nuclear Information System (INIS)

    Anderson, R.; Bonifacio, A.; Kingsley, K.; Bittner, R.; Ankrum, G.T.; Wieser, K.E.

    1987-01-01

    The paper addresses the manufacturing quality assurance (QA) concerns associated with fabrication of radioactive material packaging in one country for use in another. A case study is discussed which shows a method of implementation that has been successfully practised for casks fabricated in the Federal Republic of Germany (FRG) for use in the USA. The casks utilized are the Castor series, which are fabricated in the FRG from ductile cast iron. Although international efforts have helped to standardize QA measures, detailed implementation can vary from country to country. A means of co-ordinating requirements between countries was required. The vehicle used to accomplish this was the Quality Assurance Topical Report (QATR), which is an administrative QA document that clearly defines the roles and responsibilities of all affected organizations. The close correlation of requirements is documented in the QATR. In addition, a programme is described which permits the USA competent authority to depend on the FRG authority for inspection and enforcement procedures. It is of great importance that the fabrication and inspection of any component important to safety be properly controlled and documented. The USA requirements for these QA measures are enforced by the Nuclear Regulatory Commission (NRC). Enforcement of applicable regulations in the FRG is the responsibility of the competent authority, Bundesanstalt fuer Materialpruefung (BAM). As a part of the development of this QATR, NRC and BAM representatives met to establish a mutual understanding of QA. As a result, the QATR concept has been approved by both BAM and the NRC. A problem with manufacturing equipment in a foreign country is the need to periodically send company representatives to witness hold points and to review manufacturing records. The methods described in the QATR provide a practical and workable alternative by permitting the BAM to serve as the purchaser (or utility) agent. The utility is only required

  16. 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)

  17. Data management for the Clinch River Breeder Reactor Plant Project by use of document status and hold systems

    International Nuclear Information System (INIS)

    Hunt, C.S.; Beck, A.E.; Akhtar, M.S.

    1982-01-01

    This paper describes the development, framework, and scope of the Document Status System and the Document Hold System for the Clinch River Breeder Reactor Plant Project. It shows how data are generated at five locations and transmitted to a central computer for processing and storage. The resulting computerized data bank provides reports needed to perform day-to-day management and engineering planning. Those reports also partially satisfy the requirements of the Project's Quality Assurance Program

  18. Assessment of LANL solid low-level mixed waste documentation

    International Nuclear Information System (INIS)

    Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

    1991-04-01

    DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice

  19. Quality assurance through fire protection documentation

    Energy Technology Data Exchange (ETDEWEB)

    Spitzer, Franz [KAEFER Industrie GmbH, Kirchheim (Germany); Winter, Harald [Harald Winter Software, Unterschleissheim (Germany)

    2010-07-01

    Legal and organisational requirements regarding fire protection have become more and more stringent. In doing so owners must take account of public law and insurance law. A specialised fire protection management system - FiProMan - can assist in meeting these requirements quickly and efficiently by ensuring quality, carrying out subsequent installation work, repair work and making maintenance planable. In addition, the legal requirements of continuance are met. (orig.)

  20. Quality Assurance Project Plan for Citizen Science Projects

    Science.gov (United States)

    The Quality Assurance Project Plan is necessary for every project that collects or uses environmental data. It documents the project planning process and serves as a blueprint for how your project will run.

  1. British standard (BS) 5750--quality assurance?

    Science.gov (United States)

    Pratt, D J

    1995-04-01

    BS5750 is the British Standard on "Quality Systems". Its equivalent in European Standards is EN29000 and in the International Standards Organisation ISO9000. This paper points out that these standards lay down formalised procedures and require documentation but do not ipso facto lead to quality assurance. The author points to the Japanese post-war industrial success as being an example of Total Quality Management within the framework provided by the philosophy of Dr. W. Edwards Deming (1988 and 1993). This philosophy on the management of "systems" to provide high quality products and services is briefly outlined. The author argues that improvement in prosthetic and orthotic services will not be reached through implementation of BS5750 but rather through radical rethinking and the adoption and application of the Deming philosophy.

  2. A Framework for Requirement Elicitation, Analysis, Documentation and Prioritisation under Uncertainty

    NARCIS (Netherlands)

    Rajabali Nejad, Mohammadreza; Mladenov, V.

    2015-01-01

    This paper offers a pluralistic framework for coping with requirements in the early phases of design where there is lack of knowledge about a system, its architect and functions. The framework is used to elicit, analyze, document and prioritize the requirements. It embeds probabilistic approach and

  3. Ontario's Quality Assurance Framework: A Critical Response

    Science.gov (United States)

    Heap, James

    2013-01-01

    Ontario's Quality Assurance Framework (QAF) is reviewed and found not to meet all five criteria proposed for a strong quality assurance system focused on student learning. The QAF requires a statement of student learning outcomes and a method and means of assessing those outcomes, but it does not require that data on achievement of intended…

  4. LANL Safeguards and Security Assurance Program. Revision 6

    International Nuclear Information System (INIS)

    1995-01-01

    The Safeguards and Security (S and S) Assurance Program provides a continuous quality improvement approach to ensure effective, compliant S and S program implementation throughout the Los Alamos National Laboratory. Any issues identified through the various internal and external assessments are documented, tracked and closed using the Safeguards and Security Issue Management Program. The Laboratory utilizes an integrated S and S systems approach to protect US Department of Energy (DOE) interests from theft or diversion of special nuclear material (SNM), sabotage, espionage, loss or theft of classified/controlled matter or government property, and other hostile acts that may cause unacceptable impacts on national security, health and safety of employees and the public, and the environment. This document explains the basis, scope, and conduct of the S and S process to include: self-assessments, issue management, risk assessment, and root cause analysis. It also provides a discussion of S and S topical areas, roles and responsibilities, process flow charts, minimum requirements, methodology, terms, and forms

  5. Good manufacturing practice - quality assurance programs

    International Nuclear Information System (INIS)

    Masefield, John; Thompson, Steven

    1986-01-01

    The concept of good manufacturing practice (GMP) in the medical device industry requires the use of controlled methods and equipment in performing each step in the device manufacturing process. Quality assurance programs are used to maintain compliance with GMP requirements by prescribing the operating and control procedures to be used. The specific elements of a quality assurance program for the radiation sterilization of medical devices are described. (author)

  6. 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

  7. 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

  8. Supplemental design requirements document solid waste operations complex

    International Nuclear Information System (INIS)

    Ocampo, V.P.; Boothe, G.F.; Broz, D.R.; Eaton, H.E.; Greager, T.M.; Huckfeldt, R.A.; Kooiker, S.L.; Lamberd, D.L.; Lang, L.L.; Myers, J.B.

    1994-11-01

    This document provides additional and supplemental information to the WHC-SD-W112-FDC-001, WHC-SD-W113-FDC-001, and WHC-SD-W100-FDC-001. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design common to the Solid Waste Operations Complex (SWOC) Facilities (Project W-112, Project W-113, and WRAP 2A)

  9. Software Quality Assurance activities of ITER CODAC

    Energy Technology Data Exchange (ETDEWEB)

    Pande, Sopan, E-mail: sopan.pande@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); DiMaio, Franck; Kim, Changseung; Kim, Joohan; Klotz, Wolf-Dieter; Makijarvi, Petri; Stepanov, Denis; Wallander, Anders [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France)

    2013-10-15

    Highlights: ► Comprehensive and consistent software engineering and quality assurance of CODAC. ► Applicable to all CODAC software projects executed by ITER DAs and contractors. ► Configurable plans for cost effective application of SQA processes. ► CODAC software plans SQAP, SVVP, SDP, and SCMP. ► CODAC software processes based on IEEE 12207-2008. -- Abstract: Software as an integral part of the plant system I and C is crucial in the manufacturing and integrated operation of ITER plant systems. Software Quality Assurance is necessary to ensure the development and maintenance of consistently high quality I and C software throughout the lifetime of ITER. CODAC decided to follow IEEE 12207-2008 software lifecycle processes for Software Engineering and Software Quality Assurance. Software Development Plan, Software Configuration Management Plan and Software Verification and Validation Plan are the mainstay of Software Quality Assurance which is documented in the Software Quality Assurance Plan. This paper describes the Software Quality Assurance (SQA) activities performed by CODAC. The SQA includes development and maintenance of above plans, processes and resources. With the help of Verification and Validation Teams they gather evidence of process conformance and product conformance, and record process data for quality audits and perform process improvements.

  10. Software Quality Assurance activities of ITER CODAC

    International Nuclear Information System (INIS)

    Pande, Sopan; DiMaio, Franck; Kim, Changseung; Kim, Joohan; Klotz, Wolf-Dieter; Makijarvi, Petri; Stepanov, Denis; Wallander, Anders

    2013-01-01

    Highlights: ► Comprehensive and consistent software engineering and quality assurance of CODAC. ► Applicable to all CODAC software projects executed by ITER DAs and contractors. ► Configurable plans for cost effective application of SQA processes. ► CODAC software plans SQAP, SVVP, SDP, and SCMP. ► CODAC software processes based on IEEE 12207-2008. -- Abstract: Software as an integral part of the plant system I and C is crucial in the manufacturing and integrated operation of ITER plant systems. Software Quality Assurance is necessary to ensure the development and maintenance of consistently high quality I and C software throughout the lifetime of ITER. CODAC decided to follow IEEE 12207-2008 software lifecycle processes for Software Engineering and Software Quality Assurance. Software Development Plan, Software Configuration Management Plan and Software Verification and Validation Plan are the mainstay of Software Quality Assurance which is documented in the Software Quality Assurance Plan. This paper describes the Software Quality Assurance (SQA) activities performed by CODAC. The SQA includes development and maintenance of above plans, processes and resources. With the help of Verification and Validation Teams they gather evidence of process conformance and product conformance, and record process data for quality audits and perform process improvements

  11. Quality assurance for packaging of radioactive and hazardous materials

    International Nuclear Information System (INIS)

    Gustafson, L.D.

