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Sample records for assurance program description dwpf

  1. 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

  2. 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.

  3. 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

  4. Technical bases for the DWPF testing program

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1990-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will be the first production facility in the United States for the immobilization of high-level nuclear waste. Production of DWPF canistered wasteforms will begin prior to repository licensing, so decisions on facility startup will have to be made before the final decisions on repository design are made. The Department of Energy's Office of Civilian Radioactive Waste Management (RW) has addressed this discrepancy by defining a Waste Acceptance Process. This process provides assurance that the borosilicate-glass wasteform, in a stainless-steel canister, produced by the DWPF will be acceptable for permanent storage in a federal repository. As part of this process, detailed technical specifications have been developed for the DWPF product. SRS has developed detailed strategies for demonstrating compliance with each of the Waste Acceptance Process specifications. An important part of the compliance is the testing which will be carried out in the DWPF. In this paper, the bases for each of the tests to be performed in the DWPF to establish compliance with the specifications are described, and the tests are detailed. The results of initial tests relating to characterization of sealed canisters are reported

  5. The DWPF waste form qualification program

    International Nuclear Information System (INIS)

    Marra, S.L.; Plodinec, M.J.

    1994-01-01

    Prior to the introduction of radioactive feed into the Defense Waste Processing Facility for immobilization in borosilicate glass an extensive waste qualification program must be completed. The DWPF must demonstrate its ability to comply with the Waste Acceptance Product Specifications. This ability is being demonstrated through laboratory and pilot scale work and will be completed after the full operation of the DWPF using various simulated feeds

  6. 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

  7. 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

  8. 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

  9. Glass sampling program during DWPF Integrated Cold Runs

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1990-01-01

    The described glass sampling program is designed to achieve two objectives: To demonstrate Defense Waste Processing Facility (DWPF) ability to control and verify the radionuclide release properties of the glass product; To confirm DWPF's readiness to obtain glass samples during production, and SRL's readiness to analyze and test those samples remotely. The DWPF strategy for control of the radionuclide release properties of the glass product, and verification of its acceptability are described in this report. The basic approach of the test program is then defined

  10. Quality assurance requirements and description for the Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    1992-01-01

    The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through application for an operating license; (5) the high-level-waste form from production through acceptance. Section 2.0 defines in greater detail criteria for determining work subject to QARD requirements. The QARD is organized into sections, supplements, appendices, and a glossary. The sections contain requirements that are common to all Program elements. The supplements contain requirements for specialized activities. The appendices contain requirements that are specific to an individual Program element. The glossary establishes a common vocabulary for the Quality Assurance Program

  11. 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

  12. Program plan: DWPF/HLWDP stirred Melter Program Plan

    International Nuclear Information System (INIS)

    Smith, M.E.

    1994-01-01

    Slurry Fed Melters (SFM) have been developed in the United States, Europe, and Japan for the conversion of high-level radioactive waste (HLW) to borosilicate glass for permanent disposal. The newest design, the stirred melter, combines the high production rates and high glass quality features of the Joule-heated melters with the low-cost, compact, simple maintenance features of the pot melters. However, further engineering design and demonstrations are needed to operate the stirred melter on a large scale. This document outlines the program which develops a full scale stirred melter for the DWPF (240 pph), and provides a basis which will allow further scale-up of the technology for use in the Hanford High Level Waste Disposal Program (HLWDP) for up to four times the reference capacity

  13. Canister disposition plan for the DWPF Startup Test Program

    International Nuclear Information System (INIS)

    Harbour, J.R.; Payne, C.H.

    1990-01-01

    This report details the disposition of canisters and the canistered waste forms produced during the DWPF Startup Test Program. The six melter campaigns (DWPF Startup Tests FA-13, WP-14, WP-15, WP-16, WP-17, and FA-18) will produce 126 canistered waste forms. In addition, up to 20 additional canistered waste forms may be produced from glass poured during the transition between campaigns. In particular, this canister disposition plan (1) assigns (by alpha-numeric code) a specific canister to each location in the six campaign sequences, (2) describes the method of access for glass sampling on each canistered waste form, (3) describes the nature of the specific tests which will be carried out, (4) details which tests will be carried out on each canistered waste form, (5) provides the sequence of these tests for each canistered waste form, and (6) assigns a storage location for each canistered waste form. The tests are designed to provide evidence, as detailed in the Waste Form Compliance Plan (WCP 1 ), that the DWPF product will comply with the Waste Acceptance Product Specifications (WAPS 2 ). The WAPS must be met before the canistered waste form is accepted by DOE for ultimate disposal at the Federal Repository. The results of these tests will be included in the Waste Form Qualification Report (WQR)

  14. 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

  15. Quality Assurance Requirements and Description

    International Nuclear Information System (INIS)

    Ram Murthy

    2002-01-01

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

  16. DWPF Development Plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Holtzscheiter, E.W.

    1994-05-09

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ``DWPF Process Development Systems.`` To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant.

  17. DWPF Development Plan. Revision 1

    International Nuclear Information System (INIS)

    Holtzscheiter, E.W.

    1994-01-01

    The DWPF Development Plan is based on an evaluation process flowsheet and related waste management systems. The scope is shown in Figure 1 entitled ''DWPF Process Development Systems.'' To identify the critical development efforts, each system has been analyzed to determine: The identification of unresolved technology issues. A technology issue (TI) is one that requires basic development to resolve a previously unknown process or equipment problem and is managed via the Technology Assurance Program co-chaired by DWPF and SRTC. Areas that require further work to sufficiently define the process basis or technical operating envelop for DWPF. This activity involves the application of sound engineering and development principles to define the scope of work required to complete the technical data. The identification of the level of effort and expertise required to provide process technical consultation during the start-up and demonstration of this first of a kind plant

  18. 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

  19. 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.

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

    International Nuclear Information System (INIS)

    Hand, R.L.

    1990-12-01

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

  1. Defense Waste Processing Facility (DWPF), Modular CSSX Unit (CSSX), and Waste Transfer Line System of Salt Processing Program (U)

    International Nuclear Information System (INIS)

    CHANG, ROBERT

    2006-01-01

    All of the waste streams from ARP, MCU, and SWPF processes will be sent to DWPF for vitrification. The impact these new waste streams will have on DWPF's ability to meet its canister production goal and its ability to support the Salt Processing Program (ARP, MCU, and SWPF) throughput needed to be evaluated. DWPF Engineering and Operations requested OBU Systems Engineering to evaluate DWPF operations and determine how the process could be optimized. The ultimate goal will be to evaluate all of the Liquid Radioactive Waste (LRW) System by developing process modules to cover all facilities/projects which are relevant to the LRW Program and to link the modules together to: (1) study the interfaces issues, (2) identify bottlenecks, and (3) determine the most cost effective way to eliminate them. The results from the evaluation can be used to assist DWPF in identifying improvement opportunities, to assist CBU in LRW strategic planning/tank space management, and to determine the project completion date for the Salt Processing Program

  2. Hanford Waste Vitrification Plant Quality Assurance Program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1992-01-01

    This document describes the quality assurance (QA) program of the Hanford Waste Vitrification Plant (HWVP) Project. The purpose of the QA program is to control project activities in such a manner as to achieve the mission of the HWVP Project in a safe and reliable manner. A major aspect of the HWVP Project QA program is the control of activities that relate to high-level waste (HLW) form development and qualification. This document describes the program and planned actions the Westinghouse Hanford Company (Westinghouse Hanford) will implement to demonstrate and ensure that the HWVP Project meets the US Department of Energy (DOE) and ASME regulations. The actions for meeting the requirements of the Waste Acceptance Preliminary Specifications (WAPS) will be implemented under the HWVP product qualification program with the objective of ensuring that the HWVP and its processes comply with the WAPS established by the federal repository

  3. 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

  4. DWPF Stage 2: precipitation test program at Mott

    International Nuclear Information System (INIS)

    Schmitz, M.A.

    1981-01-01

    This memorandum covers the results of the test program conducted at Mott Metallurgical to determine cross-flow filter performance on potassium/cesium tetraphenylborate (K/Cs TPB)-sodium titanate slurries. The test program was designed to provide essential basic operating data to supplement the 1000-gallon cold process tests planned at TNX and the shielded cell tests with actual waste supernate planned by Chemical Technology. The specific Mott Metallurgical test objectives are outlined in DPST-81-722. During the Mott Metallurgical test program an average filtrate flow rate of approximately 0.05 gpm/ft 2 was repeatedly demonstrated over an 8-hr run with 0.5 micron filter elements. Initial Fe/Al sludge concentrations up to 150 ppM did not affect filter performance. Rheologies of the K/Cs TPB-sodium titanate slurries up to 13% by weight, the maximum concentration achieved, are summarized. Several recommendations are made to act as a guide for optimal filter performance

  5. 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

  6. 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

  7. 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.)

  8. DWPF process control

    International Nuclear Information System (INIS)

    Heckendoin, F.M. II

    1983-01-01

    The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant (SRP) is in the final design stage. Instrumentation to provide the parameter sensing required to assure the quality of the two-foot-diameter, ten-foot-high waste canister is in the final stage of development. All step of the process and instrumentation are now operating as nearly full-scale prototypes at SRP. Quality will be maintained by assuring that only the intended material enters the canisters, and by sensing the resultant condition of the filled canisters. Primary emphasis will be on instrumentation of the process

  9. 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

  10. 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

  11. 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.

  12. Measurement of the volatility and glass transition temperatures of glasses produced during the DWPF startup test program

    International Nuclear Information System (INIS)

    Marra, J.C.; Harbour, J.R.

    1995-01-01

    The Defense Waste Processing Facility (DWPF) will immobilize high-level radioactive waste currently stored in underground tanks at the Savannah River Site by incorporating the waste into a glass matrix. The molten waste glass will be poured into stainless steel canisters which will be welded shut to produce the final waste form. One specification requires that any volatiles produced as a result of accidentally heating the waste glass to the glass transition temperature be identified. Glass samples from five melter campaigns, run as part of the DWPF Startup Test Program, were analyzed to determine glass transition temperatures and to examine the volatilization (by weight loss). Glass transition temperatures (T g ) for the glasses, determined by differential scanning calorimetry (DSC), ranged between 445 C and 474 C. Thermogravimetric analysis (TGA) scans showed that no overall weight loss occurred in any of the glass samples when heated to 500 C. Therefore, no volatility will occur in the final glass product when heated up to 500 C

  13. Initial results from the canistered waste forms produced during the first campaign of the DWPF Startup Test Program

    International Nuclear Information System (INIS)

    Harbour, J.R.

