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Sample records for safety assurance program

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.
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
Application of quality assurance program to safety related aging equipment or components

International Nuclear Information System (INIS)

Papaiya, N.C.

1990-01-01

This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements
Technical Excellence and Communication: The Cornerstones for Successful Safety and Mission Assurance Programs

Science.gov (United States)

Malone, Roy W.; Livingston, John M.

2010-01-01

The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center (MSFC) Safety and Mission Assurance (S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.
Technical Excellence and Communication, the Cornerstones for Successful Safety and Mission Assurance Programs

Science.gov (United States)

Malone, Roy W.; Livingston, John M.

2010-09-01

The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center(MSFC) Safety and Mission Assurance(S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization’s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.
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
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.
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
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
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
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
Experience in the implementation of quality assurance program and safety culture assessment of research reactor operation and maintenance

International Nuclear Information System (INIS)

Syarip; Suryopratomo, K.

2001-01-01

The implementation of quality assurance program and safety culture for research reactor operation are of importance to assure its safety status. It comprises an assessment of the quality of both technical and organizational aspects involved in safety. The method for the assessment is based on judging the quality of fulfillment of a number of essential issues for safety i.e. through audit, interview and/or discussions with personnel and management in plant. However, special consideration should be given to the data processing regarding the fuzzy nature of the data i.e. in answering the questionnaire. To accommodate this situation, the SCAP, a computer program based on fuzzy logic for assessing plant safety status, has been developed. As a case study, the experience in the assessment of Kartini research reactor safety status shows that it is strongly related to the implementation of quality assurance program in reactor operation and awareness of reactor operation staffs to safety culture practice. It is also shown that the application of the fuzzy rule in assessing reactor safety status gives a more realistic result than the traditional approach. (author)
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)
Evaluation of reliability assurance approaches to operational nuclear safety

International Nuclear Information System (INIS)

Mueller, C.J.; Bezella, W.A.

1984-01-01

This report discusses the results of research to evaluate existing and/or recommended safety/reliability assurance activities among nuclear and other high technology industries for potential nuclear industry implementation. Since the Three Mile Island (TMI) accident, there has been increased interest in the use of reliability programs (RP) to assure the performance of nuclear safety systems throughout the plant's lifetime. Recently, several Nuclear Regulatory Commission (NRC) task forces or safety issue review groups have recommended RPs for assuring the continuing safety of nuclear reactor plants. 18 references
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.
A Quality Assurance Program for decommissioning

International Nuclear Information System (INIS)

Briggs, P.M.

1986-01-01

Defining the Quality Assurance Program for the US Department of Energy Shippingport Station Decommissioning Project (SSDP) was a unique opportunity because this is the first full-sized commercial nuclear power plant to be decommissioned. General Electric Company defined a Quality Assurance Program that provided adequate control, yet was stripped down to the essentials. The Program is designed to provide a flexible degree of monitoring of subcontractor work, built around a core of radiation safety monitoring, detailed planning, inspection and auditing, and operated with a minimum of dedicated personnel. This paper will concentrate on the traditional quality assurance activities, leaving radiation and environmental monitoring for other presentations
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
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.
Technology and Tool Development to Support Safety and Mission Assurance

Science.gov (United States)

Denney, Ewen; Pai, Ganesh

2017-01-01

The Assurance Case approach is being adopted in a number of safety-mission-critical application domains in the U.S., e.g., medical devices, defense aviation, automotive systems, and, lately, civil aviation. This paradigm refocuses traditional, process-based approaches to assurance on demonstrating explicitly stated assurance goals, emphasizing the use of structured rationale, and concrete product-based evidence as the means for providing justified confidence that systems and software are fit for purpose in safely achieving mission objectives. NASA has also been embracing assurance cases through the concepts of Risk Informed Safety Cases (RISCs), as documented in the NASA System Safety Handbook, and Objective Hierarchies (OHs) as put forth by the Agency's Office of Safety and Mission Assurance (OSMA). This talk will give an overview of the work being performed by the SGT team located at NASA Ames Research Center, in developing technologies and tools to engineer and apply assurance cases in customer projects pertaining to aviation safety. We elaborate how our Assurance Case Automation Toolset (AdvoCATE) has not only extended the state-of-the-art in assurance case research, but also demonstrated its practical utility. We have successfully developed safety assurance cases for a number of Unmanned Aircraft Systems (UAS) operations, which underwent, and passed, scrutiny both by the aviation regulator, i.e., the FAA, as well as the applicable NASA boards for airworthiness and flight safety, flight readiness, and mission readiness. We discuss our efforts in expanding AdvoCATE capabilities to support RISCs and OHs under a project recently funded by OSMA under its Software Assurance Research Program. Finally, we speculate on the applicability of our innovations beyond aviation safety to such endeavors as robotic, and human spaceflight.
The development of quality assurance program in Reactor TRIGA PUSPATI (RTP)

International Nuclear Information System (INIS)

Rosli Darmawan; Mohd Rizal Mamat; Mohamad Zaid Mohamad; Mohd Ridzuan Abdul Mutalib

2007-01-01

One of the trivial issues in the operation of Nuclear Reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing has always bring about general public fear on anything related to nuclear. IAEA has always emphasized on the assurance of nuclear safety for all nuclear installations and activities. According to the IAEA safety guides, all research reactors are required to implement quality assurance programs to ensure the conduct of operations are in accordance with the safety standards required. This paper discusses the activities carried out toward the establishment of Quality Assurance Program for Reaktor TRIGA PUSPATI (RTP). (Author)

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
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
Organizing safety: conditions for successful information assurance programs.

Science.gov (United States)

Collmann, Jeff; Coleman, Johnathan; Sostrom, Kristen; Wright, Willie

2004-01-01

Organizations must continuously seek safety. When considering computerized health information systems, "safety" includes protecting the integrity, confidentiality, and availability of information assets such as patient information, key components of the technical information system, and critical personnel. "High Reliability Theory" (HRT) argues that organizations with strong leadership support, continuous training, redundant safety mechanisms, and "cultures of high reliability" can deploy and safely manage complex, risky technologies such as nuclear weapons systems or computerized health information systems. In preparation for the Health Insurance Portability and Accountability Act (HIPAA) of 1996, the Office of the Assistant Secretary of Defense (Health Affairs), the Offices of the Surgeons General of the United States Army, Navy and Air Force, and the Telemedicine and Advanced Technology Research Center (TATRC), US Army Medical Research and Materiel Command sponsored organizational, doctrinal, and technical projects that individually and collectively promote conditions for a "culture of information assurance." These efforts include sponsoring the "P3 Working Group" (P3WG), an interdisciplinary, tri-service taskforce that reviewed all relevant Department of Defense (DoD), Miliary Health System (MHS), Army, Navy and Air Force policies for compliance with the HIPAA medical privacy and data security regulations; supporting development, training, and deployment of OCTAVE(sm), a self-directed information security risk assessment process; and sponsoring development of the Risk Information Management Resource (RIMR), a Web-enabled enterprise portal about health information assurance.
Role of quality assurance in reactor safety

International Nuclear Information System (INIS)

Roedel, J.A.

1975-01-01

A quality assurance program based on common sense, designed to accomplish what is reasonable and necessary, giving proper consideration to safety and economics can be an effective and essential management tool for the design, construction and operation of safe and economical nuclear power plants
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
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
DOE's Assurance Program for Remedial Action (APRA)

International Nuclear Information System (INIS)

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

1985-01-01

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

International Nuclear Information System (INIS)

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

1984-10-01

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

International Nuclear Information System (INIS)

Kryukov, O.V.; Vasil'ev, V.A.; Nikishin, D.A.; Linge, I.I.; Obodinskij, A.N.

2012-01-01

The Federal Program Nuclear and Radiation Safety Assurance for 2008-2015 is presented. Specifics of Federal target program management as well as changes to program management are discussed. Data on evaluation of management effectiveness is given. Further efforts to resolve the nuclear legacy problem in Russia are also presented [ru
The Evolution of the NASA Commercial Crew Program Mission Assurance Process

Science.gov (United States)

Canfield, Amy C.

2016-01-01

In 2010, the National Aeronautics and Space Administration (NASA) established the Commercial Crew Program (CCP) 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 that the Commercial Provider's 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% of these safety critical verifications were typically confirmed by NASA. The traditional Safety and Mission Assurance (S&MA) model does not support the nature of the CCP. To that end, NASA S&MA is implementing a Risk Based Assurance 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.
Quality and Safety Assurance - Priority Task at Nuclear Power Projects Implementation

International Nuclear Information System (INIS)

Nenkova, B.; Manchev, B.; Tomov, E.

2010-01-01

Quality and safety assurance at implementation of nuclear power engineering projects is important and difficult task for realization. Many problems arise during this process, when many companies from different countries participate, with various kinds of activities and services provided. The scope of activities necessary for quality and safety assurance is therefore quite expanded and diverse. In order to increase the safety and reliability of Kozloduy NPP Plc (KNPP) Units 5 and 6, as well as to bring the units in conformity with the newest international requirements for quality and safety in the field of nuclear energy, a program for their modernization on the basis of different technical studies and assessments was implemented. The Units 5 and 6 Modernization Program of Kozloduy Nuclear Power Plant was composed of 212 modifications aimed to improve the safety, operability, and reliability of the Units. The Program was realized by stages during yearly planned outages since year 2002 to 2007, without additional outages. A major Program Objective was to extend the Units Life Time in at least 15 Years, under a continuous, safe, and reliable operation. The Modernization Program of Units 5 and 6 of the Bulgarian Nuclear Power Plant in Kozloduy was the first and for the time being the only one in the world, program in the field of nuclear power engineering, by which the full scope of recommendations for improvement of the Kozloduy NPP units was applied. The main goal of the National Electric Company, which is the Employer for the construction of new nuclear facility in Bulgaria, is after completion of all activities regarding construction of Belene NPP the plant to meet or exceed the requirements of the respective national and international quality and safety codes and standards, as well as the IAEA guidelines, as they are established. The objective of this report is to describe different aspects of the quality assurance according to the requirements of quality and
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...
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.
The assurance management program for the Nova laser fusion project

International Nuclear Information System (INIS)

Levy, A.J.

1983-01-01

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

Science.gov (United States)

Raab, Stephen S

2006-05-01

Anatomic pathology laboratories use several quality assurance tools to detect errors and to improve patient safety. To review some of the anatomic pathology laboratory patient safety quality assurance practices. Different standards and measures in anatomic pathology quality assurance and patient safety were reviewed. Frequency of anatomic pathology laboratory error, variability in the use of specific quality assurance practices, and use of data for error reduction initiatives. Anatomic pathology error frequencies vary according to the detection method used. Based on secondary review, a College of American Pathologists Q-Probes study showed that the mean laboratory error frequency was 6.7%. A College of American Pathologists Q-Tracks study measuring frozen section discrepancy found that laboratories improved the longer they monitored and shared data. There is a lack of standardization across laboratories even for governmentally mandated quality assurance practices, such as cytologic-histologic correlation. The National Institutes of Health funded a consortium of laboratories to benchmark laboratory error frequencies, perform root cause analysis, and design error reduction initiatives, using quality assurance data. Based on the cytologic-histologic correlation process, these laboratories found an aggregate nongynecologic error frequency of 10.8%. Based on gynecologic error data, the laboratory at my institution used Toyota production system processes to lower gynecologic error frequencies and to improve Papanicolaou test metrics. Laboratory quality assurance practices have been used to track error rates, and laboratories are starting to use these data for error reduction initiatives.
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
Dynamic Safety Cases for Through-Life Safety Assurance

Science.gov (United States)

Denney, Ewen; Pai, Ganesh; Habli, Ibrahim

2015-01-01

We describe dynamic safety cases, a novel operationalization of the concept of through-life safety assurance, whose goal is to enable proactive safety management. Using an example from the aviation systems domain, we motivate our approach, its underlying principles, and a lifecycle. We then identify the key elements required to move towards a formalization of the associated framework.
Probabilistic studies for a safety assurance program

International Nuclear Information System (INIS)

Iyer, S.S.; Davis, J.F.

1985-01-01

The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

Reactor system safety assurance

International Nuclear Information System (INIS)

Mattson, R.J.

1984-01-01

The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment
Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

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

Science.gov (United States)

Johnson, Teresa A.

2006-01-01

Knowledge Management is a proactive pursuit for the future success of any large organization faced with the imminent possibility that their senior managers/engineers with gained experiences and lessons learned plan to retire in the near term. Safety and Mission Assurance (S&MA) is proactively pursuing unique mechanism to ensure knowledge learned is retained and lessons learned captured and documented. Knowledge Capture Event/Activities/Management helps to provide a gateway between future retirees and our next generation of managers/engineers. S&MA hosted two Knowledge Capture Events during 2005 featuring three of its retiring fellows (Axel Larsen, Dave Whittle and Gary Johnson). The first Knowledge Capture Event February 24, 2005 focused on two Safety and Mission Assurance Safety Panels (Space Shuttle System Safety Review Panel (SSRP); Payload Safety Review Panel (PSRP) and the latter event December 15, 2005 featured lessons learned during Apollo, Skylab, and Space Shuttle which could be applicable in the newly created Crew Exploration Vehicle (CEV)/Constellation development program. Gemini, Apollo, Skylab and the Space Shuttle promised and delivered exciting human advances in space and benefits of space in people s everyday lives on earth. Johnson Space Center's Safety & Mission Assurance team work over the last 20 years has been mostly focused on operations we are now beginning the Exploration development program. S&MA will promote an atmosphere of knowledge sharing in its formal and informal cultures and work processes, and reward the open dissemination and sharing of information; we are asking "Why embrace relearning the "lessons learned" in the past?" On the Exploration program the focus will be on Design, Development, Test, & Evaluation (DDT&E); therefore, it is critical to understand the lessons from these past programs during the DDT&E phase.
EPRI program in water reactor safety

International Nuclear Information System (INIS)

Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

1975-01-01

The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs
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.)
Methods of Software Quality Assurance under a Nuclear Quality Assurance Program

International Nuclear Information System (INIS)

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

2005-01-01

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

International Nuclear Information System (INIS)

Park, J. W.; Kim, C. L.; Park, J. B.; Lee, E. Y.; Lee, Y. M.; Kang, C. H.; Zhou, W.; Kozak, M. W.

2003-01-01

A quality assurance safety assessment database, called QUARK (QUality Assurance program for Radioactive waste management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of Low- and Intermediate-Level radioactive Waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code
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)
Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the System-Wide Safety and Assurance Technologies Project

Science.gov (United States)

Withrow, Colleen A.; Reveley, Mary S.

2015-01-01

The Aviation Safety Program (AvSP) System-Wide Safety and Assurance Technologies (SSAT) Project asked the AvSP Systems and Portfolio Analysis Team to identify SSAT-related trends. SSAT had four technical challenges: advance safety assurance to enable deployment of NextGen systems; automated discovery of precursors to aviation safety incidents; increasing safety of human-automation interaction by incorporating human performance, and prognostic algorithm design for safety assurance. This report reviews incident data from the NASA Aviation Safety Reporting System (ASRS) for system-component-failure- or-malfunction- (SCFM-) related and human-factor-related incidents for commercial or cargo air carriers (Part 121), commuter airlines (Part 135), and general aviation (Part 91). The data was analyzed by Federal Aviation Regulations (FAR) part, phase of flight, SCFM category, human factor category, and a variety of anomalies and results. There were 38 894 SCFM-related incidents and 83 478 human-factorrelated incidents analyzed between January 1993 and April 2011.
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
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
Design-reliability assurance program application to ACP600

International Nuclear Information System (INIS)

Zhichao, Huang; Bo, Zhao

2012-01-01

ACP600 is a newly nuclear power plant technology made by CNNC in China and it is based on the Generation III NPPs design experience and general safety goals. The ACP600 Design Reliability Assurance Program (D-RAP) is implemented as an integral part of the ACP600 design process. A RAP is a formal management system which assures the collection of important characteristic information about plant performance throughout each phase of its life and directs the use of this information in the implementation of analytical and management process which are specifically designed to meet two specific objects: confirm the plant goals and cost effective improvements. In general, typical reliability assurance program have 4 broad functional elements: 1) Goals and performance criteria; 2) Management system and implementing procedures; 3) Analytical tools and investigative methods; and 4) Information management. In this paper we will use the D-RAP technical and Risk-Informed requirements, and establish the RAM and PSA model to optimize the ACP600 design. Compared with previous design process, the D-RAP is more competent for the higher design targets and requirements, enjoying more creativity through an easier implementation of technical breakthroughs. By using D-RAP, the plants goals, system goals, performance criteria and safety criteria can be easier to realize, and the design can be optimized and more rational
Auditing of quality assurance programs for nuclear power plants - September 1980 - (Rev.1)

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of structures, systems, and components of nuclear power plants important to safety. Criterion XVIII, Audits, of Appendix B to 10 CFR Part 50 establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to auditing of quality assurance programs for nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position
Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

International Nuclear Information System (INIS)

Patch, R.L.

1993-01-01

The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about
Elements of a nuclear criticality safety program

International Nuclear Information System (INIS)

Hopper, C.M.

1995-01-01

Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance
A quality assurance program in stereotactic radiosurgery using the gamma knife unit

International Nuclear Information System (INIS)

Stuecklschweiger, G.F.; Feichtinger, K.

1998-01-01

Because of the large single fraction dose in stereotactic radiosurgery it is important to guarantee a high geometric and dosimetric accuracy. The paper represent the quality assurance program for the Gamma Knife unit at the University Clinic of Neurosurgery in Graz. The program includes the following procedures: Timer control, mechanical radiation isocenter coincidence, trunnion centricity, helmet microswitches test, radiation output and relative helmet factors, dose profile verification, safety interlocks checks and software quality assurance. In summary, the mechanical accuracy and reproducibility of the Gamma Knife unit are [de
Comprehensive Lifecycle for Assuring System Safety

Science.gov (United States)

Knight, John C.; Rowanhill, Jonathan C.

2017-01-01

CLASS is a novel approach to the enhancement of system safety in which the system safety case becomes the focus of safety engineering throughout the system lifecycle. CLASS also expands the role of the safety case across all phases of the system's lifetime, from concept formation to decommissioning. As CLASS has been developed, the concept has been generalized to a more comprehensive notion of assurance becoming the driving goal, where safety is an important special case. This report summarizes major aspects of CLASS and contains a bibliography of papers that provide additional details.
Role of computers in quality assurance in the LLL Criticality Safety Program

International Nuclear Information System (INIS)

Koponen, B.L.

1978-01-01

Some of the aspects of computational criticality safety quality assurance that have been emphasized in recent years at LLL are summarized. In particular, computer code changes that have been made that help the criticality analyst reduce the number of errors that he makes and to locate those that he does make; and how a computerized ''benchmark'' data base aids him in the validation of his computational methods are discussed
UMTRA technical assistance contractor quality assurance program plan

International Nuclear Information System (INIS)

1994-10-01

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
Safety assurance logic techniques for evaluation of accident prevention and mitigation

International Nuclear Information System (INIS)

McWethy, L.M.; Hagan, J.W.

1976-01-01

Safety assurance methods have been developed and applied in reactor safety assessments of FFTF. These methods promote visibility of the total safety provided by the plant, both in prevention of off-normal or accident conditions as well as provision of various features which terminate conditions within acceptable bounds if such conditions should occur. One of the primary techniques applied in safety assurance is the development of safety assurance diagrams. These diagrams explicitly identify the multiple lines of defense which prevent accident progression. The diagrams graphically demonstrate the defense-in-depth provided by the plant for each postulated occurrence. Lines of defense are shown against ever having an occurrence in the first place; thus giving appropriate emphasis on accident prevention, and visibility to the designer's role in promoting this level of safety. These diagrams, or accident process trees, also show graphically the various paths of postulated accident progression to their logical termination. Evaluation of the importance and strength of each line-of-defense assures fulfillment of the safety objectives of the overall plant system

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
Safety assurance for nuclear chemical plants - regulatory practice in the UK

International Nuclear Information System (INIS)

Driscoll, J.; Charlesworth, F.

1983-01-01

This paper describes the legislation and licensing requirements for nuclear installations as well as the related safety assurance procedures in the UK. Developments in safety assurance practice are identified and discussed in relation to the role of the regulator and of the operator. (NEA) [fr
Quality assurance applied to an environmental surveillance program

International Nuclear Information System (INIS)

Oakes, T.W.; Shank, K.E.; Eldridge, J.S.

1977-01-01

A discussion of a quality assurance program applied to environmental surveillance activities is presented. This includes the philosophy and concepts of quality assurance, along with a detailed assessment of the sources of uncertainty in a monitoring program. The role management must play for a successful program is also discussed, and the quality assurance program implemented at Oak Ridge National Laboratory is presented
Application of 5700.6B, quality assurance, to ES and H programs: Mound's approach and results

International Nuclear Information System (INIS)

Edling, D.A.

1985-01-01

Quality Assurance has always been integral to Mound's production and support operations. Weapons material and other designated material for WR programs are processed and controlled per the requirements of DOE/AL Quality Control Policy QC-1. Mound's non-WR activities, such as siting, design, construction, testing, operation, maintenance, development and production of materials, components, and systems, and acquisition of research and technology data are to be processed and controlled per the requirements of AL Order 5700.6. This paper presents an overview of the entire Quality Assurance Program at Mound and specifically addresses Mound's formal application of Quality Assurance to our comprehensive Environmental, Safety and Health (ES and H) Programs. 4 figures, 1 table
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
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
Technical assistance to Department of Energy/Office of Operational Safety Assurance Program for remedial action

International Nuclear Information System (INIS)

Denham, D.H.; Cross, F.T.; Kennedy, W.E. Jr.; Marks, S.; Soldat, J.K.; Stenner, R.D.

1986-01-01

This project was initiated in FY 1984 to provide technical assistance to the Department of Energy (DOE), Office of Operational Safety (OOS) in developing and implementing its Assurance Program for Remedial Action (APRA), i.e., overview of the DOE remedial action programs. During this second year of the project,* the technical assistance included report and procedure reviews, and assistance with conducting the Uranium Mill Tailings Remedial Action Program (UMTRAP) Office (DOE/AL) appraisal. This included participation in preappraisal visits to UMTRAP sites in Canonsburg, Pennsylvania; Grand Junction, Colorado; and Salt Lake City, Utah. Pacific Northwest Laboratory (PNL) also transferred the PNL-developed document review software to the Oak Ridge Associated Universities (ORAU) staff in Grand Junction, Colorado, in anticipation of future document reviews by the ORAU staff. Other accomplishments have included publication of two formal documents and three project reports, preparation and presentation of five topical reports at national and international meetings, two foreign trip reports, and comments on proposed draft standards of the Environmental Protection Agency (40 CFR 193). The project manager has also participated on National Council on Radiation Protection and Measurements (NCRP) and American Society for Testing and Materials (ASTM) subcommittees developing decommissioning standards, as well as International Atomic Energy Agency (IAEA) advisory groups developing environmental monitoring guidelines
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
Assuring bridge safety and serviceability in Europe

Science.gov (United States)

2010-08-01

U.S. engineers need advanced tools and protocols to better assess and assure safety and serviceability of bridges. The Federal Highway Administration, American Association of State Highway and Transportation Officials, and National Cooperative Highwa...
Nova laser assurance-management system

International Nuclear Information System (INIS)

Levy, A.J.

1983-01-01

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

International Nuclear Information System (INIS)

Salinas, F; Sansogne, R; Arbiser, S; Suarez, V; Franco, M; Escobar, J

2012-01-01

Quality assurance and safety controls in radiation therapy delivery processes that involve the Physics Department of an institution are commonly time consuming tasks. Carrying out daily controls in very busy clinics without compromising patient schedule is challenging. This work describes the usage of Electronic Portal Imaging Devices in combination with some in-house software to simplify and systematize three different tasks of the Physics Department Quality Assurance Program, improving the easiness, reliability and velocity of daily tests (author)
Quality assurance for software important to safety

International Nuclear Information System (INIS)

2000-01-01

Software applications play an increasingly relevant role in nuclear power plant systems. This is particularly true of software important to safety used in both: calculations for the design, testing and analysis of nuclear reactor systems (design, engineering and analysis software); and monitoring, control and safety functions as an integral part of the reactor systems (monitoring, control and safety system software). Computer technology is advancing at a fast pace, offering new possibilities in nuclear reactor design, construction, commissioning, operation, maintenance and decommissioning. These advances also present new issues which must be considered both by the utility and by the regulatory organization. Refurbishment of ageing instrumentation and control systems in nuclear power plants and new safety related application areas have emerged, with direct (e.g. interfaces with safety systems) and indirect (e.g. operator intervention) implications for safety. Currently, there exist several international standards and guides on quality assurance for software important to safety. However, none of the existing documents provides comprehensive guidance to the developer, manager and regulator during all phases of the software life-cycle. The present publication was developed taking into account the large amount of available documentation, the rapid development of software systems and the need for updated guidance on h ow to do it . It provides information and guidance for defining and implementing quality assurance programmes covering the entire life-cycle of software important to safety. Expected users are managers, performers and assessors from nuclear utilities, regulatory bodies, suppliers and technical support organizations involved with the development and use of software applied in nuclear power plants
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.
Fast reactor safety program. Progress report, January-March 1980

International Nuclear Information System (INIS)

1980-05-01

The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development
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
Pacific Northwest Laboratory annual report for 1988 to the Assistant Secretary for Environment, Safety, and Health: Part 5, Environment, safety, health, and quality assurance

International Nuclear Information System (INIS)

Faust, L.G.; Pennell, W.T.; Selby, J.M.

1989-02-01

This document summarizes the research programs now underway at Battelle's Pacific Northwest Laboratory in the areas of environmental safety, health, and quality assurance. Topics include internal irradiation, emergency plans, dose equivalents, risk assessment, dose equivalents, surveys, neutron dosimetry, and radiation accidents
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
International organisations assure nuclear safety competence

International Nuclear Information System (INIS)

Alonso, A.

2000-01-01

Irrespective of current views on the future of nuclear power programmes, concerns are arising with respect to the long-term ability to preserve safety competence because student enrollments in nuclear engineering are decreasing rapidly and experienced staff are reaching retirement age. 'Assuring Nuclear Safety Competence into the 21. Century' was discussed in depth by workshop participants. The need for a long-term strategic view was emphasised, and policy recommendations were made. These proceedings will be of particular interest to those playing a policy role in the nuclear industry, regulatory bodies and the education sector
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
Quality assurance program for isotopic power systems

International Nuclear Information System (INIS)

Hannigan, R.L.; Harnar, R.R.

1982-12-01

This report summarizes the Sandia National Laboratories Quality Assurance Program that applies to non-weapon (reimbursable) Radioisotopic Thermoelectric Generators. The program has been implemented over the past 16 years on power supplies used in various space and terrestrial systems. The quality assurance (QA) activity of the program is in support of the Department of Energy, Office of Space Nuclear Projects. Basic elements of the program are described in the report and examples of program decumentation are presented

Quality assurance program for isotopic power systems

Energy Technology Data Exchange (ETDEWEB)

Hannigan, R.L.; Harnar, R.R.

1982-12-01

This report summarizes the Sandia National Laboratories Quality Assurance Program that applies to non-weapon (reimbursable) Radioisotopic Thermoelectric Generators. The program has been implemented over the past 16 years on power supplies used in various space and terrestrial systems. The quality assurance (QA) activity of the program is in support of the Department of Energy, Office of Space Nuclear Projects. Basic elements of the program are described in the report and examples of program decumentation are presented.
Pacific Northwest Laboratory annual report for 1988 to the Assistant Secretary for Environment, Safety, and Health: Part 5, Environment, safety, health, and quality assurance

Energy Technology Data Exchange (ETDEWEB)

Faust, L.G.; Pennell, W.T.; Selby, J.M.

1989-02-01

This document summarizes the research programs now underway at Battelle's Pacific Northwest Laboratory in the areas of environmental safety, health, and quality assurance. Topics include internal irradiation, emergency plans, dose equivalents, risk assessment, dose equivalents, surveys, neutron dosimetry, and radiation accidents. (TEM)
Philosophy of safety assurance after the Fukushima Daiichi accident. From views of experts

International Nuclear Information System (INIS)

Hisada, Tsukasa

2014-01-01

Knowledge incorporating meetings were held to exchange views of experts in order to learn respective safety concept and philosophy of safety assurance except nuclear area, how should be prepared for beyond expectation and what was needed to build social credibility, and how to upgrade safety measures of nuclear power station after the Fukushima Daiichi accident. Meeting had been held twice a year since FY2012 and two lecturers were invited at each meeting to give a lecture on the specified theme such as safety assurance in aviation area and chemical plants, and 'safety target of engineering system'. Common or different views on safety assurance between nuclear and other areas were identified, and risk concept and sincere attitude of explaining engineer were mentioned quite important for preparation for beyond expectation and building social credibility. (T. Tanaka)
10 CFR 76.93 - Quality assurance.

Science.gov (United States)

2010-01-01

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

NARCIS (Netherlands)

Stewart, S.; Koornneef, F.; Akselsson, R.; Barton, P.