    1986-01-01

    The Department of Energy (DOE) has required for many years that quality assurance programs be established and implemented for the packaging of radioactive and hazardous materials. This paper identifies various requirement principles and related actions involved in establishing effective quality assurance for packaging of radioactive and hazardous materials. A primary purpose of these quality assurance program activities is to provide assurance that the packaging and transportation of hazardous materials, which includes radioactive and fissile materials, are in conformance with appropriate governmental regulations. Applicable regulations include those issued by the Nuclear Regulatory Commission (NRC), the Department of Transportation (DOT), and the Environmental Protection Agency (EPA). DOE Order 5700.6A establishes that quality assurance requirements are to be applied in accordance with national consensus standards where suitable ones are available. In the nuclear area, ANSI/ASME NQA-1 is the preferred standard

  12. Surveillance Analysis Computer System (SACS): Software requirements specification (SRS). Revision 2

    International Nuclear Information System (INIS)

    Glasscock, J.A.

    1995-01-01

    This document is the primary document establishing requirements for the Surveillance Analysis Computer System (SACS) database, an Impact Level 3Q system. SACS stores information on tank temperatures, surface levels, and interstitial liquid levels. This information is retrieved by the customer through a PC-based interface and is then available to a number of other software tools. The software requirements specification (SRS) describes the system requirements for the SACS Project, and follows the Standard Engineering Practices (WHC-CM-6-1), Software Practices (WHC-CM-3-10) and Quality Assurance (WHC-CM-4-2, QR 19.0) policies

  13. Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  14. Test design requirements for overcoring stress measurements

    International Nuclear Information System (INIS)

    Stickney, R.G.

    1985-12-01

    This document establishes the test design requirements for a series of overcoring stress measurements to be performed in the Exploratory Shaft Facility. The stress measurements will be made to determine the in situ state of stress within the candidate repository horizon and to determine the magnitude and distribution of the stresses induced by the mined openings of the facility. The overcoring technique involves the measurement of strain (or deformation) in a volume of rock as the stress acting on the rock volume is relieved. This document presents an overview of the measurements, including objectives and rationale for the measurements. A description of the measurements is included. The support requirements are identified as are constraints for the design of the measurements. Discussions on Quality Assurance and Safety are also included in the document. 13 refs

  15. Project Specific Quality Assurance Plan Project (QAPP) W-211 Initial Tank Retrieval Systems (ITRS)

    International Nuclear Information System (INIS)

    HALL, L.R.

    2000-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Project Hanford Quality Assurance Program is implemented by CH2M HILL Hanford Group Inc (CHG) for managing the Initial Tank Retrieval Systems (ITRS), Project W-211. This QAPP is responsive to the CHG Quality Assurance Program Description (QAPD) (LMH-MP-599) which provides direction for compliance to 10 CFR 830 120, ''Nuclear Safety Management, Quality Assurance Requirements'', and DOE Order 5700 6C, ''Quality Assurance'' Project W-211 modifies existing facilities and provides systems for retrieval of radioactive wastes from selected double-shell tanks (DST). The contents of these tanks are a combination of supernatant liquids and settled solids. To retrieve waste from the tanks, it is first necessary to mix the liquid and solids prior to transferring the slurry to alternative storage or treatment facilities. The ITRS will provide systems to mobilize the settled solids and transfer the wastes out of the tanks. In so doing, ITRS provides feed for future processing plants, allows for consolidation of tank solids to manage space within existing DST storage capacity, and supports continued safe storage of tank waste. This project includes the design, procurement, construction, startup and turnover of these retrieval systems This QAPP identifies organizational structures and responsibilities. Implementing procedures used by CHG project management can be found in the CHG Quality Assurance Program (CHG QAP) Implementation Matrix located in HNF-IP-0842, Volume XI, Attachment Proposed verification and inspection activities for critical items within the scope of project W-211 are identified in Attachment 1 W-211. Project participants will identify the implementing procedures used by their organization within their QAF'Ps. This project specific QAPP is used to identify requirements in addition to the QAPD and provide, by reference, additional information to other project documents

  16. 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

  17. Program prioritization system user requirements document for Gas Cooled Reactor Associates

    International Nuclear Information System (INIS)

    1981-01-01

    Efficient management of the national HTGR program requires the establishment of an information system that will facilitate a more rational allocation of resources and task prioritization consistent with program policies. The system described in this document provides a data analysis mechanism for processing top level summary status and planning information in a rapid, timely and selective manner. Data produced by the system can be used by management to provide a rational basis for prioritizing tasks, evaluating program changes and program planning regarding costs, schedules and overall program development logic. The purpose of this document is to delineate the program prioritization system (PPS) requirements for use as a guide to acquiring and implementing the system

  18. DOE Integrated Safeguards and Security (DISS) historical document archival and retrieval analysis, requirements and recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Guyer, H.B.; McChesney, C.A.

    1994-10-07

    The overall primary Objective of HDAR is to create a repository of historical personnel security documents and provide the functionality needed for archival and retrieval use by other software modules and application users of the DISS/ET system. The software product to be produced from this specification is the Historical Document Archival and Retrieval Subsystem The product will provide the functionality to capture, retrieve and manage documents currently contained in the personnel security folders in DOE Operations Offices vaults at various locations across the United States. The long-term plan for DISS/ET includes the requirement to allow for capture and storage of arbitrary, currently undefined, clearance-related documents that fall outside the scope of the ``cradle-to-grave`` electronic processing provided by DISS/ET. However, this requirement is not within the scope of the requirements specified in this document.

  19. Guidance on the application of quality assurance for characterizing a low-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Pittiglio, C.L. Jr.; Starmer, R.J.; Hedges, D.

    1990-10-01

    This document provides the Nuclear Regulatory Commission's staff guidance to an applicant on meeting the quality control (QC) requirements of Title 10 of the Code of Federal Regulations, Part 61, Section 61.12 (10 CFR 61.12), for a low-level waste disposal facility. The QC requirements combined with the requirements for managerial controls and audits are the basis for developing a quality assurance (QA) program and for the guidance provided herein. QA guidance is specified for site characterization activities necessary to meet the performance objectives of 10 CFR Part 61 and to limit exposure to or the release of radioactivity. 1 tab

  20. 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.)

  1. [Quality assurance in oncology: experiences of an ISO certification].

    Science.gov (United States)

    Szentirmay, Zoltán; Cseh, Lujza; Ottó, Szabolcs; Kásler, Miklós

    2002-01-01

    The ISO 9001 quality assurance of the National Institute of Oncology has been achieved successfully. We give an account of the brief history and the structure of the assurance system of the Institute, the process of setting our goals, and also the experience gained from drafting ISO 9001 handbook and flowcharts. Apart from the bureaucratic nature of quality assurance, it is a good opportunity for us to investigate our everyday work, put it into orderly manner and work more reliably. Experience has shown that the introduction of a quality assurance system increases the level of patient care, the documentation helps the Institute or some of its departments, or even individuals prevent law suits, and serves as a sound basis for proposing promotion, salary increases and bonuses, or even honors.

  2. Elements of quality assurance in environmental surveillance

    International Nuclear Information System (INIS)

    Johnson, L.J.

    1975-01-01

    Qualities of an environmental surveillance program requiring control or assurance are reviewed. Requirements of accuracy, reproducibility, sensitivity, acceptability, and time and cost effectiveness are qualities discussed. The controls applicable to sample collection, handling, chemical analysis, measurement and data presentation are identified and discussed as they pertain to environmental monitoring. Quality assurance program recommendations for developing and reporting environmental surveillance data are provided

  3. Multinationals' accountability on sustainability: the evolution of third-party assurance of sustainability reports

    NARCIS (Netherlands)

    Perego, P.; Kolk, A.

    2012-01-01

    In this article we explore how multinational corporations (MNCs) adopt assurance practices to develop and sustain organizational accountability for sustainability. Using a panel of Fortune Global 250 firms over a period of 10 years, we document the diffusion patterns of third-party assurance of

  4. Amendment of the assured delivery provisions of BPA's Long-Term Intertie Access Policy and increased assured delivery: Access for non-scheduling utilities. Record of decision

    International Nuclear Information System (INIS)

    1994-06-01

    Bonneville Power Administration's BPA's preferred alternative for providing non-Federal Pacific Northwest-Pacific Southwest (PNW-PSW) Intertie access is to adopt the Capacity Ownership alternative combined with the Increased Assured Delivery--Access for Non-Scheduling Utilities alternative. BPA's decision to offer Capacity Ownership was documented in a March 1994 Non-Federal Capacity Ownership Record of Decision (ROD). This ROD documents BPA's decision to facilitate PNW-PSW Intertie access by proceeding with (1) bidirectional Increased Assured Delivery--Access for Non Scheduling Utilities; and (2) amending the Assured Delivery provisions of BPA's Long-Term Intertie Access Policy (LTIAP). Given that the various non-Federal PNW-PSW Intertie access alternatives in the NFP EIS all allowed for different types of contracts, little environmental impact difference among the alternatives was found. Rather, environmental impact was found to be associated with whether exchange contracts or firm power sales contracts would predominate. Such impacts and related environmental analysis are discussed further in section 3.0 of this ROD

  5. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance.