    1995-01-01

    As part of the Defense Waste Processing Facility (DWPF) Startup Test Program, approximately 90 canisters will be filled with glass containing simulated radioactive waste during five separate campaigns. The first campaign is a facility acceptance test to demonstrate the operability of the facility and to collect initial data on the glass and the canistered waste forms. During the next four campaigns (the waste qualification campaigns) data will be obtained which will be used to demonstrate that the DWPF product meets DOE's Waste Acceptance Product Specifications (WAPS). Currently 12 of the 16 canisters have been filled with glass during the first campaign (FA-13). This paper describes the tests that have been carried out on these 12 glass-filled canisters and presents the data with reference to the acceptance criteria of the WAPS. These tests include measurement of canister dimensions prior to and after glass filling. dew point, composition, and pressure of the gas within the free volume of the canister, fill height, free volume, weight, leak rates of welds and temporary seals, and weld parameters

  14. DWPF MATERIALS EVALUATION SUMMARY REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Gee, T.; Chandler, G.; Daugherty, W.; Imrich, K.; Jankins, C.

    1996-09-12

    To better ensure the reliability of the Defense Waste Processing Facility (DWPF) remote canyon process equipment, a materials evaluation program was performed as part of the overall startup test program. Specific test programs included FA-04 ('Process Vessels Erosion/Corrosion Studies') and FA-05 (melter inspection). At the conclusion of field testing, Test Results Reports were issued to cover the various test phases. While these reports completed the startup test requirements, DWPF-Engineering agreed to compile a more detailed report which would include essentially all of the materials testing programs performed at DWPF. The scope of the materials evaouation programs included selected equipment from the Salt Process Cell (SPC), Chemical Process Cell (CPC), Melt Cell, Canister Decon Cell (CDC), and supporting facilities. The program consisted of performing pre-service baseline inspections (work completed in 1992) and follow-up inspections after completion of the DWPF cold chemical runs. Process equipment inspected included: process vessels, pumps, agitators, coils, jumpers, and melter top head components. Various NDE (non-destructive examination) techniques were used during the inspection program, including: ultrasonic testing (UT), visual (direct or video probe), radiography, penetrant testing (PT), and dimensional analyses. Finally, coupon racks were placed in selected tanks in 1992 for subsequent removal and corrosion evaluation after chemical runs.

  15. SCIX IMPACT ON DWPF CPC

    Energy Technology Data Exchange (ETDEWEB)

    Koopman, D.

    2011-07-14

    A program was conducted to systematically evaluate potential impacts of the proposed Small Column Ion Exchange (SCIX) process on the Defense Waste Processing Facility (DWPF) Chemical Processing Cell (CPC). The program involved a series of interrelated tasks. Past studies of the impact of crystalline silicotitanate (CST) and monosodium titanate (MST) on DWPF were reviewed. Paper studies and material balance calculations were used to establish reasonable bounding levels of CST and MST in sludge. Following the paper studies, Sludge Batch 10 (SB10) simulant was modified to have both bounding and intermediate levels of MST and ground CST. The SCIX flow sheet includes grinding of the CST which is larger than DWPF frit when not ground. Nominal ground CST was not yet available, therefore a similar CST ground previously in Savannah River National Laboratory (SRNL) was used. It was believed that this CST was over ground and that it would bound the impact of nominal CST on sludge slurry properties. Lab-scale simulations of the DWPF CPC were conducted using SB10 simulants with no, intermediate, and bounding levels of CST and MST. Tests included both the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) cycles. Simulations were performed at high and low acid stoichiometry. A demonstration of the extended CPC flowsheet was made that included streams from the site interim salt processing operations. A simulation using irradiated CST and MST was also completed. An extensive set of rheological measurements was made to search for potential adverse consequences of CST and MST and slurry rheology in the CPC. The SCIX CPC impact program was conducted in parallel with a program to evaluate the impact of SCIX on the final DWPF glass waste form and on the DWPF melter throughput. The studies must be considered together when evaluating the full impact of SCIX on DWPF. Due to the fact that the alternant flowsheet for DWPF has not been selected, this study did not

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  17. 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

  18. 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

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. 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

  4. 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)

  5. Tritium systems test assembly quality assurance program

    International Nuclear Information System (INIS)

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

    1986-07-01

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

  6. 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...

  7. 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)

  8. Quality Assurance Based on Descriptive and Parsimonious Appearance Models

    DEFF Research Database (Denmark)

    Nielsen, Jannik Boll; Eiríksson, Eyþór Rúnar; Kristensen, Rasmus Lyngby

    2015-01-01

    In this positional paper, we discuss the potential benefits of using appearance models in additive manufacturing, metal casting, wind turbine blade production, and 3D content acquisition. Current state of the art in acquisition and rendering of appearance cannot easily be used for quality assurance...... in these areas. The common denominator is the need for descriptive and parsimonious appearance models. By ‘parsimonious’ we mean with few parameters so that a model is useful both for fast acquisition, robust fitting, and fast rendering of appearance. The word ‘descriptive’ refers to the fact that a model should...

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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

  14. Respiratory Protection Program. Programmatic description

    Energy Technology Data Exchange (ETDEWEB)

    Brooks, J.M.; Porter, W.E.

    1986-03-01

    The ORNL Respirator Program is designed to provide employees with devices which afford maximum protection with minimum inconvenience and discomfort. Teamwork is essential since a comprehensive program involves the Medical Department, the Industrial Hygiene Department, Radiation and Safety Surveys, the Operations Division, Quality Assurance and Inspection, and the Fire Department. The purpose of this manual is to describe in detail the ORNL Respirator Program. Included are discussions of the following elements: quality assurance, selection, fit-testing, maintenance and issue, certified breathing air for self-contained breathing apparatus, inspection, program surveillance, available devices, and standard operating procedures. As program modifications develop and improvements are made, periodic revisions may be necessary. The Industrial Hygiene Department will perform this task on an ''as required'' basis.

  15. 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

  16. 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

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

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

    International Nuclear Information System (INIS)

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

    1984-10-01

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

  19. 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.

  20. 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

  1. 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

  2. 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

  3. 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

  4. Land reclamation program description

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-05-01

    The Land Reclamation Program will address the need for coordinated applied and basic research into the physical and ecological problems of land reclamation, and advance the development of cost-effective techniques for reclaiming and rehabilitating mined coal land to productive end uses. The purpose of this new program is to conduct integrated research and development projects focused on near- and long-term reclamation problems in all major U.S. coal resource regions including Alaska and to coordinate, evaluate, and disseminate the results of related studies conducted at other research institutions. The activities of the Land Reclamation Laboratory program will involve close cooperation with industry and focus on establishing a comprehensive field and laboratory effort. Research demonstration sites will be established throughout the United States to address regional and site-specific problems. Close cooperation with related efforts at academic institutions and other agencies, to transfer pertinent information and avoid duplication of effort, will be a primary goal of the program. The major effort will focus on the complete coal extraction/reclamation cycle where necessary to develop solutions to ameliorating the environmental impacts of coal development. A long-range comprehensive national reclamation program will be established that can schedule and prioritize research activities in all of the major coal regions. A fully integrated data management system will be developed to store and manage relevant environmental and land use data. Nine research demonstration sites have been identified.

  5. RIMS Program Description.

    Science.gov (United States)

    Kraepelien, Hans

    Computer routines for the translation of teacher-prepared mark sense forms to magnetic tape are described. The program, Receiving IMS (RIMS), is part of the Southwest Regional Laboratory's (SWRL) Instructional Management System (IMS). It accepts mark sense sheets from remotely located Xerox 660 scanner copiers and/or IMS update information from…

  6. 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.)

  7. GROUNDWATER PROTECTION MANAGEMENT PROGRAM DESCRIPTION.

    Energy Technology Data Exchange (ETDEWEB)

    PAQUETTE,D.E.; BENNETT,D.B.; DORSCH,W.R.; GOODE,G.A.; LEE,R.J.; KLAUS,K.; HOWE,R.F.; GEIGER,K.

    2002-05-31

    THE DEPARTMENT OF ENERGY ORDER 5400.1, GENERAL ENVIRONMENTAL PROTECTION PROGRAM, REQUIRES THE DEVELOPMENT AND IMPLEMENTATION OF A GROUNDWATER PROTECTION PROGRAM. THE BNL GROUNDWATER PROTECTION MANAGEMENT PROGRAM DESCRIPTION PROVIDES AN OVERVIEW OF HOW THE LABORATORY ENSURES THAT PLANS FOR GROUNDWATER PROTECTION, MONITORING, AND RESTORATION ARE FULLY DEFINED, INTEGRATED, AND MANAGED IN A COST EFFECTIVE MANNER THAT IS CONSISTENT WITH FEDERAL, STATE, AND LOCAL REGULATIONS.

  8. 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)

  9. DWPF waste glass Product Composition Control System

    International Nuclear Information System (INIS)

    Brown, K.G.; Postles, R.L.

    1992-01-01

    The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canisters for cooling and, ultimately, shipment to and storage in a geologic repository. The Product Composition Control System (PCCS) is the system intended to ensure that the melt will be processible and that the glass wasteform will be acceptable. This document provides a description of this system

  10. REMOTE IN-CELL SAMPLING IMPROVEMENTS PROGRAM AT THESAVANNAH RIVER SITE (SRS) DEFENSE WASTE PROCESSING FACILITY (DWPF)

    International Nuclear Information System (INIS)

    Marzolf, A

    2007-01-01

    Remote Systems Engineering (RSE) of the Savannah River National Lab (SRNL) in combination with the Defense Waste Processing Facility(DWPF) Engineering and Operations has evaluated the existing equipment and processes used in the facility sample cells for 'pulling' samples from the radioactive waste stream and performing equipment in-cell repairs/replacements. RSE has designed and tested equipment for improving remote in-cell sampling evolutions and reducing the time required for in-cell maintenance of existing equipment. The equipment within the present process tank sampling system has been in constant use since the facility start-up over 17 years ago. At present, the method for taking samples within the sample cells produces excessive maintenance and downtime due to frequent failures relative to the sampling station equipment and manipulator. Location and orientation of many sampling stations within the sample cells is not conducive to manipulator operation. The overextension of manipulators required to perform many in-cell operations is a major cause of manipulator failures. To improve sampling operations and reduce downtime due to equipment maintenance, a Portable Sampling Station (PSS), wireless in-cell cameras, and new commercially available sampling technology has been designed, developed and/or adapted and tested. The uniqueness of the design(s), the results of the scoping tests, and the benefits relative to in-cell operation and reduction of waste are presented

  11. 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

  12. 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)

  13. 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.