2009-01-01

Chapter 6: Safety Assurance Process for FRMS - eJcase Implementation The European Commission HILAS project (Human Integration into the Lifecycle of Aviation Systems - a project supported by the European Commission’s 6th Framework between 2005-2009) was focused on using human factors knowledge and
An institutional review board-based clinical research quality assurance program.

Science.gov (United States)

Lad, Pramod M; Dahl, Rebecca

2013-01-01

Despite the acknowledged importance of quality assurance in the clinical research process, the problem of how such a program should be implemented at the level of an academic teaching hospital or a similar institution has not been addressed in the literature. Despite the fact that quality assurance is expected in programs which certify and accredit Institutional Review Boards (IRBs), very little is known about the role of the IRB in programs of clinical research quality assurance. In this article we consider the definition of clinical research quality assurance, and describe a program designed to achieve it. The key elements of such a program are education at the site level, which has both mandatory and voluntary components, and an auditing and monitoring program, which reinforces the education on quality assurance. The role of the IRB in achieving the program goals and the organizational placement of the quality assurance program within the IRB structure and function are important items of discussion.
FURNAS activities in safety and quality assurance

International Nuclear Information System (INIS)

Dezordi, W.L.; Correa Filho, S.M.; Sacco, W.; Morais, L.H.G. de

1980-01-01

The aspects involved in the quality assurance performed by FURNAS for Nuclear Power Plant - Angra Unit I, are shown. Furnas' responsabilities in the licensing regarding reactor safety are also discussed. A summary of the computer codes used in the licensing process is given. (e.G.) [pt
Final Report of the NASA Office of Safety and Mission Assurance Agile Benchmarking Team

Science.gov (United States)

Wetherholt, Martha

2016-01-01

To ensure that the NASA Safety and Mission Assurance (SMA) community remains in a position to perform reliable Software Assurance (SA) on NASAs critical software (SW) systems with the software industry rapidly transitioning from waterfall to Agile processes, Terry Wilcutt, Chief, Safety and Mission Assurance, Office of Safety and Mission Assurance (OSMA) established the Agile Benchmarking Team (ABT). The Team's tasks were: 1. Research background literature on current Agile processes, 2. Perform benchmark activities with other organizations that are involved in software Agile processes to determine best practices, 3. Collect information on Agile-developed systems to enable improvements to the current NASA standards and processes to enhance their ability to perform reliable software assurance on NASA Agile-developed systems, 4. Suggest additional guidance and recommendations for updates to those standards and processes, as needed. The ABT's findings and recommendations for software management, engineering and software assurance are addressed herein.
Department of Energy hazardous waste remedial actions program: Quality assurance program

International Nuclear Information System (INIS)

Horne, T.E.

1988-01-01

This paper describes the Quality Assurance Program developed for the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAP SCO). Key topics discussed include an overview of the HAZWRAP SCO mission and organization, the basic quality assurance program requirements and the requirements for the control of quality for the Department of Energy and Work for Others hazardous waste management programs, and the role of ensuring quality through the project team concept for the management of remedial response actions. The paper focuses on planning for quality assurance for this remedial waste management process from preliminary assessments of remedial sites to feasibility studies. Some observations concerning the control of quality during the implementation of remedial actions are presented. (2 refs.)
Tritium systems test assembly quality assurance program

International Nuclear Information System (INIS)

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

1986-07-01

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

International Nuclear Information System (INIS)

Liddle, P.

2006-01-01

Application software is defined as safety-critical if a fault in the software could prevent the system components from performing their nuclear-safety functions. Therefore, for nuclear-safety systems, the AREVA TELEPERM R XS (TXS) system is classified 1E, as defined in the Inst. of Electrical and Electronics Engineers (IEEE) Std 603-1998. The application software is classified as Software Integrity Level (SIL)-4, as defined in IEEE Std 7-4.3.2-2003. The AREVA NP Inc. Software Program Manual (SPM) describes the measures taken to ensure that the TELEPERM XS application software attains a level of quality commensurate with its importance to safety. The manual also describes how TELEPERM XS correctly performs the required safety functions and conforms to established technical and documentation requirements, conventions, rules, and standards. The program manual covers the requirements definition, detailed design, integration, and test phases for the TELEPERM XS application software, and supporting software created by AREVA NP Inc. The SPM is required for all safety-related TELEPERM XS system applications. The program comprises several basic plans and practices: 1. A Software Quality-Assurance Plan (SQAP) that describes the processes necessary to ensure that the software attains a level of quality commensurate with its importance to safety function. 2. A Software Safety Plan (SSP) that identifies the process to reasonably ensure that safety-critical software performs as intended during all abnormal conditions and events, and does not introduce any new hazards that could jeopardize the health and safety of the public. 3. A Software Verification and Validation (V and V) Plan that describes the method of ensuring the software is in accordance with the requirements. 4. A Software Configuration Management Plan (SCMP) that describes the method of maintaining the software in an identifiable state at all times. 5. A Software Operations and Maintenance Plan (SO and MP) that
Assurance management program for the 30 Nova laser fusion project

International Nuclear Information System (INIS)

Levy, A.J.

1983-01-01

The Nova assurance management program was developed using the quality assurance (QA) approach first implemented at LLNL in early 1978. The LLNL QA program is described as an introduction to the Nova assurance management program. The Nova system is described pictorially through the Nova configuration, subsystems and major components, interjecting the QA techniques which are being pragmatically used to assure the successful completion of the project
Changing the Safety and Mission Assurance (S and MA) Paradigm

Science.gov (United States)

Malone, Roy W.; Safie, Fayssal M.

2010-01-01

This slide presentation reviews the change in the work and impact of the Safety and Mission Assurance directorate at Marshall Space Flight Center. It reviews the background and the reasons given for a strong Safety & Mission Assurance presence in all planning for space flight. This was pointed out by the Rogers Commission Report after the Space Challenger accident, by the Columbia Accident Investigation Board (CAIB) and by a 2006 NASA Exploration Safety Study (NESS) Team. The overall objective of the work in this area was to improve and maintain S&MA expertise and skills. Training for this work was improved and the S&MA organization was reorganized. This has resulted in a paradigm shift for NASA's safety efforts, which is described. The presentation then reviews the impact of the new S&MA work in the Ares I design and development.
National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B
German Light-Water-Reactor Safety-Research Program

International Nuclear Information System (INIS)

Seipel, H.G.; Lummerzheim, D.; Rittig, D.

1977-01-01

The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments
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
A quality assurance program for ancillary high technology devices on a dual-energy accelerator

International Nuclear Information System (INIS)

Klein, Eric E.; Low, Daniel A.; Maag, Derek; Purdy, James A.

1996-01-01

Our facility has added high-technology ancillary devices to our dual-energy linear accelerator. After commissioning and acceptance testing of dual asymmetric jaws, dynamic wedge, portal imaging, and multileaf collimation (MLC), quality assurance programs were instituted. The programs were designed to be both periodic and patient specific when required. In addition, when dosimetric aspects were affected by these technologies, additional quality assurance checks were added. Positional accuracy checks (light and radiation) are done for both asymmetric jaws and MLC. Each patient MLC field is checked against the original simulation or digitally reconstructed radiographs. Off-axis factors and output checks are performed for asymmetric fields. Dynamic wedge transmission factors and profiles are checked periodically, and a patient diode check is performed for every new dynamic wedge portal. On-line imaging checks encompass safety checks along with periodic measurement of contrast and spatial resolution. The most important quality assurance activity is the annual review of proper operation and procedures for each device. Our programs have been successful in avoiding patient-related errors or device malfunctions. The programs are a team effort involving physicists, maintenance engineers, and therapists
Quality assurance programs from laboratories offering radiological protection services

International Nuclear Information System (INIS)

Marrero Garcia, M.; Prendes Alonso, M.; Jova Sed, L.; Morales Monzon, J.A.

1998-01-01

The implementation of an adequate program for quality assurance in institutions servicing radiological protection programs will become an additional tool to achieve security targets included in that program. All scientific and technical services offered by CPHR employ quality assurance systems

Commercial Crew Program Crew Safety Strategy

Science.gov (United States)

Vassberg, Nathan; Stover, Billy

2015-01-01

The purpose of this presentation is to explain to our international partners (ESA and JAXA) how NASA is implementing crew safety onto our commercial partners under the Commercial Crew Program. It will show them the overall strategy of 1) how crew safety boundaries have been established; 2) how Human Rating requirements have been flown down into programmatic requirements and over into contracts and partner requirements; 3) how CCP SMA has assessed CCP Certification and CoFR strategies against Shuttle baselines; 4) Discuss how Risk Based Assessment (RBA) and Shared Assurance is used to accomplish these strategies.
Quality assurance in the nuclear test program

International Nuclear Information System (INIS)

Shearer, J.N.

1979-01-01

In February 1979 Test Program laid the ground work for a new quality assurance structure. The new approach was based on the findings and recommendations of the Ad Hoc QA Program Review panel, which are summarized in this report. The new structure places the responsibility for quality assurance in the hands of the line organizations, both in the programmatic and functional elements of the LLL matrix
Software Quality Assurance for Nuclear Safety Systems

International Nuclear Information System (INIS)

Sparkman, D R; Lagdon, R

2004-01-01

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

International Nuclear Information System (INIS)

2006-12-01

Recently in Japan, introduction of nuclear safety regulations using risk information such as probabilistic safety assessment (PSA) has been considered and utilization of risk information in the rational and practical measures on safety assurance has made a progress to start with the operation or inspection area. The report compiled results of investigation and studies of PSA quality assurance in risk-informed activities in the USA. Relevant regulatory guide and standard review plan as well as issues and recommendations were reviewed for technical adequacy and advancement of probabilistic risk assessment technology in risk-informed decision making. Useful and important information to be referred as issues in PSA quality assurance was identified. (T. Tanaka)
Food safety and quality assurance : foods of animal origin

National Research Council Canada - National Science Library

Hughes, Keith L; Hinton, Michael H; Hubbert, William T; Hagstad, Harry V; Spangler, Elizabeth

1996-01-01

The second edition of Food Safety and Quality Assurance is a basic reference for veterinarians, extension specialists, and others who help food-animal producers throughout the food chain to provide...
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
Design reliability assurance program for Korean next generation reactor

International Nuclear Information System (INIS)

Lee, Beom-Su; Han, Jin-Kyu; Na, Jang Hwan; Yoo, Kyung Yeong

1997-01-01

The Korean Next Generation Reactor (KNGR) project is to develop standardized nuclear power plant design for the construction of future nuclear power plants in Korea. The main purpose of the KNGR project is to develop the advanced nuclear power plants, which enhance safety and economics significantly through the incorporation of design concepts for severe accident prevention and mitigation, supplementary passive safety concept, simplification and application of modularization and so on. For those, Probabilistic Safety Assessment (PSA) and availability study will be performed at the early stage of the design, and the Design Reliability Assurance Program (D-RAP) is applied in the development of the KNGR to ensure that the safety and availability evaluated in the PSA and availability study at the early phase of the design is maintained through the detailed design, construction, procurement and operation of the plants. This paper presents the D-RAP concept that could be applied at the stage of the basic design of the nuclear power plants, based on the models for the reference plants and/or similar plants. 4 refs., 1 fig
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
Overview of the Hanford Site Performance Assurance Program

International Nuclear Information System (INIS)

Duncan, M.R.; Billings, M.P.; Delvin, W.L.; Scott, D.D.; Weatherby, J.W.

1991-01-01

This paper reports on a safeguards and security performance assurance program which encompasses the routine and special activities carried out to assure that safeguards and security subsystems and components are operating in a effective and reliable manner. At the Hanford Site, performance assurance involves widely varied activities, e.g., force-on-force exercises, functional testing of security components, and limited scope performance testing of material control and accountability subsystems. These activities belong to one of four categories: performance testing, functional testing, inspection, and preventive maintenance. Using categories has aided in identifying and assessing the relevant contribution each activity makes to the performance assurance program. Efforts have progressed toward incorporating performance assurance activities into the assessment of protection effectiveness required for Master Safeguards and Security Agreement development and its associated verification and validation process
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)
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)
Code of practice on quality assurance for safety in nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The code sets forth the management principles and objectives to be met during the implementation of activities in different phases of the nuclear power plants (NPPs) for assuring safety. It is intended for use by organisations and individuals responsible for safety related functions in design, manufacturing, construction, commissioning, operation and decommissioning of NPPs. It covers the functions of management, performance, verification and corrective action. It also deals with the quality assurance records. (M.G.B.)
Quality assurance for safety in the radioactive waste management: a quality assurance system in Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Petrova, A.; Kolev, I.

2000-01-01

Novi Han Radioactive Waste Repository (RWR) is still the only place in Bulgaria for storage of low and intermediate level radioactive waste. It is necessary to establish and maintain a Quality Assurance (QA) system to ensure that the RWR can be operated safely with regard to the health and safety of the general public and site personnel. A QA system has to establish the basic requirements for quality assurance in order to enhance nuclear safety by continuously improving the methods employed to achieve quality. It is envisaged that the QA system for the Novi Han RWR will cover the operation and maintenance of the radioactive waste disposal facilities, the radiation protection and monitoring of the site, as well as the scientific and technology development aspects. The functions of the Novi Han RWR presume the availability of an environmental management system. It is appropriate to establish a QA system based on the requirements of the ISO Standards 9001 and 14000, using the recommendations of the IAEA (Quality assurance for safety in NPPs and other nuclear installations, code and safety guides Q1-Q14). (authors)
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)
One complex tool and three simple approaches to the improvement of quality assurance and safety in external beam radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Salinas, F.; Sansogne, R.; Arbiser, S.; Suarez, V., E-mail: flavio.salinas@rtp.com.ar [Vidt Centro Medico (Argentina); Franco, M., E-mail: mauricio.franco@rtp.com.ar [Centro de Radioterapia San Juan (Argentina); Escobar, J., E-mail: jorge.escobar@iprc.com.ar [Instituto Privado de Radioterapia Cuyo, Buenos Aires (Argentina)

2013-10-01

Quality assurance and safety controls in radiation therapy delivery processes that involve the Physics Department of an institution are commonly time consuming tasks. Carrying out daily controls in very busy clinics without compromising patient schedule is challenging. This work describes the usage of Electronic Portal Imaging Devices in combination with some in-house software to simplify and systematize three different tasks of the Physics Department Quality Assurance Program, improving the easiness, reliability and velocity of daily tests. (author)
One complex tool and three simple approaches to the improvement of quality assurance and safety in external beam radiotherapy

International Nuclear Information System (INIS)

Salinas, F.; Sansogne, R.; Arbiser, S.; Suarez, V.; Franco, M.; Escobar, J.

2013-01-01

Quality assurance and safety controls in radiation therapy delivery processes that involve the Physics Department of an institution are commonly time consuming tasks. Carrying out daily controls in very busy clinics without compromising patient schedule is challenging. This work describes the usage of Electronic Portal Imaging Devices in combination with some in-house software to simplify and systematize three different tasks of the Physics Department Quality Assurance Program, improving the easiness, reliability and velocity of daily tests. (author)
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.
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
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
An augmented audit program for assuring radiation safety during radiographic examination operations

International Nuclear Information System (INIS)

Jervey, R.A. Jr.; Papin, P.J.

1993-01-01

Auditing a gamma radiography program is required as part of the authorizing license. Checklists and cursory reviews are the typical approach to addressing program requirements. A more proactive approach is recommended. The audit program described was prepared for a specific set of operating conditions but can be applied to any given program. Improvements in the effectiveness of the radiography safety program can be made with additional examination and emphasis on direct observation of licensed activities

30 CFR 250.806 - Safety and pollution prevention equipment quality assurance requirements.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Safety and pollution prevention equipment... Gas Production Safety Systems § 250.806 Safety and pollution prevention equipment quality assurance... install only certified safety and pollution prevention equipment (SPPE) in wells located on the OCS. SPPE...
National Program of Quality Assurance in Radiotherapy in Cuba

International Nuclear Information System (INIS)

Alonso Samper, J. L.; Dominguez Hung, L.; Morales Lopez, J. L.; Alfonso Laguardia, R.; Garcia Yip, F.

2001-01-01

It tries on the establishment of a Quality Assurance Nacional System, a Quality Assurance Committee implemented in Cuba, and a Quality Auditory National Program implemented in Cuba to control and assure radiotherapy quality
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
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
Development of a Reliability Program approach to assuring operational nuclear safety

International Nuclear Information System (INIS)

Mueller, C.J.; Bezella, W.A.

1985-01-01

A Reliability Program (RP) model based on proven reliability techniques used in other high technology industries is being formulated for potential application in the nuclear power industry. Research findings are discussed. The reliability methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed with several reliability concepts (e.g., quantitative reliability goals, reliability centered maintenance) appearing to be directly transferable. Other tasks in the RP development effort involved the benchmarking and evaluation of the existing nuclear regulations and practices relevant to safety/reliability integration. A review of current risk-dominant issues was also conducted using results from existing probabilistic risk assessment studies. The ongoing RP development tasks have concentrated on defining a RP for the operating phase of a nuclear plant's lifecycle. The RP approach incorporates safety systems risk/reliability analysis and performance monitoring activities with dedicated tasks that integrate these activities with operating, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the RP
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
Assurance program for remedial action (APRA) microcomputer-operated bibliography management system

International Nuclear Information System (INIS)

Stenner, R.D.; Washburn, D.K.; Denham, D.H.

1985-10-01

Pacific Northwest Laboratory (PNL) provided technical assistance to the Office of Operational Safety (OOS) in developing their Assurance Program for Remedial Action (APRA). The APRA Bibliography Management System (BMS), a microcomputer-operated system designed to file, locate and retrieve project-specific bibliographic data, was developed to manage the documentation associated with APRA. The BMS uses APRABASE, a PNL-developed computer program written in dBASE II language, which is designed to operate using the commercially available dBASE II database software. The paper describes the APRABASE computer program, its associated subprograms, and the dBASE II APRA file. Although the BMS was designed to manage APRA-associated documents, it could be easily adapted for use in handling bibliographic data associated with any project
Assurance Program for Remedial Action (APRA) microcomputer-operated bibliography management system

International Nuclear Information System (INIS)

Stenner, R.D.; Washburn, D.K.; Denham, D.H.

1986-01-01

Pacific Northwest Laboratory (PNL) provided technical assistance to the Office of Operational Safety (OOS) in developing their Assurance Program for Remedial Action (APRA). The APRA Bibliography Management System (BMS), a microcomputer-operated system designed to file, locate and retrieve project-specific bibliographic data, was developed to manage the documentation associated with APRA. The BMS uses APRABASE, a PNL-developed computer program written in dBASE II/sup (b)/ language, which is designed to operate using the commercially available dBASE II database software. This paper describes the APRABASE computer program, its associated subprograms, and the dBASE II APRA file. Although the BMS was designed to manage APRA-associated documents, it could be easily adapted for use in handling bibliographic data associated with any project
Safety program of the Oak Ridge National Laboratory: a different approach

International Nuclear Information System (INIS)

Burger, G.H.

1981-01-01

The uniqueness and therefore different approach to Oak Ridge National Laboratory's safety program is not a result of elimination of the usual industrial safety organization, but results from the three organizations which supplement it and the areas of safety concerns that they cover. While industrial safety is primarily concerned with day-to-day routine worker activities (wearing of safety glasses and hard hats, adherence to electrical safety work procedures, proper safety lockout and tagout of equipment for maintenance activities, etc.), the other organizations, the Office of Operational Safety, Division Safety Officers and Radiation Control Officers, and the Laboratory director's Review Committees, are concerned with themuch broader spectrum of the total work environment. These organizations are concerned not only with the day-to-day worker activities but the design and conduction of all operations from a process viewpoint. The emphasis of these groups is assuring first that operations, experiments, facilities, etc., are designed properly and then secondly operated properly to assure safety of the operators, Laboratory population, and the public. Responsibilities of the three safety organizations constituting operational or process safety are described and discussed
Quality Assurance Program Description

Energy Technology Data Exchange (ETDEWEB)

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

2017-07-01

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

Directory of Open Access Journals (Sweden)

Kirti Tyagi

2014-01-01

Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.
Measurement assurance program for LSC analyses of tritium samples

International Nuclear Information System (INIS)

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

1997-01-01

Liquid Scintillation Counting (LSC) for Tritium is done on 600 to 800 samples daily as part of a contamination control program at the Savannah River Site's Tritium Facilities. The tritium results from the LSCs are used: to release items as radiologically clean; to establish radiological control measures for workers; and to characterize waste. The following is a list of the sample matrices that are analyzed for tritium: filter paper smears, aqueous, oil, oily rags, ethylene glycol, ethyl alcohol, freon and mercury. Routine and special causes of variation in standards, counting equipment, environment, operators, counting times, samples, activity levels, etc. produce uncertainty in the LSC measurements. A comprehensive analytical process measurement assurance program such as JTIPMAP trademark has been implemented. The process measurement assurance program is being used to quantify and control many of the sources of variation and provide accurate estimates of the overall measurement uncertainty associated with the LSC measurements. The paper will describe LSC operations, process improvements, quality control and quality assurance programs along with future improvements associated with the implementation of the process measurement assurance program
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
Assuring nuclear safety competence into the 21. century

International Nuclear Information System (INIS)

2000-01-01

Irrespective of current views on the future of nuclear power programmes, concerns are arising with respect to the long-term ability to preserve safety competence because student enrollments in nuclear engineering are decreasing rapidly and experienced staff are reaching retirement age. 'Assuring Nuclear Safety Competence into the 21. Century' was discussed in depth by workshop participants. The need for a long-term strategic view was emphasised, and policy recommendations were made. These proceedings will be of particular interest to those playing a policy role in the nuclear industry, regulatory bodies and the education sector. (author)
Safety and Mission Assurance Knowledge Management Retention

Science.gov (United States)

Johnson, Teresa A.

2006-01-01

This viewgraph presentation reviews the issues surrounding the management of knowledge in regards to safety and mission assurance. The JSC workers who were hired in the 1960's are slated to retire in the next two to three years. The experiences and knowledge of these NASA workers must be identified, and disseminated. This paper reviews some of the strategies that the S&MA is developing to capture that valuable institutional knowledge.
Implementation of radiation safety program in a medical institution

International Nuclear Information System (INIS)

Palanca, Elena D.

1999-01-01

A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and
Army Programs: Army Finance and Accounting Quality Assurance Program

National Research Council Canada - National Science Library

1988-01-01

This regulation discusses the primary responsibilities of commanders and staff officers at installation and higher levels for execution of the Army Finance and Accounting Quality Assurance (QA) Program...
Improving safety of personnel exposed to disinfectants by introducing an Endoscopy Quality Assurance Program

OpenAIRE

Ahmed Gado; Basel Ebeid; Aida Abdelmohsen; Anthony Axon

2014-01-01

Background: Chemical disinfection is the most commonly used method in gastrointestinal endoscopy reprocessing. The main problem with chemical disinfection is that it is potentially harmful to humans. Risk assessment of employees using toxic substances is recommended and the control of exposure to these substances is required. In 2003, an endoscopy quality-assurance program was instituted in a secondary care governmental hospital in Egypt. Aim: The aim of the study was to assess the risk to...
Quality assurance program. Topical report, GIBSAR-7

International Nuclear Information System (INIS)

1975-09-01

The quality assurance program developed by Gibbs and Hill to satisfy the requirement that design, engineering, procurement, fabrication, and construction activities for nuclear power plants are performed in accordance with applicable codes, standards, and regulatory criteria is outlined. The program was developed to conform to the criteria of Appendix B to 10 CFR Part 50 and is presented in such a manner that each of the 18 criteria are individually set forth. The Gibbs and Hill program, implemented by the procedures of the corporate Quality Assurance Manual also follows the guidelines of the NRC Gray Book, WASH 1283, Rev. 1, May 24, 1974, and Green Book, WASH 1309, May 10, 1974. (auth)

The quality assurance program at K & S

Energy Technology Data Exchange (ETDEWEB)

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

1993-12-31

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

International Nuclear Information System (INIS)

Kmetyuk, Ya.V.; Radosh, H.V.; Bezshyyko, O.A.; Golinka-Bezshyyko, L.O.; Kadenko, I.M.; Kazinova, O.A.; Nagai, A.O.

2012-01-01

Scientific studies, clinical experience and economic analysis have shown that the positron emission tomography (PET) is clinically and cost effective cancer diagnostics method. Combined PET and computed tomography (PET/CT) has proven clinical utility, particularly in the diagnosis, staging or restaging malignant disease and metastases, surgical planning, radiation therapy planning and evaluation of treatment response. The use of PET/CT has grown substantially in the past few years, with an increasing number of hospitals and installations of PET/CT imaging centers each year. In the same time combination of 2 procedures, each of which impart a radiation dose and, as a result, increases the deleterious influence for health, creates additional radiation safety issues. In these conditions the role of quality assurance (QA) and quality control (QC) programs is getting more and more important. We considered main QA and radiation safety requirements for whole PET technology chain from radio-pharmacy facilities to PET/CT scanning and patient release criteria. All these issues were considered and assessed having the example of PET facilities and technology chain of All-Ukrainian Center for Radiosurgery of the Clinical Hospital 'Feofania'
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
Summary report of the Department of Energy, Division of Operational and Environmental Safety: Quality Assurance Programs 1 through 4

International Nuclear Information System (INIS)

Welford, G.A.; Fisenne, I.M.; Sanderson, C.

1978-01-01

Analytical Laboratories which provide environmental monitoring data for assessment of radioactive contamination, under the Department of Energy (DOE) Contract, were requested to participate in a Quality Assurance Program. The Environmental Measurements Laboratory (EML) was asked to prepare intercomparison samples for radionuclide analysis of soil, water, air filters, tissue ash, and vegetation ash for distribution to the Analytical Laboratories. Samples were collected in the environment of DOE facilities, since only water and air samples could be conveniently spiked. A set of 6 to 8 samples is distributed quarterly to about 28 laboratories. EML performed multiple analyses on the samples, however, the results are considered intercomparisons not standards. This report summarizes the program and evaluates the data for Quality Assurance Programs (QAP) from 1 through 4
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
Quality assurance in the measurement of internal radioactive contamination and dose assessment and the United States Department of Energy Laboratory Accreditation Program

International Nuclear Information System (INIS)

Bhatt, Anita

2016-01-01

The Quality Assurance for analytical measurement of internal radioactive contamination and dose assessment in the United States (US) is achieved through the US Department of Energy (DOE) Laboratory Accreditation Program (DOELAP) for both Dosimetry and Radio bioassay laboratories for approximately 150,000 radiation workers. This presentation will explain the link between Quality Assurance and the DOELAP Accreditation process. DOELAP is a DOE complex-wide safety program that ensures the quality of worker radiation protection programs. DOELAP tests the ability of laboratories to accurately measure and quantify radiation dose to workers and assures the laboratories quality systems are capable of defending and sustaining their measurement results. The United States Law in Title 10 of the Code of Federal Regulations 835 requires that personnel Dosimetry and Radio bioassay programs be tested and accredited
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
Radiation safety and quality control assurance in X-ray diagnostics 1998

International Nuclear Information System (INIS)

Servomaa, A.

1998-03-01

The report is based on a seminar course of lectures 'Radiation safety and quality assurance in X-ray diagnostics 1998' organized by the Radiation and Nuclear Safety Authority (STUK) in Finland. The lectures included actual information on X-ray examinations: methods of quality assurance, methods of measuring and calculating patient doses, examination frequencies, patient doses, occupational doses, and radiation risks. Paediatric X-ray examinations and interventional procedures were the most specific topics. The new Council Directive 97/43/Euratom on medical exposure, and the European Guidelines on quality criteria for diagnostic radiographic images, were discussed in several lectures. Lectures on general radiation threats and preparedness, examples of radiation accidents, and emergency preparedness in hospitals were also included. (editor)
Unilever food safety assurance system for refined vegetable oils and fats

Directory of Open Access Journals (Sweden)

van Duijn Gerrit

2010-03-01

Full Text Available The Unilever Food Safety Assurance system for refined oils and fats is based on risk assessments for the presence of contaminants or pesticide residues in crude oils, and refining process studies to validate the removal of these components. Crude oil risk assessments were carried out by combining supply chain visits, and analyses of the contaminant and pesticide residue levels in a large number of crude oil samples. Contaminants like poly-aromatic hydrocarbons and hydrocarbons of mineral origin, and pesticide residues can largely be removed by refining. For many years, this Food Safety Assurance System has proven to be effective in controlling contaminant levels in refined vegetable oils and fats.
New Paradigm in Nuclear Safety from Quality Assurance to Safety Management System

International Nuclear Information System (INIS)

Lim, Nam-Jin; Park, Chan-Gook; Nam, Ji-Hee; Kim, Kwan-Hyun; Kwon, Hyuk-il; Lee, Young-Gun Lee

2006-01-01

The initial concept of Quality Control (QC) controlling the quality of products is now evolving toward the Management System (MS) achieving safety, through Quality Assurance (QA) ensuring the quality of products and Quality Management (QM) managing the quality by a systematic approach. Nuclear safety can be achieved through an integrated MS that ensures the health, environmental, security, quality and economic requirements being considered together with nuclear safety requirements. MS approach is developed through realizing that most of nuclear accidents had occurred not by the malfunction of hardware or equipment, but by the human error. The MS is a set of inter-related or interacting elements (system) that establishes policies and objectives and which enables those objectives to be achieved in an efficient and effective way
Assuring future competence in nuclear safety in Finland

International Nuclear Information System (INIS)

Koskinen, K.