  6. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 3) presents the standards and requirements for the following sections: Safeguards and Security, Engineering Design, and Maintenance

  7. Recognition and categorization considerations for information assurance requirements development and speficication

    Science.gov (United States)

    Stytz, Martin R.; May, Michael; Banks, Sheila B.

    2009-04-01

    Department of Defense (DoD) Information Technology (IT) systems operate in an environment different from the commercial world, the differences arise from the differences in the types of attacks, the interdependencies between DoD software systems, and the reliance upon commercial software to provide basic capabilities. The challenge that we face is determining how to specify the information assurance requirements for a system without requiring changes to the commercial software and in light of the interdependencies between systems. As a result of the interdependencies and interconnections between systems introduced by the global information grid (GIG), an assessment of the IA requirements for a system must consider three facets of a system's IA capabilities: 1) the IA vulnerabilities of the system, 2) the ability of a system to repel IA attacks, and 3) the ability of a system to insure that any IA attack that penetrates the system is contained within the system and does not spread. Each facet should be assessed independently and the requirements should be derived independently from the assessments. In addition to the desired IA technology capabilities of the system, a complete assessment of the system's overall IA security technology readiness level cannot be accomplished without an assessment of the capabilities required of the system for its capability to recover from and remediate IA vulnerabilities and compromises. To allow us to accomplish these three formidable tasks, we propose a general system architecture designed to separate the system's IA capabilities from its other capability requirements; thereby allowing the IA capabilities to be developed and assessed separately from the other system capabilities. The architecture also enables independent requirements specification, implementation, assessment, measurement, and improvement of a system's IA capabilities without requiring modification of the underlying application software.

  8. 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

  9. Evaluation of the reports on the status of quality assurance systems in the power plants. Pt. 1, annex, pt. 2

    International Nuclear Information System (INIS)

    1983-01-01

    The problem required the development of a presentation and evaluation of the overall results based on the results of the systems analysis with regard to: - further development of control equipment, - discovery of overlapping points, gaps and weak points, especially at the boundaries between the systems, - standardized application of the principles of efficient quality assurance systems for all participants. The results of the systems analyses for the status of quality assurance in producers and suppliers of systems can be summarized as follows: 1. Both systems analyses show that the quality assurance systems introduced are operable but that there are also some weak points. 2. Basically, the results of the systems analyses coincide; there are differences in the assessment of single issues or in a more detailed treatment. The weak points identified by the systems analysis can be summarized under the following catchwords: - structural organization; here, a greater formalization of the descriptions of positions and qualifications of personnel as well as the presentation of the structural organization in organization charts are required. - Procedural organization resp. operational modulei; here, improvements of the interfaces between the QA systems, information feedback, information and documentation are dealt with and the revision and improvement of invalid documents (withdrawal/exchange) as well as the qualification mode for auditors are pointed out separately. (orig./HP) [de

  10. Waste Receiving and Packaging, Module 2A, Supplemental Design Requirements Document

    International Nuclear Information System (INIS)

    Lamberd, D.L.; Boothe, G.F.; Hinkle, A.L.; Horgos, R.M.; LeClair, M.D.; Nash, C.R.; Ocampo, V.P.; Pauly, T.R.; Stroup, J.L.; Weingardt, K.M.

    1994-01-01

    The Supplemental Design Requirements Document (SDRD) is used to communicate plant design information from Westinghouse Hanford Company (WHC) to the US Department of Energy (DOE) and the cognizant Architect Engineer (A/E). Information in the SDRD serves two purposes: to convey design requirements that are too detailed for inclusion in a Functional Design Criteria (FDC) report; and to serve as a means of change control for design commitments in the Conceptual Design Report. The mission of WRAP 2A on the Hanford site is the treatment of contact handled low level mixed waste (MW) for final disposal. The overall systems engineering steps used to reach construction and operation of WRAP 2A are depicted in Figure 1. The WRAP 2A SDRD focuses on the requirements to address the functional analysis provided in Figure 1. This information is provided in sections 2 through 5 of this SDRD. The mission analysis and functional analysis are to be provided in a separate supporting document. The organization of sections 2 through 5 corresponds to the requirements identified in the WRAP 2A functional analysis

  11. UMTRA project technical assistance contractor quality assurance implementation plan for surface and ground water, Revision 2

    International Nuclear Information System (INIS)

    1995-11-01

    This document contains the Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project. The QAIP outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QA program is designed to use monitoring, audit, and surveillance activities as management tools to ensure that UMTRA Project activities are carried out in amanner to protect public health and safety, promote the success of the UMTRA Project, and meet or exceed contract requirements

  12. Concept of Draft International Standard for a Unified Approach to Space Program Quality Assurance

    Science.gov (United States)

    Stryzhak, Y.; Vasilina, V.; Kurbatov, V.

    2002-01-01

    For want of the unified approach to guaranteed space project and product quality assurance, implementation of many international space programs has become a challenge. Globalization of aerospace industry and participation of various international ventures with diverse quality assurance requirements in big international space programs requires for urgent generation of unified international standards related to this field. To ensure successful fulfillment of space missions, aerospace companies should design and process reliable and safe products with properties complying or bettering User's (or Customer's) requirements. Quality of the products designed or processed by subcontractors (or other suppliers) should also be in compliance with the main user (customer)'s requirements. Implementation of this involved set of unified requirements will be made possible by creating and approving a system (series) of international standards under a generic title Space Product Quality Assurance based on a system consensus principle. Conceptual features of the baseline standard in this system (series) should comprise: - Procedures for ISO 9000, CEN and ECSS requirements adaptation and introduction into space product creation, design, manufacture, testing and operation; - Procedures for quality assurance at initial (design) phases of space programs, with a decision on the end product made based on the principle of independence; - Procedures to arrange incoming inspection of products delivered by subcontractors (including testing, audit of supplier's procedures, review of supplier's documentation), and space product certification; - Procedures to identify materials and primary products applied; - Procedures for quality system audit at the component part, primary product and materials supplier facilities; - Unified procedures to form a list of basic performances to be under configuration management; - Unified procedures to form a list of critical space product components, and unified

  13. 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

  14. 45 CFR 400.43 - Requirements for documentation of refugee status.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 2 2010-10-01 2010-10-01 false Requirements for documentation of refugee status. 400.43 Section 400.43 Public Welfare Regulations Relating to Public Welfare OFFICE OF REFUGEE RESETTLEMENT, ADMINISTRATION FOR CHILDREN AND FAMILIES, DEPARTMENT OF HEALTH AND HUMAN SERVICES REFUGEE...

  15. Drosophila Longevity Assurance Conferred by Reduced Insulin Receptor Substrate Chico Partially Requires d4eBP.

    Directory of Open Access Journals (Sweden)

    Hua Bai

    Full Text Available Mutations of the insulin/IGF signaling (IIS pathway extend Drosophila lifespan. Based on genetic epistasis analyses, this longevity assurance is attributed to downstream effects of the FOXO transcription factor. However, as reported FOXO accounts for only a portion of the observed longevity benefit, suggesting there are additional outputs of IIS to mediate aging. One candidate is target of rapamycin complex 1 (TORC1. Reduced TORC1 activity is reported to slow aging, whereas reduced IIS is reported to repress TORC1 activity. The eukaryotic translation initiation factor 4E binding protein (4E-BP is repressed by TORC1, and activated 4E-BP is reported to increase Drosophila lifespan. Here we use genetic epistasis analyses to test whether longevity assurance mutants of chico, the Drosophila insulin receptor substrate homolog, require Drosophila d4eBP to slow aging. In chico heterozygotes, which are robustly long-lived, d4eBP is required but not sufficient to slow aging. Remarkably, d4eBP is not required or sufficient for chico homozygotes to extend longevity. Likewise, chico heterozygote females partially require d4eBP to preserve age-dependent locomotion, and both chico genotypes require d4eBP to improve stress-resistance. Reproduction and most measures of growth affected by either chico genotype are always independent of d4eBP. In females, chico heterozygotes paradoxically produce more rather than less phosphorylated 4E-BP (p4E-BP. Altered IRS function within the IIS pathway of Drosophila appears to have partial, conditional capacity to regulate aging through an unconventional interaction with 4E-BP.

  16. 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.

  17. Effect of an Individual Readiness Assurance Test on a Team Readiness Assurance Test in the Team-Based Learning of Physiology

    Science.gov (United States)

    Gopalan, Chaya; Fox, Dainielle J.; Gaebelein, Claude J.

    2013-01-01

    We examined whether requiring an individual readiness assurance test (iRAT) before a team readiness assurance test (tRAT) would benefit students in becoming better problem solvers in physiology. It was tested in the form of tRAT scores, the time required to complete the tRAT assignment, and individual performance on the unit examinations. Students…

  18. Master Pump Shutdown MPS Software Quality Assurance Plan (SQAP)

    International Nuclear Information System (INIS)

    BEVINS, R.R.

    2000-01-01

    The MPSS Software Quality Assurance (SQAP) describes the tools and strategy used in the development of the MPSS software. The document also describes the methodology for controlling and managing changes to the software

  19. Proactive quality assurance in environmental research

    International Nuclear Information System (INIS)

    Flanagan, J.B.; Kulkarni, S.V.; Wasson, S.J.; Ford, J.S.; Harmon, D.L.