  14. DWPF glass transition temperatures: What they are and why they are important

    International Nuclear Information System (INIS)

    Marra, S.L.; Jantzen, C.M.; Ramsey, A.A.

    1991-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site will immobilize high-level radioactive liquid waste in borosilicate glass. The glass will be poured into stainless steel canisters for eventual disposal in a geologic repository. The Department of Energy has defined a set of requirements for the DWPF canistered waste form which must be met in order to assure compatibility with, and acceptance by, the repository. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). The WAPS require DWPF to report glass transition temperatures for the projected range of compositions. This information will be used by the repository to establish waste package design limits

  15. DWPF glass transition temperatures - What they are and why they are important

    International Nuclear Information System (INIS)

    Marra, S.L.; Applewhite-Ramsey, A.L.; Jantzen, C.M.

    1991-01-01

    The Department of Energy has defined a set of requirements for the DWPF canistered waste form which must be met in order to assure compatibility with, and acceptance by, the first geologic repository. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). The WAPS require DWPF to report glass transition temperatures for the projected range of compositions. This information will be used by the repository to establish waste package design limits

  16. 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

  17. 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...

  18. 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

  19. 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

  20. The DWPF strategy for producing an acceptable product

    International Nuclear Information System (INIS)

    Goldston, W.T.; Plodinec, M.J.

    1991-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will convert the 130 million liters of high-level nuclear waste at SRS into stable borosilicate glass. Production of canistered waste forms by the DWPF is scheduled to begin well before submission of the license application for the first repository. The Department of Energy has defined waste acceptance specifications to ensure that DWPF canistered waste forms will be acceptable for eventual disposal. To ensure that canistered waste forms meet those specifications, a program is being carried out to qualify the waste form and those aspects of the production process which affect product quality. This program includes: Pre-production qualification testing of simulated and actual waste forms; Disciplined demonstrations of the ability to produce an acceptable product during startup testing; and Application of a rigorous product control program during production

  1. 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

  2. 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.

  3. 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

  4. Transuranic Waste Characterization Quality Assurance Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-30

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

  5. Transuranic Waste Characterization Quality Assurance Program Plan

    International Nuclear Information System (INIS)

    1995-01-01

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

  6. 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)

  7. 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

  8. 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

  9. 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.

  10. Can-in-canister cold demonstration in DWPF (U)

    International Nuclear Information System (INIS)

    Kuehn, N.H.

    1996-07-01

    The Department of Energy Fissile Materials Disposition Program is evaluating a number of options for disposition of weapons-usable plutonium surplus to national defense needs. One of the immobilization options is the Can-In-Canister approach. In this option small cans of a plutonium glass, which contains a neutron absorber, are placed on a support structure in a large Savannah River Site Defense Waste Processing Facility (DWPF) canister. The top is then welded onto the canister. This canister is filled with High Level Waste (HLW) glass at the DWPF. The HLW glass provides the radiation source for proliferation resistance. These canisters are to be placed in a Federal Repository. To provide information on the technical feasibility of this option prior to the Record of Decision on plutonium disposition, the Department of Energy Fissile Materials Disposition Program funded a demonstration in the DWPF. This demonstration was conducted before the start of radioactive operations. Two test canisters containing cans of surrogate (non- radioactive) plutonium glass were successfully filled with simulated HLW glass at the DWPF using standard pouring procedures. One canister had twenty cans of surrogate plutonium glass. The other had eight cans of surrogate plutonium glass. After the canisters were filled, the contents of the canisters were examined to provide data on the effect of the rack and cans on the filling of the DWPF canister, the effect of the pour on the surrogate plutonium glass and the effect of the rack and cans on the simulated HLW glass. There was no deformation of the support racks during the pour. The simulated HLW glass filled all the regions around the rack and cans and the regions between the cans and the wall of the canister. This report discusses the design of the racks and cans, the modification of the DWPF canisters to accommodate the rack and cans, the conditions during the pours and the results of the post pour analysis

  11. 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.)

  12. The corrosion behavior of DWPF glasses

    International Nuclear Information System (INIS)

    Ebert, W.L.; Bates, J.K.

    1995-01-01

    The authors analyzed the corroded surfaces of reference glasses developed for the Defense Waste Processing Facility (DWPF) to characterize their corrosion behavior. The corrosion mechanism of nuclear waste glasses must be known in order to provide source terms describing radionuclide release for performance assessment calculations. Different DWPF reference glasses were corroded under conditions that highlighted various aspects of the corrosion process and led to different extents of corrosion. The glasses corroded by similar mechanisms, and a phenomenological description of their corrosion behavior is presented here. The initial leaching of soluble glass components results in the formation of an amorphous gel layer on the glass surface. The gel layer is a transient phase that transforms into a layer of clay crystallites, which equilibrates with the solution as corrosion continues. The clay layer does not act as a barrier to either water penetration or glass dissolution, which continues beneath it, and may eventually separate from the glass. Solubility limits for glass components may be established by the eventual precipitation of secondary phases; thus, corrosion of the glass becomes controlled by the chemical equilibrium between the solution and the assemblage of secondary phases. In effect, the solution is an intermediate phase through which the glass transforms to an energetically more favorable assemblage of phases. Implications regarding the prediction of long-term glass corrosion behavior are discussed

  13. 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)

  14. 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

  15. Quality assurance program plan for SNF characterization support project

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

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

  16. 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

  17. Relaxation of the lower frit loading constraint for DWPF process control

    International Nuclear Information System (INIS)

    Brown, K.G.

    2000-01-01

    The lower limit on the frit loading parameter when measurement uncertainty is introduced has impacted DWPF performance during immobilization of Tank 42 Sludge; therefore, any defensible relaxation or omission of this constraint should correspondingly increase DWPF waste loading and efficiency. Waste loading should be increased because the addition of frit is the current remedy for exceeding the lower frit loading constraint. For example, frit was added to DWPF SME Batches 94, 97 and 98 to remedy these batches for low frit loading. Attempts were also made to add frit in addition to the optimum computed to assure the lower frit loading constraint would be satisfied; however, approximately half of the SME Batches produced after Batch 98 have violated the lower frit loading constraint. If the DWPF batches did not have to be remediated and additional frit added because of the lower frit loading limit, then both, the performance of the DWPF process and the waste loading in the glass produced would be increased. Before determining whether or not the lower frit loading limit can be relaxed or omitted, the origin of this and the other constraints related to durability prediction must be examined. The lower limit loading constraint results from the need to make highly durable glass in DWPF. It is required that DWPF demonstrate that the glass produced would have durability that is at least two standard deviations greater than that of the Environmental Assessment (EA) glass. Glass durability cannot be measured in situ, it must be predicted from composition which can be measured. Fortunately, the leaching characteristics of homogeneous waste glasses is strongly related to the total molar free energy of the constituent species. Thus the waste acceptance specification has been translated into a requirement that the total molar free energy associated with the glass composition that would be produced from a DWPF melter feed batch be less than that of the EA glass accounting for

  18. 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

  19. 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

  20. DWPF recycle minimization: Brainstorming session

    International Nuclear Information System (INIS)

    Jacobs, R.A.; Poirier, M.R.

    1993-01-01

    The recycle stream from the DWPF constitutes a major source of water addition to the High Level Waste evaporator system. As now designed, the entire flow of 3.5 to 6.5 gal/min (at sign 25% and 75% attainment, respectively), or 2 gal/min during idling, flow to the 2H evaporator system (Tank 43). Substantial improvement in the HLW water balance and tank volume management is expected if the DWPF recycle to the HLW evaporator system can be significantly reduced. A task team has been appointed to study alternatives for reducing the flow to the HLW evaporator system and make recommendations for implementation and/or further study and evaluation. The brainstorming session detailed in this report was designed to produce the first cut options for the task team to further evaluate

  1. 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…

  2. 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

  3. 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...

  4. 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...

  5. 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

  6. 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.

  7. 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)

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. AGRIS: Description of computer programs

    International Nuclear Information System (INIS)

    Schmid, H.; Schallaboeck, G.

    1976-01-01

    The set of computer programs used at the AGRIS (Agricultural Information System) Input Unit at the IAEA, Vienna, Austria to process the AGRIS computer-readable data is described. The processing flow is illustrated. The configuration of the IAEA's computer, a list of error messages generated by the computer, the EBCDIC code table extended for AGRIS and INIS, the AGRIS-6 bit code, the work sheet format, and job control listings are included as appendixes. The programs are written for an IBM 370, model 145, operating system OS or VS, and require a 130K partition. The programming languages are PL/1 (F-compiler) and Assembler

  15. Firebird-III program description

    International Nuclear Information System (INIS)

    Lin, M.R.; Prawirosochardjo, S.; Rennick, D.F.; Wessman, E.; Blain, R.J.D.; Wilson, J.M.

    1979-09-01

    The FIREBIRD-III digital computer program is a general network code developed primarily for predicting the thermalhydraulic behaviour of CANDU power reactors during a postulated loss-of-coolant accident and the subsequent emergency coolant injection. Because of its flexibility, the code can also be used to solve a large variety of general two-phase flow problems. This report describes the thermalhydraulic models and the computation methods used in the program

  16. 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

  17. 40 CFR 233.11 - Program description.

    Science.gov (United States)

    2010-07-01

    ... organization and structure of the State agency (agencies) which will have responsibility for administering the... under § 233.10 shall include: (a) A description of the scope and structure of the State's program. The... will coordinate its enforcement strategy with that of the Corps and EPA; (h) A description of the...

  18. Quality assurance program in diagnostic radiology

    International Nuclear Information System (INIS)

    Yacovenco, Alejandro; Borges, J.C.