2004-01-01

Full text: Background: Within last few years we have been faced the fact that ageing of experts in nuclear safety field cannot be ignored in Finland. A great number of all experts/specialists with special competence on nuclear safety studied in the early 70's and had their first permanent jobs in the 'golden era' of nuclear power. These experts are going to retire within next ten years. Therefore both the regulatory body and licensees in Finland have the situation where the age distribution of staff member has become distorted. Also the amount of students in universities which have nuclear technology as their major subject has diminished remarkably until the decision of the new nuclear power plant unit in Finland was made in May 2001. After that the amount of students has risen. Assuring competences within the regulatory body STUK adopted the systematic approach to training in early 90's, this method is widely presented in IAEA TECDOC 1254 (2001). However, the very low turnover of staff led to decrease of training needs and therefore also the systematic training efforts decreased. In 2001 a need to restart the systematic approach to assuring competences was identified. To improve competence management at the regulatory body a competence analysis was carried out and a human resource plan for nuclear safety area for the near future was made. Competence analysis is a method which is quite commonly used on public sector and governmental organisations in Finland. STUK studied carefully the models used in other public sector organisations and adjusted the method to its own purposes. The model used has four competence categories: substance related, management skills, common working skills and STUK related working skills. Substance related competences were defined and described at working unit level. Descriptions for the rest three categories were made at STUK level and those were common for all departments. Substance related competencies common to all working at the
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)
Krsko NPP Quality Assurance Plan Application to Nuclear Safety Upgrade Projects (PCFV System and PAR System)

International Nuclear Information System (INIS)

Biscan, Romeo; Fifnja, Igor

2014-01-01

Nuklearna Elektrarna Krsko (NEK) has undertaken Nuclear Safety Upgrade Projects as a safety improvement driven by the lessons learned from the Fukushima-Daiichi Accident. Among other projects, new modification 1008-VA-L Passive Containment Filtered Vent (PCFV) System has been installed which acts as the last barrier minimizing the release of radioactive material into the environment in case of failure of all safety systems, and to insure containment integrity during beyond design basis accidents (BDBA). In addition, modification 1002-GH-L Severe Accident Hydrogen Control System (PAR) has been implemented to prevent and mitigate the consequences of explosive gas generation (hydrogen and carbon monoxide) in case of reactor core melting. To ensure containment integrity for all design basis accidents (DBA) and BDBA conditions, NEK has eliminated existing safety-related electrical recombiners, replaced them with two safety-related passive autocatalytic recombiners (PARs) and added 20 new PARs designed for the BDBA conditions. Krsko NPP Quality Assurance Plan has been applied to Nuclear Safety Upgrade Projects (PCFV System and PAR System) through the following activities: · Internal audit of modification process was performed. · Supplier audits were performed to evaluate QA program efficiency of the main design organization and engineering organizations. · Evaluation and approval of Suppliers were performed. · QA engineer was involved in the review and approval of 1008-VA-L and 1002-GH-L modification documentation (Conceptual Design Package, Design Modification Package, Installation Package, Field Design Change Request, Problem/Deficiency Report, and Final Documentation Package). · Purchasing documentation for modifications 1008-VA-L and 1002-GH-L (technical specifications, purchase orders) has been verified and approved by QA. · QA and QC engineers were involved in oversight of production and testing of the new 1008-VA-L and 1002-GH-L plant components. �
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
Quality assurance program for prototype stereotactic system developed for neptun 10 Pc linac

International Nuclear Information System (INIS)

Khoshbin Khoshnazar, A.R.; Bahreyni Toossi, M.T.; Hashemiyan, A.R.; Bahreyni Toossi, M.T.; Salek, R.

2005-01-01

A prototype stereotactic radiosurgery set was designed and constructed for a Neptun 10 Pc linac that is currently being used at Imam Reza hospital in Mashad. Materials and Methods: A complete quality assurance program was designed and performed for the constructed system including isocentric accuracy test, localization accuracy test, dose delivery accuracy test and leakage radiation test. Target simulator, control alignment device and plexiglass phantom which were parts of the developed hardware were used to fulfill quality assurance program. Results: The average isocentric shift resulted from the gantry rotation and couch turning were respectively obtained to be 1.4 and 2 mm. The average localization error in the three coordinates was found to be 2.2 mm. The total treatment uncertainty due to all of the probable errors in the system was equal to 4.32 mm. The dose delivery accuracy test was carried out, the result indicated a 3.7% difference between the given and measured dose. Conclusion: The quality assurance tests showed consistent performance of the constructed system within the accepted limits; however, some inconsistency might exist in certain cases. The safety of stereotactic radiosurgery system method is increased when the overall uncertainty is minimized nd the treatment of the lesions adjacent to critical organs is avoided
Quality Assurance program plan - plutonium stabilization and handling project W-460

International Nuclear Information System (INIS)

SCHULTZ, J.W.

1999-01-01

This Quality Assurance Program Plan (QAPP) identifies Project Quality Assurance (QA) program requirements for all parties participating in the design, procurement, demolition, construction, installation, inspection and testing for Project W-460
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
Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability

International Nuclear Information System (INIS)

1978-01-01

The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program made up of reliability prediction analysis, failure mode analysis and criticality analysis
Call for NDT leadership role in assuring safety of nuclear power

International Nuclear Information System (INIS)

Anders, W.A.; Simpson, J.W.

1976-01-01

Nondestructive Testing and its potential role in assuring the safety of nuclear power were given emphasis at a conference on Nondestructive Testing in the Nuclear Industry sponsored by the American Society for Metals Dec. 1--3 in Denver, Colo. Excerpts from two major addresses challenging the NDT community to assume leadership in solving nuclear safety problems are presented
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

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).
Safer electronic health records safety assurance factors for EHR resilience

CERN Document Server

Sittig, Dean F

2015-01-01

This important volume provide a one-stop resource on the SAFER Guides along with the guides themselves and information on their use, development, and evaluation. The Safety Assurance Factors for EHR Resilience (SAFER) guides, developed by the editors of this book, identify recommended practices to optimize the safety and safe use of electronic health records (EHRs). These guides are designed to help organizations self-assess the safety and effectiveness of their EHR implementations, identify specific areas of vulnerability, and change their cultures and practices to mitigate risks.This book pr
An Application Example Analysis of Quality Assurance Program for STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Project

International Nuclear Information System (INIS)

Jung, Minhwan; Gam, Dayoung; Eoh, Jae-Hyuk; Jeong, Ji-Young

2015-01-01

KAERI has been conducting various basic R and D activities in the field of nuclear technology. In addition, KAERI is now participating in the Generation IV International Forum (GIF), preparing for the development of key technologies for Generation IV nuclear energy system, including Sodium cooled Fast Reactor (SFR) development. All of the key technologies for SFR development need an appropriate level of QA activities to achieve the GIF safety and performance objectives. Therefore, QA activities have been conducted as an essential part of the national SFR project. As a result, QAM (Quality Assurance Manual) and QAP (Quality Assurance Procedures) have been developed for the SFR project, which are based on ASME NQA-1, KEPIC QAP and the GIF Quality Management System Guidelines. In this work, the introduction background and application examples of the QA program for the STELLA project were investigated. Application of the QA for the STELLA project has great significance because the QA has been mainly applied for the nuclear power plant area in operation, which helps ensure the reliability of the test data and completeness of the research performance. Nevertheless, developing more appropriate QA procedures remains a major task because some parts of them are not applicable to the Na-experiment
An Application Example Analysis of Quality Assurance Program for STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) Project

Energy Technology Data Exchange (ETDEWEB)

Jung, Minhwan; Gam, Dayoung; Eoh, Jae-Hyuk; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

KAERI has been conducting various basic R and D activities in the field of nuclear technology. In addition, KAERI is now participating in the Generation IV International Forum (GIF), preparing for the development of key technologies for Generation IV nuclear energy system, including Sodium cooled Fast Reactor (SFR) development. All of the key technologies for SFR development need an appropriate level of QA activities to achieve the GIF safety and performance objectives. Therefore, QA activities have been conducted as an essential part of the national SFR project. As a result, QAM (Quality Assurance Manual) and QAP (Quality Assurance Procedures) have been developed for the SFR project, which are based on ASME NQA-1, KEPIC QAP and the GIF Quality Management System Guidelines. In this work, the introduction background and application examples of the QA program for the STELLA project were investigated. Application of the QA for the STELLA project has great significance because the QA has been mainly applied for the nuclear power plant area in operation, which helps ensure the reliability of the test data and completeness of the research performance. Nevertheless, developing more appropriate QA procedures remains a major task because some parts of them are not applicable to the Na-experiment.
Water reactor safety research program. A description of current and planned research

International Nuclear Information System (INIS)

1978-07-01

The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described
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
Independent oversight review of the Department of Energy Quality Assurance Program for suspect/counterfeit parts. Revision 1

International Nuclear Information System (INIS)

1996-05-01

To address the potential threat that suspect/counterfeit parts could pose to DOE workers and the public, the Office of the Deputy Assistant Secretary for Oversight initiated a number of activities beginning in mid-1995. Oversight placed increased emphasis on the field's quality assurance-suspect/counterfeit parts programs during safety management evaluations, in keeping with the Office of Environment, Safety and Health (EH) oversight responsibilities, which include oversight of the Department's quality assurance (QA) programs. In addition, Oversight reviewed relevant policy documents and occurrence reports to determine the nature and magnitude of the problem within the Department. The results of that review, contained in an Office of Oversight report, Independent Oversight Analysis of Suspect/Counterfeit Parts Within the Department of Energy (November 1995), indicate a lack of consistency and comprehensiveness in the Department's QA-suspect/counterfeit parts program. A detailed analysis of the causes and impacts of the problem was recommended. In response, this review was initiated to determine the effectiveness of the Department's QA program for suspect/counterfeit parts. This study goes beyond merely assessing and reporting the status of the program, however. It is the authors intention to highlight the complex issues associated with suspect/counterfeit parts in the Department today and to present approaches that DOE managers might consider to address these issues
Independent oversight review of the Department of Energy Quality Assurance Program for suspect/counterfeit parts. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

To address the potential threat that suspect/counterfeit parts could pose to DOE workers and the public, the Office of the Deputy Assistant Secretary for Oversight initiated a number of activities beginning in mid-1995. Oversight placed increased emphasis on the field`s quality assurance-suspect/counterfeit parts programs during safety management evaluations, in keeping with the Office of Environment, Safety and Health (EH) oversight responsibilities, which include oversight of the Department`s quality assurance (QA) programs. In addition, Oversight reviewed relevant policy documents and occurrence reports to determine the nature and magnitude of the problem within the Department. The results of that review, contained in an Office of Oversight report, Independent Oversight Analysis of Suspect/Counterfeit Parts Within the Department of Energy (November 1995), indicate a lack of consistency and comprehensiveness in the Department`s QA-suspect/counterfeit parts program. A detailed analysis of the causes and impacts of the problem was recommended. In response, this review was initiated to determine the effectiveness of the Department`s QA program for suspect/counterfeit parts. This study goes beyond merely assessing and reporting the status of the program, however. It is the authors intention to highlight the complex issues associated with suspect/counterfeit parts in the Department today and to present approaches that DOE managers might consider to address these issues.
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.
Nuclear reactor safety program in US department of energy and future perspectives

International Nuclear Information System (INIS)

Song, Y.T.

1988-01-01

The US Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and implement DOE orders. Teams of experts in the Department, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The Application of artificial intelligence technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs
Nevada Nuclear Waste Storage Investigations Quality-Assurance Program Plan: management and overview

International Nuclear Information System (INIS)

1981-10-01

This Quality Assurance Program Plan (QAPP) defines the quality assurance program in effect for those activities of the Nevada Nuclear Waste Storage (NNWSI) that are directly controlled by: DOE/NV, the Technical Overview Contractor, and the Quality Assurance Overview Contractor. It is intended as a supplement to the NNWSI-QAP
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
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
Measurement assurance program for FTIR analyses of deuterium oxide samples

International Nuclear Information System (INIS)

Johnson, S.R.; Clark, J.P.

1997-01-01

Analytical chemistry measurements require an installed criterion based assessment program to identify and control sources of error. This program should also gauge the uncertainty about the data. A self- assessment was performed of long established quality control practices against the characteristics of a comprehensive measurement assurance program. Opportunities for improvement were identified. This paper discusses the efforts to transform quality control practices into a complete measurement assurance program. The resulting program heightened the laboratory's confidence in the data it generated, by providing real-time statistical information to control and determine measurement quality
NRC assessment of the high-level waste repository quality assurance program

International Nuclear Information System (INIS)

Kennedy, J.E.

1987-01-01

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

International Nuclear Information System (INIS)

Alvarez Buergo, L. de; Santoma Juncadella, L.

1977-01-01

One condition which must be fulfilled in order for a nucleoelectric station to be successfully introduced, in countries being developed, is to define and structure the necessary organizations which will carry out the programs and insure that the stations be reliable, safe and economical. The two basic organizations which should be defined and structured are: a) The Government organization, whose objective is to insure the health and safety of the public, by means of evaluation, revision and control of the projects and their future operation; and b) The Project Management organization, whose objective is to select the site and the prototype of the station to be installed as well as carry out the project in such a way that the stations produce the expected amount of energy at a competitive kwh price and so that the operation does not create undue or unacceptable risks for the public. The importance of the quality assurance on the job is analyzed to achieve the indicated objectives, specific missions are defined and the quality assurance is presented as the link between the binomial National Participation-Quality Demands. The Spanish experience, referring to the application of quality in its present nuclear program with about 6500 Mwe in the construction stage and another 15.000 Mwe in various study and contracting stages, is also analyzed [es
The quality assurance program at K ampersand S

International Nuclear Information System (INIS)

Slowey, T.W.

1993-01-01

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

Science.gov (United States)

Struhar, Paul T., Jr.

2004-01-01

The Safety and Assurance Directorate (SAAD) has a vision. The vision is to be an essential part of NASA Glenn's journey to excellence. SAAD is in charge of leading safety, security, and quality and is important to our customers. When it comes to programmatic and technical decision making and implementation, SAAD provides clear safety, reliability, maintainable, quality assurance and security. I worked on a couple different things during my internship with Sandra Hardy. I did a lot of logistics for meeting and trips. I helped run the budget for the SAAD directorate. I also worked with Rich Miller for one week and we took water samples and ran tests. We also calibrated the different equipment. There is a lot more to meetings than people see. I did one for a retirement party. I had to get work orders and set up the facilities where the event is going to take place. I also set up a trip to Plum Brook Station. I had to order vans and talk with the people up there to see when a good time was. I also had to make invitations and coordinate everything. I also help Sandy run the numbers in the budget. We use excel to do this, which makes it a lot easier. things. He is in the environmental safety office. I learned how to collaborate the equipment using alpha and beta sources. I went out with him and we took water samples and tested them for conductivity and chlorine. I have learned a lot in the short time I've been here. It has been a great experience and I have has the pleasure of meeting and working with great people.
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.
A proposed approach for enhancing design safety assurance of future plants

International Nuclear Information System (INIS)

Oh, Kyu Myeng; Ahn, Sang Kyu; Lee, Chang Ju; Kim, Inn Seock

2010-01-01

This paper provides various insights from a detailed review of deterministic approaches typically applied to ensure design safety of nuclear power plants (NPPs) and risk-informed approaches proposed to evaluate safety of advanced reactors such as Generation IV reactors. Also considered herein are the risk-informed safety analysis (RISA) methodology suggested by Westinghouse as a means to improve the conventional accident analysis, together with the Technology Neutral Framework recently suggested by the U.S. NRC for safety evaluation of future plants. These insights from the comparative review of deterministic and risk-informed approaches could be used in further enhancing the methodology for design safety assurance of future plants

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
Quality assurance program. Braun topical report 21

International Nuclear Information System (INIS)

1975-01-01

The Quality Assurance (QA) policies and procedures described have been developed specifically for use in commercial nuclear projects. These policies and procedures are intended to provide assurance to Braun Management and the client that the plant will be safe, reliable, and operable, plus meet the requirements of the Nuclear Regulatory Commission, NRC. The Braun QA Manual provides QA procedures for (1) engineering and design, (2) procurement of materials, equipment, and services, and (3) construction and installation. The controls for safety-related systems established in the manual cover all phases of work from project inception to plant completion prior to operation by the owner. The manual standardizes Braun QA control procedures. These procedures are supplemented by Project QA Instructions prepared for each project. (U.S.)
Role of human factor in safety assurance in the nuclear industry

International Nuclear Information System (INIS)

Agapov, A.M.; Mikhajlov, M.V.; Novikov, G.A.

2010-01-01

The authors discuss the issues of human resource activities in the Rosatom Corporation that aim to achieve and maintain the required levels of safety culture and qualification of personnel involved in the operations of nuclear energy sites. These activities are supported by the appropriate resources, organisational management structure and quality control system, legislation, regulations and methodological support. It is emphasized that systematic and versatile HR-related activities in the nuclear industry represent one of the key areas of production operations that assure safety and reliability of nuclear sites at all stages of their life cycle. Especially important is the assurance of high professional level of nuclear regulators. They believe that it would appear sensible, in addition to the existing system of training, to engage the mechanisms of rotation of personnel from utility organisations to regulatory authorities [ru
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
Construction safety program for the National Ignition Facility

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF's management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES ampersand H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES ampersand H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES ampersand H support organizations and administrative groups, and describes their interactions with the NIF Program
Construction safety program for the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-01-01

The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES&H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES&H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES&H support organizations and administrative groups, and describes their interactions with the NIF Program.
Radiation safety program in a high dose rate brachytherapy facility

International Nuclear Information System (INIS)

Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

2001-01-01

The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)
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
Safety Assurance for Irradiating Experiments in the Advanced Test Reactor

Energy Technology Data Exchange (ETDEWEB)

T. A. Tomberlin; S. B. Grover

2004-11-01

The Advanced Test Reactor (ATR), located at the Idaho National Engineering and Environmental Laboratory (INEEL), was specifically designed to provide a high neutron flux test environment for conducting a variety of experiments. This paper addresses the safety assurance process for two general types of experiments conducted in the ATR facility and how the safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore, this type of experiment is addressed in more detail in the ATR safety basis. This allows the individual safety analysis for this type of experiment to be more standardized. The second type of experiment is defined in more general terms in the ATR safety basis and is permitted under more general controls. Therefore, the individual safety analysis for the second type of experiment tends to be more unique and is tailored to each experiment.
Safety Assurance for Irradiating Experiments in the Advanced Test Reactor

International Nuclear Information System (INIS)

T. A. Tomberlin; S. B. Grover

2004-01-01

The Advanced Test Reactor (ATR), located at the Idaho National Engineering and Environmental Laboratory (INEEL), was specifically designed to provide a high neutron flux test environment for conducting a variety of experiments. This paper addresses the safety assurance process for two general types of experiments conducted in the ATR facility and how the safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore, this type of experiment is addressed in more detail in the ATR safety basis. This allows the individual safety analysis for this type of experiment to be more standardized. The second type of experiment is defined in more general terms in the ATR safety basis and is permitted under more general controls. Therefore, the individual safety analysis for the second type of experiment tends to be more unique and is tailored to each experiment
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)
Recommendations for quality assurance programs in nuclear medicine facilities. Radiation recommendations series

International Nuclear Information System (INIS)

Segal, P.; Hamilton, D.R.

1984-10-01

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

International Nuclear Information System (INIS)

1980-08-01

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

International Nuclear Information System (INIS)

Fornicola, J.C.

1987-01-01

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

International Nuclear Information System (INIS)

Farman, A.G.; Hunter, N.; Grammer, S.

1986-01-01

A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively
A Concept of Operations for an Integrated Vehicle Health Assurance System

Science.gov (United States)

Hunter, Gary W.; Ross, Richard W.; Berger, David E.; Lekki, John D.; Mah, Robert W.; Perey, Danie F.; Schuet, Stefan R.; Simon, Donald L.; Smith, Stephen W.

2013-01-01

This document describes a Concept of Operations (ConOps) for an Integrated Vehicle Health Assurance System (IVHAS). This ConOps is associated with the Maintain Vehicle Safety (MVS) between Major Inspections Technical Challenge in the Vehicle Systems Safety Technologies (VSST) Project within NASA s Aviation Safety Program. In particular, this document seeks to describe an integrated system concept for vehicle health assurance that integrates ground-based inspection and repair information with in-flight measurement data for airframe, propulsion, and avionics subsystems. The MVS Technical Challenge intends to maintain vehicle safety between major inspections by developing and demonstrating new integrated health management and failure prevention technologies to assure the integrity of vehicle systems between major inspection intervals and maintain vehicle state awareness during flight. The approach provided by this ConOps is intended to help optimize technology selection and development, as well as allow the initial integration and demonstration of these subsystem technologies over the 5 year span of the VSST program, and serve as a guideline for developing IVHAS technologies under the Aviation Safety Program within the next 5 to 15 years. A long-term vision of IVHAS is provided to describe a basic roadmap for more intelligent and autonomous vehicle systems.
Development of a training assurance program

International Nuclear Information System (INIS)

Palchinsky, J.; Waylett, W.J. Jr.

1987-01-01

The nuclear industry has made a significant commitment to improve training through the implementation of accredited performance-based training programs. Senior management expects that human performance will improve as a result of significant resource allocations. How do they know if training is effective in achieving improved human performance? Florida Power and Light Company is developing a Training Assurance Program to track indicators of training performance and future trends. Integrating the company's Quality Improvement Program processes with systematic training processes is resulting in personnel functioning in a proactive mode and increased customer satisfaction with training performance
Self–Evaluation of Distance Learning Study Program as a Part of Internal Quality Assurance

Directory of Open Access Journals (Sweden)

Radojka Krneta

2012-02-01

Full Text Available This paper features quality assurance of specific distance learning master study program through self-evaluation. This unique program involving e-learning as the program content, as well as delivery method, is presented in the paper from the aspects of its quality assurance. Student evaluation of this study program as a part of the internal quality assurance is performed at the end of every school year in the aim of its quality assurance. Results and conclusions of self-evaluation conducted in this school year by known SEVAQ+ evaluation tool are presented here.
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
Compliance assurance for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2009-01-01

The objectives of this Safety Guide are to assist competent authorities in the development and maintenance of compliance assurance programmes in connection with the transport of radioactive material, and to assist applicants, licensees and organizations in their interactions with competent authorities. In order to increase cooperation between competent authorities and to promote the uniform application of international regulations and recommendations, it is desirable to adopt a common approach to regulatory activities. This Safety Guide is intended to assist in accomplishing such a uniform application by recommending most of the actions for which competent authorities need to provide in their programmes for ensuring compliance with the Transport Regulations. This Safety Guide addresses radiation safety aspects of the transport of radioactive material; that is, the subjects that are covered by the Transport Regulations. Radioactive material may have other dangerous properties, however, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness; these properties are required to be taken into account in the regulatory control of the design and transport of packages. Physical protection and systems for accounting for and control of nuclear material are also discussed in this Safety Guide. These subjects are not within the scope of the Transport Regulations, but information on them is included here because they must be taken into account in the overall regulatory control of transport, especially when the regulatory framework is being established. Section 1 informs about the background, the objective, the scope and the structure of this publication. Section 2 provides recommendations on the responsibilities and functions of the competent authority. Section 3 provides information on the various national and international regulations and guides for the transport of radioactive material. Section 4 provides recommendations on carrying out

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.
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
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
Integrating Safety and Mission Assurance into Systems Engineering Modeling Practices

Science.gov (United States)

Beckman, Sean; Darpel, Scott

2015-01-01

During the early development of products, flight, or experimental hardware, emphasis is often given to the identification of technical requirements, utilizing such tools as use case and activity diagrams. Designers and project teams focus on understanding physical and performance demands and challenges. It is typically only later, during the evaluation of preliminary designs that a first pass, if performed, is made to determine the process, safety, and mission quality assurance requirements. Evaluation early in the life cycle, though, can yield requirements that force a fundamental change in design. This paper discusses an alternate paradigm for using the concepts of use case or activity diagrams to identify safety hazard and mission quality assurance risks and concerns using the same systems engineering modeling tools being used to identify technical requirements. It contains two examples of how this process might be used in the development of a space flight experiment, and the design of a Human Powered Pizza Delivery Vehicle, along with the potential benefits to decrease development time, and provide stronger budget estimates.
TU-FG-201-12: Designing a Risk-Based Quality Assurance Program for a Newly Implemented Y-90 Microspheres Procedure

Energy Technology Data Exchange (ETDEWEB)

Vile, D; Zhang, L; Cuttino, L; Kim, S; Palta, J [Virginia Commonwealth University, Richmond, VA (United States)

2016-06-15

Purpose: To create a quality assurance program based upon a risk-based assessment of a newly implemented SirSpheres Y-90 procedure. Methods: A process map was created for a newly implemented SirSpheres procedure at a community hospital. The process map documented each step of this collaborative procedure, as well as the roles and responsibilities of each member. From the process map, different potential failure modes were determined as well as any current controls in place. From this list, a full failure mode and effects analysis (FMEA) was performed by grading each failure mode’s likelihood of occurrence, likelihood of detection, and potential severity. These numbers were then multiplied to compute the risk priority number (RPN) for each potential failure mode. Failure modes were then ranked based on their RPN. Additional controls were then added, with failure modes corresponding to the highest RPNs taking priority. Results: A process map was created that succinctly outlined each step in the SirSpheres procedure in its current implementation. From this, 72 potential failure modes were identified and ranked according to their associated RPN. Quality assurance controls and safety barriers were then added for failure modes associated with the highest risk being addressed first. Conclusion: A quality assurance program was created from a risk-based assessment of the SirSpheres process. Process mapping and FMEA were effective in identifying potential high-risk failure modes for this new procedure, which were prioritized for new quality assurance controls. TG 100 recommends the fault tree analysis methodology to design a comprehensive and effective QC/QM program, yet we found that by simply introducing additional safety barriers to address high RPN failure modes makes the whole process simpler and safer.
TU-FG-201-12: Designing a Risk-Based Quality Assurance Program for a Newly Implemented Y-90 Microspheres Procedure

International Nuclear Information System (INIS)

Vile, D; Zhang, L; Cuttino, L; Kim, S; Palta, J

2016-01-01

Purpose: To create a quality assurance program based upon a risk-based assessment of a newly implemented SirSpheres Y-90 procedure. Methods: A process map was created for a newly implemented SirSpheres procedure at a community hospital. The process map documented each step of this collaborative procedure, as well as the roles and responsibilities of each member. From the process map, different potential failure modes were determined as well as any current controls in place. From this list, a full failure mode and effects analysis (FMEA) was performed by grading each failure mode’s likelihood of occurrence, likelihood of detection, and potential severity. These numbers were then multiplied to compute the risk priority number (RPN) for each potential failure mode. Failure modes were then ranked based on their RPN. Additional controls were then added, with failure modes corresponding to the highest RPNs taking priority. Results: A process map was created that succinctly outlined each step in the SirSpheres procedure in its current implementation. From this, 72 potential failure modes were identified and ranked according to their associated RPN. Quality assurance controls and safety barriers were then added for failure modes associated with the highest risk being addressed first. Conclusion: A quality assurance program was created from a risk-based assessment of the SirSpheres process. Process mapping and FMEA were effective in identifying potential high-risk failure modes for this new procedure, which were prioritized for new quality assurance controls. TG 100 recommends the fault tree analysis methodology to design a comprehensive and effective QC/QM program, yet we found that by simply introducing additional safety barriers to address high RPN failure modes makes the whole process simpler and safer.
The ARPANSA quality assurance program for radiopharmaceuticals

International Nuclear Information System (INIS)

Baldas, J.; Ivanov, Z.