    1991-01-01

    The Quality Assurance policy of the US Environmental Protection Agency (EPA) stipulates that every project involving environmentally related monitoring, measurements, and data collection activities must have a written and approved quality assurance project plan (QAPjP). A QAPjP is a written document which presents, in specific terms, the policies, organizations, objectives, functional activities, and the quality assurance/quality control activities designed to achieve the quality goals for data collection. In the research studies involving novel or non-routine measurements that use unvalidated methods, measurement quality goals are often difficult or impossible to specify at the beginning of the project for which a QAPjP must be written. Furthermore, it may not be possible for the QAPjP reviewers to evaluate the reasonableness of these goals without initial information about the system under study. For the project to evaluate chlorofluorocarbon for recycling from domestic refrigerators, the QAPjP incorporated standard analytical techniques used by industry. These techniques did not provide accuracy and precision or other validation information. For the initial version of the QAPjP, measurement quality goals were assigned based on limited experience. Quality assurance support was called upon to evaluate the performance of the measurement system for this project through a series of audits. The performance evaluation audits necessitated designing novel audit materials and sample delivery techniques. Continued interaction is necessary between the project and QA teams to permit evolution of reasonable data quality indicators for meaningful assessment of data quality. By treating the QAPjP as a living document that is updated and amended as more knowledge of a system is obtained, AQ becomes an integral part of the research program. This results in a greater understanding of the system under study

  20. Quality Assurance Roadmap for High Performance Residential Buildings

    Energy Technology Data Exchange (ETDEWEB)

    None

    2008-10-05

    This report outlines the approach to quality assurance in the construction process for new residential construction, including seven process steps from the assessment of current construction practice, through design and documentation changes, to training and quality control for on-site personnel.

  1. 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.

  2. 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

  3. How to understand requirements of nuclear and defense welding contracts

    International Nuclear Information System (INIS)

    Dickinson, O.D.

    1986-01-01

    This paper presents a basic requirements control plan for contract documentation and software validation and maintenance for nuclear operation. The objective is designing an integrated configuration control plan of both old, new, large or small, critical and noncritical software programs. There are positive advantages to managing a planned requirements program for product delivery or business operations. A requirements baseline like this is preferable to many iterations of design effort in the maintenance of nonbaselined programs, documentation and software. The plan that applies program requirements needs to address different levels of criticality and define matching program requirements for those levels. The plan needs to describe old vs. new requirements and define scope/responsibility that is needed to support the design, development and completion of these program requirements. Presented are management goals, relative costs, quality assurance goals, and program assessment plans. Outlined is a set of program QA requirements and document/software functional requirements for planning of program; also presented are some criteria for criticality assessment to establish levels of contract documentation or software activity. The paper shows two examples of planning work on this configuration control plan. The integrated configuration control requirements plan can be computer based or paper based for activity. It is designed to cover existing or new requirements and to cover either no documentation or all documentation

  4. John F. Kennedy Space Center, Safety, Reliability, Maintainability and Quality Assurance, Survey and Audit Program

    Science.gov (United States)

    1994-01-01

    This document is the product of the KSC Survey and Audit Working Group composed of civil service and contractor Safety, Reliability, and Quality Assurance (SR&QA) personnel. The program described herein provides standardized terminology, uniformity of survey and audit operations, and emphasizes process assessments rather than a program based solely on compliance. The program establishes minimum training requirements, adopts an auditor certification methodology, and includes survey and audit metrics for the audited organizations as well as the auditing organization.

  5. Applicability of PSD Requirements to the Wisconsin Electric Power Company Port Washington Life Extension Project

    Science.gov (United States)

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  6. Management control and quality assurance during plant operation

    International Nuclear Information System (INIS)

    Modemann, G.; Ettemeyer, R.; Stephan, W.

    1980-01-01

    The present paper deals with basic aspects of quality assurance for owners of nuclear power plants, with quality assurance for plant operation and with consequences from KTA regulatory requirements. (RW)

  7. 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

  8. 50 CFR 23.25 - What additional information is required on a non-Party CITES document?

    Science.gov (United States)

    2010-10-01

    ... a non-Party CITES document? 23.25 Section 23.25 Wildlife and Fisheries UNITED STATES FISH AND... IN ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Prohibitions, Exemptions, and Requirements § 23.25 What additional information is required on a non-Party CITES document? (a) Purpose. Under Article...

  9. Application of software quality assurance to a specific scientific code development task

    International Nuclear Information System (INIS)

    Dronkers, J.J.

    1986-03-01

    This paper describes an application of software quality assurance to a specific scientific code development program. The software quality assurance program consists of three major components: administrative control, configuration management, and user documentation. The program attempts to be consistent with existing local traditions of scientific code development while at the same time providing a controlled process of development

  10. International Thermonuclear Experimental Reactor U.S. Home Team Quality Assurance Plan

    Energy Technology Data Exchange (ETDEWEB)

    Sowder, W. K.

    1998-10-01

    The International Thermonuclear Experimental Reactor (ITER) project is unique in that the work is divided among an international Joint Central Team and four Home Teams, with the overall responsibility for the quality of activities performed during the project residing with the ITER Director. The ultimate responsibility for the adequacy of work performed on tasks assigned to the U.S. Home Team resides with the U.S. Home Team Leader and the U.S. Department of Energy Office of Fusion Energy (DOE-OFE). This document constitutes the quality assurance plan for the ITER U.S. Home Team. This plan describes the controls exercised by U.S. Home Team management and the Performing Institutions to ensure the quality of tasks performed and the data developed for the Engineering Design Activities assigned to the U.S. Home Team and, in particular, the Research and Development Large Projects (7). This plan addresses the DOE quality assurance requirements of 10 CFR 830.120, "Quality Assurance." The plan also describes U.S. Home Team quality commitments to the ITER Quality Assurance Program. The ITER Quality Assurance Program is based on the principles described in the International Atomic Energy Agency Standard No. 50-C-QA, "Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Facilities." Each commitment is supported with preferred implementation methodology that will be used in evaluating the task quality plans to be submitted by the Performing Institutions. The implementing provisions of the program are based on guidance provided in American National Standards Institute/American Society of Mechanical Engineers NQA-1 1994, "Quality Assurance." The individual Performing Institutions will implement the appropriate quality program provisions through their own established quality plans that have been reviewed and found to comply with U.S. Home Team quality assurance plan commitments to the ITER Quality Assurance Program. The extent of quality program provisions

  11. Recommendations for a software quality assurance policy for the nuclear waste disposal risk assessment programme

    International Nuclear Information System (INIS)

    Hill, I.E.

    1985-05-01

    This study reviewed a number of published standards for software quality assurance, and included a series of interviews with software developers aimed at exploring their attitudes to software quality assurance. Recommendations for software quality assurance policy are made based on the above investigations. This document provides a summary of the recommendations made in the full report on project, reference MR-CDS-4. (author)

  12. 48 CFR 752.7005 - Submission requirements for development experience documents.

    Science.gov (United States)

    2010-10-01

    ... (referenced in paragraph (a)(1) of this clause) in electronic format and hard copy (one copy) to U.S. Agency... final equivalent of the hard copy submitted. (iv) Acceptable software formats for electronic documents... paragraph (b)(1)(i) of this clause. (2) Format. (i) Descriptive information is required for all Contractor...

  13. IAEA code and safety guides on quality assurance

    International Nuclear Information System (INIS)

    Raisic, N.

    1980-01-01

    In the framework of its programme in safety standards development, the IAEA has recently published a Code of Practice on Quality Assurance for Safety in Nuclear Power Plants. The Code establishes minimum requirements for quality assurance which Member States should use in the context of their own nuclear safety requirements. A series of 10 Safety Guides which describe acceptable methods of implementing the requirements of specific sections of the Code are in preparation. (orig.)

  14. Quality Assurance in Higher Education in Zimbabwe

    Science.gov (United States)

    Garwe, Evelyn Chiyevo

    2014-01-01

    The purpose of this paper is to furnish local and global stakeholders with detailed information regarding the development and current status of quality assurance in the Zimbabwean higher education sector. The study used document analysis, observation and interviews with key informants as sources of data. This paper addresses the dearth of…

  15. 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

  16. Planning is not sufficient - Reliable computers need good requirements specifications

    International Nuclear Information System (INIS)

    Matras, J.R.

    1992-01-01

    Computer system reliability is the assurance that a computer system will perform its functions when required to do so. To ensure such reliability, it is important to plan the activities needed for computer system development. These development activities, in turn, require a Computer Quality Assurance Plan (CQAP) that provides the following: a Configuration Management Plan, a Verification and Validation (V and V) Plan, documentation requirements, a defined life cycle, review requirements, and organizational responsibilities. These items are necessary for system reliability; ultimately, however, they are not enough. Development of a reliable system is dependent on the requirements specification. This paper discusses how to use existing industry standards to develop a CQAP. In particular, the paper emphasizes the importance of the requirements specification and of methods for establishing reliability goals. The paper also describes how the revision of ANSI/IEE-ANS-7-4.3.2, Application Criteria for Digital Computer Systems of Nuclear Power Generating Stations, has addressed these issues

  17. Exploration of reliability assurance program (RAP) for advanced nuclear power plant

    International Nuclear Information System (INIS)

    Chen Fang; Xu Rongbin

    2009-01-01

    This article describes the new requirements in US SRP on Reliability Assurance Program, inquires into the evolution of the reliability assurance requirements, and investigates the regulatory requirements on reliability assurance program for advanced reactors, it's main contents, and evaluation review practices and related issues, with the aim of enabling staff to understand be familiar and pay attention to this engineering program. This article may be as a reference for related workers. (authors)

  18. Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    2000-01-01

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables

  19. Quality-assurance plan for water-quality activities in the U.S. Geological Survey Washington Water Science Center

    Science.gov (United States)

    Conn, Kathleen E.; Huffman, Raegan L.; Barton, Cynthia

    2017-05-08

    In accordance with guidelines set forth by the Office of Water Quality in the Water Mission Area of the U.S. Geological Survey, a quality-assurance plan has been created for use by the Washington Water Science Center (WAWSC) in conducting water-quality activities. This qualityassurance plan documents the standards, policies, and procedures used by the WAWSC for activities related to the collection, processing, storage, analysis, and publication of water-quality data. The policies and procedures documented in this quality-assurance plan for water-quality activities complement the quality-assurance plans for surface-water and groundwater activities at the WAWSC.