    1994-01-01

    Aiming to elaborate a methodology to optimize the performance of the Radiology Service of the Military Police Hospital, in Rio dee Janeiro, some goals were established: improvement of the attendance to patients; improvement of the qualification of technicians; achievement and maintenance of high degrees of quality in each step of the radiological process; improvement of the image quality; optimization of dose per examination and cost reduction. The procedure used to detect faults in the radiological process was the analysis of causes of film losses. Results show a 70% reduction in the film rejection rate. 74% of total identified faults were due to equipment, 11% to films, 10% to patients and 5% to developing. The reduction in the cost of developed film reached 75%. A training course given to the staff of the radiological service fully reached its goals, contributing, with the staff motivation, mostly to the success of the program. This success indicates that, with a serious persistent work, it is possible to offer to patients services within their expectations, even at a public hospital. Such programs should be supported by health authorities, not only due to their technical and economic needs but, mostly, due to their social implications. (author). 10 refs., 11 figs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-12-31

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

  20. [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.

  1. 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

  2. Optimization of radio-therapeutic treatment and the program of quality assurance in ionizing radiation therapy

    International Nuclear Information System (INIS)

    Rosca, A.; Bahnarel, I.; Coretchi, L.

    2015-01-01

    The Program of Quality Assurance (PQA) in Ionizing Radiation Therapy (IRT) addresses the most important problems of assuring the quality of IRT utilization in the treatment of patients with neoplasm. In this context, the IRT value grows considerably, hence the implementation of PQA is of great significance. The study concentrates on a detailed description of the PQA as concerns the activity involving IRT devices applied in the IRT departments (rooms) of public medical/sanitary institutions, science research institutions etc., where IRT is employed using technogenic sources and ionizing radiation generators. For the performing of the study, annual statistics reports about the activity of the IRT, and data of Cancer Registry of the Oncologic Institute of the Republic of Moldova were analyzed. The work also includes an in-depth description of the personnel categories involved in PQA, possible errors in radiotherapy, the responsibilities of the bioengineer in this program, importance of source calibration, the impact of the quality control in PQA, the role of topometric training, the interaction between the medical and technical personnel and the patient. Optimization of IRT is very important and necessary in the Republic of Moldova. PQA incontestably contributes to reducing specialist's errors in planning correct treatment, dictates the need of team work and proper delegation of the responsibilities in co-optation of other professionals, performance of duty of bioengineering, the influence of quality control of profile installations, meaning accurate topographic planning, applying several methods of work, quality assurance program assuming the major importance. (authors)

  3. 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

  4. DWPF Recycle Evaporator Simulant Tests

    International Nuclear Information System (INIS)

    Stone, M

    2005-01-01

    Testing was performed to determine the feasibility and processing characteristics of an evaporation process to reduce the volume of the recycle stream from the Defense Waste Processing Facility (DWPF). The concentrated recycle would be returned to DWPF while the overhead condensate would be transferred to the Effluent Treatment Plant. Various blends of evaporator feed were tested using simulants developed from characterization of actual recycle streams from DWPF and input from DWPF-Engineering. The simulated feed was evaporated in laboratory scale apparatus to target a 30X volume reduction. Condensate and concentrate samples from each run were analyzed and the process characteristics (foaming, scaling, etc) were visually monitored during each run. The following conclusions were made from the testing: Concentration of the ''typical'' recycle stream in DWPF by 30X was feasible. The addition of DWTT recycle streams to the typical recycle stream raises the solids content of the evaporator feed considerably and lowers the amount of concentration that can be achieved. Foaming was noted during all evaporation tests and must be addressed prior to operation of the full-scale evaporator. Tests were conducted that identified Dow Corning 2210 as an antifoam candidate that warrants further evaluation. The condensate has the potential to exceed the ETP WAC for mercury, silicon, and TOC. Controlling the amount of equipment decontamination recycle in the evaporator blend would help meet the TOC limits. The evaporator condensate will be saturated with mercury and elemental mercury will collect in the evaporator condensate collection vessel. No scaling on heating surfaces was noted during the tests, but splatter onto the walls of the evaporation vessels led to a buildup of solids. These solids were difficult to remove with 2M nitric acid. Precipitation of solids was not noted during the testing. Some of the aluminum present in the recycle streams was converted from gibbsite to

  5. Employee assistance programs: history and program description.

    Science.gov (United States)

    Gilbert, B

    1994-10-01

    1. The history and development of Employee Assistance Programs (EAPs) can be traced back to the 1800s. There are currently over 10,000 EAPs in the United States. 2. Standards for program accreditation and counselor certification have been established for EAPs. The "core technology of Employee Assistance Programs" includes identification of behavioural problems based on job performance issues, expert consultation with supervisors, appropriate use of constructive confrontation, microlinkages with treatment providers and resources, macrolinkages between providers, resources, and work organizations, focus on substance abuse, and evaluation of employee success based on job performance. 3. Some EAPs take a broad brush approach, and incorporate health promotion and managed care functions.

  6. Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling

    International Nuclear Information System (INIS)

    Marra, S.L.; Jantzen, C.M.

    1992-05-01

    Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Eventually these canistered waste forms will be sent to a geologic repository for final disposal. In order to assure acceptability by the repository, the Department of Energy has defined requirements which DWPF canistered waste forms must meet. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). The WAPS require DWPF to identify the crystalline phases expected to be present in the final glass product. Knowledge of the thermal history of the borosilicate glass during filling and cooldown of the canister is necessary to determine the amount and type of crystalline phases present in the final glass product. Glass samples of seven projected DWPF compositions were cooled following the same temperature profile as that of glass at the centerline of the full-scale DWPF canister. The glasses were characterized by x-ray diffraction and scanning electron microscopy to identify the crystalline phases present The volume percents of each crystalline phase present were determined by quantitative x-ray diffraction. The Product Consistency Test (PCI) was used to determine the durability of the heat-treated glasses

  7. 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.

  8. 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

  9. 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

  10. 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)

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. ELIMINATION OF THE CHARACTERIZATION OF DWPF POUR STREAM SAMPLE AND THE GLASS FABRICATION AND TESTING OF THE DWPF SLUDGE BATCH QUALIFICATION SAMPLE

    Energy Technology Data Exchange (ETDEWEB)

    Amoroso, J.; Peeler, D.; Edwards, T.

    2012-05-11

    A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In

  16. Elimination Of The Characterization Of DWPF Pour Stream Sample And The Glass Fabrication And Testing Of The DWPF Sludge Batch Qualification Sample

    International Nuclear Information System (INIS)

    Amoroso, J.; Peeler, D.; Edwards, T.

    2012-01-01

    A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In contrast, the

  17. 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)

  18. 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

  19. 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

  20. 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)

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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.)

  7. 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

  8. 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…

  9. 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

  10. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-03-01

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

  11. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  12. 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)

  13. 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.

  14. Description of mathematical models and computer programs

    International Nuclear Information System (INIS)

    1977-01-01

    The paper gives a description of mathematical models and computer programs for analysing possible strategies for spent fuel management, with emphasis on economic analysis. The computer programs developed, describe the material flows, facility construction schedules, capital investment schedules and operating costs for the facilities used in managing the spent fuel. The computer programs use a combination of simulation and optimization procedures for the economic analyses. Many of the fuel cycle steps (such as spent fuel discharges, storage at the reactor, and transport to the RFCC) are described in physical and economic terms through simulation modeling, while others (such as reprocessing plant size and commissioning schedules, interim storage facility commissioning schedules etc.) are subjected to economic optimization procedures to determine the approximate lowest-cost plans from among the available feasible alternatives

  15. 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

  16. 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

  17. 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

  18. 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

  19. DWPF simulant CPC studies for SB8

    Energy Technology Data Exchange (ETDEWEB)

    Koopman, D. C.; Zamecnik, J. R.

    2013-06-25

    The Savannah River National Laboratory (SRNL) accepted a technical task request (TTR) from Waste Solidification Engineering to perform simulant tests to support the qualification of Sludge Batch 8 (SB8) and to develop the flowsheet for SB8 in the Defense Waste Processing Facility (DWPF). These efforts pertained to the DWPF Chemical Process Cell (CPC). Separate studies were conducted for frit development and glass properties (including REDOX). The SRNL CPC effort had two primary phases divided by the decision to drop Tank 12 from the SB8 constituents. This report focuses on the second phase with SB8 compositions that do not contain the Tank 12 piece. A separate report will document the initial phase of SB8 testing that included Tank 12. The second phase of SB8 studies consisted of two sets of CPC studies. The first study involved CPC testing of an SB8 simulant for Tank 51 to support the CPC demonstration of the washed Tank 51 qualification sample in the SRNL Shielded Cells facility. SB8-Tank 51 was a high iron-low aluminum waste with fairly high mercury and moderate noble metal concentrations. Tank 51 was ultimately washed to about 1.5 M sodium which is the highest wash endpoint since SB3-Tank 51. This study included three simulations of the DWPF Sludge Receipt and Adjustment Tank (SRAT) cycle and Slurry Mix Evaporator (SME) cycle with the sludge-only flowsheet at nominal DWPF processing conditions and three different acid stoichiometries. These runs produced a set of recommendations that were used to guide the successful SRNL qualification SRAT/SME demonstration with actual Tank 51 washed waste. The second study involved five SRAT/SME runs with SB8-Tank 40 simulant. Four of the runs were designed to define the acid requirements for sludge-only processing in DWPF with respect to nitrite destruction and hydrogen generation. The fifth run was an intermediate acid stoichiometry demonstration of the coupled flowsheet for SB8. These runs produced a set of processing

  20. DWPF simulant CPC studies for SB8

    International Nuclear Information System (INIS)

    Koopman, D. C.; Zamecnik, J. R.