2003-01-01

Full text: The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) conducts a radiopharmaceutical quality assurance test program in which radiopharmaceuticals used in nuclear medicine in Australia are tested for compliance with specifications. Where the radiopharmaceutical is the subject of a monograph in the British Pharmacopoeia or the European Pharmacopoeia, then the specifications given in these Pharmacopoeias are adopted. Where a monograph is only available in the US Pharmacopoeia, then this specification is generally adopted. In other cases the specifications quoted have been adopted by this Agency. Animal biodistribution testing was discontinued in 1997 due to resource limitation. Samples for testing were obtained through commercial channels. All technetium-99m cold kits were reconstituted according to the directions in the package insert using Sodium Pertechnetate [ 99m Tc] injection. The results of testing conducted by the ARPANSA during 1984-1999 are summarised. A significant cause of failure to meet full specifications has been due to non-compliance of the vial/package labels. Copyright (2003) The Australian and New Zealand Society of Nuclear Medicine Inc
Development of a quality assurance program for ionizing radiation secondary calibration laboratories

Energy Technology Data Exchange (ETDEWEB)

Heaton, H.T. II; Taylor, A.R. Jr. [Center for Devices and Radiological Health, Rockville, MD (United States)

1993-12-31

For calibration laboratories, routine calibrations of instruments meeting stated accuracy goals are important. One method of achieving the accuracy goals is to establish and follow a quality assurance program designed to monitor all aspects of the calibration program and to provide the appropriate feedback mechanism if adjustments are needed. In the United States there are a number of organizations with laboratory accreditation programs. All existing accreditation programs require that the laboratory implement a quality assurance program with essentially the same elements in all of these programs. Collectively, these elements have been designated as a Measurement Quality Assurance (MQA) program. This paper will briefly discuss the interrelationship of the elements of an MQA program. Using the Center for Devices and Radiological Health (CDRH) X-ray Calibration Laboratory (XCL) as an example, it will focus on setting up a quality control program for the equipment in a Secondary Calibration Laboratory.
Development of a quality assurance program for ionizing radiation secondary calibration laboratories

International Nuclear Information System (INIS)

Heaton, H.T. II; Taylor, A.R. Jr.

1993-01-01

For calibration laboratories, routine calibrations of instruments meeting stated accuracy goals are important. One method of achieving the accuracy goals is to establish and follow a quality assurance program designed to monitor all aspects of the calibration program and to provide the appropriate feedback mechanism if adjustments are needed. In the United States there are a number of organizations with laboratory accreditation programs. All existing accreditation programs require that the laboratory implement a quality assurance program with essentially the same elements in all of these programs. Collectively, these elements have been designated as a Measurement Quality Assurance (MQA) program. This paper will briefly discuss the interrelationship of the elements of an MQA program. Using the Center for Devices and Radiological Health (CDRH) X-ray Calibration Laboratory (XCL) as an example, it will focus on setting up a quality control program for the equipment in a Secondary Calibration Laboratory
Nuclear reactor safety program in U.S. Department of Energy and future perspectives

International Nuclear Information System (INIS)

Song, Y.T.

1987-01-01

The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)
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
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.
Development of a quality-assurance program for the Tritium Systems Test Assembly

International Nuclear Information System (INIS)

Minor, R.C.

1981-01-01

A quality assurance program was developed for TSTA with the attempt in mind to satisfy the developmental nature of the project. Numerous reviews replace strict guidelines because guidelines are one of the objectives of the project, not a basis for it. The reviews assure adequate technical consideration and avoid unilateral decisions. Other major requirements of the program plan include interfacing with another quality assurance organization, the assignment of responsibilities, and instructions for the preparation of SDD's. Areas of concern are, in general, budget related, and include receiving inspection and acceptance of items. A software program is only now being established
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
Implementation of Programmatic Quality and the Impact on Safety

Science.gov (United States)

Huls, Dale Thomas; Meehan, Kevin

2005-01-01

The purpose of this paper is to discuss the implementation of a programmatic quality assurance discipline within the International Space Station Program and the resulting impact on safety. NASA culture has continued to stress safety at the expense of quality when both are extremely important and both can equally influence the success or failure of a Program or Mission. Although safety was heavily criticized in the media after Colimbiaa, strong case can be made that it was the failure of quality processes and quality assurance in all processes that eventually led to the Columbia accident. Consequently, it is possible to have good quality processes without safety, but it is impossible to have good safety processes without quality. The ISS Program quality assurance function was analyzed as representative of the long-term manned missions that are consistent with the President s Vision for Space Exploration. Background topics are as follows: The quality assurance organizational structure within the ISS Program and the interrelationships between various internal and external organizations. ISS Program quality roles and responsibilities with respect to internal Program Offices and other external organizations such as the Shuttle Program, JSC Directorates, NASA Headquarters, NASA Contractors, other NASA Centers, and International Partner/participants will be addressed. A detailed analysis of implemented quality assurance responsibilities and functions with respect to NASA Headquarters, the JSC S&MA Directorate, and the ISS Program will be presented. Discussions topics are as follows: A comparison of quality and safety resources in terms of staffing, training, experience, and certifications. A benchmark assessment of the lessons learned from the Columbia Accident Investigation (CAB) Report (and follow-up reports and assessments), NASA Benchmarking, and traditional quality assurance activities against ISS quality procedures and practices. The lack of a coherent operational
Evidence for the safety assurance of the radiation associated equipments for stat-up check

International Nuclear Information System (INIS)

Takahashi, Yasuyuki; Igarashi, Hiroshi; Saito, Kyoko; Kawaharada, Yasuhiro; Hirano, Kunihiro; Murase, Kenya; Mochizuki, Teruhito

2008-01-01

Based on the new amendment of the Medical Service Law and the Pharmaceutical Affairs Law, the safety control for the medical equipments and devices was strengthened; and a radiological technologist should be stipulated as a safety control manager for the medical equipments and devices. Although it is thought that Start-up check is important for the safety assurance, the enforcement situation is not clear until now. In this report, on the occasion of the start-up of the new Law, questionnaire about the start up check (time and a check items) were investigated from 56 hospitals applying the visit interview. Modality by modality check up time was obtained from 261 institutions by the descriptive study paper type. Start-up check and arming up were applied for almost all modalities about 30 minutes before start of the clinical tests. The check up items for the medical equipments and devices depended on each hospital. Therefore, safety assurance should be established, cooperating with the medical equipment distributors, the hospital sharing the checked results for the patients' safety. (author)
Quality assurance program

International Nuclear Information System (INIS)

Brooks, G.L.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-07-01

This Standard contains the requirements for the quality assurance program applicable to the design phase of a nuclear plant, and is applicable to the design of safety-related equipment, systems, and structures, as identified by the owner. 1 fig.
Design quality assurance for nuclear power plants

International Nuclear Information System (INIS)

1986-07-01

This Standard contains the requirements for the quality assurance program applicable to the design phase of a nuclear plant, and is applicable to the design of safety-related equipment, systems, and structures, as identified by the owner. 1 fig
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)

10 CFR 72.142 - Quality assurance organization.

Science.gov (United States)

2010-01-01

... activities are performed, the organizational structure for executing the quality assurance program may take... the required authority and organizational freedom. Irrespective of the organizational structure, the... functions of structures, systems, and components which are important to safety. These activities include...
Risk assessment in the DOE Assurance Program for Remedial Action

International Nuclear Information System (INIS)

Marks, S.; Cross, F.T.; Denham, D.H.; Kennedy, W.E.; Stenner, R.D.

1985-08-01

This document provides information obtained during the performance of risk assessment tasks in support of the Assurance Program for Remedial Action (APRA) sponsored by the Office of Operational Safety of the Department of Energy. We have presented a method for the estimation of projected health effects at properties in the vicinity of uranium mill tailing piles due to transported tailings or emissions from the piles. Because radon and radon daughter exposure is identified as the principal factor contributing to health effects at such properties, the basis for estimating lung cancer risk as a result of such exposure is discussed in detail. Modeling of health risk due to a secondary pathway, ingestion of contaminated, home-grown food products, is also discussed since it is a potentially important additional source of exposure in certain geographic locations. Risk assessment methods used in various mill tailings reports are reviewed. The protocols for radiological surveys conducted in DOE-sponsored remedial action programs are critically reviewed with respect to their relevance to the needs of health risk estimation. The relevance of risk assessment to the APRA program is discussed briefly
Quality assurance of radiotherapy in cancer treatment. Toward improvement of patient safety and quality of care

International Nuclear Information System (INIS)

Ishikura, Satoshi

2008-01-01

The process of radiotherapy (RT) is complex and involves understanding of the principles of medical physics, radiobiology, radiation safety, dosimetry, radiation treatment planning, simulation and interaction of radiation with other treatment modalities. Each step in the integrated process of RT needs quality control and quality assurance (QA) to prevent errors and to give high confidence that patients will receive the prescribed treatment correctly. Recent advances in RT, including intensity-modulated and image-guided RT, focus on the need for a systematic RTQA program that balances patient safety and quality with available resources. It is necessary to develop more formal error mitigation and process analysis methods, such as failure mode and effect analysis, to focus available QA resources optimally on process components. External audit programs are also effective. The International Atomic Energy Agency has operated both an on-site and off-site postal dosimetry audit to improve practice and to assure the dose from RT equipment. Several countries have adopted a similar approach for national clinical auditing. In addition, clinical trial QA has a significant role in enhancing the quality of care. The Advanced Technology Consortium has pioneered the development of an infrastructure and QA method for advanced technology clinical trials, including credentialing and individual case review. These activities have an impact not only on the treatment received by patients enrolled in clinical trials, but also on the quality of treatment administered to all patients treated in each institution, and have been adopted globally; by the USA, Europe and Japan also. (author)
Quality assurance of radiotherapy in cancer treatment: toward improvement of patient safety and quality of care.

Science.gov (United States)

Ishikura, Satoshi

2008-11-01

The process of radiotherapy (RT) is complex and involves understanding of the principles of medical physics, radiobiology, radiation safety, dosimetry, radiation treatment planning, simulation and interaction of radiation with other treatment modalities. Each step in the integrated process of RT needs quality control and quality assurance (QA) to prevent errors and to give high confidence that patients will receive the prescribed treatment correctly. Recent advances in RT, including intensity-modulated and image-guided RT, focus on the need for a systematic RTQA program that balances patient safety and quality with available resources. It is necessary to develop more formal error mitigation and process analysis methods, such as failure mode and effect analysis, to focus available QA resources optimally on process components. External audit programs are also effective. The International Atomic Energy Agency has operated both an on-site and off-site postal dosimetry audit to improve practice and to assure the dose from RT equipment. Several countries have adopted a similar approach for national clinical auditing. In addition, clinical trial QA has a significant role in enhancing the quality of care. The Advanced Technology Consortium has pioneered the development of an infrastructure and QA method for advanced technology clinical trials, including credentialing and individual case review. These activities have an impact not only on the treatment received by patients enrolled in clinical trials, but also on the quality of treatment administered to all patients treated in each institution, and have been adopted globally; by the USA, Europe and Japan also.
12: Assuring the quality of critical software

International Nuclear Information System (INIS)

Jacky, J.; Kalet, I.

1987-01-01

The authors recommend quality assurance procedures for radiation therapy software. Software quality assurance deals with preventing, detecting and repairing programming errors. Error detection difficulties are most severe in computer-based control systems, for example therapy machine control systems, because it may be impossible for users to confirm correct operation while treatments are in progress, or to intervene if things go wrong. Software quality assurance techniques observed in other industries in which public safety is at risk are reviewed. In some of these industries software must be approved or certified before it can be used. Approval is subject to technical reviews and audits by experts other than the program authors. The main obstacles to adoption of these techniques in the radiation therapy field are costs, lack of familiarity and doubts regarding efficacy. 18 refs
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
Quality assurance program : bituminous concrete and central mix aggregates.

Science.gov (United States)

1980-01-01

This report presents the results of a pilot quality assurance program initiated in the Richmond District in 1978. Under this program the producer's control tests are used for the acceptance of central mix aggregate and bituminous concrete and the Dep...
Qality assurance program for biomedical radiography

International Nuclear Information System (INIS)

Korolyuk, I.P.; Gurvich, A.M.

1986-01-01

Essence and purposes of quality assurance program (QAP) in biomedical radiography of population are considered. This program can be determined as organizational and executive activity of radiological service personnel providing the necessary for diagnosis quality of investigation at minimum radiation loads to patients and personnel and the lowest cost of the investigation. QAP includes quality control of technical means and of investigation implementation. Attention is paid to means and methods of quality control. QAP organizational problems are discussed. Necessity of further investigations and technical developments in this direction is noted
24 CFR 232.630 - Assurance of completion.

Science.gov (United States)

2010-04-01

... URBAN DEVELOPMENT MORTGAGE AND LOAN INSURANCE PROGRAMS UNDER NATIONAL HOUSING ACT AND OTHER AUTHORITIES MORTGAGE INSURANCE FOR NURSING HOMES, INTERMEDIATE CARE FACILITIES, BOARD AND CARE HOMES, AND ASSISTED... Fire Safety Equipment Special Requirements § 232.630 Assurance of completion. If the property upon...
10 CFR 71.105 - Quality assurance program.

Science.gov (United States)

2010-01-01

... which functional compliance can be demonstrated by inspection or test; and (5) The quality history and... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance program. 71.105 Section 71.105 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Quality...
Repository construction management and quality assurance

International Nuclear Information System (INIS)

Hood, F.C.

1984-01-01

An emphasis on preventive rather than reactive management is key to an efficient construction management operation. Development of contingency plans to deal with unexpected adverse conditions, e.g., brine pockets during mining operations, are an integral part of the management program to ensure project safety, quality, cost, schedule and environmental objectives are met. A viable quality assurance program with active management support will optimize management effectiveness in reaching project goals. With adequate planning and perceptive application of the proper management controls, Quality Assurance becomes an essential ingredient for efficiently managing a job because it has been built into the management system rather than being an uninvolved peripheral entity. 6 references, 3 figures
Quality assurance FY 1995 site support program plan WBS 6.7.2.5

International Nuclear Information System (INIS)

Dell, L.D.

1994-09-01

This report is a summary of the quality assurance plan and program for the Westinghouse Hanford Company. The quality assurance plan verifies that the appropriate quality assurance programs and controls are applied to activities that affect quality related to work in: waste management; environmental activities (restoration, remediation, and monitoring); implementation of environmental, state, local, and federal regulations; tri-party agreement activities; facility operation and deactivation/transition to shutdown; new facility construction and operation
Quality assurance FY 1995 site support program plan WBS 6.7.2.5

Energy Technology Data Exchange (ETDEWEB)

Dell, L.D.

1994-09-01

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

International Nuclear Information System (INIS)

Boler-Melton, C.; Holland, M.K.

1991-01-01

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a ''Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a ''Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points
75 FR 68224 - Safety Management Systems for Part 121 Certificate Holders

Science.gov (United States)

2010-11-05

... safety audit (LOSA), and an advanced qualification program (AQP) as part of the SMS. The FAA must issue a... the SMS safety assurance process, periodic audits of flight crew performance, such as Line Operations... programs: ASAPs, flight operational quality assurance systems (FOQAs), LOSAs, and advanced qualification...
Relevant aspects of a quality assurance program applied to a nuclear power plant operation

International Nuclear Information System (INIS)

Fernandez, J.C.

1987-01-01

The purpose of this work was to enumerate the most relevant subjects to be taken into account for the elaboration of a Quality Assurance Program aimed to regulate a nuclear power plant operation. At first, it was necessary to point out the relevance that implies the presence of a group of personnel, experienced in quality assurance with enough knowledge on the technical and organizing aspects of the plant. Other aspect to be taken into account was the contemplation of the international requirements, through the International Atomic Energy Agency and of the national requirements that each country had set up by the corresponding regulating agencies. These organizations pointed out the minimum rules that must be followed for the adequate and efficient execution of a program. The Quality Assurance Manual and the program and work procedures constituted the Quality Assurance Program which must be checked as regards its fulfillment by auditors and quality assurance supervisions. (Author)
Reliability and safety program plan outline for the operational phase of a waste isolation facility

International Nuclear Information System (INIS)

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

1977-01-01

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

International Nuclear Information System (INIS)

Weiss, E.V.

1998-01-01

This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM
Management assessments of Quality Assurance Program implementation effectiveness

International Nuclear Information System (INIS)

Snyder, D.A.

1984-01-01

This paper describes a method currently being used by UNC Nuclear Industries, Richland, Washington, to help assure the effectiveness of Quality Assurance (QA) Program implementation. Assessments are conducted annually by management in each department, and the results summarized to the president and his staff. The purpose of these assessments is to review the adequacy of the department's implementing procedures, training/instruction on implementing procedures, and procedure implementation effectiveness. The primary purpose is to assess effectiveness and take improvement action where the need is indicated. The QA organization provides only general guidance in conducting the assessments
One in a Million Given the Accident: Assuring Nuclear Weapon Safety

Energy Technology Data Exchange (ETDEWEB)

Weaver, Jason [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2015-08-25

Since the introduction of nuclear weapons, there has not been a single instance of accidental or unauthorized nuclear detonation, but there have been numerous accidents and “close calls.” As the understanding of these environments has increased, the need for a robust nuclear weapon safety philosophy has grown. This paper describes some of the methods used by the Nuclear Weapon Complex today to assure nuclear weapon safety, including testing, modeling, analysis, and design features. Lastly, it also reviews safety’s continued role in the future and examines how nuclear safety’s present maturity can play a role in strengthening security and other areas and how increased coordination can improve safety and reduce long-term cost.

Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

International Nuclear Information System (INIS)

Dey, M.

1993-09-01

These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission's Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements
Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Dey, M. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Arsenault, F.; Patterson, M.; Gaal, M. [SCIENTECH, Inc., Rockville, MD (United States)

1993-09-01

These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission`s Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements.
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
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
Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

International Nuclear Information System (INIS)

Gone, J.K.; Wang, T.W.

2000-01-01

Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)
Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

Energy Technology Data Exchange (ETDEWEB)

Gone, J.K. [TRR-II Project Team, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China); Wang, T.W. [Division of Health Physics, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China)

2000-05-01

Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)
Building quality into performance and safety assessment software

International Nuclear Information System (INIS)

Wojciechowski, L.C.

2011-01-01

Quality assurance is integrated throughout the development lifecycle for performance and safety assessment software. The software used in the performance and safety assessment of a Canadian deep geological repository (DGR) follows the CSA quality assurance standard CSA-N286.7 [1], Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants. Quality assurance activities in this standard include tasks such as verification and inspection; however, much more is involved in producing a quality software computer program. The types of errors found with different verification methods are described. The integrated quality process ensures that defects are found and corrected as early as possible. (author)
10 CFR 72.144 - Quality assurance program.

Science.gov (United States)

2010-01-01

... quality history and degree of standardization of the item. (d) The licensee, applicant for a license... 10 Energy 2 2010-01-01 2010-01-01 false Quality assurance program. 72.144 Section 72.144 Energy... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Quality...
What is the role of a project or program manager in implementing and maintaining a quality assurance program

International Nuclear Information System (INIS)

Anon.

1989-01-01

The task of managing a government-funded program has changed significantly from the days when a program manager managed the funds and depended on reports from a contractor to measure the program's progress. Today's manager of waste management program must be personally involved in every aspect of the program. The successful manager of a waste management program will lead the development of management controls to ensure successful accomplishment of project objectives. This paper describes the responsibilities of the project manager, the quality assurance staff and how they interface to develop and implement a quality assurance program for a waste management program
Nuclear medicine quality assurance program in Argentina

International Nuclear Information System (INIS)

Levi de Cabrejas, Mariana; Arashiro, Jorge G.; Giannone, Carlos A.

1999-01-01

A two steps program has been implemented: the first one is the quality control of the equipment and the second one the development of standard procedures for clinical studies of patients. A training program for doctors and technicians of the nuclear medicine laboratories was carried out. Workshops on instrumentation and quality assurance in nuclear medicine have been organized in several parts of the country. A joint program of the CNEA and the University of Buenos Aires has trained medical physicists. A method has been established to evaluate the capability of the laboratories to produce high quality images and to follow up the implementation of the quality control program
Quality assurance of radiation therapy machines

International Nuclear Information System (INIS)

Francois, P.

2002-01-01

Due to the modifications of components, to unexpected breakage of elements or to electronic dysfunctions, the performance of radiotherapy machines may decrease with age. Quality Assurance procedures and maintenance program are necessary to guarantee the performances. For linear accelerators, modus operandi of control tests and their frequency are based on regulations and recommendations widely published, that are presented here. Concerning accessories, especially those recently developed (multi-leaf collimators, dynamic wedges,...), recommendations remains to be defined. Simple tests are proposed. Concerning numerical imaging systems, widely used for three dimensional dosimetry, image quality and geometry controls must be performed with fantom tests. For portal imaging, a quality assurance program is proposed. A strict and complete Quality Assurance program is essential to guarantee quality and safety of the treatment. A regular control of linear accelerator is one of the important component of this program. It suppose the implementation of permanent tests procedures, periodically modified following technological progresses and treatment techniques. Measurements must be sensible to variations below the tolerance level defined during the installation process. The analysis of the variations of measurements with time are an objective criterion of quality. (author)
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)
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
Assuring safety without animal testing: Unilever's ongoing research programme to deliver novel ways to assure consumer safety.

Science.gov (United States)

Westmoreland, Carl; Carmichael, Paul; Dent, Matt; Fentem, Julia; MacKay, Cameron; Maxwell, Gavin; Pease, Camilla; Reynolds, Fiona

2010-01-01

Assuring consumer safety without the generation of new animal data is currently a considerable challenge. However, through the application of new technologies and the further development of risk-based approaches for safety assessment, we remain confident it is ultimately achievable. For many complex, multi-organ consumer safety endpoints, the development, evaluation and application of new, non-animal approaches is hampered by a lack of biological understanding of the underlying mechanistic processes involved. The enormity of this scientific challenge should not be underestimated. To tackle this challenge a substantial research programme was initiated by Unilever in 2004 to critically evaluate the feasibility of a new conceptual approach based upon the following key components: 1.Developing new, exposure-driven risk assessment approaches. 2.Developing new biological (in vitro) and computer-based (in silico) predictive models. 3.Evaluating the applicability of new technologies for generating data (e.g. "omics", informatics) and for integrating new types of data (e.g. systems approaches) for risk-based safety assessment. Our research efforts are focussed in the priority areas of skin allergy, cancer and general toxicity (including inhaled toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biology and molecular mechanisms that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement in EU-funded projects (e.g. Sens-it-iv, Carcinogenomics), participation in cross-industry collaborative research (e.g. Colipa, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US "Human Toxicology Project" consortium).
Analysis of a comprehensive quality assurance program with computer-enhanced monitors

International Nuclear Information System (INIS)

Arenson, R.L.; Mintz, M.C.; Goldstein, E.; Stevens, J.F.; Jovais, C.

1987-01-01

The authors' quality assurance (QA) program provides communication pathways among its constituent committees, which include patient care, professional review, medical staff, missed case, quality control, safety, and management committees. The QA monitors are based on data from these committees but also include data from the information management system, such as patient delays, contrast reactions, incidents, complications, time-flow analyses, film library retrieval, cancellations, missing reports, and missing clinical data. Committee data include complaints, missed diagnoses, patient identification problems, and equipment failure. The QA monitors have now been incorporated into summary reports as part of their computer networks. A systematic method for follow-up ensures corrective action and documentation. Examples of improved quality of care resulting from this approach includes reductions in delays for report signature and in repeat films
Benefits of a good quality assurance program to an electric utility

Energy Technology Data Exchange (ETDEWEB)

Mahoney, W.J. (Detroit Edison, Detroit, MI (United States))

1994-10-01

A good quality assurance program at a coal mine or power plant should be timely and consistent. The quality analysis is accurate due to a complete sampling of the coal stream loaded into the unit train. The sample analysis is accurate because standardized testing procedures are applied. A good coal quality assurance program includes: coal quality analysis of the delivered coal; bias testing of mechanical coal samplers; dust control during coal handling; and freeze conditioning during the winter. 2 figs., 2 plates
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.
A quality assurance program for the on-board imager[reg

International Nuclear Information System (INIS)

Yoo, Sua; Kim, Gwe-Ya; Hammoud, Rabih

2006-01-01

To develop a quality assurance (QA) program for the On-Board Imager (OBI) system and to summarize the results of these QA tests over extended periods from multiple institutions. Both the radiographic and cone-beam computed tomography (CBCT) mode of operation have been evaluated. The QA programs from four institutions have been combined to generate a series of tests for evaluating the performance of the On-Board Imager. The combined QA program consists of three parts: (1) safety and functionality (2) geometry, and (3) image quality. Safety and functionality tests evaluate the functionality of safety features and the clinical operation of the entire system during the tube warm-up. Geometry QA verifies the geometric accuracy and stability of the OBI/CBCT hardware/software. Image quality QA monitors spatial resolution and contrast sensitivity of the radiographic images. Image quality QA for CBCT includes tests for Hounsfield Unit (HU) linearity, HU uniformity, spatial linearity, and scan slice geometry, in addition. All safety and functionality tests passed on a daily basis. The average accuracy of the OBI isocenter was better than 1.5 mm with a range of variation of less than 1 mm over 8 months. The average accuracy of arm positions in the mechanical geometry QA was better than 1 mm, with a range of variation of less than 1 mm over 8 months. Measurements of other geometry QA tests showed stable results within tolerance throughout the test periods. Radiographic contrast sensitivity ranged between 2.2% and 3.2% and spatial resolution ranged between 1.25 and 1.6 lp/mm. Over four months the CBCT images showed stable spatial linearity, scan slice geometry, contrast resolution (1%; 6 lp/cm). The HU linearity was within ±40 HU for all measurements. By combining test methods from multiple institutions, we have developed a comprehensive, yet practical, set of QA tests for the OBI system. Use of the tests over extended periods show that the OBI system has reliable mechanical
Laboratory quality assurance and its role in the safeguards analytical laboratory evaluation (SALE) program

International Nuclear Information System (INIS)

Delvin, W.L.; Pietri, C.E.

1981-07-01

Since the late 1960's, strong emphasis has been given to quality assurance in the nuclear industry, particularly to that part involved in nuclear reactors. This emphasis has had impact on the analytical chemistry laboratory because of the importance of analytical measurements in the certification and acceptance of materials used in the fabrication and construction of reactor components. Laboratory quality assurance, in which the principles of quality assurance are applied to laboratory operations, has a significant role to play in processing, fabrication, and construction programs of the nuclear industry. That role impacts not only process control and material certification, but also safeguards and nuclear materials accountability. The implementation of laboratory quality assurance is done through a program plan that specifies how the principles of quality assurance are to be applied. Laboratory quality assurance identifies weaknesses and deficiencies in laboratory operations and provides confidence in the reliability of laboratory results. Such confidence in laboratory measurements is essential to the proper evaluation of laboratories participating in the Safeguards Analytical Laboratory Evaluation (SALE) Program
Quality assurance of the modernized Dukovany I and C safety system software

International Nuclear Information System (INIS)

Karpeta, C.

2005-01-01

The approach to quality assurance of the software that implements the instrumentation and control functions for safety category A as per IEC 61226, which has been adopted within the 'NPP Dukovany I and C Refurbishment' project, is described. A survey of the requirements for software quality assurance of the systems that initiate protection interventions in the event of anticipated operational occurrences or accident conditions is given. The software development process applied by the system designers and manufacturers, from the software requirements specification phase to the software testing phase, is outlined. Basic information on technical audits of the software development process is also provided. (orig.)

Evaluation and recommendations on U.C. Lawrence Livermore Labortory Quality Assurance Program

International Nuclear Information System (INIS)

Carpenter, F.D.; Horner, M.H.

1978-01-01

A study was conducted of the University of California's Lawrence Livermore Laboratory Quality Assurance Program, which focused on training needs and recommendations tailored to the various on-going programs. Specific attention was directed to an assessment of the quality status for the MFTF facility and the capabilities of assigned quality project engineers. Conclusions and recommendations are presented which not only address the purpose of this study, but extend into other areas to provide insight and needs for a total cost effective application of a quality assurance program
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
Quality assurance program description for shipping packages of radioactive material

International Nuclear Information System (INIS)

1978-01-01

This quality assurance plan describes the quality assurance program at the Pacific Northwest Laboratory (PNL), for shipping packages of radioactive material. The purpose of this report is to describe how PNL will comply with the Code of Federal Regulations, Title 10, Part 71, Appendix E. In compliance with the instructions from the Nuclear Regulatory Commission (NRC), the 18 criteria from Appendix E are covered
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
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
Management of National Nuclear Power Programs for assured safety

Energy Technology Data Exchange (ETDEWEB)

Connolly, T.J. (ed.)

1985-01-01

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).
Management of National Nuclear Power Programs for assured safety

International Nuclear Information System (INIS)

Connolly, T.J.

1985-01-01

Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA)
Laser safety considerations for a mobile laser program

Science.gov (United States)

Flor, Mary

1997-05-01

An increased demand for advanced laser technology, especially in the area of cutaneous and cosmetic procedures has prompted physicians to use mobile laser services. Utilization of a mobile laser service allows physicians to provide the latest treatments for their patients while minimizing overhead costs. The high capital expense of laser systems is often beyond the financial means of individual clinicians, group practices, free-standing clinics and smaller community hospitals. Historically rapid technology turnover with laser technology places additional risk which is unacceptable to many institutions. In addition, health care reform is mandating consolidation of equipment within health care groups to keep costs at a minimum. In 1994, Abbott Northwestern Hospital organized an in-house mobile laser technology service which employs a group of experienced laser specialists to deliver and support laser treatments for hospital outreach and other regional physicians and health care facilities. Many of the hospital's internal safety standards and policies are applicable to the mobile environment. A significant challenge is client compliance because of the delicate balance of managing risk while avoiding being viewed as a regulator. The clinics and hospitals are assessed prior to service to assure minimum laser safety standards for both the patient and the staff. A major component in assessing new sites is to inform them of applicable regulatory standards and their obligations to assure optimum laser safety. In service training is provided and hospital and procedures are freely shared to assist the client in establishing a safe laser environment. Physician and nursing preceptor programs are also made available.
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)
The performance regulatory approach in quality assurance: Its application to safety in nuclear power plants

International Nuclear Information System (INIS)

Sajaroff, Pedro M.