  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. User requirements for information systems in nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Todd-Pokropek, A. (University Coll., London (United Kingdom)); Vauramo, E.; Sippo-Tujunen, I. (Helsinki City Health Dept. (Finland)); Cosgriff, P. (Pilgrim Hospital, Boston (UK)); Britton, K. (Saint Bartholomew' s Hospital, London (United Kingdom))

    1992-05-01

    In the field of COST cooperation (COST = European Cooperation in the Field of Scientific and Technical Research) a project B2 for Quality Assurance in Nuclear Medicine Software has been established. In a memorandum of understanding setting up this project, user requirements were to be defined for the hardware and software used for data acquisition, processing and presentation. A subgroup of the management committee of COST B2 were interested in the Advanced Informatics in Medicine, AIM, task T-734 'Quality Assurance of Medical Software', and the AIM Project 'A 1034', coordinated by Dr. K. Britton, was initiated. The initial drafts of this document were written in Helsinki during 1988-1990, and submitted for comment by the members of the management committee of COST B2. These comments were integrated in the text and this document was finalized by the UK group so as to make it available for international discussion. It is anticipated that, after appropriate international discussion, these User Requirements for Information Systems in Nuclear Medicine will be adopted by the management committee of COST B2 as a COST document. Towards these ends, a working group chaired by Dr Britton, including the British and Finnish teams and Ulrich Noelpp from Switzerland, was appointed by the management committee of COST B2 in April 1990. (Author).

  2. User requirements for information systems in nuclear medicine

    International Nuclear Information System (INIS)

    Todd-Pokropek, A.; Vauramo, E.; Sippo-Tujunen, I.; Cosgriff, P.; Britton, K.

    1992-01-01

    In the field of COST cooperation (COST = European Cooperation in the Field of Scientific and Technical Research) a project B2 for Quality Assurance in Nuclear Medicine Software has been established. In a memorandum of understanding setting up this project, user requirements were to be defined for the hardware and software used for data acquisition, processing and presentation. A subgroup of the management committee of COST B2 were interested in the Advanced Informatics in Medicine, AIM, task T-734 'Quality Assurance of Medical Software', and the AIM Project 'A 1034', coordinated by Dr. K. Britton, was initiated. The initial drafts of this document were written in Helsinki during 1988-1990, and submitted for comment by the members of the management committee of COST B2. These comments were integrated in the text and this document was finalized by the UK group so as to make it available for international discussion. It is anticipated that, after appropriate international discussion, these User Requirements for Information Systems in Nuclear Medicine will be adopted by the management committee of COST B2 as a COST document. Towards these ends, a working group chaired by Dr Britton, including the British and Finnish teams and Ulrich Noelpp from Switzerland, was appointed by the management committee of COST B2 in April 1990. (Author)

  3. 76 FR 7145 - Notice of Public Information Collection Requirements Submitted to OMB for Review

    Science.gov (United States)

    2011-02-09

    ... organizations that engage in terrorism. The purpose of this requirement is to assure that USAID does not..., except advice or assistance, safehouses, false documentation or identification, communications equipment... one of the 12 United Nations Conventions and Protocols related to terrorism (see UN terrorism...

  4. Evaluation of financial assurance alternatives of licensees

    Energy Technology Data Exchange (ETDEWEB)

    Douglas, J N

    1995-09-01

    The Uranium and Thorium Mining Regulations of the Atomic Energy Control Act require that applicants/licensees indicate to the AECB what financial assurance plans they have made to fund the decommissioning plan they propose to put in place. We have determined through our own business knowledge from other projects, as well as information provided by contacts in the banking, accounting, legal, investment and insurance communities, what financial assurance plans might be available. We have tabulated these alternatives, included explanations of how each might be implemented, and recorded advantages and disadvantages of each alternative to both the AECB and the applicant/licensee. In addition we have ranked the alternatives in order of most suitable to least suitable, from the AECB`s perspective. Although these financial assurance mechanisms have been tabulated with a view to decommissioning of a uranium mine, they could be used in other licence or business arrangements that require financial assurance. (author). 3 tabs., 1 fig.

  5. Evaluation of financial assurance alternatives of licensees

    International Nuclear Information System (INIS)

    Douglas, J.N.

    1995-09-01

    The Uranium and Thorium Mining Regulations of the Atomic Energy Control Act require that applicants/licensees indicate to the AECB what financial assurance plans they have made to fund the decommissioning plan they propose to put in place. We have determined through our own business knowledge from other projects, as well as information provided by contacts in the banking, accounting, legal, investment and insurance communities, what financial assurance plans might be available. We have tabulated these alternatives, included explanations of how each might be implemented, and recorded advantages and disadvantages of each alternative to both the AECB and the applicant/licensee. In addition we have ranked the alternatives in order of most suitable to least suitable, from the AECB's perspective. Although these financial assurance mechanisms have been tabulated with a view to decommissioning of a uranium mine, they could be used in other licence or business arrangements that require financial assurance. (author). 3 tabs., 1 fig

  6. Guidance for implementing an environmental, safety and health assurance program. Volume 2. A model plan for environmental, safety and health staff audits and appraisals

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1980-09-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This document is concerned with ES and H audit and appraisal activities of an ES and H Staff Organization as they might be performed in an institution whose ES and H program is based upon the ES and H Assurance Program Standard. An annotated model plan for ES and H Staff audits and appraisals is presented and discussed

  7. Guidance for implementing an environmental, safety, and health assurance program. Volume 10. Model guidlines for line organization environmental, safety and health audits and appraisals

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1981-10-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. The Standard specifies that the operational level of an institution must have an internal assurance function, and this document provides guidance for the audit/appraisal portion of the operational level's ES and H program. The appendixes include an ES and H audit checklist, a sample element rating guide, and a sample audit plan for working level line organization internal audits

  8. Spinal cord testing: auditing for quality assurance.

    Science.gov (United States)

    Marr, J A; Reid, B

    1991-04-01

    A quality assurance audit of spinal cord testing as documented by staff nurses was carried out. Twenty-five patient records were examined for accuracy of documented testing and compared to assessments performed by three investigators. A pilot study established interrater reliability of a tool that was designed especially for this study. Results indicated staff nurses failed to meet pre-established 100% standard in all categories of testing when compared with investigator's findings. Possible reasons for this disparity are discussed as well as indications for modifications in the spinal testing record, teaching program and preset standards.

  9. Establishment of ''Internal Rules'' and EDMS - Electronic Document Management System at NPP NEK

    International Nuclear Information System (INIS)

    Mandic, D.

    2012-01-01

    two applications (DCM-Document Control Module andQRM-Quality Records Management). Both computer applications were designed in order to fulfil requirements of the criteria VI (Document Control) and criteria XVII (Quality Assurance Records) of the US code [3]. In order to prevent confusion, clarifications regarding the terms ''documents'' and ''records'' are the following: Documents are an organized collection of information or objects that can be treated as a unit. A document may or may not meet the definition of a record. Records are sub-set of all information or all documents held by a person or organisation. Records present information, regardless of physical form or characteristics, appropriate for preservation as evidence of the organization, functions, policies, decisions, procedures, operations, or other activities of the organization. Examples of where this information may reside are books, papers, maps, photographs, machine-readable electronic files, or other documentary materials. Quality Assurance Records related to the NPPs are the records which furnish documentary evidence of the quality of items and activities affecting quality. For the purpose of the standards [4] and [5], a document is considered a quality assurance record when it has been completed.(author).

  10. System engineering of complex optical systems for mission assurance and affordability

    Science.gov (United States)

    Ahmad, Anees

    2017-08-01

    Affordability and reliability are equally important as the performance and development time for many optical systems for military, space and commercial applications. These characteristics are even more important for the systems meant for space and military applications where total lifecycle costs must be affordable. Most customers are looking for high performance optical systems that are not only affordable but are designed with "no doubt" mission assurance, reliability and maintainability in mind. Both US military and commercial customers are now demanding an optimum balance between performance, reliability and affordability. Therefore, it is important to employ a disciplined systems design approach for meeting the performance, cost and schedule targets while keeping affordability and reliability in mind. The US Missile Defense Agency (MDA) now requires all of their systems to be engineered, tested and produced according to the Mission Assurance Provisions (MAP). These provisions or requirements are meant to ensure complex and expensive military systems are designed, integrated, tested and produced with the reliability and total lifecycle costs in mind. This paper describes a system design approach based on the MAP document for developing sophisticated optical systems that are not only cost-effective but also deliver superior and reliable performance during their intended missions.