    2013-01-01

    The Savannah River National Laboratory (SRNL) accepted a technical task request (TTR) from Waste Solidification Engineering to perform simulant tests to support the qualification of Sludge Batch 8 (SB8) and to develop the flowsheet for SB8 in the Defense Waste Processing Facility (DWPF). These efforts pertained to the DWPF Chemical Process Cell (CPC). Separate studies were conducted for frit development and glass properties (including REDOX). The SRNL CPC effort had two primary phases divided by the decision to drop Tank 12 from the SB8 constituents. This report focuses on the second phase with SB8 compositions that do not contain the Tank 12 piece. A separate report will document the initial phase of SB8 testing that included Tank 12. The second phase of SB8 studies consisted of two sets of CPC studies. The first study involved CPC testing of an SB8 simulant for Tank 51 to support the CPC demonstration of the washed Tank 51 qualification sample in the SRNL Shielded Cells facility. SB8-Tank 51 was a high iron-low aluminum waste with fairly high mercury and moderate noble metal concentrations. Tank 51 was ultimately washed to about 1.5 M sodium which is the highest wash endpoint since SB3-Tank 51. This study included three simulations of the DWPF Sludge Receipt and Adjustment Tank (SRAT) cycle and Slurry Mix Evaporator (SME) cycle with the sludge-only flowsheet at nominal DWPF processing conditions and three different acid stoichiometries. These runs produced a set of recommendations that were used to guide the successful SRNL qualification SRAT/SME demonstration with actual Tank 51 washed waste. The second study involved five SRAT/SME runs with SB8-Tank 40 simulant. Four of the runs were designed to define the acid requirements for sludge-only processing in DWPF with respect to nitrite destruction and hydrogen generation. The fifth run was an intermediate acid stoichiometry demonstration of the coupled flowsheet for SB8. These runs produced a set of processing

  1. 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.

  2. CANGEO program description and user's instruction

    International Nuclear Information System (INIS)

    Park, Joo Hwan; Jun, J. S.; Suk, H. C.; Hwang, D. H.; Yoo, Y. J.

    1997-10-01

    This is a report for the description and user's instruction of CANGEO (CANdu GEOmetry) program. CANGEO program is able to generate the geometry input for thermalhydraulic subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel data for a complicated geometry such as a CANDU fuel channel. And this code can be applicable to a bundle eccentricity from pressure tube center to bundle center, pressure tube creep, rod ballooning, and any symmetric subchannel geometry required by thermalhydraulic subchannel analysis code. The report also describes the basic calculation method of subchannel geometry, including user's manual, input and output for a CANDU fuel channel loaded with 37-element fuel bundle. (author). 35 refs., 6 figs

  3. 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.

  4. 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

  5. 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

  6. A reference standard-based quality assurance program for radiology.

    Science.gov (United States)

    Liu, Patrick T; Johnson, C Daniel; Miranda, Rafael; Patel, Maitray D; Phillips, Carrie J

    2010-01-01

    The authors have developed a comprehensive radiology quality assurance (QA) program that evaluates radiology interpretations and procedures by comparing them with reference standards. Performance metrics are calculated and then compared with benchmarks or goals on the basis of published multicenter data and meta-analyses. Additional workload for physicians is kept to a minimum by having trained allied health staff members perform the comparisons of radiology reports with the reference standards. The performance metrics tracked by the QA program include the accuracy of CT colonography for detecting polyps, the false-negative rate for mammographic detection of breast cancer, the accuracy of CT angiography detection of coronary artery stenosis, the accuracy of meniscal tear detection on MRI, the accuracy of carotid artery stenosis detection on MR angiography, the accuracy of parathyroid adenoma detection by parathyroid scintigraphy, the success rate for obtaining cortical tissue on ultrasound-guided core biopsies of pelvic renal transplants, and the technical success rate for peripheral arterial angioplasty procedures. In contrast with peer-review programs, this reference standard-based QA program minimizes the possibilities of reviewer bias and erroneous second reviewer interpretations. The more objective assessment of performance afforded by the QA program will provide data that can easily be used for education and management conferences, research projects, and multicenter evaluations. Additionally, such performance data could be used by radiology departments to demonstrate their value over nonradiology competitors to referring clinicians, hospitals, patients, and third-party payers. Copyright 2010 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  7. DWPF remotable television and cell lighting facilities

    International Nuclear Information System (INIS)

    Heckendorn, F.M. II.

    1984-01-01

    The Defense Waste Processing Facility (DWPF) for radioactive waste vitrification at the Savannah River Plant (SRP) is now under construction. Development of specialized low cost television (TV) viewing equipment for in-cell and within-melter applications is now complete. High resolution TV cameras not originally designed for high radiation environments have been demonstrated in crane remotable packages to be well suited to the DWPF. High intensity in-cell lighting has also been demonstrated in crane remotable assemblies. These dual 1000 W units (2000 W total) are used to support the multiplicity of TV and cell window viewing requirements. 8 figures

  8. Extending cluster lot quality assurance sampling designs for surveillance programs.

    Science.gov (United States)

    Hund, Lauren; Pagano, Marcello

    2014-07-20

    Lot quality assurance sampling (LQAS) has a long history of applications in industrial quality control. LQAS is frequently used for rapid surveillance in global health settings, with areas classified as poor or acceptable performance on the basis of the binary classification of an indicator. Historically, LQAS surveys have relied on simple random samples from the population; however, implementing two-stage cluster designs for surveillance sampling is often more cost-effective than simple random sampling. By applying survey sampling results to the binary classification procedure, we develop a simple and flexible nonparametric procedure to incorporate clustering effects into the LQAS sample design to appropriately inflate the sample size, accommodating finite numbers of clusters in the population when relevant. We use this framework to then discuss principled selection of survey design parameters in longitudinal surveillance programs. We apply this framework to design surveys to detect rises in malnutrition prevalence in nutrition surveillance programs in Kenya and South Sudan, accounting for clustering within villages. By combining historical information with data from previous surveys, we design surveys to detect spikes in the childhood malnutrition rate. Copyright © 2014 John Wiley & Sons, Ltd.

  9. Quality assurance in mammography and the DQM program

    International Nuclear Information System (INIS)

    Rimondi, O.; Giambaccini, M.; Marziani, M.

    1991-01-01

    The aim of the optimization program for mammography (DQM) in Italy is to achieve the best compromise between image quality and dose to patient. 272 centers agreed to the second phase of the program, from February 1987 to January 1990. Exposure, half-value layer (HVL) and focal spot size were measured according to the same methods employed in the first phase of the DQM program (1985), while image quality was evaluated by means of a new performance phantom. The average exposure was 0.96 R (2.48x10 -4 C/Kg); in 173 (64.3%) centers exposure was 5 R (12.9x10 -4 C/Kg). In every center the average whole-breast dose to a reference organ (5cm thick, composed of 50% fat +50% water) was calculated on the basis of entrance exposure, HVL, and focus-skin distance; in 63.2% of the centers doses <0.15 cGy were employed. The results allowed dose and image quality to be correlated in order to divide the centers (using a film-screen system) into groups with a different efficiency level: in 101 centers dose and image quality were good, in 64 centers too high a dose was employed, 66 centers image quality was poor, and in 38 centers dose was too high and image quality was poor. It must be stressed that the DQM program can play its role only if each center carries out its Quality Assurance activity after the methods recommended by the World Health Organization

  10. 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).

  11. 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

  12. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

    Energy Technology Data Exchange (ETDEWEB)

    Pareizs, J.; Billings, A.; Click, D.

    2011-07-08

    -radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

  13. 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

  14. ISOLOK VALVE ACCEPTANCE TESTING FOR DWPF SME SAMPLING PROCESS

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, T.; Hera, K.; Coleman, C.; Jones, M.; Wiedenman, B.

    2011-12-05

    Evaluation of the Defense Waste Processing Facility (DWPF) Chemical Process Cell (CPC) cycle time identified several opportunities to improve the CPC processing time. Of the opportunities, a focus area related to optimizing the equipment and efficiency of the sample turnaround time for DWPF Analytical Laboratory was identified. The Mechanical Systems & Custom Equipment Development (MS&CED) Section of the Savannah River National Laboratory (SRNL) evaluated the possibility of using an Isolok{reg_sign} sampling valve as an alternative to the Hydragard{reg_sign} valve for taking process samples. Previous viability testing was conducted with favorable results using the Isolok sampler and reported in SRNL-STI-2010-00749 (1). This task has the potential to improve operability, reduce maintenance time and decrease CPC cycle time. This report summarizes the results from acceptance testing which was requested in Task Technical Request (TTR) HLW-DWPF-TTR-2010-0036 (2) and which was conducted as outlined in Task Technical and Quality Assurance Plan (TTQAP) SRNL-RP-2011-00145 (3). The Isolok to be tested is the same model which was tested, qualified, and installed in the Sludge Receipt Adjustment Tank (SRAT) sample system. RW-0333P QA requirements apply to this task. This task was to qualify the Isolok sampler for use in the DWPF Slurry Mix Evaporator (SME) sampling process. The Hydragard, which is the current baseline sampling method, was used for comparison to the Isolok sampling data. The Isolok sampler is an air powered grab sampler used to 'pull' a sample volume from a process line. The operation of the sampler is shown in Figure 1. The image on the left shows the Isolok's spool extended into the process line and the image on the right shows the sampler retracted and then dispensing the liquid into the sampling container. To determine tank homogeneity, a Coliwasa sampler was used to grab samples at a high and low location within the mixing tank. Data from

  15. 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

  16. 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)

  17. 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

  18. 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

  19. Critical Infrastructure Protection and Information Assurance (CIPIA) Fellow Program

    National Research Council Canada - National Science Library

    Chen, Peter

    2003-01-01

    LSU was one of the universities chosen to participate in the project of training new researchers to work on the Critical Infrastructure Protection and Information Assurance (CIPIA) areas. Three Ph.D...

  20. 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

  1. 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

  2. International Nuclear Model. Volume 3. Program description

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

  3. 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

  4. 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.

  5. 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

  6. DWPF Simulant CPC Studies For SB8

    Energy Technology Data Exchange (ETDEWEB)

    Newell, J. D.