2000-01-01

In early 1991, the IAEA assembled an Advisory Group on the Comprehensive Revision of the Code and the Safety on Quality Assurance of the NUSS Programme. The Group was made up by specialists from a number of countries and from ISO, FORATOM, the EC and the IAEA itself, and its objective was completed in June 1995. This paper is aimed at describing the conceptual contents of the final draft of the revision 2 of the 50-C-QA Code 'Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Facilities' (hereinafter, the Code) which is essentially based on performance. Although the performance regulatory approach is not new in Argentina and in other countries, what is indeed novel is applying performance based QA. In such a way the Code will contribute to preventing both QA misinterpretations (i.e., a formalistic regulatory requirement) and the execution of non-effective work without attaining the needed quality level (what may be seen as a pathological deviation of QA). The Code contains ten basic requirements to be adopted when QA programmes are established and implemented in nuclear power plants. The goal is improving safety through an improvement in the methods applied for attaining quality. In line with the current developments in quality management techniques, priority is given to effectiveness of the QA programme. All the involved individuals (that is those in the managerial level, those performing the work and those assessing the work performed) must contribute to quality in a co-ordinated manner. The revised Safety Guides are being introduced, standing out those non existing before. Interrelation between quality assurance, safety culture and quality culture is to be noted. Besides QA for safety-related software mentioned as an issue to be considered by the IAEA. (author)
The meteorological monitoring audit, preventative maintenance and quality assurance programs at a former nuclear weapons facility

International Nuclear Information System (INIS)

Maxwell, D.R.

1995-01-01

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

International Nuclear Information System (INIS)

Okamoto, Sunao; Nishihara, Hideaki; Shibata, Toshikazu

1981-01-01

For the purpose of assuring reactor safety and strengthening research in the related fields, a multi-disciplinary group was formed among university researchers, including social scientists, with a special allocation of the Grant-in-Aid from the Ministry of Education, Science and Culture. An excerpt from the first year's report (1979 -- 1980) is edited here, which contains an interpretation of Murphy's reliability engineering law, a scope of reactor diagnostic studies to be pursued at universities, and safety measures already implemented or suggested to be implemented in university research reactors. (author)
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
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
Quality Assurance of Joint Degree Programs from the Perspective of Quality Assurance Agencies: Experience in East Asia

Science.gov (United States)

Hou, Yung-Chi; Ince, Martin; Tsai, Sandy; Wang, Wayne; Hung, Vicky; Lin Jiang, Chung; Chen, Karen Hui-Jung

2016-01-01

Joint degree programs have gained popularity in East Asia, due to the growth of transnational higher education in the region since 2000. However, the external quality assurance (QA) and accreditation of joint degree programs is a challenge for QA agencies, as it normally involves the engagement of several institutions and multiple national…
Quality assurance program description. Topical report SDQAPD-1

International Nuclear Information System (INIS)

1975-01-01

The topical report presented describes the SDG and E QA Program that is applied to the design, procurement, construction, and preoperational testing of nuclear power plants. The QA plan describes the SDG and E organizational structure for quality assurance; identifies the functions, duties, and responsibilities of key departments and individuals; describes interrelationships and interfaces among internal groups and external organizations; delineates program requirements, and prescribes methods of implementation. SDG and E Procedures and Directives provide detailed direction for accomplishment of program requirements in consonance with the methods specified in the QA Plan
State and local safety program

Energy Technology Data Exchange (ETDEWEB)

Carlyle Thompson, G D [Utah State Division of Health, Salt Lake City, UT (United States)

1969-07-01

This paper will give emphasis to the need for an increasing role of the states, along with the Federal agencies, in the Plowshare Program in order to assure state and local confidence with respect to the safety of their residents as the Federal government seeks new methods to benefit society. First will be stressed the age-old principle of control at the source. Other factors to be discussed are monitoring; standards and their use; control action; public relations; predictions and the need to have certain advance knowledge of tests - even if security clearance is necessary for appropriate state representatives; the state and local government responsibility to their citizens; the isolation of national decision making from state and local concern and responsibility; cost assessments and their responsibility; and research as it relates to the ecological system as well a the direct short- or long-term effects of radioactivity on man. (author)
State and local safety program

International Nuclear Information System (INIS)

Carlyle Thompson, G.D.

1969-01-01

This paper will give emphasis to the need for an increasing role of the states, along with the Federal agencies, in the Plowshare Program in order to assure state and local confidence with respect to the safety of their residents as the Federal government seeks new methods to benefit society. First will be stressed the age-old principle of control at the source. Other factors to be discussed are monitoring; standards and their use; control action; public relations; predictions and the need to have certain advance knowledge of tests - even if security clearance is necessary for appropriate state representatives; the state and local government responsibility to their citizens; the isolation of national decision making from state and local concern and responsibility; cost assessments and their responsibility; and research as it relates to the ecological system as well a the direct short- or long-term effects of radioactivity on man. (author)
Quality and Safety Assurance of Iron Casts and Manufacturing Processes

OpenAIRE

Kukla S.

2016-01-01

The scope of this work focuses on the aspects of quality and safety assurance of the iron cast manufacturing processes. Special attention was given to the processes of quality control and after-machining of iron casts manufactured on automatic foundry lines. Due to low level of automation and huge work intensity at this stage of the process, a model area was established which underwent reorganization in accordance with the assumptions of the World Class Manufacturing (WCM). An analysis of wor...
49 CFR 385.317 - Will a safety audit result in a safety fitness determination by the FMCSA?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Will a safety audit result in a safety fitness... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.317 Will a safety audit result in a safety fitness determination by the FMCSA? A safety audit will not result in a safety...

Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

International Nuclear Information System (INIS)

2010-01-01

A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about SAFIR
Operational and environmental safety

International Nuclear Information System (INIS)

Anon.

1978-01-01

The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed
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
Quality assurance program in the External dosimetry laboratory of the CPHR

International Nuclear Information System (INIS)

Molina P, D.; Pernas S, R.; Martinez H, E.; Cardenas H, J.

2006-01-01

From 1999 the Laboratory of External Dosimetry of the Radiation Protection and Hygiene Center comes applying in its service of personal dosimetry a Program of Quality Assurance. This program was designed according to the recommendations of national and international organizations as the National Assuring Office of the Republic of Cuba (ONARC), the International Standards Organization (ISO), the International Electro technique Commission (IEC) and the International Atomic Energy Agency (IAEA). In this work it is presented in a summarized way the operation of this Program of Quality Assurance which includes the administration and conservation of the results and the documentation of the service, the controls that are carried out to the equipment, the acceptance tests that are applied to the equipment and new dosemeters, the shipment and prosecution of the dosemeters, the evaluation, storage and conservation of the doses, the report of the results, the traceability and reproducibility of the measurements, the attention to the reclamations and the clients complaints and the internal and external audits to those that it undergoes periodically the laboratory. (Author)
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
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).
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)
Quality Assurance Program Plan for FFTF effluent controls. Revision 1

International Nuclear Information System (INIS)

Seamans, J.A.

1995-01-01

This Quality Assurance Program Plan is specific to environmental related activities within the FFTF Property Protected Area. The activities include effluent monitoring and Low Level Waste Certification
Developing and Implementing a Quality Assurance Strategy for Electroconvulsive Therapy.

Science.gov (United States)

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

2018-04-17

The literature provides scant guidance in effective quality assurance strategies concerning the use of electroconvulsive therapy (ECT) for the treatment of psychiatric conditions. Numerous guidelines are published that provide guidance in the delivery of care; however, little has been done to determine how a program or facility might ensure compliance to best practice for safety, tolerability, and efficacy in performing ECT. The objective of this project was to create a quality assurance strategy specific to ECT. Determining standards for quality care and clarifying facility policy were key outcomes in establishing an effective quality assurance strategy. An audit tool was developed utilizing quality criteria derived from a systematic review of ECT practice guidelines, peer review, and facility policy. All ECT procedures occurring over a 2-month period of May to June 2017 were retrospectively audited and compared against target compliance rates set for the facility's ECT program. Facility policy was adapted to reflect quality standards, and audit findings were used to inform possible practice change initiatives, were used to create benchmarks for continuous quality monitoring, and were integrated into regular hospital quality meetings. Clarification on standards of care and the use of clinical auditing in ECT was an effective starting point in the development of a quality assurance strategy. Audit findings were successfully integrated into the hospital's overall quality program, and recognition of practice compliance informed areas for future quality development and policy revision in this small community-based hospital in the southeastern United States. This project sets the foundation for a quality assurance strategy that can be used to help monitor procedural safety and guide future improvement efforts in delivering ECT. Although it is just the first step in creating meaningful quality improvement, setting clear standards and identifying areas of greatest
Radiation safety and quality control assurance in X-ray diagnostics 1998; Saeteilyturvallisuus ja laadunvarmistus roentgendiagnostiikassa 1998

Energy Technology Data Exchange (ETDEWEB)

Servomaa, A [ed.

1998-03-01

The report is based on a seminar course of lectures `Radiation safety and quality assurance in X-ray diagnostics 1998` organized by the Radiation and Nuclear Safety Authority (STUK) in Finland. The lectures included actual information on X-ray examinations: methods of quality assurance, methods of measuring and calculating patient doses, examination frequencies, patient doses, occupational doses, and radiation risks. Paediatric X-ray examinations and interventional procedures were the most specific topics. The new Council Directive 97/43/Euratom on medical exposure, and the European Guidelines on quality criteria for diagnostic radiographic images, were discussed in several lectures. Lectures on general radiation threats and preparedness, examples of radiation accidents, and emergency preparedness in hospitals were also included. (editor)
Quality Assurance--Best Practices for Assessing Online Programs

Science.gov (United States)

Wang, Qi

2006-01-01

Educators have long sought to define quality in education. With the proliferation of distance education and online learning powered by the Internet, the tasks required to assess the quality of online programs become even more challenging. To assist educators and institutions in search of quality assurance methods to continuously improve their…
Bridging the Divide between Safety and Risk Management for your Project or Program

Science.gov (United States)

Lutomski, Mike

2005-01-01

This presentation will bridge the divide between these separate but overlapping disciplines and help explain how to use Risk Management as an effective management decision support tool that includes safety. Risk Management is an over arching communication tool used by management to prioritize and effectively mitigate potential problems before they concur. Risk Management encompasses every kind of potential problem that can occur on a program or project. Some of these are safety issues such as hazards that have a specific likelihood and consequence that need to be controlled and included to show an integrated picture of accepted) mitigated, and residual risk. Integrating safety and other assurance disciplines is paramount to accurately representing a program s or projects risk posture. Risk is made up of several components such as technical) cost, schedule, or supportability. Safety should also be a consideration for every risk. The safety component can also have an impact on the technical, cost, and schedule aspect of a given risk. The current formats used for communication of safety and risk issues are not consistent or integrated. The presentation will explore the history of these disciplines, current work to integrate them, and suggestions for integration for the future.
The contribution of quality assurance to safety and reliability in nuclear power plants

International Nuclear Information System (INIS)

Raisic, N.

1978-01-01

The potential contribution of quality assurance to nuclear power plant safety and reliability is analysed. An attempt is made to establish a relationship between quality and reliability. The reliability may be expressed in quantitative terms as ''the probability that an item will perform a required function for a stated period of time''. Quality, however, cannot be expressed in simple quantitative terms but only as a set of required properties which an item should have for a specific application. The achievement of quality and additional reliability objectives is a task of project activities such as design, construction, installation, operation, etc. The elements of a quality assurance system and its functions in nuclear power projects are presented in some detail. Confidence in plant quality, which should be a basis for the regulatory body issuing the construction permit or operation licence, should be based on the capability of quality assurance activities to prevent errors and correct deficiencies in nuclear power plants. An analysis is made of those errors in plant design, manufacture, construction and operation which contribute most frequently to plant outages. It is concluded that these errors can be avoided or corrected by strict adherence to quality assurance principles and by the efficient functioning of quality assurance systems. In fact, quality assurance may be considered an effective defence against common cause failures originating in errors in the design, manufacture, installation or operation of a nuclear power plant
Software quality assurance and software safety in the Biomed Control System

International Nuclear Information System (INIS)

Singh, R.P.; Chu, W.T.; Ludewigt, B.A.; Marks, K.M.; Nyman, M.A.; Renner, T.R.; Stradtner, R.

1989-01-01

The Biomed Control System is a hardware/software system used for the delivery, measurement and monitoring of heavy-ion beams in the patient treatment and biology experiment rooms in the Bevalac at the Lawrence Berkeley Laboratory (LBL). This paper describes some aspects of this system including historical background philosophy, configuration management, hardware features that facilitate software testing, software testing procedures, the release of new software quality assurance, safety and operator monitoring. 3 refs
Quality Assurance Plans under the Renewable Fuel Standard Program

Science.gov (United States)

Quality Assurance Plan or (QAP) is a voluntary program where independent third-parties may audit and verify that RINs have been properly generated and are valid for compliance purposes. RINs verified under a QAP may be purchased by regulated parties.
A quality assurance program for nuclear power reactor materials tests at the Ford nuclear reactor

International Nuclear Information System (INIS)

Burn, R.R.

1989-01-01

The University of Michigan Nuclear Reactor Laboratory Quality Assurance Program has been established to assure that materials testing services provided to electric utilities produce accurate results in accordance with industry standards, sound engineering practice, and customer requirements. The program was prepared to comply with applicable requirements of 10CFR50, Appendix B, of the Code of Federal Regulations and a standard of the American National Standards Institute (ANSI), N45.2. The paper discusses the quality assurance program applicability, organization, qualification and training of personnel, material identification and control, examination and testing, measuring and test equipment, nonconforming test equipment, records, audits, and distribution
Assuring fish safety and quality in international fish trade

International Nuclear Information System (INIS)

Ababouch, Lahsen . E-mail lahsen.ababouch@fao.org

2006-01-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building
Assuring fish safety and quality in international fish trade

Energy Technology Data Exchange (ETDEWEB)

Ababouch, Lahsen [United Nations, Food and Agricultural Organization, Chief, Fish Utilization and Marketing Services, FAO Headquarters, F-607 Rome (Italy)]. E-mail lahsen.ababouch@fao.org

2006-07-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building.
Proposed quality assurance manual for the Office of Waste Isolation

International Nuclear Information System (INIS)

1977-01-01

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

International Nuclear Information System (INIS)

Fernandez, L.

1995-01-01

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

Office of Civilian Radioactive Waste Management ensuring quality assurance in the waste management program

International Nuclear Information System (INIS)

Kehew, W.J.; Barrett, L.H.

1991-01-01

This paper focuses on the Quality Assurance (QA) program of the U.S. Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). It describes the objectives and philosophy of quality assurance and the plans and activities that OCRWM is undertaking to implement a fully qualified QA program prior to beginning new site characterization activities in Nevada. This paper outlines OCRWM's plan to implement and use a well-designed and effective QA program throughout all elements of the program. (author) 1 fig., 5 refs
Utility QA viewpoint: Quality assurance program conforming to 10CFR50, Appendix B and 10CFR71, subpart H

International Nuclear Information System (INIS)

Grodi, D.L.

1987-01-01

The Nuclear Regulatory Commission issued IE Information Notice No. 84-50: ''Clarification of Scope of Quality Assurance Programs for Transport Packages Pursuant to 10CFR50, Appendix B, in June, 1984. The reason for this notice was to eliminate confusion applicable to the quality assurance provisions of Appendix B, 10CFR50 to certain transport packages for which a quality assurance program is required by 10 CFR 71. The purpose of this paper is to provide methodology for establishing, implementing and verifying that all 10CFR71, Subpart H requirements are met with the utility's NRC approved 10CFR50, Appendix B Quality Assurance Program when utilizing a contractor (with a NRC approved Quality Assurance Program for Radioactive Waste Packaging and Transport) providing the radioactive waste solidification, packaging and transport for the utility. Collectively (utility and contractor) the quality assurance programs will meet the applicable regulatory requirements without the necessity of the utility establishing a separate and specific quality assurance program for Packaging and Transport of Radioactive Waste
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.
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
Pipe support program at Pickering

International Nuclear Information System (INIS)

Sahazizian, L.A.; Jazic, Z.

1997-01-01

This paper describes the pipe support program at Pickering. The program addresses the highest priority in operating nuclear generating stations, safety. We present the need: safety, the process: managed and strategic, and the result: assurance of critical piping integrity. In the past, surveillance programs periodically inspected some systems, equipment, and individual components. This comprehensive program is based on a managed process that assesses risk to identify critical piping systems and supports and to develop a strategy for surveillance and maintenance. The strategy addresses all critical piping supports. Successful implementation of the program has provided assurance of critical piping and support integrity and has contributed to decreasing probability of pipe failure, reducing risk to worker and public safety, improving configuration management, and reducing probability of production losses. (author)
49 CFR 385.321 - What failures of safety management practices disclosed by the safety audit will result in a...

Science.gov (United States)

2010-10-01

... disclosed by the safety audit will result in a notice to a new entrant that its USDOT new entrant... MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.321 What failures of safety management practices disclosed by the safety audit will result in a notice...
Investigating the Availability of Quality Assurance Standards of Academic Programs in the Music Teacher Preparation Program- University of Jordan, from the Students’ Perspective

Directory of Open Access Journals (Sweden)

Nedal M. Nsairat

2017-08-01

Full Text Available This study aimed to find out how far quality assurance standards were applied in the music teacher preparation program at the University of Jordan, from the viewpoint of the students enrolled in the same program. The population of this study consisted of all the students (53 enrolled in the program , and majoring in music education and music performance. The study followed a descriptive analytical approach to collect the data. The study results revealed the extent of relevance of the BA program of preparing music teachers in the University of Jordan, which came as a result of applying each quality assurance standard in the program except the standard of facilities and equipment. In light of the findings, the study recommended that all those in charge of the educational process should pay more heed to certification programs of music teacher education. This should be done by designing and implementing programs to support this type of program, so as to be in conformity with quality assurance standards of music teacher education. Keywords: Preparation , Music teacher education , Standard , Quality assurance.
Quality assurance for safety in nuclear power plants. A code of practice

International Nuclear Information System (INIS)

1978-01-01

The Code of Practice is a part of the International Atomic Energy Agency's programme, referred to as the NUSS programme (Nuclear Safety Standards), for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. The documents are based on documentation and experience from various national systems and practices. The present document provides the recommended principles and objectives for the establishment and implementation of a quality assurance programme during design, manufacture, construction, commissioning and operation of structures, system and components important to safety. They are applicable by all those responsible for the power plant, by plant designers, suppliers, architect-engineers, plant constructors, plant operators and other organizations participating in activities affecting quality. The Lists of relevant definition and the Provisional List of NUSS Programme Titles are given
The Rockford School of Medicine Undergraduate Quality Assurance Program

Science.gov (United States)

Barr, Daniel; And Others

1976-01-01

An undergraduate program of ambulatory care quality assurance is described which has been operational at the Rockford School of Medicine for three years. Focus is on involving students in peer review and related audit activities. Results of preliminary evaluation are reported and generalizations offered. (JT)
[Extraction of management information from the national quality assurance program].

Science.gov (United States)

Stausberg, Jürgen; Bartels, Claus; Bobrowski, Christoph

2007-07-15

Starting with clinically motivated projects, the national quality assurance program has established a legislative obligatory framework. Annual feedback of results is an important means of quality control. The annual reports cover quality-related information with high granularity. A synopsis for corporate management is missing, however. Therefore, the results of the University Clinics in Greifswald, Germany, have been analyzed and aggregated to support hospital management. Strengths were identified by the ranking of results within the state for each quality indicator, weaknesses by the comparison with national reference values. The assessment was aggregated per clinical discipline and per category (indication, process, and outcome). A composition of quality indicators was claimed multiple times. A coherent concept is still missing. The method presented establishes a plausible summary of strengths and weaknesses of a hospital from the point of view of the national quality assurance program. Nevertheless, further adaptation of the program is needed to better assist corporate management.
Highway Safety Program Manual: Volume 3: Motorcycle Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…
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.)
Design and implementation of a quality assurance program for gamma cameras

International Nuclear Information System (INIS)

Montoya M, A.; Rodriguez L, A.; Trujillo Z, F. E.

2010-09-01

In nuclear medicine more than 90% of the carried out procedures are diagnostic. To assure an appropriate diagnostic quality of the images and the doses optimization received by the patients originated in the radioactive material, it is indispensable the periodic surveillance of the operation and performance of the equipment s by means of quality assurance tests. This work presents a proposal of a quality assurance program for gamma cameras based on recommendations of the IAEA, the American Association of Medical Physics and the National Electrical Manufacturers Association. Some tests of the program were applied to an e.cam gamma camera (Siemens) of the Nuclear Medicine Department of the National Institute of Cancer. The intrinsic and extrinsic uniformity, the intrinsic spatial resolution and the extrinsic sensibility were verified. For intrinsic uniformity the average daily values of the integral uniformity and differential uniformity in the useful vision field were 2.61% and 1.58% respectively, the average monthly values of intrinsic uniformity for the integral and differential uniformity in the useful vision field were 4.10% and 1.66% respectively. The used acceptance criterions were respectively of 3.74% and 2.74%. The average values of extrinsic uniformity for the useful vision field were of 7.65% (intrinsic uniformity) and 2.69% (extrinsic uniformity), in this case the acceptance criterion is a value of 6.00%. The average value of intrinsic spatial resolution went 4.67 mm superior to 4.4. mm that is the acceptance limit. Finally, maximum variations of 1.8% were observed (minors than 2% that is the acceptance criterion) for the extrinsic sensibility measured in different regions of the detector. Significant variations of extrinsic sensibility were not observed among the monthly lectures. Of the realized measurements was concluded that the system requires of a maintenance service by part of the manufacturer, which one carries out later on to this work. The
Planning and implementation of reliability/quality programs to energy plants

International Nuclear Information System (INIS)

Quenon, J.

1986-01-01

Quality Assurance principles have long been applied in part to many varied industrial enterprises. The advent of commercial nuclear power brought the evolution of a more comprehensive approach to the applications of quality assurance programs in this industry. However, the application philosophy was almost totally aimed at assuring the safety of the worker and the public. Recently, there has been a strong movement by industries and business in the U.S. and Europe to apply quality assurance in a more general way to assure overall reliability as well as safety. This paper describes an approach to enable management to not only make initial determinations of how to apply the elements of a reliability/quality assurance program, but how to continuously adjust the program to optimize the benefits that can be obtained
78 FR 54510 - New Entrant Safety Assurance Program Operational Test

Science.gov (United States)

2013-09-04

... safety management controls; (2) consider their effects on small businesses; and (3) consider establishing alternate locations where such reviews may be conducted for the convenience of small businesses. In response... safety review within 18 months of starting interstate operations. [49 U.S.C. 31144(g)]. In issuing these...
Quality assurance considerations for nuclear power system selection

International Nuclear Information System (INIS)

Bender, M.

1977-01-01

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

International Nuclear Information System (INIS)

Mullan, J.V.

1983-01-01

Quality assurance in the nuclear industry was born in the late 1960s. Atomic Energy Control Board staff began its regulatory practice on quality assurance during that period. In this presentation the author traces the circumstances that first led to the establishment of Canadian nuclear power plant quality assurance programmes, summarizes progress over the last decade and a half, and outlines the current regulatory approach and what has been learned so far
Radiation oncology and medical physicists quality assurance in British Columbia Cancer Agency Provincial Prostate Brachytherapy Program.

Science.gov (United States)

Keyes, Mira; Morris, William James; Spadinger, Ingrid; Araujo, Cynthia; Cheung, Arthur; Chng, Nick; Crook, Juanita; Halperin, Ross; Lapointe, Vince; Miller, Stacy; Pai, Howard; Pickles, Tom

2013-01-01

To describe in detail British Columbia (BC) Cancer Agency (BCCA) Provincial Prostate Brachytherapy (PB) Quality Assurance (QA) Program. The BCCA PB Program was established in 1997. It operates as one system, unified and supported by electronic and information systems, making it a single PB treatment provider for province of BC and Yukon. To date, >4000 patients have received PB (450 implants in 2011), making it the largest program in Canada. The Program maintains a large provincial prospective electronic database with records on all patients, including disease characteristics, risk stratification, pathology, preplan and postimplant dosimetric data, follow-up of prostate-specific antigen, and toxicity outcomes. QA was an integral part of the program since its inception. A formal QA Program was established in 2002, with key components that include: unified eligibility criteria and planning system, comprehensive database, physics and oncologist training and mentorship programs, peer review process, individual performance outcomes and feedback process, structured continuing education and routine assessment of the program's dosimetry, toxicity and prostate-specific antigen outcomes, administration and program leadership that promotes a strong culture of patient safety. The emphasis on creating a robust, broad-based network of skilled providers has been achieved by the program's requirements for training, education, and the QA process. The formal QA process is considered a key factor for the success of cancer control outcomes achieved at BCCA. Although this QA model may not be wholly transferable to all PB programs, some of its key components may be applicable to other programs to ensure quality in PB and patient safety. Crown Copyright © 2013. Published by Elsevier Inc. All rights reserved.
Quality assurance for gamma knives

International Nuclear Information System (INIS)

Jones, E.D.; Banks, W.W.; Fischer, L.E.

1995-09-01

This report describes and summarizes the results of a quality assurance (QA) study of the Gamma Knife, a nuclear medical device used for the gamma irradiation of intracranial lesions. Focus was on the physical aspects of QA and did not address issues that are essentially medical, such as patient selection or prescription of dose. A risk-based QA assessment approach was used. Sample programs for quality control and assurance are included. The use of the Gamma Knife was found to conform to existing standards and guidelines concerning radiation safety and quality control of external beam therapies (shielding, safety reviews, radiation surveys, interlock systems, exposure monitoring, good medical physics practices, etc.) and to be compliant with NRC teletherapy regulations. There are, however, current practices for the Gamma Knife not covered by existing, formalized regulations, standards, or guidelines. These practices have been adopted by Gamma Knife users and continue to be developed with further experience. Some of these have appeared in publications or presentations and are slowly finding their way into recommendations of professional organizations
Quality assurance for gamma knives

Energy Technology Data Exchange (ETDEWEB)

Jones, E.D.; Banks, W.W.; Fischer, L.E. [Lawrence Livermore National Lab., CA (United States)

1995-09-01

This report describes and summarizes the results of a quality assurance (QA) study of the Gamma Knife, a nuclear medical device used for the gamma irradiation of intracranial lesions. Focus was on the physical aspects of QA and did not address issues that are essentially medical, such as patient selection or prescription of dose. A risk-based QA assessment approach was used. Sample programs for quality control and assurance are included. The use of the Gamma Knife was found to conform to existing standards and guidelines concerning radiation safety and quality control of external beam therapies (shielding, safety reviews, radiation surveys, interlock systems, exposure monitoring, good medical physics practices, etc.) and to be compliant with NRC teletherapy regulations. There are, however, current practices for the Gamma Knife not covered by existing, formalized regulations, standards, or guidelines. These practices have been adopted by Gamma Knife users and continue to be developed with further experience. Some of these have appeared in publications or presentations and are slowly finding their way into recommendations of professional organizations.

Changing the S and MA [Safety and Mission Assurance] Paradigm

Science.gov (United States)

Malone, Roy W., Jr.

2010-01-01

Objectives: 1) Optimize S&MA organization to best facilitate Shuttle transition in 2010, successfully support Ares developmental responsibilities, and minimize the impacts of the gap between last Shuttle flight and start of Ares V Project. 2) Improve leveraging of critical skills and experience between Shuttle and Ares. 3) Split technical and supervisory functions to facilitate technical penetration. 4) Create Chief Safety and Mission Assurance Officer (CSO) stand-alone position for successfully implementation of S&MA Technical Authority. 5) Minimize disruption to customers. 6) Provide early involvement of S&MA leadership team and frequent/open communications with S&MA team members and steak-holders.
Quality assurance program plan for the radiological survey activities program: Uranium Mill Tailings Remedial Action Project

International Nuclear Information System (INIS)

Ramos, S.J.; Berven, B.A.; Little, C.A.

1986-08-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups
Quality assurance program plan for the Radiological Survey Activities Program - Uranium Mill Tailings Remedial Action Project

International Nuclear Information System (INIS)

Ramos, S.J.; Berven, B.A.; Little, C.A.