  11. Construction quality assurance closure report, Lawrence Livermore National Laboratory Site 300, Pits 1 and 7

    International Nuclear Information System (INIS)

    1993-02-01

    This document presents the Final Construction Quality Assurance (CQA) report for the closure cover system of two mixed, low-level radioactive and hazardous waste landfills (pits) at Site 300. Site 300, operated by the Lawrence Livermore National Laboratory (LLNL), is located in the Altamont Hills, approximately 15 miles southeast of Livermore, California. The purpose of this report is to document the CQA program established to assure that construction is completed in accordance with the design intent and the approved Closure and Post Closure Plans dated May 1989 and revised January 1990 (EPA ID Number: CA 2890090002). Inclusive within the Closure and Post Closure Plan were the CQA Plan and the Technical Specifications for the final cover system. This report contains a complete narrative with photographic documentation of the construction activities and progress, problems encountered and solutions utilized, and third party testing and monitoring results, thus establishing the verification of compliance with the Quality Assurance Plan for the project

  12. 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

  13. Establishing the quality assurance programme for a nuclear power plant project

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide provides requirements, recommendations and illustrative examples for establishing the overall quality assurance programme, and its constituent programmes, for a nuclear power plant project. It also provides guidance on the planning and documenting of programme plans and actions that are intended to ensure the achievement of the appropriate quality throughout the design, procurement, manufacture, construction, commissioning, operation and decommissioning of the nuclear power plant. The provisions of this Safety Guide are applicable to all organizations performing activities affecting the quality of items important to safety, such as designing, purchasing, fabricating, manufacturing, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling, modifying and decommissioning

  14. Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1990-12-01

    The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

  15. 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

  16. 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

  17. Report on the activities of the ASME-NQA Committee Working Group on Quality Assurance Requirements for Research and Development, April 1990 to August 1991

    Energy Technology Data Exchange (ETDEWEB)

    Dronkers, J.J.

    1991-09-01

    This report transmits to the public eye the activities of the American Society of Mechanical Engineers-Nuclear Quality Assurance (ASME-NQA) Committee Working Group on Quality Assurance Requirements for Research and Development. The appendix lists the members of this group as of August 1991. The report covers a period of 17 months. The working group met eight times in this period, and much intellectual ground was traversed. There was seldom agreement on the nature of the task, but there was no doubt as to its urgency. The task was how to adapt the nuclear quality assurance standard, the NQA-1, to research and development work. 1 fig., 7 tabs.

  18. Painting for nuclear power stations and machinery and equipments according to quality assurance program of ANSI

    International Nuclear Information System (INIS)

    Fukuda, Shinzo; Tsuchiya, Yukikazu.

    1979-01-01

    Recently, painting for nuclear power stations is carried out with the paints made domestically, and these paints are tested and judged generally according to the items of performance evaluation decided by the American National Standard Institute. In Japan, there is no standard regarding the paints for nuclear power stations. Painting is very important process, and it is appropriate to introduce quality assurance program into it. In this paper, the contents of ANSI standard concerning the paints and painting for nuclear power stations are explained, and the outline of the painting of heat exchangers carried out in accordance with the quality assurance program in the Tamano Shipyard, Mitsui Shipbuilding and Engineering Co., Ltd., is described. The test items for evaluating the general performance of the paints, the testing method for evaluating the endurance at the time of an accident, the quality assurance for the paints used for the facilities handling radiation and others are explained. Various problems arise when the quality assurance program of ANSI is applied actually to painting. It is difficult to judge the quality of paints and painting with numerical values, and much efforts were required to establish the quality assurance organization. The conditions for painting, the handling of many documents, the measures to unsatisfactory painting and so on caused much difficulties. (Kako, I.)

  19. Manual on the selection of appropriate quality assurance programmes for items and services of a nuclear power plant

    International Nuclear Information System (INIS)

    1984-02-01

    This manual provides guidance and illustrative examples for devising a system by which applicable quality assurance activities may be selected and applied to items and services in conformance with the requirements of the Code and the guidance of SG-QA 1. The selective application system described herein contains the following elements: (1) Classification of items and services; (2) Grading of quality assurance activities; (3) Correlation of applicable quality assurance activities with items and services; (4) Adaptation of selected quality assurance activities to the unique needs of the items or services; (5) Specifying of applicable quality assurance activities in bid specifications or in a contract. This selective application system is intended to be used by plant systems designers in the classifying of items (structures, components and materials) and related services; and by the organizations designing, manufacturing, installing and operating items or performing support services for such items in the specifying of applicable quality assurance activities that are to be implemented. The parts of the system should be developed to the degree and sophistication necessary for the particular needs of the project or organization. There are many methods and techniques that may be used effectively and those of one organization may not suit the purposes of another organization. It is important that the methodology of the system is developed with sufficient instructions documented to guide its consistent and disciplined execution

  20. Quality Assurance Program Plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Vance, L.M.

    1993-07-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance requirements and responsibilities for radioactive airborne emissions measurements activities from regulated stacks are controlled at the Hanford Site. Detailed monitoring requirements apply to stacks exceeding 1% of the standard of 10 mrem annual effective dose equivalent to the maximally exposed individual from operations of the Hanford Site

  1. Quality Assurance Program Plan for radionuclide airborne emissions monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Vance, L.M.

    1993-07-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance requirements and responsibilities for radioactive airborne emissions measurements activities from regulated stacks are controlled at the Hanford Site. Detailed monitoring requirements apply to stacks exceeding 1% of the standard of 10 mrem annual effective dose equivalent to the maximally exposed individual from operations of the Hanford Site.

  2. Current conceptions of industrial quality assurance

    International Nuclear Information System (INIS)

    Zeller, H.

    1978-01-01

    In the electrical engineering industry quality assurance is mainly oriented in accordance with the customers', users', and consumers' requirements concerning the quality of products (including reliability). These requirements are as manifold as the range of products itself. They do not only comprise functional criteria, but also safety against malfunctions, bodily injury or property damage. Quality assurance is embedded in the overall activities of a company; the peripheral conditions, such as organization, profitability, qualification, and responsibility of staff have to be considered. Thus, quality assurance in the electrical engineering industry proceeds in efficient systems which are adapted to the individual forms of production. These systems may include planning, testing, feedback of quality data, statistical procedures, costs and profitability. Their obvious interaction is based on the system of coordinates of integrated quality control. The paper will illustrate the basic features of this interaction by reference to various examples. (orig.) [de

  3. Quality assurance of nuclear medicine computer software

    International Nuclear Information System (INIS)

    Cradduck, T.D.

    1986-01-01

    Although quality assurance activities have become well established for the hardware found in nuclear medicine little attention has been paid to computer software. This paper outlines some of the problems that exist and indicates some of the solutions presently under development. The major thrust has been towards establishment of programming standards and comprehensive documentation. Some manufacturers have developed installation verification procedures which programmers are urged to use as models for their own programs. Items that tend to cause erroneous results are discussed with the emphasis for error detection and correction being placed on proper education and training of the computer operator. The concept of interchangeable data files or 'software phantoms' for purposes of quality assurance is discussed. (Author)

  4. [Topic identification for cross-sectoral quality assurance in stroke and TIA treatment].

    Science.gov (United States)

    Meyer, Sven; Willms, Gerald; Broge, Björn; Szecsenyi, Joachim

    2016-10-01

    The development of cross-sectoral quality assurance programs usually requires extensive topic identification. Illustrated by the complex processes of care for stroke and transient ischemic attacks (TIAs), a method for comprehensive topic identification is presented. The first step involves a thorough literature search in terms of systematic reviews, health technology assessments, guidelines, studies into healthcare delivery and the use of specific instruments. Routine data as well as epidemiologic studies are used to analyze the reality of service provision. In addition, experts are consulted to gain expertise concerning deficits of care, approaches to quality assurance and experience with existing quality assurance programs. Furthermore individual patient experiences are collected to add the patients' perceptions of care. Because of the limitation on the regulatory scope of Book V of the German Social Code, which, in this case, was necessary, another source of information was the legal framework and its impact on rescue chain, acute treatment and rehabilitation. Existent quality management systems, accreditations and quality assurance programs in prevention, acute treatment and rehabilitation have been searched in order to avoid any overlap with existing measures. After identifying a total of 71 quality targets according to deficits of care, recommendations for care and expert opinions in primary and secondary prevention, rescue chain, acute treatment, rehabilitation and supply of assistive equipment and therapies, respectively, the usability of instruments was tested. These instruments included case documentation, patient surveys and routine data. 14 quality targets proved to be reproducible by these instruments and were included in the recommendations for a cross-sectoral quality assurance program for stroke and TIA. Copyright © 2016. Published by Elsevier GmbH.

  5. A document-driven method for certifying scientific computing software for use in nuclear safety analysis

    International Nuclear Information System (INIS)

    Smith, W. Spencer; Koothoor, Mimitha

    2016-01-01

    This paper presents a documentation and development method to facilitate the certification of scientific computing software used in the safety analysis of nuclear facilities. To study the problems faced during quality assurance and certification activities, a case study was performed on legacy software used for thermal analysis of a fuel pin in a nuclear reactor. Although no errors were uncovered in the code, 27 issues of incompleteness and inconsistency were found with the documentation. This work proposes that software documentation follow a rational process, which includes a software requirements specification following a template that is reusable, maintainable, and understandable. To develop the design and implementation, this paper suggests literate programming as an alternative to traditional structured programming. Literate programming allows for documenting of numerical algorithms and code together in what is termed the literate programmer's manual. This manual is developed with explicit traceability to the software requirements specification. The traceability between the theory, numerical algorithms, and implementation facilitates achieving completeness and consistency, as well as simplifies the process of verification and the associated certification

  6. A document-driven method for certifying scientific computing software for use in nuclear safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Smith, W. Spencer; Koothoor, Mimitha [Computing and Software Department, McMaster University, Hamilton (Canada)

    2016-04-15

    This paper presents a documentation and development method to facilitate the certification of scientific computing software used in the safety analysis of nuclear facilities. To study the problems faced during quality assurance and certification activities, a case study was performed on legacy software used for thermal analysis of a fuel pin in a nuclear reactor. Although no errors were uncovered in the code, 27 issues of incompleteness and inconsistency were found with the documentation. This work proposes that software documentation follow a rational process, which includes a software requirements specification following a template that is reusable, maintainable, and understandable. To develop the design and implementation, this paper suggests literate programming as an alternative to traditional structured programming. Literate programming allows for documenting of numerical algorithms and code together in what is termed the literate programmer's manual. This manual is developed with explicit traceability to the software requirements specification. The traceability between the theory, numerical algorithms, and implementation facilitates achieving completeness and consistency, as well as simplifies the process of verification and the associated certification.