    2013-09-25

    Prior to processing a Sludge Batch (SB) in the Defense Waste Processing Facility (DWPF), flowsheet studies using simulants are performed. Typically, the flowsheet studies are conducted based on projected composition(s). The results from the flowsheet testing are used to 1) guide decisions during sludge batch preparation, 2) serve as a preliminary evaluation of potential processing issues, and 3) provide a basis to support the Shielded Cells qualification runs performed at the Savannah River National Laboratory (SRNL). SB8 was initially projected to be a combination of the Tank 40 heel (Sludge Batch 7b), Tank 13, Tank 12, and the Tank 51 heel. In order to accelerate preparation of SB8, the decision was made to delay the oxalate-rich material from Tank 12 to a future sludge batch. SB8 simulant studies without Tank 12 were reported in a separate report.1 The data presented in this report will be useful when processing future sludge batches containing Tank 12. The wash endpoint target for SB8 was set at a significantly higher sodium concentration to allow acceptable glass compositions at the targeted waste loading. Four non-coupled tests were conducted using simulant representing Tank 40 at 110-146% of the Koopman Minimum Acid requirement. Hydrogen was generated during high acid stoichiometry (146% acid) SRAT testing up to 31% of the DWPF hydrogen limit. SME hydrogen generation reached 48% of of the DWPF limit for the high acid run. Two non-coupled tests were conducted using simulant representing Tank 51 at 110-146% of the Koopman Minimum Acid requirement. Hydrogen was generated during high acid stoichiometry SRAT testing up to 16% of the DWPF limit. SME hydrogen generation reached 49% of the DWPF limit for hydrogen in the SME for the high acid run. Simulant processing was successful using previously established antifoam addition strategy. Foaming during formic acid addition was not observed in any of the runs. Nitrite was destroyed in all runs and no N2O was detected

  7. Energy Assurance Technical Training and Awareness Program/Energy Infrastructure Training and Analysis Center

    Energy Technology Data Exchange (ETDEWEB)

    Barbara McCabe

    2005-11-15

    destruction, respiratory protection, and decontamination. All of the courses and training modules are described in detail in the ''Training Course and Module Description Catalog'', April 2004. The OENHP has developed a Compendium of reference materials, training demonstration/hands-on models, and is revising its student manual. Course and instructor evaluations and the input of a general Advisory Board and an Advisory Board made up of Stationary (Building) Engineers has provided direction for modification and improvement of the Energy Security (Assurance) Training Program. The OENHP has identified the target training population, IUOE Stationary (Building) Engineers as being the primary population and IUOE heavy equipment operators as also being a targeted population. The OENHP however, has also identified several applicable populations outside of its membership, such as the Transport Workers Union and special populations within its membership, such as IUOE Local Union 25 Maritime Division. During Year One, a redesigned web site and brochures have been developed to assist in promotion of the energy security (assurance) program and the benefits of its training courses.

  8. 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

  9. 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)

  10. Radioactive demonstration of DWPF product control strategy

    International Nuclear Information System (INIS)

    Andrews, M.K.; Bibler, N.E.

    1992-01-01

    The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition similar to that predicted using the PCCS

  11. Liquidus Temperature Data for DWPF Glass

    International Nuclear Information System (INIS)

    Piepel, G.F.; Vienna, J.D.; Crum, J.V.; Mika, M.; Hrma, P.

    1999-01-01

    This report provides new liquidus temperature (T L ) versus composition data that can be used to reduce uncertainty in T L calculation for DWPF glass. According to the test plan and test matrix design PNNL has measured T L for 53 glasses within and just outside of the current DWPF processing composition window. The T L database generated under this task will directly support developing and enhancing the current T L process-control model. Preliminary calculations have shown a high probability of increasing HLW loading in glass produced at the SRS and Hanford. This increase in waste loading will decrease the life-cycle tank cleanup costs by decreasing process time and the volume of waste glass produced

  12. Bounding estimate of DWPF mercury emissions

    International Nuclear Information System (INIS)

    Jacobs, R.A.

    1992-01-01

    Purges required for H2 flammability control and verification of elevated Formic Acid Vent Condenser (FAVC) exit temperatures due to NO x reactions have lead to significant changes in Chemical Process Cell (CPC) operating conditions. Accordingly, mercury emissions estimates have been updated based upon the new operating requirements, IDMS (Integrated DWPF Melter System) experience, and development of an NO x /FAVC model which predicts FAVC exit temperatures. Using very conservative assumptions and maximum purge rates, the maximum calculated Hg emissions is approximately 130 lbs/yr. A range of 100 to 120 lbs/yr is conservatively predicted for other operating conditions. Defense Waste Processing Facility (DWPF) permitted Hg emissions are 175 lbs/yr (0.02 lbs/hr annual average)

  13. 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

  14. 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)

  15. DWPF waste form compliance plan (Draft Revision)

    International Nuclear Information System (INIS)

    Plodinec, M.J.; Marra, S.L.

    1991-01-01

    The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan

  16. 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

  17. 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

  18. 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...

  19. 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

  20. A survey of medical quality assurance programs in Ontario hospitals.

    OpenAIRE

    Barrable, B

    1992-01-01

    OBJECTIVE: To determine the prevalence and types of medical quality assurance practices in Ontario hospitals. DESIGN: Survey. SETTING: All teaching, community, chronic care, rehabilitation and psychiatric hospitals that were members of the Ontario Hospital Association as of May 1990. PARTICIPANTS: The person deemed by the chief executive officer of each hospital to be most responsible for medical administration. INTERVENTION: A questionnaire to obtain information on each hospital's use of cri...

  1. Extending cluster Lot Quality Assurance Sampling designs for surveillance programs

    OpenAIRE

    Hund, Lauren; Pagano, Marcello

    2014-01-01

    Lot quality assurance sampling (LQAS) has a long history of applications in industrial quality control. LQAS is frequently used for rapid surveillance in global health settings, with areas classified as poor or acceptable performance based on the binary classification of an indicator. Historically, LQAS surveys have relied on simple random samples from the population; however, implementing two-stage cluster designs for surveillance sampling is often more cost-effective than ...

  2. 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

  3. 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

  4. Hazards analyses of hydrogen evolution and ammonium nitrate accumulation in DWPF -- Revision 1

    International Nuclear Information System (INIS)

    Holtzscheiter, E.W.

    1994-01-01

    This revision consists of two reports, the first of which is an analysis of potential ammonium nitrate explosion hazards in the DWPF (Defense Waste Processing Facility). Sections describe the effect of impurities (organic and inorganic (chlorides, chromates, metals and oxides)); the consequences of a hydrogen deflagration or detonation; the role of confinement; the action of heat on ammonium nitrate; the thermal decomposition of ammonium nitrate; the hazard of spontaneous heating; and the explosive decomposition of ammonium nitrate. The second report, Hazard analysis of hydrogen evolution in DWPF: Process vessels and vent system for the late wash/nitric acid flowsheet, contains a description of a revised model for hydrogen generation based on the late wash/nitric acid process. The second part of the report is a sensitivity analysis of the base case conditions and the hydrogen generation model

  5. 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.

  6. 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

  7. DWPF liquid sample station: Status of equipment development

    International Nuclear Information System (INIS)

    Caplan, J.R.

    1987-01-01

    This report summarizes operating experience and equipment status of the DWPF liquid sample cell. Operation hours to date, results of equipment inspections and problems encountered and their solutions are discussed. An equipment and instrumentation status updating DPST-85-592, DWPF LIQUID SAMPLE CELL MOCK-UP, is presented. Remaining development items are also outlined

  8. Conditions for precipitation of copper phases in DWPF waste glass

    International Nuclear Information System (INIS)

    Schumacher, R.F.; Ramsey, W.G.

    1993-01-01

    The Defense Waste Processing Facility (DWPF) precipitate hydrolysis process requires the use of copper formate catalyst. The expected absorbed radiation doses to the precipitate require levels of copper formate that increase the potential for the precipitation of metallic copper in the DWPF Melter. The conditions required to avoid the precipitation of copper are described

  9. 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

  10. Hanford Site Composite Analysis Technical Approach Description: Automated Quality Assurance Process Design.

    Energy Technology Data Exchange (ETDEWEB)

    Dockter, Randy E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2017-07-31

    The U.S. Department of Energy (DOE) in DOE O 435.1 Chg. 1, Radioactive Waste Management, requires the preparation and maintenance of a composite analysis (CA). The primary purpose of the CA is to provide a reasonable expectation that the primary public dose limit is not likely to be exceeded by multiple source terms that may significantly interact with plumes originating at a low-level waste disposal facility. The CA is used to facilitate planning and land use decisions that help assure disposal facility authorization will not result in long-term compliance problems; or, to determine management alternatives, corrective actions, or assessment needs if potential problems are identified.

  11. Study of the Nuclear Regulatory Commission quality assurance program

    International Nuclear Information System (INIS)

    Muller, F.W.

    1977-08-01

    Recommendations from a three month study are presented for quality assurance in nuclear power plants as it is practiced in industry and regulated by the NRC. Requested by the NRC, the study was accomplished through on-site visits by Sandia personnel at NRC offices and industry locations and through discussion with relevant technical society groups and interested individuals. The study group recommended changes to improve QA regulation by the NRC, to improve industry application of 10CFR50, Appendix B criteria, and to extend and expand the scope of QA activities by both industry and NRC

  12. Quality assurance programs at the PNL calibrations laboratory

    International Nuclear Information System (INIS)

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

    1993-03-01

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

  13. NRC/RSR Data Bank Program description

    International Nuclear Information System (INIS)

    Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., at Idaho National Engineering Laboratory. The NRC/RSR Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, and training and advisory services to users and the NRC. The NRC/RSR Data Bank Program and the capabilities of the data access software are described

  14. DWPF Sample Vial Insert Study-Statistical Analysis of DWPF Mock-Up Test Data

    Energy Technology Data Exchange (ETDEWEB)

    Harris, S.P. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-09-18

    This report is prepared as part of Technical/QA Task Plan WSRC-RP-97-351 which was issued in response to Technical Task Request HLW/DWPF/TTR-970132 submitted by DWPF. Presented in this report is a statistical analysis of DWPF Mock-up test data for evaluation of two new analytical methods which use insert samples from the existing HydragardTM sampler. The first is a new hydrofluoric acid based method called the Cold Chemical Method (Cold Chem) and the second is a modified fusion method.Either new DWPF analytical method could result in a two to three fold improvement in sample analysis time.Both new methods use the existing HydragardTM sampler to collect a smaller insert sample from the process sampling system. The insert testing methodology applies to the DWPF Slurry Mix Evaporator (SME) and the Melter Feed Tank (MFT) samples.The insert sample is named after the initial trials which placed the container inside the sample (peanut) vials. Samples in small 3 ml containers (Inserts) are analyzed by either the cold chemical method or a modified fusion method. The current analytical method uses a HydragardTM sample station to obtain nearly full 15 ml peanut vials. The samples are prepared by a multi-step process for Inductively Coupled Plasma (ICP) analysis by drying, vitrification, grinding and finally dissolution by either mixed acid or fusion. In contrast, the insert sample is placed directly in the dissolution vessel, thus eliminating the drying, vitrification and grinding operations for the Cold chem method. Although the modified fusion still requires drying and calcine conversion, the process is rapid due to the decreased sample size and that no vitrification step is required.A slurry feed simulant material was acquired from the TNX pilot facility from the test run designated as PX-7.The Mock-up test data were gathered on the basis of a statistical design presented in SRT-SCS-97004 (Rev. 0). Simulant PX-7 samples were taken in the DWPF Analytical Cell Mock

  15. 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

  16. 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

  17. 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.