1986-01-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) is responsible for surveying designated sites in the vicinity of 24 inactive mill sites involved in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP). The purpose of these surveys is to provide a recommendation to DOE whether to include or exclude the site from UMTRAP based on whether the onsite residual radioactive material (if any) originated from the former mill sites, and radiation levels onsite are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the quality assurance program plan for the RASA program in conducting all activities related to the UMTRA project. All quality assurance provisions given by the DOE, DOE/UMTRA, and ORNL organizations are integrated into this plan. Specifically, this report identifies the policies and procedures followed in accomplishing the RASA/UMTRAP QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups
Core components of a comprehensive quality assurance program in anatomic pathology.

Science.gov (United States)

Nakhleh, Raouf E

2009-11-01

In this article the core components of a comprehensive quality assurance and improvement plan are outlined. Quality anatomic pathology work comes with focus on accurate, timely, and complete reports. A commitment to continuous quality improvement and a systems approach with a persistent effort helps to achieve this end. Departments should have a quality assurance and improvement plan that includes a risk assessment of real and potential problems facing the laboratory. The plan should also list the individuals responsible for carrying out the program with adequate resources, a defined timetable, and annual assessment for progress and future directions. Quality assurance monitors should address regulatory requirements and be organized by laboratory division (surgical pathology, cytology, etc) as well as 5 segments (preanalytic, analytic, postanalytic phases of the test cycle, turn-around-time, and customer satisfaction). Quality assurance data can also be used to evaluate individual pathologists using multiple parameters with peer group comparison.
Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

International Nuclear Information System (INIS)

VINCENT, Andrew

2005-01-01

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the
Chemical analysis quality assurance at the ICPP

International Nuclear Information System (INIS)

Hand, R.L.

1990-01-01

This document discusses the chemical analysis quality assurance program at the ICPP which involves records management, analytical methods quality control, analysis procedures and training and qualification. Since 1979, the major portion of the quality assurance program has been implemented on a central analytical computer system. The individual features provided by the system are storage, retrieval, and search capabilities over all general request and sample analysis information, automatic method selection for all process streams, automation of all method calculations, automatic assignment of bias and precision estimates at all analysis levels, with-method-use requalification, untrained or unqualified analyst method lockout, statistical testing of all process stream results for replicate agreement, automatic testing of process results against pre- established operating, safety, or failure limits at varying confidence levels, and automatic transfer and report of all analysis data plus all statistical testing to the Production Department
Occupational Safety and Health Program at the West Valley Demonstration Project

International Nuclear Information System (INIS)

L. M. Calderon

1999-01-01

The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment
U.S. Nuclear Regulatory Commission Safety Culture Oversight

International Nuclear Information System (INIS)

Sieracki, D. J.

2016-01-01

The NRC recognises that it is important for all organizations performing or overseeing regulated activities to establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The NRC’s approach to safety culture is based on the premise that licencees bear the primary responsibility for safety. The NRC provides oversight of safety culture through expectations detailed in policy statements, safety culture assessor training for NRC inspectors, the oversight process, and the Allegations and Enforcement Programs. The NRC’s Safety Culture Policy Statement (SCPS) sets forth the Commission’s expectation that individuals and organizations establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The SCPS is not a regulation. It applies to all licencees, certificate holders, permit holders, authorisation holders, holders of quality assurance program approvals, vendors and suppliers of safety-related components, and applicants for a licence, certificate, permit, authorisation, or quality assurance program approval, subject to NRC authority.
FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

Energy Technology Data Exchange (ETDEWEB)

GARVIN, L. J.; JENSEN, M. A.

2004-04-13

This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.
Program management plan for the conduct of a research, development, and demonstration program for improving the safety of nuclear powerplants

International Nuclear Information System (INIS)

1981-12-01

Congress passed Public Law 96-567, Nuclear Safety Research, Development, and Demonstration Act of 1980, (hereafter referred to as the Act) to provide for an accelerated and coordinated program of light water reactor safety research, development, and demonstration to be carried out by the Department of Energy. In order to assure that this program would be compatible with the needs of Nuclear Regulatory Commission (NRC) and industry, the Department of Energy (DOE) initiated its response to Section 4 of the Act by conducting individual information gathering meetings with NRC and a wide cross section of the nuclear industry. The Department received recommendations on needs of what type of activities would and would not be appropriate for the Department to assist in satisfying these needs. Based on the evaluation of these inputs, it is concluded that the Department's ongoing Light Water Reactor (LWR) safety program is responsive to the Act. Specifically, the Department's ongoing program includes tasks in the areas of regulatory assessment, risk assessment, fission product source term, and emergency preparedness as well as providing technical assistance to the Institute of Nuclear Power Operations (INPO) to improve training of nuclear power personnel. These were among the very high priority efforts that were identified as necessary and appropriate for support by the Department
Quality assurance program for surveillance of fast reactor mixed oxide fuel analytical chemistry

International Nuclear Information System (INIS)

Rein, J.E.; Zeigler, R.K.; Waterbury, G.R.; McClung, W.E.; Praetorius, P.R.; Delvin, W.L.

1976-01-01

An effective quality assurance program for the chemical analysis of nuclear fuel is essential to assure that the fuel will meet the strict chemical specifications required for optimum reactor performance. Such a program has been in operation since 1972 for the fuels manufactured for the Fast Flux Test Facility. This program, through the use of common quality control and calibration standards, has consistently provided high levels of agreement among laboratories in all areas of analysis. The paper presented gives a summary of the chemical specifications for the fuel and source material, an outline of the requirements for laboratory qualifications and the preparation of calibration and quality control materials, general administration details of the plan, and examples where the program has been useful in solving laboratory problems
Obtaining Valid Safety Data for Software Safety Measurement and Process Improvement

Science.gov (United States)

Basili, Victor r.; Zelkowitz, Marvin V.; Layman, Lucas; Dangle, Kathleen; Diep, Madeline

2010-01-01

We report on a preliminary case study to examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Our goal is to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. Our purpose was two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to identify potential risks due to incorrect application of the safety process, deficiencies in the safety process, or the lack of a defined process. One early outcome of this work was to show that there are structural deficiencies in collecting valid safety data that make software safety different from hardware safety. In our conclusions we present some of these deficiencies.
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
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
Balancing compliance and cost when implementing a Quality Assurance program

International Nuclear Information System (INIS)

Pickering, S.Y.

1997-12-01

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

International Nuclear Information System (INIS)

Jankovich, J.P.

1991-01-01

In this paper the quality assurance inspections of the transportation packaging supplier industry, conducted by the U.S. Nuclear Regulatory Commission (NRC) on a routine basis since 1989 are discussed. The term supplier is used to include designers, fabricators, and distributors that hold NRC approved Quality Assurance Programs and Certificates of Compliance for packagings to transport radioactive materials. The objective of the inspections is to provide assurance that transportation packagings are fabricated and procured in accordance with 10 CFR Parts 21 and 71 requirements. The inspections are conducted in a systematic and comprehensive manner, utilizing uniform inspection techniques in order to assure uniformity and comparability. During the April 1989 and May 1991 period approximately 21 inspections were conducted by the Transportation Branch, Office of Nuclear Material Safety and Safeguards of the NRC. The majority of the findings were identified in the areas of quality assurance procedures, control of special processes (e.g. welding, radiography), and maintenance of QA records
Quality assurance in nuclear power plant

International Nuclear Information System (INIS)

Magalhaes, M.T. de

1981-01-01

The factors related to the licensing procedures of a nuclear power plant (quality assurance and safety analysis) are presented and discussed. The consequences of inadequate attitudes towards these factors are shown and suggestions to assure the safety of nuclear power plants in Brazil are presented. (E.G.) [pt
The association between event learning and continuous quality improvement programs and culture of patient safety.

Science.gov (United States)

Mazur, Lukasz; Chera, Bhishamjit; Mosaly, Prithima; Taylor, Kinley; Tracton, Gregg; Johnson, Kendra; Comitz, Elizabeth; Adams, Robert; Pooya, Pegah; Ivy, Julie; Rockwell, John; Marks, Lawrence B

2015-01-01

To present our approach and results from our quality and safety program and to report their possible impact on our culture of patient safety. We created an event learning system (termed a "good catch" program) and encouraged staff to report any quality or safety concerns in real time. Events were analyzed to assess the utility of safety barriers. A formal continuous quality improvement program was created to address these reported events and make improvements. Data on perceptions of the culture of patient safety were collected using the Agency for Health Care Research and Quality survey administered before, during, and after the initiatives. Of 560 good catches reported, 367 could be ascribed to a specific step on our process map. The calculated utility of safety barriers was highest for those embedded into the pretreatment quality assurance checks performed by physicists and dosimetrists (utility score 0.53; 93 of 174) and routine checks done by therapists on the initial day of therapy. Therapists and physicists reported the highest number of good catches (24% each). Sixty-four percent of events were caused by performance issues (eg, not following standardized processes, including suboptimal communications). Of 31 initiated formal improvement events, 26 were successfully implemented and sustained, 4 were discontinued, and 1 was not implemented. Most of the continuous quality improvement program was conducted by nurses (14) and therapists (7). Percentages of positive responses in the patient safety culture survey appear to have increased on all dimensions (p continuous quality improvement programs can be successfully implemented and that there are contemporaneous improvements in the culture of safety. Copyright © 2015 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.
The Role and Quality of Software Safety in the NASA Constellation Program

Science.gov (United States)

Layman, Lucas; Basili, Victor R.; Zelkowitz, Marvin V.

2010-01-01

In this study, we examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Obtaining an accurate, program-wide picture of software safety risk is difficult across multiple, independently-developing systems. We leverage one source of safety information, hazard analysis, to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. The goal of this research is two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to quantify the level of risk presented by software in the hazard analysis. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. To quantify the importance of software, we collected metrics based on the number of software-related causes and controls of hazardous conditions. To quantify the level of risk presented by software, we created a metric scheme to measure the specificity of these software causes. We found that from 49-70% of hazardous conditions in the three systems could be caused by software or software was involved in the prevention of the hazardous condition. We also found that 12-17% of the 2013 hazard causes involved software, and that 23-29% of all causes had a software control. Furthermore, 10-12% of all controls were software-based. There is potential for inaccuracy in these counts, however, as software causes are not consistently scoped, and the presence of software in a cause or control is not always clear. The application of our software specificity metrics also identified risks in the hazard reporting process. In particular, we found a number of traceability risks in the hazard reports may impede verification of software and system safety.

Dukovany nuclear power plant safety

International Nuclear Information System (INIS)

1999-01-01

Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program
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
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)
Analysis of an image quality assurance program

International Nuclear Information System (INIS)

Goethlin, J.H.; Alders, B.

1985-01-01

Reject film analysis before and after the introduction of a quality assurance program showed a 45% decrease in rejected films. The main changes in equipment and routines were: 1. Increased control of film processors and X-ray generators. 2. New film casettes and screens. 3. Decreased number of film sizes. 4. Information to and supervision of radiographing personnel. Savings in costs and increased income from an increased amount of out-patients corresponded to about 4.5% of the total cost of operating and maintaining the department. (orig.)
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
Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

International Nuclear Information System (INIS)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program
Reliability assurance program for operational emergency ac power system

International Nuclear Information System (INIS)

Heineman, J.B.; Ragland, W.A.; Mueller, C.J.

1985-01-01

A comprehensive review of emergency ac power systems in nuclear generating plants (the vast majority of these plants contain redundant diesel generator systems) delineates several operational areas that can be improved by instituting a reliability assurance program (RAP), which initially upgrades the diesel generator performance and provides for ongoing monitoring and maintenance based upon alert levels
A strategy to develop and implement Canadian standards for quality assurance in radiation therapy

International Nuclear Information System (INIS)

1999-05-01

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

International Nuclear Information System (INIS)

O'Neill, L.J.

1989-01-01

This paper discusses a quality assurance program that would satisfy the requirements and expectations of the U.S. Department of Energy, the EPA, and the state of Nevada. The author outlines the basic philosophy, concepts, and implementation of the program that would satisfy all three agencies
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.)
The successful Chief Executive Officer understands quality assurance

International Nuclear Information System (INIS)

Hedges, D.

1984-01-01

The successful Chief Executive Officer (CEO) will have recognized the benefits of, and have implemented, a total quality assurance program. The quality assurance program will be adequately defined in policies and procedures such that managers and supervisors of each organizational element understand their primary and supporting roles in carrying out an effective quality assurance program. The traditional practice of having all quality assurance activities reside in a quality assurance organization will have been cast aside. Instead, the quality assurance activities necessary to achieve and assure the quality of the desired end product will have been defined and assigned to responsible organization elements. The quality assurance organization's primary role will be to define the total quality assurance program, insure that the achieving and assuring functions are assigned in policies and procedures, conduct training necessary to have management and supervisors understand the total quality assurance program, measure the effectiveness of the program and feedback measurement data for improvements in the program. The successful CEO will have implemented a quality assurance program that provides for a graded approach for application of the program based upon the importance of the intended use of the product or service. The successful CEO will rely heavily on the scheduled progress reports and assessments to measure the pulse of his organization's successes and improvement needs. This paper will describe suggested approaches for the Quality Assurance Manager to implement a quality assurance program which results in his corporation's CEO being a supporter of and a driving force in the implementation of the quality assurance program
77 FR 50723 - Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety...

Science.gov (United States)

2012-08-22

... regulations with respect to software verification and auditing of digital computer software used in the safety... Standards and Records,'' which requires, in part, that a quality assurance program be established and implemented to provide adequate assurance that systems and components important to safety will satisfactorily...
Regulatory activities in gaining assurance of training program effectiveness in Canada

International Nuclear Information System (INIS)

Legare, Michele

2003-01-01

This presentation shows the regulator's point of view on evaluating a training program effectiveness. The mission of the Training Program Evaluation Section of the Canadian Atomic Energy Control Board is to obtain and document assurance that the training of NPP operators is effective in providing them with the knowledge and skills needed to become and remain competent. Proposals are made to be considered when drafting the IAEA guideline on evaluation of training program effectiveness
Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification

Energy Technology Data Exchange (ETDEWEB)

Benoit, Timothy [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Hlotke, John Daniel [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Yacout, Abdellatif [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division

2017-07-05

This document contains an evaluation of the applicability of the current Quality Assurance Standards from the American Society of Mechanical Engineers Standard NQA-1 (NQA-1) criteria and identifies and describes the quality assurance process(es) by which attributes of historical, analytical, and other data associated with sodium-cooled fast reactor [SFR] metallic fuel and/or related reactor fuel designs and constituency will be evaluated. This process is being instituted to facilitate validation of data to the extent that such data may be used to support future licensing efforts associated with advanced reactor designs. The initial data to be evaluated under this program were generated during the US Integral Fast Reactor program between 1984-1994, where the data includes, but is not limited to, research and development data and associated documents, test plans and associated protocols, operations and test data, technical reports, and information associated with past United States Nuclear Regulatory Commission reviews of SFR designs.
Operating the plant, quality assurance, and the job of the operating staff, Volume Twelve

International Nuclear Information System (INIS)

Anon.

1986-01-01

Subject matter includes operating the plant (the role of the operator, the control room, plant technical specifications, plant operating procedures, initial startup program, BWR/PWR plant startup, BWR/PWR steady state power operation, BWR/PWR transient operation, emergency operation), quality assurance (what is quality, what is quality control, quality assurance includes quality control, government regulation and quality assurance, administrative controls for nuclear power plants, the necessity of reviews and audits, practical quality assurance), and the job of the operating staff (the plant operating staff, plant safety, first aid and resuscitation, general plant hazards, personnel protective equipment, handling chemicals, handling compressed gas, equipment repair and maintenance, communicating with others
Periodical in-service inspection as part of individual program of quality assurance of steam generators and pressurizers of WWER 440 nuclear power plant

International Nuclear Information System (INIS)

Kawalec, M.

1982-01-01

The manufacturers of equipment for nuclear power plants in the Czechoslovak Socialist Republic are obligated to process so-called individual programs of quality assurance in order to secure the quality of selected equipment in nuclear power. These programmes should include the evaluation of the design of the individual equipments with regard to the implementation of in-service inspection. The main problems are discussed related to the processing of the program of quality assurance for the steam generator and pressurizer. To solve these problems it is necessary that the general project designer should make a classification of the components according to safety categories and that the manufacturers should determine the weak points of the design on the basis of an analysis of the design of individual component nodes. On the basis of such an analysis it is then necessary to evaluate the existing design of the scale of in-service inspections and to decide whether or not new inspection methods should be added. (Z.M.)
Safety performance indicators program

International Nuclear Information System (INIS)

Vidal, Patricia G.

2004-01-01

In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)
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
Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Revision 1, Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

Davis, C. M.; El-Messidi, O. E.; Cowser, D. K.; Kannard, J. R.; Carvin, R. T.; Will, III, A. S.; Clark, Jr., C.; Garland, S. B.

1993-05-01

This Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES&H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES&H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements.
Operational safety at the FFTF

International Nuclear Information System (INIS)

Baird, Q.L.; Hagan, J.W.; Seeman, S.E.; Baker, S.M.

1981-02-01

An extensive operational nuclear safety program has been an integral part of the design, startup, and initial operating phases of the Fast Flux Test Facility (FFTF). During the design and construction of the facility, a program of independent safety overviews and analyses assured the provision of responsible safety margins within the plant, protective systems, and engineered safety features for protection of the public, operating staff, and the facility. The program is continuing through surveillance of operations to verify continued adherence to the established operating envelope and for timely identification of any trends potentially adverse to those margins. Experience from operation of FFTF is being utilized in the development of enhanced operational nuclear safety aids for application in follow-on breeder reactor power systems. The commendable plant and personnel safety experiences of FFTF through its startup and ascension to full power demonstrate the overall effectiveness of the FFTF operational nuclear safety program

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
49 CFR 385.313 - Who will conduct the safety audit?

Science.gov (United States)

2010-10-01

... FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.313 Who will conduct the safety audit? An individual certified under the FMCSA regulations to perform safety audits will conduct the safety audit. ... 49 Transportation 5 2010-10-01 2010-10-01 false Who will conduct the safety audit? 385.313 Section...
10 CFR 71.37 - Quality assurance.

Science.gov (United States)

2010-01-01

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

International Nuclear Information System (INIS)

Abaza, A.

2016-01-01

Radiotherapy (RT) has played important roles in cancer treatment for more than one century. The development of RT techniques allows high-dose irradiation to tumors while reducing the radiation doses delivered to surrounding normal tissues. However, RT is a complex process and involves understanding of the principles of medical physics, radiobiology, radiation safety, dosimetry, radiation treatment planning, simulation and interaction of radiation with other treatment modalities. Each step in the integrated process of RT needs quality control and quality assurance (QA) to prevent errors and to ensure that patients will receive the prescribed treatment correctly. The aim of this study is to help the radio therapists in identifying a system for QA that balances patient safety and quality with available resources. Recent advances in RT focus on the need for a systematic RT QA program that balances patient safety and quality with available resources. It is necessary to develop more formal error mitigation and process analysis methods, such as failure mode and effect analysis (FMEA), to focus available QA resources optimally on the process components. External audit programs are also effective. Additionally, Clinical trial QA has a significant role in enhancing the quality of care. The International Atomic Energy Agency (IAEA) has operated both an on-site and off-site postal dosimetry audit to improve practice and to assure the dose from RT equipment. Both postal dosimetry audit and clinical trial RTQA, especially for advanced technologies, in collaboration with global networks, will serve to enhance patient safety and quality of care
Development of a VMAT quality assurance program

International Nuclear Information System (INIS)

Silva, Ricardo Goulart da

2013-01-01

Modern radiation therapy keeps evolving and the technological changes include new imaging modalities, new patient immobilization devices and new treatment delivery systems. These advances have made it possible to reduce the dose to normal tissue structures and consequently minimize the risk of toxicity and morbidity, while allowing for dose escalation to the tumor volumes, potentially leading to improved locoregional control. Traditional IMRT techniques offer all of these features but the treatment session time is usually long, mainly for the head and neck cases. Currently, the VMAT technique is a reality in reference centers around the world. This technology has improved delivery efficiency over IMRT, decreasing the treatment application time, as this modality introduces extra degrees of freedom in the optimization process. The modulation of the radiation beams is achieved by simultaneous variation of dynamic parameters such as dose rate, gantry speed and leaves speed. The high level of complexity associated to the new treatment trends, inevitably, requires more accuracy and more rigorous quality assurance programs. The commissioning methods reported for the Varian RapidArc system were extended to an Elekta Synergy linear accelerator, using custom files built in the iComCAT software. Specific tests for the machine quality assurance are presented and also the dosimetric validation process applied to the Monaco treatment planning system. The MLC parameters, modeled by the Monte Carlo algorithm, were analyzed and the TG 119 tests were adapted for VMAT planning. In the end, a specific program developed for the VMAT technology for Elekta accelerators is presented. (author)
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
Nuclear quality assurance programs, their role and their impacts

International Nuclear Information System (INIS)

Lex, B.L.

1978-01-01

The major steps in the development of control and instrumentation design requirements for a nuclear station, the execution of the detailed design and the procurement, installation and start-up of the control equipment and systems are outlined. The principal quality assurance program requirements related to each of these steps are described and the impact of these requirements on the conduct of the work are examined. (author)
Darlington steam generator life assurance program

International Nuclear Information System (INIS)

Jelinski, E.; Dymarski, M.; Maruska, C.; Cartar, E.

1995-01-01

The Darlington Nuclear Generating Station belonging to Ontario Hydro is one of the most modern and advanced nuclear generating stations in the world. Four reactor units each generate 881 net MW, enough to provide power to a major city, and representing approximately 20% of the Ontario grid. The nuclear generating capacity in Ontario represents approximately 60% of the grid. In order to look after this major asset, many proactive preventative and predictive maintenance programs are being put in place. The steam generators are a major component in any power plant. World wide experience shows that nuclear steam generators require specialized attention to ensure reliable operation over the station life. This paper describes the Darlington steam generator life assurance program in terms of degradation identification, monitoring and management. The requirements for chemistry control, surveillance of process parameters, surveillance of inspection parameters, and the integration of preventative and predictive maintenance programs such as water lancing, chemical cleaning, RIHT monitoring, and other diagnostics to enhance our understanding of life management issues are identified and discussed. We conclude that we have advanced proactive activities to avoid and to minimize many of the problems affecting other steam generators. An effective steam generator maintenance program must expand the knowledge horizon to understand life limiting processes and to analyze and synthesize observations with theory. (author)
Patient dosimetry quality assurance program with a commerical diode system

International Nuclear Information System (INIS)

Lee, P.C.; Sawicka, J.M.; Glasgow, G.P.

1994-01-01

The purpose was to evaluate a commercial silicone diode dosimeter for a patient dosimetry quality assurance program. The diode dosimeter was calibrated against an ion chamber, and percentage depth dose, linearity, anisotrophy, virtual source position, and field size factor studies were performed. Correction factors for lack of full scatter medium in the diode entrance and exit dose measurements were acquired. Dosimetry equations were proposed for calculation of dose delivered at isocenter. Diode dose accuracy and reproducibility were tested on phantom and on four patients. A patient dosimetry quality assurance program based on diode-measured dose was instituted and patient dose data were collected. Diode measured percentage depth dose and field factors agreed to within 3% with those measured with an ion chamber. The diode exhibited less than 1.7% angular dose anisotrophy and less than 0.5% nonlinearity up to 4 Gy. Diode dose measurements in phantom showed that the calculated doses differed from the prescribed dose by less than 1.%; the diode exhibited a daily dose reproducibility of better than 0.2%. On four selected patients, the measured dose reproducibility was 1.5%; the average calculated doses were all within ± 7% of the prescribed doses. For 33 of 40 patients treated with a 6 MW beam, measured doses were within ± 7% of the prescribed doses. For 11 out of 12 patients, a second repeat measurements yielded doses within ± 7% of the prescribed doses. The proposed diode-based patient dosimetry quality assurance program with dose tolerance at ± 7% is simple and feasible. It is capable of detecting certain serious treatment errors such as incorrect daily dose greater than 7%, incorrect wedge use, incorrect photon energy and patient setup errors involving some incorrect source-to-surface-distance vs. source-to-axis-distance treatments. 13 refs., 5 figs., 5 tabs
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
Management of a comprehensive radiation safety program in a major American University and affiliated academic medical center

International Nuclear Information System (INIS)

Yoshizumi, T.T.; Reiman, R.E.; Vylet, V.; Clapp, J.R.; Thomann, W.R.; Lyles, K.W.

2000-01-01

Duke University, which operates under eight radiation licenses issued by the State of North Carolina, consists of a leading medical center including extensive inpatient and outpatient facilities, a medical school, biomedical research labs, and an academic campus including two major accelerator facilities. The Nuclear Medicine and Radiation Oncology departments handle over 40,000 diagnostic and therapeutic procedures annually, including approximately 160 radioiodine therapeutic cases. In biomedical research labs, about 300 professors are authorized to use radioactive materials. Over 2,000 radiation workers are identified on campus. Over the past two years, we have transformed the existing radiation safety program into a more responsive and more accountable one. Simultaneously, the institutional 'culture' changed, and the Radiation Safety Division came to be viewed as a helpful ally by investigators. The purpose of this paper is to present our experiences that have made this transformation possible. Our initiatives included; (a) defining short-term and long-term goals; (b) establishing a definitive chain of authority; (c) obtaining an external review by a consultant Health Physicist; (d) improving existing radiation safety programs; (e) reorganizing the Radiation Safety Division, with creation of multidisciplinary professional staff positions; (f) implementing campus-wide radiation safety training, (g) increasing technician positions; (h) establishing monthly medical center radiation safety executive meeting. As a result progress made at the Divisional level includes; (a) culture change by recruiting professionals with academic credentials and recent college graduates; (b) implementing weekly staff meetings and monthly quality assurance meetings; (c) achieving academic prominence by publishing and presenting papers in national meetings; (d) senior staff achieving faculty appointments with academic departments; (e) senior staff participating in graduate student
Concepts of nuclear quality assurance

International Nuclear Information System (INIS)

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

1976-01-01

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

Science.gov (United States)

Cheng, Mei-Ai; Leung, Noel W.

2014-01-01

This study examines the current government policy and institutional practice on quality assurance of non-local accounting programs conducted in Hong Kong. Both international guidelines, national regulations and institutional frameworks in higher education and transnational higher education, and professional practice in accounting education are…
Quality Assurance in Gerontological and Geriatric Training Programs: The European Case

Science.gov (United States)

Politynska, Barbara; van Rijsselt, Rene J. T.; Lewko, Jolanta; Philp, Ian; Figueiredo, Daniella; De Sousa, Lilliana

2012-01-01

Quality assurance (QA) in gerontological and geriatric education programs is regarded as essential to maintain standards, strengthen accountability, improve readability of qualifications, and facilitate professional mobility. In this article the authors present a summary of international developments in QA and elaborate four international trends,…
49 CFR 385.315 - Where will the safety audit be conducted?

Science.gov (United States)

2010-10-01

... SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.315 Where will the safety audit be conducted? The safety audit will generally be conducted at the new entrant's business premises. ... 49 Transportation 5 2010-10-01 2010-10-01 false Where will the safety audit be conducted? 385.315...
Nursing Student Experiences Regarding Safe Use of Electronic Health Records: A Pilot Study of the Safety and Assurance Factors for EHR Resilience Guides.

Science.gov (United States)

Whitt, Karen J; Eden, Lacey; Merrill, Katreena Collette; Hughes, Mckenna

2017-01-01

Previous research has linked improper electronic health record configuration and use with adverse patient events. In response to this problem, the US Office of the National Coordinator for Health Information Technology developed the Safety and Assurance Factors for EHR Resilience guides to evaluate electronic health records for optimal use and safety features. During the course of their education, nursing students are exposed to a variety of clinical practice settings and electronic health records. This descriptive study evaluated 108 undergraduate and 51 graduate nursing students' ratings of electronic health record features and safe practices, as well as what they learned from utilizing the computerized provider order entry and clinician communication Safety and Assurance Factors for EHR Resilience guide checklists. More than 80% of the undergraduate and 70% of the graduate students reported that they experienced user problems with electronic health records in the past. More than 50% of the students felt that electronic health records contribute to adverse patient outcomes. Students reported that many of the features assessed were not fully implemented in their electronic health record. These findings highlight areas where electronic health records can be improved to optimize patient safety. The majority of students reported that utilizing the Safety and Assurance Factors for EHR Resilience guides increased their understanding of electronic health record features.
49 CFR 385.311 - What will the safety audit consist of?

Science.gov (United States)

2010-10-01

... SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.311 What will the safety audit consist of? The safety audit will consist of a review of the new entrant's safety management systems and a... 49 Transportation 5 2010-10-01 2010-10-01 false What will the safety audit consist of? 385.311...
Safety considerations in the design and operation of large wind turbines

Science.gov (United States)

Reilly, D. H.

1979-01-01

The engineering and safety techniques used to assure the reliable and safe operation of large wind turbine generators utilizing the Mod 2 Wind Turbine System Program as an example is described. The techniques involve a careful definition of the wind turbine's natural and operating environments, use of proven structural design criteria and analysis techniques, an evaluation of potential failure modes and hazards, and use of a fail safe and redundant component engineering philosophy. The role of an effective quality assurance program, tailored to specific hardware criticality, and the checkout and validation program developed to assure system integrity are described.
Geologic software for nuclear waste repository studies: A quality assurance program

International Nuclear Information System (INIS)

Figuli, S.; English, S.L.