  7. Quality assurance and quality control in fabrication of heat exchanger tubes

    International Nuclear Information System (INIS)

    Duennewald, A.

    1980-01-01

    Object of this report is the manufacture of heat exchanger tubes. A comprehensive manufacturing and test program has to be established to assure and prove and equal tube quality. This requires a functionally operating quality assurance system combined with a production exactly planned in advance. A specific continuous production line for heat exchanger tubes has been erected at the Hellenthal plant of the Mannesmannroehren-Werke. All production steps and heat treatments are generally controlled by a quality control department. Non-destructive testing of each tube produced in standard length is performed on several agregates in line using ultrasonic and/or eddy current technique. All tests are generally performed in the presence of quality inspectors or surveyors. For a lot of heat exchangers the straight tubes have to be hairpin bended. To avoid the risk of stress corrosion cracking, it is recommended to procreate defined compression stresses in the outside tube surface. Prior to releasing the tubes to shipment, the completeness of the documentation as to the manufacturing steps and inspection agreed upon is thoroughly checked. (RW)

  8. Tool Use Within NASA Software Quality Assurance

    Science.gov (United States)

    Shigeta, Denise; Port, Dan; Nikora, Allen P.; Wilf, Joel

    2013-01-01

    As space mission software systems become larger and more complex, it is increasingly important for the software assurance effort to have the ability to effectively assess both the artifacts produced during software system development and the development process itself. Conceptually, assurance is a straightforward idea - it is the result of activities carried out by an organization independent of the software developers to better inform project management of potential technical and programmatic risks, and thus increase management's confidence in the decisions they ultimately make. In practice, effective assurance for large, complex systems often entails assessing large, complex software artifacts (e.g., requirements specifications, architectural descriptions) as well as substantial amounts of unstructured information (e.g., anomaly reports resulting from testing activities during development). In such an environment, assurance engineers can benefit greatly from appropriate tool support. In order to do so, an assurance organization will need accurate and timely information on the tool support available for various types of assurance activities. In this paper, we investigate the current use of tool support for assurance organizations within NASA, and describe on-going work at JPL for providing assurance organizations with the information about tools they need to use them effectively.

  9. Review of SKB's Quality Assurance Programme

    Energy Technology Data Exchange (ETDEWEB)

    Baldwin, Tamara D.; Hicks, Timothy W. (Galson Sciences LTD, Oakham, Rutland (United Kingdom))

    2009-06-15

    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

  10. 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)

  11. 42 CFR 431.53 - Assurance of transportation.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Assurance of transportation. 431.53 Section 431.53... Requirements § 431.53 Assurance of transportation. A State plan must— (a) Specify that the Medicaid agency will ensure necessary transportation for recipients to and from providers; and (b) Describe the methods that...

  12. 50 CFR 23.53 - What are the requirements for obtaining a retrospective CITES document?

    Science.gov (United States)

    2010-10-01

    ... retrospective CITES document? 23.53 Section 23.53 Wildlife and Fisheries UNITED STATES FISH AND WILDLIFE SERVICE... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Application Procedures, Criteria, and Conditions § 23.53 What are the requirements for obtaining a retrospective CITES document? (a) Purpose. Retrospective...

  13. Test design requirements: Canister-scale heater test

    International Nuclear Information System (INIS)

    Schauer, M.I.; Craig, P.A.; Stickney, R.G.

    1986-03-01

    This document establishes the Test Design Requirements for the design of a canister scale heater test to be performed in the Exploratory Shaft test facility. The purpose of the test is to obtain thermomechanical rock mass response data for use in validation of the numerical models. The canister scale heater test is a full scale simulation of a high-level nuclear waste container in a prototypic emplacement borehole. Electric heaters are used to simulate the heat loads expected in an actual waste container. This document presents an overview of the test including objectives and justification for the test. A description of the test as it is presently envisioned is included. Discussions on Quality Assurance and Safety are also included in the document. 12 refs., 1 fig

  14. The NASA Commercial Crew Program (CCP) Mission Assurance Process

    Science.gov (United States)

    Canfield, Amy

    2016-01-01

    In 2010, NASA established the Commercial Crew Program in order to provide human access to the International Space Station and low earth orbit via the commercial (non-governmental) sector. A particular challenge to NASA has been how to determine the commercial providers transportation system complies with Programmatic safety requirements. The process used in this determination is the Safety Technical Review Board which reviews and approves provider submitted Hazard Reports. One significant product of the review is a set of hazard control verifications. In past NASA programs, 100 percent of these safety critical verifications were typically confirmed by NASA. The traditional Safety and Mission Assurance (SMA) model does not support the nature of the Commercial Crew Program. To that end, NASA SMA is implementing a Risk Based Assurance (RBA) process to determine which hazard control verifications require NASA authentication. Additionally, a Shared Assurance Model is also being developed to efficiently use the available resources to execute the verifications. This paper will describe the evolution of the CCP Mission Assurance process from the beginning of the Program to its current incarnation. Topics to be covered include a short history of the CCP; the development of the Programmatic mission assurance requirements; the current safety review process; a description of the RBA process and its products and ending with a description of the Shared Assurance Model.

  15. Policy Decisions With Regard To The Applicability Of The Clean Air Act Requirements To The Strategic Petroleum Reserve

    Science.gov (United States)

    This document may be of assistance in applying the New Source Review (NSR) air permitting regulations including the Prevention of Significant Deterioration (PSD) requirements. This document is part of the NSR Policy and Guidance Database. Some documents in the database are a scanned or retyped version of a paper photocopy of the original. Although we have taken considerable effort to quality assure the documents, some may contain typographical errors. Contact the office that issued the document if you need a copy of the original.

  16. 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

  17. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

  18. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations

  19. 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)

  20. Implementing the AECL decommissioning quality assurance program at the Chalk River and Whiteshell Laboratories

    International Nuclear Information System (INIS)

    Colotelo, C.A.; Attas, E.M.; Stephens, M.E.

    2006-01-01

    This paper describes the approach and progress in developing, implementing and maintaining a quality assurance (QA) program for decommissioning at the nuclear facilities managed by Atomic Energy of Canada Limited (AECL). Decommissioning activities conducted by AECL are varied in nature, so the QA program must provide adequate flexibility, while maintaining consistency with accepted quality standards. Well-written documentation adhering to the applicable decommissioning standards is a key factor. Manager commitment and input during the writing of the documentation are also important to ensure relevance of the QA program and effectiveness of implementation. Training in the use of the quality assurance plan and procedures is vital to the understanding of the QA program. Beyond the training aspect there is a need for the quality assurance program to be supported by a QA subject expert who is able to advise the group in implementing the Quality Program with consistency over the range of decommissioning work activities and to provide continual assessment of the quality assurance program for efficiency and effectiveness, with a concomitant continuous improvement process. (author)

  1. High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 5

    International Nuclear Information System (INIS)

    1994-04-01

    The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 5) outlines the standards and requirements for the Fire Protection and Packaging and Transportation sections

  2. The study on the quality assurance of performance assessment for the disposal system

    International Nuclear Information System (INIS)

    Fusaeda, Shigeki; Yanagisawa, Ichiro; Katsurai, Kiyomichi; Ueda, Noriaki; Takeishi, Masayuki; Ida, Toshio; Imamura, Naoko

    1999-02-01

    The purpose of performance assessment of the geological disposal system in the second progress report is to quantitatively evaluate the performance in the near-field. For this purpose, validation of performance models and quality assurance of data used in the performance assessment are important technical subjects. To achieve the subjects, the quality of the procedure of analysis work and data acquisition work must be assured in addition to the quality assurance of data, models and analysis codes. In addition, to assure results of the performance assessment by integrating these qualities is an important matter. The following studies have been performed in order to improve the computer environment for controlling the quality information relating to the performance assessment, and to develop the integrated quality assurance system which can give reliability of the results of the performance assessment in the second progress report. (1) The study of quality assurance framework. In order to assure reliability of MESHNOTE3, we have carried out validation analysis based on experimental data and insite data. And we have revised the quality assurance manual in order to be applicable to preparing documents. We have carried out validation analysis/planning based on the experimental data which is acquired from 'Measurement of Apparent Diffusion Coefficient of 99 Tc in Compacted Bentonite with Fe powder', and confirmed validity of MESHNOTE3. We have added a postscript on the management of analysis documents to the quality assurance manual. (2) The development of the quality assurance computer system. In order to improve reliability of the analysis results and to efficiently use the quality assurance program, the quality assurance computer system on the basis of analysis management system CAPASA has been improved as follows. Database for radionuclide transport calculations that can control geometry of engineered barriers, data relating to glass dissolution and dose rate

  3. Tank waste remediation system privatization infrastructure program requirements and document management process guide

    International Nuclear Information System (INIS)

    ROOT, R.W.