  18. Solid Waste Program technical baseline description

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, A.B.

    1994-07-01

    The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

  19. 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

  20. Bounding estimate of DWPF mercury emissions

    International Nuclear Information System (INIS)

    Jacobs, R.A.

    1993-01-01

    Two factors which have substantial impact on predicted Mercury emissions are the air flows in the Chemical Process Cell (CPC) and the exit temperature of the Formic Acid Vent Condenser (FAVC). The discovery in the IDMS (Integrated DWPF Melter System) of H 2 generation by noble metal catalyzed formic acid decomposition and the resultant required dilution air flow has increased the expected instantaneous CPC air flow by as much as a factor of four. In addition, IDMS has experienced higher than design (10 degrees C) FAVC exit temperatures during certain portions of the operating cycle. These temperatures were subsequently attributed to the exothermic reaction of NO to NO 2 . Moreover, evaluation of the DWPF FAVC indicated it was undersized and unless modified or replaced, routine exit temperatures would be in excess of design. Purges required for H 2 flammability control and verification of elevated FAVC exit temperatures due to NO x reactions have lead to significant changes in CPC operating conditions. Accordingly, mercury emissions estimates have been updated based upon the new operating requirements, IDMS experience, and development of an NO x /FAVC model which predicts FAVC exit temperatures. Using very conservative assumptions and maximum purge rates, the maximum calculated Hg emissions is approximately 130 lbs/yr. A range of 100 to 120 lbs/yr is conservatively predicted for other operating conditions. The peak emission rate calculated is 0.027 lbs/hr. The estimated DWPF Hg emissions for the construction permit are 175 lbs/yr (0.02 lbs/hr annual average)

  1. 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

  2. The Caltech Concurrent Computation Program - Project description

    Science.gov (United States)

    Fox, G.; Otto, S.; Lyzenga, G.; Rogstad, D.

    1985-01-01

    The Caltech Concurrent Computation Program wwhich studies basic issues in computational science is described. The research builds on initial work where novel concurrent hardware, the necessary systems software to use it and twenty significant scientific implementations running on the initial 32, 64, and 128 node hypercube machines have been constructed. A major goal of the program will be to extend this work into new disciplines and more complex algorithms including general packages that decompose arbitrary problems in major application areas. New high-performance concurrent processors with up to 1024-nodes, over a gigabyte of memory and multigigaflop performance are being constructed. The implementations cover a wide range of problems in areas such as high energy and astrophysics, condensed matter, chemical reactions, plasma physics, applied mathematics, geophysics, simulation, CAD for VLSI, graphics and image processing. The products of the research program include the concurrent algorithms, hardware, systems software, and complete program implementations.

  3. Results of the quality assurance testing program for radiopharmaceuticals 1995

    International Nuclear Information System (INIS)

    Baldas, J.; Binnyman, J.; Ivanov, Z.; Lauder, R.

    1996-07-01

    The results of the quality assurance testing conducted by the Australian Radiation Laboratory is summarised. Overall 111 batches of 27 different types of radiopharmaceuticals were tested on samples obtained through normal commercial channels. Failure to meet full specifications was observed in 10 of the 111 batches. All technetium-99m cold kits were reconstituted according to the directions in the package insert using sodium pertechnetate ( 99m Tc) injection. Radionuclidic purity has been determined at the calibration time, except for Thallous [ 201 Tl] Chloride injection where the highest impurity level up to product expiry is quoted. Non-compliance of the vial label was observed in one of the ten batches failing specification and was the sole cause of product failure for this batch. Vial label non-compliance consisted of, absence of volume in the vial. Six batches failed the biodistribution test but in no case did this involve failure of the distribution for the target organs. tabs

  4. Results of the quality assurance testing program for radiopharmaceuticals 1995

    Energy Technology Data Exchange (ETDEWEB)

    Baldas, J.; Binnyman, J.; Ivanov, Z.; Lauder, R.

    1996-07-01

    The results of the quality assurance testing conducted by the Australian Radiation Laboratory is summarised. Overall 111 batches of 27 different types of radiopharmaceuticals were tested on samples obtained through normal commercial channels. Failure to meet full specifications was observed in 10 of the 111 batches. All technetium-99m cold kits were reconstituted according to the directions in the package insert using sodium pertechnetate ( {sup 99m}Tc) injection. Radionuclidic purity has been determined at the calibration time, except for Thallous [{sup 201}Tl] Chloride injection where the highest impurity level up to product expiry is quoted. Non-compliance of the vial label was observed in one of the ten batches failing specification and was the sole cause of product failure for this batch. Vial label non-compliance consisted of, absence of volume in the vial. Six batches failed the biodistribution test but in no case did this involve failure of the distribution for the target organs. tabs.

  5. 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

  6. 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)

  7. 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.

  8. 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)

  9. Quality Assurance Program Plan for the radiological survey activities program --- Uranium Mill Tailings Remedial Action Project

    International Nuclear Information System (INIS)

    Knott, R.R.; Little, C.A.

    1991-08-01

    The Pollutant Assessments Group (PAG) at the Grand Junction Office (GJO), Colorado, of 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 these sites from UMTRAP based on whether the on-site residual radioactive material (if any) originated from the former mill sites, and radiation levels on-site are in excess of appropriate Environmental Protection Agency (EPA) criteria. This report describes the Quality Assurance Plan (QAP) for the PAG in conducting all activities related to UMTRAP. 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 PAG/UMTRA QA program, identifies those organizational units involved in the implementation of these procedures, and outlines the respective responsibilities of those groups. 11 refs., 6 figs., 3 tabs

  10. Description of the RZV and RZF programs

    International Nuclear Information System (INIS)

    Raevskaya, V.E.; Torlin, B.Z.

    1980-01-01

    An instruction for running the P3B and P3F programs intended for an implementation of a one-group calculation of the neutron field in a polycell with multizone ring blocks in the P 3 approximation. The program is written in the FORTRAN language for the BESM-6 computer. Time for the calculation of one variant constitutes about 20 s for a simple cell and for double lattices for uniform blocks and 40 s - for double lattices from 30-zone blocks. 4 minutes is the maximum time required for the calculation of the 8x8 polycell consisting from 20 nonequivalent 30-zone blocks of 20 kinds

  11. Building Program Models Incrementally from Informal Descriptions.

    Science.gov (United States)

    1979-10-01

    specified at each step. Since the user controls the interaction, the user may determine the order in which information flows into PMB. Information is received...until only ten years ago the term aautomatic programming" referred to the development of the assemblers, macro expanders, and compilers for these

  12. Radioactive demonstration of DWPF product control strategy

    International Nuclear Information System (INIS)

    Andrews, M.K.; Bibler, N.E.

    1994-01-01

    The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150 degrees C. Process reliability and product quality are ensured by proper control of the melter feed composition. The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter an analysis of the glass product both for its composition an durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition very close to that predicted using the PCCS. 10 refs., 4 tabs

  13. 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

  14. 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

  15. 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.)

  16. 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

  17. 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

  18. Quality assurance package for routine thermoluminescence dosimetry program

    International Nuclear Information System (INIS)

    Tawil, R.A.; Bencke, G.; Moscovitch, M.

    1988-01-01

    The Quality Assurance Package presented here specifies a set of reader-related hardware diagnostics and calibration procedures and automatically maintains audit trails of generated and derived thermoluminescence data. It specifies acceptable performance criteria for the reader and dosimeter assemblies; tracks and controls Readout Cycle Temperature Profiles; and ensures that the acquired data is verified. The quality of the generated glow curves is tracked by the real-time application of Computerized Glow Curve Deconvolution to reference dosimeters that may be mixed with field dosimeters during readout sessions. This package is supported by a menu-driven software system using vertical auto-selection menus, lotus-style horizontal menus, data entry menus with automatic error checking, and pop-up windows. The menu system is supported by an extensive HELP file; data EDITING is password-protected, and a journal is maintained for each editing session as part of the audit trail. Files for the Raw Data and Derived Dose results are maintained and managed in seven databases. The paper provides an in-depth analysis of each of the procedures, specifies data validation criteria, and presents samples of the reports generated

  19. A new postal quality assurance program for diagnostic radiology departments

    International Nuclear Information System (INIS)

    Brown, L.D.

    1988-01-01

    The Federal Government of Canada has responsibility for the design and performance of new x-ray equipment, but the Provinces have responsibility for controlling the installation, maintenance and use of the equipment. For the past 30 years Saskatchewan has had regular inspection of X-ray units by radiation health officers who have ensured that deficiencies are corrected. With the present emphasis on quality assurance procedures and hospital accreditation requirements some additional needs have had to be met. These are primarily due to unusual geographical factors. The province covers a quarter to a million square miles and has a continental climate with very severe winters. This used to impede winter travel and many small communities therefore established their own hospital. Today there are a large number of very small hospitals (four beds and upwards) which are geographically widely spread and which, with current resources, can only be visited rather infrequently. A mail out test package, primarily designed to give early warning of the existence of radiation related problems, has therefore been introduced. If a test gives an unexpected result, a prompt visit can be made to the centre concerned to carry out whatever more sophisticated test procedures may be necessary. Experience has shown however that the postal test package has, in itself, a high diagnostic potential so the source of the problem can often be identified without a visit becoming necessary

  20. 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

  1. 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.

  2. The Behavior and Effects of the Noble Metals in the DWPF Melter System

    International Nuclear Information System (INIS)

    Smith, M.E.; Bickford, D.F.