1987-04-01

This paper discusses a Quality Assurance (QA) program that Kent State University (KSU) has implemented for the development of geologic software. The software being developed at KSU will be used in the site characterization of nuclear waste repositories and must meet the requirements of federal regulations. This QA program addresses the development of models that will be used in the evaluation of the long-term climatic stability of three sites in the western US
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.)

NIF Projects Controls and Information Systems Software Quality Assurance Plan

Energy Technology Data Exchange (ETDEWEB)

Fishler, B

2011-03-18

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

International Nuclear Information System (INIS)

Fishler, B.

2011-01-01

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

Science.gov (United States)

Moghadam, Marjan; Jahangiri, Leila

2015-08-01

An electronic quality assurance (eQA) program was developed to replace a paper-based system and to address standards introduced by the Commission on Dental Accreditation (CODA) and to improve educational outcomes. This eQA program provides feedback to predoctoral dental students on prosthodontic laboratory steps at New York University College of Dentistry. The purpose of this study was to compare the eQA program of performing laboratory quality assurance with the former paper-based format. Fourth-year predoctoral dental students (n=334) who experienced both the paper-based and the electronic version of the quality assurance program were surveyed about their experiences. Additionally, data extracted from the eQA program were analyzed to identify areas of weakness in the curriculum. The study findings revealed that 73.8% of the students preferred the eQA program to the paper-based version. The average number of treatments that did not pass quality assurance standards was 119.5 per month. This indicated a 6.34% laboratory failure rate. Further analysis of these data revealed that 62.1% of the errors were related to fixed prosthodontic treatment, 27.9% to partial removable dental prostheses, and 10% to complete removable dental prostheses in the first 18 months of program implementation. The eQA program was favored by dental students who have experienced both electronic and paper-based versions of the system. Error type analysis can yield the ability to create customized faculty standardization sessions and refine the didactic and clinical teaching of the predoctoral students. This program was also able to link patient care activity with the student's laboratory activities, thus addressing the latest requirements of the CODA regarding the competence of graduates in evaluating laboratory work related to their patient care. Copyright © 2015 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.
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
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
Audit Report The Procurement of Safety Class/Safety-Significant Items at the Savannah River Site

International Nuclear Information System (INIS)

2009-01-01

The Department of Energy operates several nuclear facilities at its Savannah River Site, and several additional facilities are under construction. This includes the National Nuclear Security Administration's Tritium Extraction Facility (TEF) which is designated to help maintain the reliability of the U.S. nuclear stockpile. The Mixed Oxide Fuel Fabrication Facility (MOX Facility) is being constructed to manufacture commercial nuclear reactor fuel assemblies from weapon-grade plutonium oxide and depleted uranium. The Interim Salt Processing (ISP) project, managed by the Office of Environmental Management, will treat radioactive waste. The Department has committed to procuring products and services for nuclear-related activities that meet or exceed recognized quality assurance standards. Such standards help to ensure the safety and performance of these facilities. To that end, it issued Departmental Order 414.1C, Quality Assurance (QA Order). The QA Order requires the application of Quality Assurance Requirements for Nuclear Facility Applications (NQA-1) for nuclear-related activities. The NQA-1 standard provides requirements and guidelines for the establishment and execution of quality assurance programs during the siting, design, construction, operation, and decommissioning of nuclear facilities. These requirements, promulgated by the American Society of Mechanical Engineers, must be applied to 'safety-class' and 'safety-significant' structures, systems and components (SSCs). Safety-class SSCs are defined as those necessary to prevent exposure off site and to protect the public. Safety-significant SSCs are those whose failure could irreversibly impact worker safety such as a fatality, serious injury, or significant radiological or chemical exposure. Due to the importance of protecting the public, workers, and environment, we initiated an audit to determine whether the Department of Energy procured safety-class and safety-significant SSCs that met NQA-1 standards at
200 area liquid effluent facility quality assurance program plan. Revision 1

International Nuclear Information System (INIS)

Sullivan, N.J.

1995-01-01

Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities
42 CFR 422.210 - Assurances to CMS.

Science.gov (United States)

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Assurances to CMS. 422.210 Section 422.210 Public...) MEDICARE PROGRAM MEDICARE ADVANTAGE PROGRAM Relationships With Providers § 422.210 Assurances to CMS. (a) Assurances to CMS. Each organization will provide assurance satisfactory to the Secretary that the...
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
49 CFR 385.319 - What happens after completion of the safety audit?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false What happens after completion of the safety audit... REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.319 What happens after completion of the safety audit? (a) Upon completion of the safety audit, the auditor will review the findings...
Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

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

International Nuclear Information System (INIS)

Newsom, H.C.

1999-01-01

This quality assurance project plan (QAPjP) summarizes requirements used by Lockheed Martin Energy Systems, Incorporated (LMES) Development Division at Y-12 for conducting chemical reactivity testing of Department of Energy (DOE) owned spent nuclear fuel, sponsored by the National Spent Nuclear Fuel Program (NSNFP). The requirements are based on the NSNFP Statement of Work PRO-007 (Statement of Work for Laboratory Determination of Uranium Hydride Oxidation Reaction Kinetics.) This QAPjP will utilize the quality assurance program at Y-12, QA-101PD, revision 1, and existing implementing procedures for the most part in meeting the NSNFP Statement of Work PRO-007 requirements, exceptions will be noted
Environment, safety and health, management and organization compliance assessment, West Valley Demonstration Program, West Valley, New York

International Nuclear Information System (INIS)

1989-08-01

An Environment, Safety and Health ''Tiger Team'' Assessment was conducted at the West Valley Demonstration Project. The Tiger Team was chartered to conduct an onsite, independent assessment of WVDP's environment, safety and health (ES ampersand H) programs to assure compliance with applicable Federal and State laws, regulations, and standards, and Department of Energy Orders. The objective is to provide to the Secretary of Energy the following information: current ES ampersand H compliance status of each facility; specific noncompliance items; ''root causes'' for noncompliance items; evaluation of the adequacy of ES ampersand H organization and resources (DOE and contractor) and needed modifications; and where warranted, recommendations for addressing identified problem areas
Cascade Distillation System Design for Safety and Mission Assurance

Science.gov (United States)

Sarguisingh, Miriam; Callahan, Michael R.; Okon, Shira

2015-01-01

Per the NASA Human Health, Life Support and Habitation System Technology Area 06 report "crewed missions venturing beyond Low-Earth Orbit (LEO) will require technologies with improved reliability, reduced mass, self-sufficiency, and minimal logistical needs as an emergency or quick-return option will not be feasible".1 To meet this need, the development team of the second generation Cascade Distillation System (CDS 2.0) chose a development approach that explicitly incorporate consideration of safety, mission assurance, and autonomy. The CDS 2.0 preliminary design focused on establishing a functional baseline that meets the CDS core capabilities and performance. The critical design phase is now focused on incorporating features through a deliberative process of establishing the systems failure modes and effects, identifying mitigation strategies, and evaluating the merit of the proposed actions through analysis and test. This paper details results of this effort on the CDS 2.0 design.
Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

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

Science.gov (United States)

Fitz, Rhonda; Whitman, Gerek

2016-01-01

Research into complexities of software systems Fault Management (FM) and how architectural design decisions affect safety, preservation of assets, and maintenance of desired system functionality has coalesced into a technical reference (TR) suite that advances the provision of safety and mission assurance. The NASA Independent Verification and Validation (IV&V) Program, with Software Assurance Research Program support, extracted FM architectures across the IV&V portfolio to evaluate robustness, assess visibility for validation and test, and define software assurance methods applied to the architectures and designs. This investigation spanned IV&V projects with seven different primary developers, a wide range of sizes and complexities, and encompassed Deep Space Robotic, Human Spaceflight, and Earth Orbiter mission FM architectures. The initiative continues with an expansion of the TR suite to include Launch Vehicles, adding the benefit of investigating differences intrinsic to model-based FM architectures and insight into complexities of FM within an Agile software development environment, in order to improve awareness of how nontraditional processes affect FM architectural design and system health management. The identification of particular FM architectures, visibility, and associated IV&V techniques provides a TR suite that enables greater assurance that critical software systems will adequately protect against faults and respond to adverse conditions. Additionally, the role FM has with regard to strengthened security requirements, with potential to advance overall asset protection of flight software systems, is being addressed with the development of an adverse conditions database encompassing flight software vulnerabilities. Capitalizing on the established framework, this TR suite provides assurance capability for a variety of FM architectures and varied development approaches. Research results are being disseminated across NASA, other agencies, and the
Environment, Safety, and Health Self-Assessment Report, Fiscal Year 2008

Energy Technology Data Exchange (ETDEWEB)

Chernowski, John

2009-02-27

Lawrence Berkeley National Laboratory's Environment, Safety, and Health (ES&H) Self-Assessment Program ensures that Integrated Safety Management (ISM) is implemented institutionally and by all divisions. The Self-Assessment Program, managed by the Office of Contract Assurance (OCA), provides for an internal evaluation of all ES&H programs and systems at LBNL. The functions of the program are to ensure that work is conducted safely, and with minimal negative impact to workers, the public, and the environment. The Self-Assessment Program is also the mechanism used to institute continuous improvements to the Laboratory's ES&H programs. The program is described in LBNL/PUB 5344, Environment, Safety, and Health Self-Assessment Program and is composed of four distinct assessments: the Division Self-Assessment, the Management of Environment, Safety, and Health (MESH) review, ES&H Technical Assurance, and the Appendix B Self-Assessment. The Division Self-Assessment uses the five core functions and seven guiding principles of ISM as the basis of evaluation. Metrics are created to measure performance in fulfilling ISM core functions and guiding principles, as well as promoting compliance with applicable regulations. The five core functions of ISM are as follows: (1) Define the Scope of Work; (2) Identify and Analyze Hazards; (3) Control the Hazards; (4) Perform the Work; and (5) Feedback and Improvement. The seven guiding principles of ISM are as follows: (1) Line Management Responsibility for ES&H; (2) Clear Roles and Responsibilities; (3) Competence Commensurate with Responsibilities; (4) Balanced Priorities; (5) Identification of ES&H Standards and Requirements; (6) Hazard Controls Tailored to the Work Performed; and (7) Operations Authorization. Performance indicators are developed by consensus with OCA, representatives from each division, and Environment, Health, and Safety (EH&S) Division program managers. Line management of each division performs the
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
Management of national nuclear power programs for assured safety. Report of visit by international participants to INEL on August 24, 1985

International Nuclear Information System (INIS)

Rouhani, S.Z.

1985-10-01

Through a special arrangement with the US State Department and support from the Department of Energy a group of high ranking officials from six different countries visited the Idaho National Engineering Laboratory on August 24, 1985. They were briefed on the highlights of the US-NRC's nuclear safety research programs at the INEL. The purpose of this project was to broadcast the advancements of the US nuclear safety technology to other nations that are at the start of major programs for peaceful use of nuclear energy in their countries
SOCTESQA - Solid Oxide Cell and Stack Testing, Safety and Quality Assurance

OpenAIRE

Lang, Michael; Auer, Corinna; Couturier, Karine; Nielsen, Eva Ravn; Mc Phail, Stephen; Kotsionopoulos, Nikolaos; FU, Qingxi; Liu, Qinglin

2015-01-01

For the successful market penetration of high temperature solid oxide fuel/electrolysis cell energy systems it is necessary to increase the quality assurance and the reliable assessment of the corresponding cells and stacks. Therefore in May 2014 the EU-funded project SOCTESQA was launched. Partners from different countries in Europe and one external party from Singapore are working together to develop uniform and industry wide test procedures and programs for solid oxide cell/stack (SOC) ass...

Role of Informatics in Patient Safety and Quality Assurance.

Science.gov (United States)

Nakhleh, Raouf E

2015-06-01

Quality assurance encompasses monitoring daily processes for accurate, timely, and complete reports in surgical pathology. Quality assurance also includes implementation of policies and procedures that prevent or detect errors in a timely manner. This article presents uses of informatics in quality assurance. Three main foci are critical to the general improvement of diagnostic surgical pathology. First is the application of informatics to specimen identification with lean methods for real-time statistical control of specimen receipt and processing. Second is the development of case reviews before sign-out. Third is the development of information technology in communication of results to assure treatment in a timely manner. Copyright © 2015 Elsevier Inc. All rights reserved.
Risk-Informed Safety Assurance and Probabilistic Assessment of Mission-Critical Software-Intensive Systems

Science.gov (United States)

Guarro, Sergio B.

2010-01-01

This report validates and documents the detailed features and practical application of the framework for software intensive digital systems risk assessment and risk-informed safety assurance presented in the NASA PRA Procedures Guide for Managers and Practitioner. This framework, called herein the "Context-based Software Risk Model" (CSRM), enables the assessment of the contribution of software and software-intensive digital systems to overall system risk, in a manner which is entirely compatible and integrated with the format of a "standard" Probabilistic Risk Assessment (PRA), as currently documented and applied for NASA missions and applications. The CSRM also provides a risk-informed path and criteria for conducting organized and systematic digital system and software testing so that, within this risk-informed paradigm, the achievement of a quantitatively defined level of safety and mission success assurance may be targeted and demonstrated. The framework is based on the concept of context-dependent software risk scenarios and on the modeling of such scenarios via the use of traditional PRA techniques - i.e., event trees and fault trees - in combination with more advanced modeling devices such as the Dynamic Flowgraph Methodology (DFM) or other dynamic logic-modeling representations. The scenarios can be synthesized and quantified in a conditional logic and probabilistic formulation. The application of the CSRM method documented in this report refers to the MiniAERCam system designed and developed by the NASA Johnson Space Center.
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)
Quality factors quantification/assurance for software related to safety in nuclear power plants

International Nuclear Information System (INIS)

Nunez McLeod, J.E.; Rivera, S.S.

1997-01-01

Quality assurance plan is needed to guarantee the software quality. The use of such a plan involves activities that should take place all along the life cycle, and which can be evaluated using the so called quality factors. This is due to the fact that the quality itself cannot be measured, but some of its manifestations can be used for this purpose. In the present work, a methodology to quantify a set of quality factors is proposed, for software based systems to be used in safety related areas in nuclear power plants. (author) [es
2011 Annual Criticality Safety Program Performance Summary

Energy Technology Data Exchange (ETDEWEB)

Andrea Hoffman

2011-12-01

The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The
10 CFR 70.62 - Safety program and integrated safety analysis.

Science.gov (United States)

2010-01-01

...; (iv) Potential accident sequences caused by process deviations or other events internal to the... have experience in nuclear criticality safety, radiation safety, fire safety, and chemical process... this safety program; namely, process safety information, integrated safety analysis, and management...
Standard guide for establishing a quality assurance program for analytical chemistry laboratories within the nuclear industry

CERN Document Server

American Society for Testing and Materials. Philadelphia

2006-01-01

1.1 This guide covers the establishment of a quality assurance (QA) program for analytical chemistry laboratories within the nuclear industry. Reference to key elements of ANSI/ISO/ASQC Q9001, Quality Systems, provides guidance to the functional aspects of analytical laboratory operation. When implemented as recommended, the practices presented in this guide will provide a comprehensive QA program for the laboratory. The practices are grouped by functions, which constitute the basic elements of a laboratory QA program. 1.2 The essential, basic elements of a laboratory QA program appear in the following order: Section Organization 5 Quality Assurance Program 6 Training and Qualification 7 Procedures 8 Laboratory Records 9 Control of Records 10 Control of Procurement 11 Control of Measuring Equipment and Materials 12 Control of Measurements 13 Deficiencies and Corrective Actions 14
49 CFR 385.309 - What is the purpose of the safety audit?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false What is the purpose of the safety audit? 385.309... SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.309 What is the purpose of the safety audit? The purpose of a safety audit is to: (a) Provide educational and technical assistance to...
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
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
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
A Laboratory Safety Program at Delaware.

Science.gov (United States)

Whitmyre, George; Sandler, Stanley I.

1986-01-01

Describes a laboratory safety program at the University of Delaware. Includes a history of the program's development, along with standard safety training and inspections now being implemented. Outlines a two-day laboratory safety course given to all graduate students and staff in chemical engineering. (TW)
Preliminary safety information document for the standard MHTGR. Volume 4

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)
How does the culture of medical group practices influence the types of programs used to assure quality of care?

Science.gov (United States)

Kaissi, Amer; Kralewski, John; Curoe, Ann; Dowd, Bryan; Silversmith, Janet

2004-01-01

develop quality assurance programs that fit their cultures if they are to gain buy-in by their clinicians. Future research should assess the effect of culture-structure fit on quality and safety outcomes.
Operational safety

International Nuclear Information System (INIS)

Anon.

1977-01-01

The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness
Nordic Nuclear Safety Research. Presentation of the 1994 - 1997 program

International Nuclear Information System (INIS)

Bennerstedt, Torkel

1998-01-01

NKS (Nordic Nuclear Safety Research) has just concluded its fifth 4-year program (1994 - 1997). The following nine projects were performed: Strategy for reactor safety: Studies of preparatory work to minimize the risk of accidents; Prevention of severe reactor accidents: studies of recriticality, core melt progression and support systems to minimize releases; Safe disposal of radioactive waste: Waste characterization, Performance analyses and environmental impact statements for repositories; Marine radioecology: Improved assessment methods for effects of releases of radionuclides; Long ecological half-lives in semi-natural systems: Models for transfer of cesium from nature to man; Preparedness strategies and procedures: Mobile measurements, quality assurance and interventions; Emergency preparedness drills and exercises; Preplanning of early cleanup: Check-list for planners and decision makers for various environments and fallout situations; Overriding information issues: Risk communication, real-time exchange of information after an accident. Together with additional financial support from a number of ministries and companies in the nuclear power field, the total NKS budget for the period 1994 - 1997 was some USD 5 million, evenly distributed over the years. To this should be added contributions in kind by participating organizations, worth at least another USD 10 million, without which this program would not have been possible. The nine projects and some practical results (rather than scientific detail) are outlined in this paper. (EG)
77 FR 70409 - System Safety Program

Science.gov (United States)

2012-11-26

...-0060, Notice No. 2] 2130-AC31 System Safety Program AGENCY: Federal Railroad Administration (FRA... rulemaking (NPRM) published on September 7, 2012, FRA proposed regulations to require commuter and intercity passenger railroads to develop and implement a system safety program (SSP) to improve the safety of their...
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
Using RUFDATA to guide a logic model for a quality assurance process in an undergraduate university program.

Science.gov (United States)

Sherman, Paul David

2016-04-01

This article presents a framework to identify key mechanisms for developing a logic model blueprint that can be used for an impending comprehensive evaluation of an undergraduate degree program in a Canadian university. The evaluation is a requirement of a comprehensive quality assurance process mandated by the university. A modified RUFDATA (Saunders, 2000) evaluation model is applied as an initiating framework to assist in decision making to provide a guide for conceptualizing a logic model for the quality assurance process. This article will show how an educational evaluation is strengthened by employing a RUFDATA reflective process in exploring key elements of the evaluation process, and then translating this information into a logic model format that could serve to offer a more focussed pathway for the quality assurance activities. Using preliminary program evaluation data from two key stakeholders of the undergraduate program as well as an audit of the curriculum's course syllabi, a case is made for, (1) the importance of inclusivity of key stakeholders participation in the design of the evaluation process to enrich the authenticity and accuracy of program participants' feedback, and (2) the diversification of data collection methods to ensure that stakeholders' narrative feedback is given ample exposure. It is suggested that the modified RUFDATA/logic model framework be applied to all academic programs at the university undergoing the quality assurance process at the same time so that economies of scale may be realized. Copyright © 2015 Elsevier Ltd. All rights reserved.
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

Criteria for designing an MRI quality assurance program. A multicenter trial

International Nuclear Information System (INIS)

Mascaro, L.; Baldassarri, A.M.

1999-01-01

The authors report the preliminary results of a multicenter trial aimed at defining methods, reference values and frequency of measurements for a magnetic resonance quality assurance program. In particular, they stress the definition of two attention levels (investigation and intervention) for image uniformity and signal-to-noise ratio (SNR) by means short-and long-term measurements [it
Surveillance of Salmonella enteritidis in layer houses: a retrospective comparison of the Food and Drug Administration's egg safety rule (2010-2011) and the California Egg Quality Assurance Program (2007-2011).

Science.gov (United States)

Pitesky, Maurice; Charlton, Bruce; Bland, Mark; Rolfe, Dan

2013-03-01

Between July 2007 and December 2011, 2660 environmental drag swab samples were collected in total from California layer flocks on behalf of the California Egg Quality Assurance Program (CEQAP), the egg safety rule (21 CFR Parts 16 and 118) of the Food and Drug Administration (FDA), or both. The samples were processed by the California Animal Health and Food Safety Lab, and positive or negative results for Salmonella enterica serovar Enteritidis (SE) were recorded. This study retrospectively compares the differences between the FDA and CEQAP programs with respect to their SE environmental sampling surveillance results. To accomplish this comparison, two different CEQAP (new and old) data sets representing different SE environmental surveillance approaches in the life of the flock were compared against each other and against the FDA's SE environmental testing plan. Significant differences were noted between the CEQAP and FDA programs with respect to the prevalence of SE in the farm environment. Analyses of the prevalence of SE at different stages in the flock's life cycle (chick papers, preproduction, midproduction, postmolt, and premarket) found the highest prevalence of SE in premarket (11.9%), followed by postmolt (3.5%) and midproduction (3.4%), and there was a tie between chick papers and preproduction (2.1%). To assess the main effects of the presence of SE in the farm environment, backwards binary logistic regression was used. Of six independent variables examined (age of flock, year, season, owner, CEQAP membership, and analysis of pooled samples vs. individual swabs), only age of flock, owner, and year were determined to be significant factors in the final model. Although CEQAP membership and pooling vs. individuals swabs were not included in the final model, Pearson chi-square tests did show significantly higher odds of SE for non-CEQAP member farms and higher odds of SE in pooled samples vs. individual swabs.
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)
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)
Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Novsak, M.

2001-01-01

The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)
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
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
Organizational Culture and Safety

Science.gov (United States)

Adams, Catherine A.

2003-01-01

'..only a fool perseveres in error.' Cicero. Humans will break the most advanced technological devices and override safety and security systems if they are given the latitude. Within the workplace, the operator may be just one of several factors in causing accidents or making risky decisions. Other variables considered for their involvement in the negative and often catastrophic outcomes include the organizational context and culture. Many organizations have constructed and implemented safety programs to be assimilated into their culture to assure employee commitment and understanding of the importance of everyday safety. The purpose of this paper is to examine literature on organizational safety cultures and programs that attempt to combat vulnerability, risk taking behavior and decisions and identify the role of training in attempting to mitigate unsafe acts.
Quality assurance measures applicable to IAEA anomaly and discrepancy resolution (ISPO Task D.52). Program for technical assistance to IAEA safeguards

International Nuclear Information System (INIS)

Harms, N.L.; Smith, B.W.

1984-11-01

The International Atomic Energy Agency (IAEA) safeguards program provides assurance to the international community that nations comply with their commitments for the peaceful use of nuclear energy. This assurance is based on the capabilities of the IAEA safeguards program to detect diversion of nuclear material. Anomalies and discrepancies, which occur in the event of a diversion or concealment, are detected as part of the IAEA safeguards program. Anomalies and discrepancies normally result from innocent causes and it is the purpose of the resolution process to determine the significance of them. The IAEA is instituting quality assurance measures for the IAEA inspection process. This paper reviews the anomaly and discrepancy resolution process and describes quality control measures which are the basis for quality assurance. 13 references, 6 tables
Aviation Safety/Automation Program Conference

Science.gov (United States)

Morello, Samuel A. (Compiler)

1990-01-01

The Aviation Safety/Automation Program Conference - 1989 was sponsored by the NASA Langley Research Center on 11 to 12 October 1989. The conference, held at the Sheraton Beach Inn and Conference Center, Virginia Beach, Virginia, was chaired by Samuel A. Morello. The primary objective of the conference was to ensure effective communication and technology transfer by providing a forum for technical interchange of current operational problems and program results to date. The Aviation Safety/Automation Program has as its primary goal to improve the safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers.
[Quality assurance in food production in Europe according to ISO 90000 and HACCP (Hazard Analysis and Critical Control Points)].

Science.gov (United States)

Jouve, J L

1996-12-01

HACCP is intended to make food protection programs evolve from a mainly retrospective quality control toward a preventative quality assurance approach and to provide an increased confidence in food safety. In parallel, the continuous evolution of quality concepts in the food industry resulted in the development of quality systems and quality assurance techniques with regard to the EN 29,000 (ISO 9000) series of standards. Specific to the food industry, HACCP can be seen as a very effective method to prepare specific Safety Assurance Plans (cf. the quality assurance plan concept) within a quality systems approach (Jouve, 1993). By reference to ISO 8402, a Quality Assurance Plan (QAP) basically sets out "the specific quality practices, resources and sequence of activities relevant to a particular product, service, contract or project". Quality assurance plans are more particularly useful for projects relating to new products or processes and/or comprising inter-related tasks whose interaction may be complex. In addition, in contractual or regulatory situations, such plans can be used to demonstrate the supplier's capability to meet identified objectives, specification or standards. In the food industry, the management of safety is a critical and complex issue which fits very well in the scope of application of a specific QAP; it is also where the use of HACCP is otherwise recommended by priority.
AEC controlled area safety program

Energy Technology Data Exchange (ETDEWEB)

Hendricks, D W [Nevada Operations Office, Atomic Energy Commission, Las Vegas, NV (United States)

1969-07-01

The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)
AEC controlled area safety program

International Nuclear Information System (INIS)

Hendricks, D.W.

1969-01-01

The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)
Analysis of a quality assurance program in diagnostic radiology

International Nuclear Information System (INIS)

Goethlin, J.H.

1986-01-01

Retake analysis before and after introduction of a quality assurance program showed a 45% reduction of the retake rate. The most important changes concerning equipment and organizing of labour were: (1) More detailed inspection of development machines and X-ray generators, (2) new cassettes and intensifying screens, (3) reduction of the number of film formats used, (4) information and instruction of personnel. Cost reductions and profit from increased examination rate amounted to 4.5% of the overall operating costs of the radiologic department. (author)
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)
Quality Assurance of Computer Programs for Photopeak Integration in Activation Analysis

DEFF Research Database (Denmark)

Heydorn, Kaj

1978-01-01

The purpose of a computer program for quantitative activation analysis is basically to produce information on the ratio of radioactive decays of a specific radio-nuclide observed by a detector from two alternative sources. It is assumed that at least one of the sources is known to contain...... the radionuclide in question, and qualitative analysis is therefore needed only to the extent that the decay characteristics of this radionuclide could be confused with those of other possible radionuclides, thus interfering with its determination. The quality of these computer programs can only be assured...
30 CFR 7.7 - Quality assurance.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Quality assurance. 7.7 Section 7.7 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS TESTING BY APPLICANT OR THIRD PARTY General § 7.7 Quality assurance. Applicants granted...
Fusion safety program plan

International Nuclear Information System (INIS)

Crocker, J.G.; Holland, D.F.; Herring, J.S.

1980-09-01

The program plan consists of research that has been divided into 13 different areas. These areas focus on the radioactive inventories that are expected in fusion reactors, the energy sources potentially available to release a portion of these inventories, and analysis and design techniques to assess and ensure that the safety risks associated with operation of magnetic fusion facilities are acceptably low. The document presents both long-term program requirements that must be fulfilled as part of the commercialization of fusion power and a five-year plan for each of the 13 different program areas. Also presented is a general discussion of magnetic fusion reactor safety, a method for establishing priorities in the program, and specific priority ratings for each task in the five-year plan
Quality assurance program plan for FRG sealed isotopic heat sources project (C-229)

International Nuclear Information System (INIS)

Tanke, J.M.

1997-01-01

This QAPP implements the Quality Assurance Program Plan for the FRG Sealed Isotopic Heat Sources Project (C-229). The heat source will be relocated from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)
Measurement quality assurance

International Nuclear Information System (INIS)

Eisenhower, E.H.

1988-01-01

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

Application of principles of quality assurance recommended by ISO 9000 Standards to Regulatory Program

International Nuclear Information System (INIS)

Jova Sed, Luis Andres; Bilbao Alfonso, Alejandro Victor

2001-01-01

For several years, the necessity of applying the programs of quality assurance to the radiation protection activities has been highlighted; however there has been little progress in this direction, even in the philosophical and methodological development of the topic. The objective of this work is to transmit some recommendations of how the Regulatory Authorities of developing countries can organize the quality assurance system of their own activity, following the main precepts of the international standard series ISO 9000. In very tight synthesis it describes the importance that has the definition of a policy of quality for a Regulatory Authority, the quality objectives, the definition of the responsibilities and attributions in relation with quality assurance, and others elements of the ISO 9000, and how to apply it. (author)
The U.S. commercial air tour industry: a review of aviation safety concerns.