    1999-01-01

    This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

  4. 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)

  5. 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

  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 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)

  8. Functional Requirements Document for HALE UAS Operations in the NAS: Step 1. Version 3

    Science.gov (United States)

    2006-01-01

    The purpose of this Functional Requirements Document (FRD) is to compile the functional requirements needed to achieve the Access 5 Vision of "operating High Altitude, Long Endurance (HALE) Unmanned Aircraft Systems (UAS) routinely, safely, and reliably in the national airspace system (NAS)" for Step 1. These functional requirements could support the development of a minimum set of policies, procedures and standards by the Federal Aviation Administration (FAA) and various standards organizations. It is envisioned that this comprehensive body of work will enable the FAA to establish and approve regulations to govern safe operation of UAS in the NAS on a routine or daily "file and fly" basis. The approach used to derive the functional requirements found within this FRD was to decompose the operational requirements and objectives identified within the Access 5 Concept of Operations (CONOPS) into the functions needed to routinely and safely operate a HALE UAS in the NAS. As a result, four major functional areas evolved to enable routine and safe UAS operations for an on-demand basis in the NAS. These four major functions are: Aviate, Navigate, Communicate, and Avoid Hazards. All of the functional requirements within this document can be directly traceable to one of these four major functions. Some functions, however, are traceable to several, or even all, of these four major functions. These cross-cutting functional requirements support the "Command / Control: function as well as the "Manage Contingencies" function. The requirements associated to these high-level functions and all of their supporting low-level functions are addressed in subsequent sections of this document.

  9. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  10. Quality assurance in the manufacture of pressure components

    International Nuclear Information System (INIS)

    Knoedler, D.

    1979-01-01

    New regulations for nuclear power plants emphasize more quality assurance than it was the case in the past. Quality assurance is a management tool. During erection the quality assurance measures of the manufacturer, the main contractor and the required quality and the reliability of the proof of quality. The qualification of processes, equipment and personnel is a significant measure of quality assurance. The proof for quality assurance to be effective needs not only system-oriented audits, but also product audits aimed at quality characteristics of the product itself. The existing problems of examination techniques not optimized according to latest experience and of the large volume of documetation will persist in case the existing regulations are not adjusted according to the results of relevant studies. Furthermore the effectiveness of quality assurance is too often hampered by vague definitions of the safety objectives. (orig.) [de

  11. Minimal requirements for quality controls in radiotherapy with external beams

    International Nuclear Information System (INIS)

    1999-01-01

    Physical dosimetric guidelines have been developed by the Italian National Institute of Health study group on quality assurance in radiotherapy to define protocols for quality controls in external beam radiotherapy. While the document does not determine strict rules or firm recommendations, it suggests minimal requirements for quality controls necessary to guarantee an adequate degree of accuracy in external beam radiotherapy [it

  12. AUDIT plan documenting method

    International Nuclear Information System (INIS)

    Cornecsu, M.

    1995-01-01

    The work describes a method of documenting the AUDIT plan upon the basis of two quantitative elements resulting from quality assurance program appraisal system function implementation degree as established from the latest AUDIT performed an system function weight in QAP, respectively, appraised by taking into account their significance for the activities that are to be performed in the period for which the AUDITs are planned. (Author) 3 Figs., 2 Refs

  13. [Quality assurance in human genetic testing].

    Science.gov (United States)

    Stuhrmann-Spangenberg, Manfred

    2015-02-01

    Advances in technical developments of genetic diagnostics for more than 50 years, as well as the fact that human genetic testing is usually performed only once in a lifetime, with additional impact for blood relatives, are determining the extraordinary importance of quality assurance in human genetic testing. Abidance of laws, directives, and guidelines plays a major role. This article aims to present the major laws, directives, and guidelines with respect to quality assurance of human genetic testing, paying careful attention to internal and external quality assurance. The information on quality assurance of human genetic testing was obtained through a web-based search of the web pages that are referred to in this article. Further information was retrieved from publications in the German Society of Human Genetics and through a PubMed-search using term quality + assurance + genetic + diagnostics. The most important laws, directives, and guidelines for quality assurance of human genetic testing are the gene diagnostics law (GenDG), the directive of the Federal Medical Council for quality control of clinical laboratory analysis (RiliBÄK), and the S2K guideline for human genetic diagnostics and counselling. In addition, voluntary accreditation under DIN EN ISO 15189:2013 offers a most recommended contribution towards quality assurance of human genetic testing. Legal restraints on quality assurance of human genetic testing as mentioned in § 5 GenDG are fulfilled once RiliBÄK requirements are followed.

  14. Quality assurance in the project of RECH-2 research reactor

    International Nuclear Information System (INIS)

    Goycolea Donoso, C.; Nino de Zepeda Schele, A.

    1989-01-01

    The implantation of a Quality Assurance Program for the design, supply, construction, installation, and testing of the RECH-2 research reactor, is described in this paper. The obtained results, demonstrate that a Quality Assurance Program constitutes a suitable mean to assure that the installation complies with the safety and reliability requirements. (author)

  15. Quality control and assurance in building the Dukovany nuclear power plant - check on and filing of quality certificates

    International Nuclear Information System (INIS)

    Sokola, J.

    1986-01-01

    The following documents were used for determining the range of documentation required for the construction of the Dukovany nuclear power plant: the decree valid in Czechoslovakia for all industrial structures, the respective Czechoslovak State and branch standards and several special Soviet regulations. For the central recording of all documents on the quality of deliveries and assemblies a special quality assurance unit was set up on the site of the nuclear power plant. In the system of the flow of documents on the quality of the structure of the Dukovany nuclear power plant there are 16 addressees, from outside subcontractors to on-site managerial staff, work safety inspectors, etc., to the enterprise archives and the department of scientific and technical information. A brief description is presented of the different types of documents on the quality of deliveries and assemblies, and the method of inspection of their content and completeness is described. (Z.M.)

  16. Reliability assurance for regulation of advanced reactors

    International Nuclear Information System (INIS)

    Fullwood, R.; Lofaro, R.; Samanta, P.

    1992-01-01

    The advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semi-passive protection. Reliability assurance of the advanced reactor systems is important for determining the safety of the design and for determining the plant operability. Safety is the primary concern, but operability is considered indicative of good and safe operation. this paper discusses several concerns for reliability assurance of the advanced design encompassing reliability determination, level of detail required in advanced reactor submittals, data for reliability assurance, systems interactions and common cause effects, passive component reliability, PRA-based configuration control system, and inspection, training, maintenance and test requirements. Suggested approaches are provided for addressing each of these topics

  17. Reliability assurance for regulation of advanced reactors

    International Nuclear Information System (INIS)

    Fullwood, R.; Lofaro, R.; Samanta, P.

    1991-01-01

    The advanced nuclear power plants must achieve higher levels of safety than the first generation of plants. Showing that this is indeed true provides new challenges to reliability and risk assessment methods in the analysis of the designs employing passive and semi-passive protection. Reliability assurance of the advanced reactor systems is important for determining the safety of the design and for determining the plant operability. Safety is the primary concern, but operability is considered indicative of good and safe operation. This paper discusses several concerns for reliability assurance of the advanced design encompassing reliability determination, level of detail required in advanced reactor submittals, data for reliability assurance, systems interactions and common cause effects, passive component reliability, PRA-based configuration control system, and inspection, training, maintenance and test requirements. Suggested approaches are provided for addressing each of these topics

  18. Software requirements specification document for the AREST code development

    International Nuclear Information System (INIS)

    Engel, D.W.; McGrail, B.P.; Whitney, P.D.; Gray, W.J.; Williford, R.E.; White, M.D.; Eslinger, P.W.; Altenhofen, M.K.

    1993-11-01

    The Analysis of the Repository Source Term (AREST) computer code was selected in 1992 by the U.S. Department of Energy. The AREST code will be used to analyze the performance of an underground high level nuclear waste repository. The AREST code is being modified by the Pacific Northwest Laboratory (PNL) in order to evaluate the engineered barrier and waste package designs, model regulatory compliance, analyze sensitivities, and support total systems performance assessment modeling. The current version of the AREST code was developed to be a very useful tool for analyzing model uncertainties and sensitivities to input parameters. The code has also been used successfully in supplying source-terms that were used in a total systems performance assessment. The current version, however, has been found to be inadequate for the comparison and selection of a design for the waste package. This is due to the assumptions and simplifications made in the selection of the process and system models. Thus, the new version of the AREST code will be designed to focus on the details of the individual processes and implementation of more realistic models. This document describes the requirements of the new models that will be implemented. Included in this document is a section describing the near-field environmental conditions for this waste package modeling, description of the new process models that will be implemented, and a description of the computer requirements for the new version of the AREST code

  19. quality assurance calculation in UO2 pellet manufacturing process

    International Nuclear Information System (INIS)

    Can, S.; Acarkan, S.; Guereli, L. and others

    1997-01-01

    A process qualification plan is prepared for preparation of quality assurance documentation in accordance with ISO-9000 series of standards, for sintered UO 2 pellets manufactured in the Nuclear Fuel Technology Department. The objectives of this plan are to determine quantitatively and statistically process capability of the pellet production, to check product properties (are) in conformance with specifications at the pre-( ) confidence levels, to prepare necessary documents and to assess the results. The product properties taking into account are chemical composition, cracks, density, microstructure and grain size. The statistical parameters used for qualification element of quality assurance are calculated.Statistical values for sintered pellets are: LENGTH/WEIGHT/DIAMETER/DENSITY/%TD: MEAN:13,395/16,808/12,293/10,679/97,400 STD:0,1651/ 0,252/0,0212/0,015/0,140. It was seen that sintered pellets manufactured in the Nuclear Fuel Technology Department meet the criteria within 95% confidence level. In this paper specifications, criteria and calculations will be explained in detail

  20. 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