Science.gov (United States)

Ballard, Sarah-Blythe

2014-02-01

The U.S. Title 14 Code of Federal Regulations defines commercial air tours as "flight[s] conducted for compensation or hire in an airplane or helicopter where a purpose of the flight is sightseeing." The incidence of air tour crashes in the United States is disproportionately high relative to similar commercial aviation operations, and air tours operating under Part 91 governance crash significantly more than those governed by Part 135. This paper reviews the government and industry response to four specific areas of air tour safety concern: surveillance of flight operations, pilot factors, regulatory standardization, and maintenance quality assurance. It concludes that the government and industry have successfully addressed many of these tenet issues, most notably by: advancing the operations surveillance infrastructure through implementation of en route, ground-based, and technological surveillance methods; developing Aeronautical Decision Making and cue-based training programs for air tour pilots; consolidating federal air tour regulations under Part 136; and developing public-private partnerships for raising maintenance operating standards and improving quality assurance programs. However, opportunities remain to improve air tour safety by: increasing the number and efficiency of flight surveillance programs; addressing pilot fatigue with more restrictive flight hour limitations for air tour pilots; ensuring widespread uptake of maintenance quality assurance programs, especially among high-risk operators not currently affiliated with private air tour safety programs; and eliminating the 25-mile exception allowing Part 91 operators to conduct commercial air tours without the safety oversight required of Part 135 operators.
US nuclear safety review and experience

International Nuclear Information System (INIS)

Gilinsky, V.

1977-01-01

The nuclear safety review of commercial nuclear power reactors has changed over the years from the relatively simple review of Dresden 1 in 1955 to the highly complex and sophisticated regulatory process which characterizes today's reviews. Four factors have influenced this evolution: (1) maturing of the technology and industry; (2) development of the regulatory process and associated staff; (3) feedback of operating experience; and (4) public awareness and participation. The NRC's safety review responsibilities start before an application is tendered and end when the plant is decommissioned. The safety review for reactor licensing is a comprehensive, two-phase process designed to assure that all the established conservative acceptance criteria are satisfied. Operational safety is assured through a strong inspection and enforcement program which includes shutting down operating facilities when necessary to protect the health and safety of the public. The safety of operating reactors is further insured through close regulation of license changes and selective backfitting of new regulatory requirements. An effective NRC standards development program has been implemented and coordinates closely with the national standards program. A confirmatory safety research program has been developed. Both of these efforts are invaluable to the nuclear safety review because they provide the staff with key tools needed to carry out its regulatory responsibilities. Both have been given increased emphasis since the formation of the NRC in 1975. The safety review process will continue to evolve, but changes will be slower and more deliberate. It will be influenced by standardization, early site reviews and development of advanced reactor concepts. New legislation may make possible changes which will simplify and shorten the regulatory process. Certainly the experience provided by the increasing number and types of operating plants will have a very strong impact on future trends in the
Operations Program Plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1990-09-01

This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)
30 CFR 15.8 - Quality assurance.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Quality assurance. 15.8 Section 15.8 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL OF... § 15.8 Quality assurance. (a) Applicants granted an approval or an extension of approval under this...
The development of quality assurance program for cyberknife

International Nuclear Information System (INIS)

Jang, Ji Sun; Lee, Dong Han; Kang, Young Nam

2006-01-01

Standardization quality assurance (QA)program of Cyberknife for suitable circumstances in Korea has not been established. In this research, we investigated the development of QA program for Cyberknife and evaluation of the feasibility under applications. Considering the feature of constitution for systems and the therapeutic methodology of Cyberknife, the list of quality control (QC) was established and divided dependent on the each period of operations. And then all these developed QC lists were categorized into three groups such as basic QC, delivery specific QC, and patient specific QC based on the each purpose of QA. In order to verify the validity of the established QA program, this QC lists was applied to two Cyberknife centers. The acceptable tolerance was based on the undertaking inspection list from the Cyberknife manufacturer and the QC results during last three years of two Cyberknife centers in Korea. The acquired measurement results were evaluated for the analysis of the current QA status and the verification of the propriety for the developed QA program. The current QA status of two Cyberknife centers was evaluated from the accuracy of all measurements in relation with application of the established QA program. Each measurement result was verified having a good agreement within the acceptable tolerance limit of the developed QA program. It is considered that the developed QA program in this research could be established the standardization of QC methods for Cyberknife and confirmed the accuracy and stability for the image-guided stereotactic radiotherapy
Quality assurance of metabolomics.

Science.gov (United States)

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

2015-01-01

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

International Nuclear Information System (INIS)

Warniez, P.

1984-01-01

The report presents an inventory on quality assurance for the safety of packagings for radioactive materials transport in 4 countries of the European Community : France, Federal Republic of Germany and United Kingdom. For each country the study includes: the inventory of reference documents and elements of national regulations for quality assurance, organization of quality following at the national level, quality assurance applied to spent fuel casks is examined. A preparatory program was previously submitted to competent authorities and organisms responsible in radioactive materials transport. In conclusion different quality assurance systems are in use but main criteria are found in all systems
Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…
Report on nuclear industry quality assurance procedures for safety analysis computer code development and use

International Nuclear Information System (INIS)

Sheron, B.W.; Rosztoczy, Z.R.

1980-08-01

As a result of a request from Commissioner V. Gilinsky to investigate in detail the causes of an error discovered in a vendor Emergency Core Cooling System (ECCS) computer code in March, 1978, the staff undertook an extensive investigation of the vendor quality assurance practices applied to safety analysis computer code development and use. This investigation included inspections of code development and use practices of the four major Light Water Reactor Nuclear Steam Supply System vendors and a major reload fuel supplier. The conclusion reached by the staff as a result of the investigation is that vendor practices for code development and use are basically sound. A number of areas were identified, however, where improvements to existing vendor procedures should be made. In addition, the investigation also addressed the quality assurance (QA) review and inspection process for computer codes and identified areas for improvement
Implementation of a Radiological Safety Coach program

Energy Technology Data Exchange (ETDEWEB)

Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

1998-02-01

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.
Implementation of a Radiological Safety Coach program

International Nuclear Information System (INIS)

Konzen, K.K.

1998-01-01

The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets
Summary report on the Solar Consumer Assurance Network (SOLCAN) Program Planning Task in the southern region

Energy Technology Data Exchange (ETDEWEB)

Browne, M. B. [comp.

1981-03-15

The goal of the SOLCAN Program Planning Task is to assist in the development, at the state and local levels, of consumer assurance approaches that will support the accelerated adoption and effective use of new products promoted by government incentives to consumers to meet our nation's energy needs. The task includes state-conducted evaluations and state SOLCAN meetings to identify consumer assurance mechanisms, assess their effectiveness, and identify and describe alternative means for strengthening consumer and industry assurance in each state. Results of the SOLCAN process are presented, including: a Solar Consumer Protection State Assessment Guide; State Solar Consumer Assurance Resources for Selected States; State Solar Consumer Protection Assessment Interviews for Florida; and state SOLCAN meeting summaries and participants. (LEW)
Three steps to a more successful quality assurance program

International Nuclear Information System (INIS)

Ferriss, W.E.

1975-01-01

The three steps that will be presented are by no means a cure-all for the variety of problems and challenges that a Quality Assurance (QA) Department is faced with in its role in the design and construction of a nuclear power plant. However, these steps are considered to be three of the most important ones in the realization of an effective and efficient QA program. Step 1. Awareness. With the multitude of people involved in activities that effect the resultant Quality of Design, Procurement, and Construction of a nuclear power plant, a concerted effort has been put forth at Bechtel to promote 'Quality Awareness'. This effort has resulted in presentations to thousands of engineers, buyers, superintendents, supervisors and many others to make them more aware of their role in the Quality program. These presentations cover the Quality criteria, organizations, manuals, and implementation responsibilities that constitute the Company Quality program. In addition to the above, many specialized courses covering inspection techniques, communications, auditing, problem solving, etc. have been given to the people involved in the Generic Quality Assurance functions. Step 2. Attitude. Nuclear Power Quality requirements are quite stringent and have presented additional requirements to engineers, buyers, and superintendents who have previously designed and constructed fossil fuel power plants. Logically there was a resistance to these new requirements and a number of attitudes had to be changed. The most effective way that we have found to accomplish this is through communications from top management expressing their support of the Quality Program. Step 3. Objective and economical compliance. With the increased awareness and a more positive attitude toward Quality requirements, Bechtel has been able to devote considerable effort on finding effective methods to comply with Quality requirements in the most economical way. The complete presentation will include several examples of
Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.
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.
UMTRA project technical assistance contractor quality assurance implementation plan for surface and ground water

International Nuclear Information System (INIS)

1994-09-01

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). The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. The QAIP is authorized and approved by the TAC Project Manager and QA manager. The QA program is designed to use monitoring, audit, and surveillance functions as management tools to ensure that all Project organization activities are carried out in a manner that will protect public health and safety, promote the success of the UMTRA Project and meet or exceed contract requirements
Toward development of a comprehensive external quality assurance program for polyfunctional intracellular cytokine staining assays.

Science.gov (United States)

Staats, Janet S; Enzor, Jennifer H; Sanchez, Ana M; Rountree, Wes; Chan, Cliburn; Jaimes, Maria; Chan, Ray Chun-Fai; Gaur, Amitabh; Denny, Thomas N; Weinhold, Kent J

2014-07-01

The External Quality Assurance Program Oversight Laboratory (EQAPOL) Flow Cytometry Program assesses the proficiency of NIH/NIAID/DAIDS-supported and potentially other interested research laboratories in performing Intracellular Cytokine Staining (ICS) assays. The goal of the EQAPOL Flow Cytometry External Quality Assurance Program (EQAP) is to provide proficiency testing and remediation for participating sites. The program is not punitive; rather, EQAPOL aims to help sites identify areas for improvement. EQAPOL utilizes a highly standardized ICS assay to minimize variability and readily identify those sites experiencing technical difficulties with their assays. Here, we report the results of External Proficiency 3 (EP3) where participating sites performed a 7-color ICS assay. On average, sites perform well in the Flow Cytometry EQAP (median score is "Good"). The most common technical issues identified by the program involve protocol adherence and data analysis; these areas have been the focus of site remediation. The EQAPOL Flow Cytometry team is now in the process of expanding the program to 8-color ICS assays. Evaluating polyfunctional ICS responses would align the program with assays currently being performed in support of HIV immune monitoring assays. Copyright © 2014 Elsevier B.V. All rights reserved.
Public Health Service Safety Program

Energy Technology Data Exchange (ETDEWEB)

McBride, J R [Southwestern Radiological Health Laboratory, Las Vegas, NV (United States)

1969-07-01

Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)
Public Health Service Safety Program

International Nuclear Information System (INIS)

McBride, J.R.

1969-01-01

Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

USCEA/NIST measurement assurance programs for the radiopharmaceutical and nuclear power industries

International Nuclear Information System (INIS)

Golas, D.B.

1993-01-01

In cooperation with the U.S. Council for Energy Awareness (USCEA), the National Institute of Standards and Technology (NIST) supervises and administers two measurement assurance programs for radioactivity measurement traceability. One, in existence since the mid 1970s, provides traceability to suppliers of radiochemicals and radiopharmaceuticals, dose calibrators, and nuclear pharmacy services. The second program, begun in 1987, provides traceability to the nuclear power industry for utilities, source suppliers, and service laboratories. Each program is described, and the results of measurements of samples of known, but undisclosed activity, prepared at NIST and measured by the participants are presented
USCEA/NIST measurement assurance programs for the radiopharmaceutical and nuclear power industries

Energy Technology Data Exchange (ETDEWEB)

Golas, D.B. [Council for Energy Awareness, Washington, DC (United States)

1993-12-31

In cooperation with the U.S. Council for Energy Awareness (USCEA), the National Institute of Standards and Technology (NIST) supervises and administers two measurement assurance programs for radioactivity measurement traceability. One, in existence since the mid 1970s, provides traceability to suppliers of radiochemicals and radiopharmaceuticals, dose calibrators, and nuclear pharmacy services. The second program, begun in 1987, provides traceability to the nuclear power industry for utilities, source suppliers, and service laboratories. Each program is described, and the results of measurements of samples of known, but undisclosed activity, prepared at NIST and measured by the participants are presented.
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
Light Water Reactor Sustainability Program: Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan

International Nuclear Information System (INIS)

Smith, Curtis; Rabiti, Cristian; Martineau, Richard; Szilard, Ronaldo

2016-01-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly ''over-design'' portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as ''safety margin.'' Historically, specific safety margin provisions have been formulated, primarily based on ''engineering judgment.''
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
49 CFR 385.333 - What happens at the end of the 18-month safety monitoring period?

Science.gov (United States)

2010-10-01

... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.333 What happens at the end of the 18-month safety monitoring period? (a) If a safety audit has been performed within... the same basis as any other carrier. (d) If a safety audit or compliance review has not been performed...
Improving the safety and reliability of Monju

International Nuclear Information System (INIS)

Itou, Kazumoto; Maeda, Hiroshi; Moriyama, Masatoshi

1998-01-01

Comprehensive safety review has been performed at Monju to determine why the Monju secondary sodium leakage accident occurred. We investigated how to improve the situation based on the results of the safety review. The safety review focused on five aspects of whether the facilities for dealing with the sodium leakage accident were adequate: the reliability of the detection method, the reliability of the method for preventing the spread of the sodium leakage accident, whether the documented operating procedures are adequate, whether the quality assurance system, program, and actions were properly performed and so on. As a result, we established for Monju a better method of dealing with sodium leakage accidents, rapid detection of sodium leakage, improvement of sodium drain facilities, and way to reduce damage to Monju systems after an accident. We also improve the operation procedures and quality assurance actions to increase the safety and reliability of Monju. (author)
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
Development and implementation of a quality assurance program for a hormonal contraceptive implant.

Science.gov (United States)

Owen, Derek H; Jenkins, David; Cancel, Aida; Carter, Eli; Dorflinger, Laneta; Spieler, Jeff; Steiner, Markus J

2013-04-01

The importance of the distribution of safe, effective and cost-effective pharmaceutical products in resource-constrained countries is the subject of increasing attention. FHI 360 has developed a program aimed at evaluating the quality of a contraceptive implant manufactured in China, while the product is being registered in an increasing number of countries and distributed by international procurement agencies. The program consists of (1) independent product testing; (2) ongoing evaluation of the manufacturing facility through audits and inspections; and (3) post-marketing surveillance. This article focuses on the laboratory testing of the product. The various test methods were chosen from the following test method compendia, the United States Pharmacopeia (USP), British Pharmacopeia (BP), International Organization for Standardization (ISO), the American Society for Testing and Materials (ASTM), or lot release tests mandated by Chinese regulatory requirements. Each manufactured lot is independently tested prior to its distribution to countries supported by this program. In addition, a more detailed annual testing program includes evaluation of the active ingredient (levonorgestrel), the final product and the packaging material. Over the first 4 years of this 5-year project, all tested lots met the established quality criteria. The quality assurance program developed for this contraceptive implant has helped ensure that a safe product was being introduced into developing country family planning programs. This program provides a template for establishing quality assurance programs for other cost-effective pharmaceutical products that have not yet received stringent regulatory approval and are being distributed in resource-poor settings. Copyright © 2013 Elsevier Inc. All rights reserved.
Commissioning quality assurance at Pickering NGS

International Nuclear Information System (INIS)

Wieckowski, J.T.

1983-05-01

Ontario Hydro decided in 1978 to implement a formal quality assurance program applicable to commissioning and operation of nuclear generating stations. Pickering NGS is the first station to have the commissioning quality assurance (CQA) program applied to it. This paper outlines the scope, implementation, and evaluation of the CQA program as applied to Pickering Unit 5
Cesium legacy safety project management work plan

International Nuclear Information System (INIS)

Durham, J.S.

1998-01-01

This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)
The RCPA Quality Assurance Program in Dermatopathology: A Retrospective Review.

Science.gov (United States)

Peck, Martyn; Beer, Trevor W; Badrick, Tony; Wood, Benjamin A

2018-03-01

To review the Royal College of Pathologists of Australasia (RCPA) Quality Assurance Program Dermatopathology module from 2005 to 2016 to assess diagnostic performance, changes over time, and areas of diagnostic difficulty. The computerized records of the RCPA Dermatopathology subspecialist module were reviewed. Cases were categorized into groups including nonneoplastic disorders, neoplasms, and cases with multiple diagnoses. The performance of participants over time in each of these categories and in more specific areas (including melanocytic and adnexal neoplasms) was assessed. Cases which showed high rates of discordant responses were specifically reviewed. One hundred sixteen cases circulated over 10 years were evaluated. The overall concordance rate was 77%, with a major discordance rate of 7%. There was a slightly higher concordance rate for neoplasms compared with nonneoplastic lesions (80% vs. 74%). Specific areas associated with lower concordance rates included classification of adnexal tumors and identification of multiple pathologies. A spindle cell nevus of Reed yielded a 40% discordance rate, with most misclassifications indicating melanoma. The RCPA quality assurance program module has circulated a wide range of common and uncommon cases to participants over the 12 years studied, highlighting a low but important rate of major discordant responses. Melanocytic lesions, hematolymphoid infiltrates, adnexal tumors, and identification of multiple pathologies are identified as areas worthy of particular attention in quality improvement activities.
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
Integrating quality assurance and research and development

International Nuclear Information System (INIS)

Dronkers, J.J.

1985-01-01

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

International Nuclear Information System (INIS)

1981-01-01

This Safety Guide provides requirements and recommendations related to the establishment and implementation of a quality assurance programme for those organizations involved in the manufacture of items affecting the safety of nuclear power plants. The quality-assurance-related functions of a manufacturer may include activities such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, inspecting, testing, modifying, repairing and maintaining. It is not the aim of the present Guide, which supplements the above-mentioned Code of Practice, to provide rules related to the quality assurance programme for the design of items. Manufacturers that generate designs shall follow the requirements and recommendations contained in the Safety Guide on Quality Assurance in the Design of Nuclear Power Plants (IAEA Safety Series No. 50-SG-QA6). All these publications form part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. A Provisional List of NUSS Programme Titles will be found at the end of this publication
Mammography in public hospitals at Rio de Janeiro: a quality assurance program

International Nuclear Information System (INIS)

Briquet, C.; Coutinho, C.M.C.; Mota, H.C.; Tavares, E.

1998-01-01

This paper presents the preliminary results and the methodology followed by the implementation of a Quality Assurance Program in public hospitals at Rio de Janeiro. We observed that the main problems of image are due to the processing. None facility has a dedicated processor and the processor daily quality control is a concern not yet adopted. (Author)
NASA Aviation Safety Program Systems Analysis/Program Assessment Metrics Review

Science.gov (United States)

Louis, Garrick E.; Anderson, Katherine; Ahmad, Tisan; Bouabid, Ali; Siriwardana, Maya; Guilbaud, Patrick

2003-01-01

The goal of this project is to evaluate the metrics and processes used by NASA's Aviation Safety Program in assessing technologies that contribute to NASA's aviation safety goals. There were three objectives for reaching this goal. First, NASA's main objectives for aviation safety were documented and their consistency was checked against the main objectives of the Aviation Safety Program. Next, the metrics used for technology investment by the Program Assessment function of AvSP were evaluated. Finally, other metrics that could be used by the Program Assessment Team (PAT) were identified and evaluated. This investigation revealed that the objectives are in fact consistent across organizational levels at NASA and with the FAA. Some of the major issues discussed in this study which should be further investigated, are the removal of the Cost and Return-on-Investment metrics, the lack of the metrics to measure the balance of investment and technology, the interdependencies between some of the metric risk driver categories, and the conflict between 'fatal accident rate' and 'accident rate' in the language of the Aviation Safety goal as stated in different sources.
Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety
Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP
Pressure Safety Program Implementation at ORNL

Energy Technology Data Exchange (ETDEWEB)

Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

2013-01-01

The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply

Nuclear safety in Slovak Republic. Status of safety improvements

International Nuclear Information System (INIS)

Toth, A.

1999-01-01

Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well
Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”
Light Water Reactor Sustainability Program: Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Szilard, Ronaldo [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”
21 CFR 1000.55 - Recommendation for quality assurance programs in diagnostic radiology facilities.

Science.gov (United States)

2010-04-01

... facilities where more than one department operates x-ray equipment, to the chief medical officer of the..., improved image quality, and/or financial savings will compensate for the resources required for the program... generally be delegated a basic quality assurance role by the practitioner in charge. Responsibility for...
Assuring safety without animal testing concept (ASAT). Integration of human disease data with in vitro data to improve toxicology testing

NARCIS (Netherlands)

Stierum, Rob; Aarts, Jac; Boorsma, Andre; Bosgra, Sieto; Caiment, Florian; Ezendam, Janine; Greupink, Rick; Hendriksen, Peter; Soeteman-Hernandez, Lya G.; Jennen, Danyel; Kleinjans, Jos; Kroese, Dinant; Kuper, Frieke; van Loveren, Henk; Monshouwer, Mario; Russel, Frans; van Someren, Eugene; Tsamou, Maria; Groothuis, Geny

2014-01-01

According to the Assuring Safety Without Animal Testing (ASAT) principle, risk assessment may ultimately become possible without the use of animals (Fentem et al., (2004). Altern. Lab. Anim. 32, 617-623). The ASAT concept takes human disease mechanisms as starting point and tries to define if
A program on quality assurance and dose calibration for radiation therapy units in Venezuela

International Nuclear Information System (INIS)

Padilla, M.C. de; Carrizales, L.; Diaz, J.; Gutt, F.; Cozman, A.

1996-01-01

The results of a five year program (1988-90-91-92-93) on quality assurance and dose calibration for 12 Cobalt-60 units from public hospitals, which represents 30% of total radiation therapy units in Venezuela, are presented. The remarkable improvement in the general performance of these units can be seen in the IAEA/WHO Postal TLD Intercomparison results which gave 100% within ± 5% in 1990 and 1992, while 63% in 1990 and 44% in 1992, with errors up to 37% were obtained for the participants not included in the program. The difference between the two groups lead the government to decrete through the Gaceta Oficial de la Republica de Venezuela, Resolution G-1397 on March 3, 1993, the quality assurance and dose calibration programs shall be established for all radiation therapy installations in Venezuela. The project for the standards was developed by the SSDL physicists and it was already approbated by the Health Ministry. It is expected that the Norms will enter into effect by the end of 1994. (author). 14 refs, 1 fig., 3 tabs
A program on quality assurance and dose calibration for radiation therapy units in Venezuela

Energy Technology Data Exchange (ETDEWEB)

Padilla, M.C. de; Carrizales, L; Diaz, J; Gutt, F; Cozman, A [Instituto Venezolano de Investigaciones Cientificas, Caracas (Venezuela). Lab. de Calibracion Dosimetrica

1996-08-01

The results of a five year program (1988-90-91-92-93) on quality assurance and dose calibration for 12 Cobalt-60 units from public hospitals, which represents 30% of total radiation therapy units in Venezuela, are presented. The remarkable improvement in the general performance of these units can be seen in the IAEA/WHO Postal TLD Intercomparison results which gave 100% within {+-} 5% in 1990 and 1992, while 63% in 1990 and 44% in 1992, with errors up to 37% were obtained for the participants not included in the program. The difference between the two groups lead the government to decrete through the Gaceta Oficial de la Republica de Venezuela, Resolution G-1397 on March 3, 1993, the quality assurance and dose calibration programs shall be established for all radiation therapy installations in Venezuela. The project for the standards was developed by the SSDL physicists and it was already approbated by the Health Ministry. It is expected that the Norms will enter into effect by the end of 1994. (author). 14 refs, 1 fig., 3 tabs.
Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program
Safety evaluation report. Fast Flux Test Facility. Project No. 448

Energy Technology Data Exchange (ETDEWEB)

1978-08-01

Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance.
Safety evaluation report. Fast Flux Test Facility. Project No. 448

International Nuclear Information System (INIS)

1978-01-01

Information on the safety of the FFTF Reactor is presented under the following chapter headings: site characteristics; design of structures, components, equipment, and systems; reactor; reactor coolant system and connected systems; engineered safety features; electric power; auxiliary systems; radioactive waste management systems; radiation protection; conduct of operations; initial test programs; accident analysis; and quality assurance
A philosophy for space nuclear systems safety

International Nuclear Information System (INIS)

Marshall, A.C.

1992-01-01

The unique requirements and contraints of space nuclear systems require careful consideration in the development of a safety policy. The Nuclear Safety Policy Working Group (NSPWG) for the Space Exploration Initiative has proposed a hierarchical approach with safety policy at the top of the hierarchy. This policy allows safety requirements to be tailored to specific applications while still providing reassurance to regulators and the general public that the necessary measures have been taken to assure safe application of space nuclear systems. The safety policy used by the NSPWG is recommended for all space nuclear programs and missions
Fusion safety program Annual report, Fiscal year 1995

International Nuclear Information System (INIS)

Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

1995-12-01

This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities
Quality assurance and management

International Nuclear Information System (INIS)

Newcomb, W.E.

1989-01-01

This paper traces the evolution of the quality assurance program of an office of waste management development (OWTD). The program's needs and commitment are examined. The author reports on the role of program and technical managers in such a program
The Assessment, Development, Assurance Pharmacist's Tool (ADAPT) for ensuring quality implementation of health promotion programs.

Science.gov (United States)

Truong, Hoai-An; Taylor, Catherine R; DiPietro, Natalie A

2012-02-10

To develop and validate the Assessment, Development, Assurance Pharmacist's Tool (ADAPT), an instrument for pharmacists and student pharmacists to use in developing and implementing health promotion programs. The 36-item ADAPT instrument was developed using the framework of public health's 3 core functions (assessment, policy development, and assurance) and 10 essential services. The tool's content and usage was assessed and conducted through peer-review and initial validity testing processes. Over 20 faculty members, preceptors, and student pharmacists at 5 institutions involved in planning and implementing health promotion initiatives reviewed the instrument and conducted validity testing. The instrument took approximately 15 minutes to complete and the findings resulted in changes and improvements to elements of the programs evaluated. The ADAPT instrument fills a need to more effectively plan, develop, implement, and evaluate pharmacist-directed public health programs that are evidence-based, high-quality, and compliant with laws and regulations and facilitates documentation of pharmacists' contributions to public health.
Gap Analysis Approach for Construction Safety Program Improvement

Directory of Open Access Journals (Sweden)

Thanet Aksorn

2007-06-01

Full Text Available To improve construction site safety, emphasis has been placed on the implementation of safety programs. In order to successfully gain from safety programs, factors that affect their improvement need to be studied. Sixteen critical success factors of safety programs were identified from safety literature, and these were validated by safety experts. This study was undertaken by surveying 70 respondents from medium- and large-scale construction projects. It explored the importance and the actual status of critical success factors (CSFs. Gap analysis was used to examine the differences between the importance of these CSFs and their actual status. This study found that the most critical problems characterized by the largest gaps were management support, appropriate supervision, sufficient resource allocation, teamwork, and effective enforcement. Raising these priority factors to satisfactory levels would lead to successful safety programs, thereby minimizing accidents.
Health, safety and environmental research program

International Nuclear Information System (INIS)

Dinner, P.J.

1983-01-01

This report outlines the Health, Safety and Environmental Research Program being undertaken by the CFFTP. The Program objectives, relationship to other CFFTP programs, implementation plans and expected outputs are stated. Opportunities to build upon the knowledge and experience gained in safely managing tritium in the CANDU program, by addressing generic questions pertinent to tritium safety for fusion facilities, are identified. These opportunities exist across a broad spectrum of issues covering the anticipated behaviour of tritium in fusion facilities, the surrounding environment and in man
The Royal College of Pathologists of Australasia Quality Assurance Program: Immunohistochemistry Breast Marker Audit Overview 2005-2015.

Science.gov (United States)

Haffajee, Zenobia Ayesha Mohamed; Kumar, Beena; Francis, Glenn; Peck, Martyn; Badrick, Tony

2017-11-20

The Royal College of Pathologists of Australasia Quality Assurance Program (RCPAQAP) Anatomical Pathology provides a comprehensive External Quality Assurance (EQA) exercise to review the reporting of immunohistochemistry (IHC) and in-situ hybridization (ISH) breast markers through an audit of clinical results. The aim of this exercise was to provide information regarding the quality of breast marker testing within clinical laboratories from 2005 to 2015. This comprehensive audit included estrogen, progesterone, and HER2 marker reporting. This was an important quality assurance activity established in response to ongoing difficulties experienced in laboratories in this area of testing.
Seismic safety margins research program overview

International Nuclear Information System (INIS)

Tokarz, F.J.; Smith, P.D.

1978-01-01

A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I
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
THE IMPORTANCE OF A SUCCESSFUL QUALITY ASSURANCE (QA) PROGRAM FROM A RESEARCH MANAGER'S PERSPECTIVE

Science.gov (United States)

The paper discusses the Air Pollution Prevention and Control Division's Quality Assurance (QA) program and the approaches used to meet QA requirements in the Division. The presentation is a technical manager's perspective of the Division's requirements for and approach to QA in i...

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