    1997-01-01

    Governments worldwide have committed to stabilization of high-level nuclear waste (HLW) by vitrification to a durable glass form for permanent disposal. All of these nuclear wastes contain the fission-product noble metals: ruthenium, rhodium, and palladium. SRS wastes also contain natural silver from iodine scrubbers. Closely associated with the noble metals are the fission products selenium and tellurium which are chemical analogs of sulfur and which combine with noble metals to influence their behavior and properties. Experience has shown that these melt insoluble metals and their compounds tend to settle to the floor of Joule-heated ceramic melters. In fact, almost all of the major research and production facilities have experienced some operational problem which can be associated with the presence of dense accumulations of these relatively conductive metals and/or their compounds. In most cases, these deposits have led to a loss of production capability, in some cases, to the point that melter operation could not continue. HLW nuclear waste vitrification facilities in the United States are the Department of Energy's Defense Waste Processing Facility (DWPF) at the Savannah River Site, the planned Hanford Waste Vitrification Plant (HWVP) at the Hanford Site and the operating West Valley Demonstration Project (WVDP) at West Valley, NY. The Integrated DWPF Melter System (IDMS) is a vitrification test facility at the Savannah River Technology Center (SRTC). It was designed and constructed to provide an engineering-scale representation of the DWPF melter and its associated feed preparation and off-gas treatment systems. An extensive noble metals testing program was begun in 1990. The objectives of this task were to explore the effects of the noble metals on the DWPF melter feed preparation and waste vitrification processes. This report focuses on the vitrification portion of the test program

  3. System for the quality assurance of personnel training programs

    International Nuclear Information System (INIS)

    Rjona, Orison; Venegas, Maria del C.; Rodriguez, Lazaro; Lopez, Miguel A.; Armenteros, Ana L.

    1999-01-01

    In this work are described the fundamental possibilities and characteristics of a software that allows to carry out the management and automatic evaluation of all data gotten during jobs analysis and design, development, implementation and evaluation of personnel training programs of nuclear and radioactive installations and risk industries. The system that is introduced, GESAT, proportion a tool of centralized managerial control of training data and the obtaining of the quality objectives of each installation in the training of their personnel. GESAT includes all phases of SAT method (Systematic Approach to Training). It constitutes the necessary practical support for the elaboration, implementation and evaluation of training programs, allowing the establishment of restrictions and controls and avoiding inconsistencies in the process. It offers the possibility of automatic evaluation that identify fundamental deficiencies in the planning and implementation of training programs. This evaluation facilitates the systematic feed back and the continuous improvement of the training programs.(author)

  4. Quality Assurance Plan for Transportation Management Division Transportation Training Programs

    International Nuclear Information System (INIS)

    1994-10-01

    The U.S. Department of Transportation (DOT) implemented new rules requiring minimum levels of training for certain key individuals who handle, package, transport, or otherwise prepare hazardous materials for transportation. In response to these rules, the U.S. Department of Energy (DOE), Transportation Management Division (TMD), has developed a transportation safety training program. This program supplies designed instructional methodology and course materials to provide basic levels of DOT training to personnel for whom training has become mandatory. In addition, this program provides advanced hazardous waste and radioactive material packaging and transportation training to help personnel achieve proficiency and/or certification as hazardous waste and radioactive material shippers. This training program does not include site-specific or task-specific training beyond DOT requirements

  5. 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

  6. ENDF/B-V utility programs: description and operating instructions

    International Nuclear Information System (INIS)

    McLaughlin, K.

    1984-03-01

    A description and operating instructions are supplied for the following ENDF/B-V Processing Programs: CHECKER, CRECT, STNDRD, FIZCON, PSYCHE, RESEND, INTER, INTEND, SUMRIZ, PLOTEF, LSTFCV, RIGEL. These programs can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  7. Quality Assurance Program Plan for Project W-379: Spent Nuclear Fuels Canister Storage Building Projec

    International Nuclear Information System (INIS)

    Duncan, D.W.

    1995-01-01

    This document describes the Quality Assurance Program Plan (QAPP) for the Spent Nuclear Fuels (SNF) Canister Storage Building (CSB) Project. The purpose of this QAPP is to control project activities ensuring achievement of the project mission in a safe, consistent and reliable manner

  8. 42 CFR 423.153 - Drug utilization management, quality assurance, and medication therapy management programs (MTMPs).

    Science.gov (United States)

    2010-10-01

    ... PRESCRIPTION DRUG BENEFIT Cost Control and Quality Improvement Requirements § 423.153 Drug utilization... 42 Public Health 3 2010-10-01 2010-10-01 false Drug utilization management, quality assurance, and medication therapy management programs (MTMPs). 423.153 Section 423.153 Public Health CENTERS FOR MEDICARE...

  9. 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,…

  10. 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...

  11. 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

  12. 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…

  13. 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

  14. 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)

  15. 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

  16. 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...

  17. 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

  18. [Quality assurance program for pain management after obstetrical perineal injury].

    Science.gov (United States)

    Urion, L; Bayoumeu, F; Jandard, C; Fontaine, B; Bouaziz, H

    2004-11-01

    A quality insurance program has been set up in order to improve the relief of pain in patients with perineal injury after childbirth. The program has been developed according to the French standards of accreditation. After elaboration of a referential, a first study (103 patients) allowed to evaluate the ongoing practices and to appreciate the pain intensities. After analysis of the results, an action strategy has been elaborated, with a brand new therapeutic standard and a pain-monitoring program for nurses. Six months later, a second study (105 patients) measured the efficiency of the accomplished actions. The statistic analysis used chi2 and Kruskal-Wallis tests and a multivariate analyse (p NSAI, decrease of the analgesics requests, improvement of the satisfaction referred to the relief of pain. The multivariate analyse showed a risk twice as little as in the second study to have a 36th hour VAS score superior to four (p =0.03). The apply of this quality insurance program allowed to improve the analgesia after obstetric perineal injuries. A few adaptations are needed, and also more formations of the medical and paramedical staff. The durability of the accomplished actions shall be evaluated in the future.

  19. 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.

  20. DWPF Sample Vial Insert Study-Statistical Analysis of DWPF Mock-Up Test Data

    International Nuclear Information System (INIS)

    Harris, S.P.

    1997-01-01

    This report is prepared as part of Technical/QA Task Plan WSRC-RP-97-351 which was issued in response to Technical Task Request HLW/DWPF/TTR-970132 submitted by DWPF. Presented in this report is a statistical analysis of DWPF Mock-up test data for evaluation of two new analytical methods which use insert samples from the existing HydragardTM sampler. The first is a new hydrofluoric acid based method called the Cold Chemical Method (Cold Chem) and the second is a modified fusion method.Both new methods use the existing HydragardTM sampler to collect a smaller insert sample from the process sampling system. The insert testing methodology applies to the DWPF Slurry Mix Evaporator (SME) and the Melter Feed Tank (MFT) samples. Samples in small 3 ml containers (Inserts) are analyzed by either the cold chemical method or a modified fusion method. The current analytical method uses a HydragardTM sample station to obtain nearly full 15 ml peanut vials. The samples are prepared by a multi-step process for Inductively Coupled Plasma (ICP) analysis by drying, vitrification, grinding and finally dissolution by either mixed acid or fusion. In contrast, the insert sample is placed directly in the dissolution vessel, thus eliminating the drying, vitrification and grinding operations for the Cold chem method. Although the modified fusion still requires drying and calcine conversion, the process is rapid due to the decreased sample size and that no vitrification step is required.A slurry feed simulant material was acquired from the TNX pilot facility from the test run designated as PX-7.The Mock-up test data were gathered on the basis of a statistical design presented in SRT-SCS-97004 (Rev. 0). Simulant PX-7 samples were taken in the DWPF Analytical Cell Mock-up Facility using 3 ml inserts and 15 ml peanut vials. A number of the insert samples were analyzed by Cold Chem and compared with full peanut vial samples analyzed by the current methods. The remaining inserts were analyzed by

  1. Quality assurance consideration for cement-based grout technology programs at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    McDaniel, E.W.; Tallent, O.K.; Sams, T.L.; Delzer, D.B.

    1987-01-01

    Oak Ridge National Laboratory has developed and is continuing to refine a method of immobilizing low-level radioactive liquid wastes by mixing them with cementitious dry-solid blends. A quality assurance program is vital to the project because Nuclear Regulatory Commission (NRC), Environmental Protection Agency (EPA) and state environmental regulations must be demonstrably met (the work must be defensible in a court of law). The end result of quality assurance (QA) is, by definition, a product of demonstrable quality. In the laboratory, this entails traceability, repeatability, and credibility. This paper describes the application of QA in grout technology development at Oak Ridge National Laboratory

  2. 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

  3. 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.)

  4. Task technical plan: DWPF air permit/dispersion modeling

    International Nuclear Information System (INIS)

    Lambert, D.P.

    1993-01-01

    This Task Technical Plan summarizes work required to project the benzene emissions from the Late Wash Facility (LWF) as well as update the benzene, mercury, and NO x emissions from the remainder of the Defense Waste Processing Facility (DWPF). These calculations will reflect (1) the addition of the LWF and (2) the replacement of formic acid with nitric acid in the melter preparation process. The completed calculations will be used to assist DWPF in applying for the LWF Air Quality Permit

  5. Chemical compatibility of DWPF canistered waste forms

    International Nuclear Information System (INIS)

    Harbour, J.R.

    1993-01-01

    The Waste Acceptance Preliminary Specifications (WAPS) require that the contents of the canistered waste form are compatible with one another and the stainless steel canister. The canistered waste form is a closed system comprised of a stainless steel vessel containing waste glass, air, and condensate. This system will experience a radiation field and an elevated temperature due to radionuclide decay. This report discusses possible chemical reactions, radiation interactions, and corrosive reactions within this system both under normal storage conditions and after exposure to temperatures up to the normal glass transition temperature, which for DWPF waste glass will be between 440 and 460 degrees C. Specific conclusions regarding reactions and corrosion are provided. This document is based on the assumption that the period of interim storage prior to packaging at the federal repository may be as long as 50 years

  6. Parametric testing of a DWPF glass

    International Nuclear Information System (INIS)

    Bazan, F.; Rego, J.

    1985-03-01

    A series of tests has been performed to characterize the chemical stability of a DWPF borosilicate glass sample as part of the Waste Package Task of the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. This material was prepared at the Savannah River Laboratory for the purpose of testing the 165-frit matrix doped with a simulated nonradioactive waste. All tests were conducted at 90 0 C using deionized water and J-13 water (a tuffaceous formation ground water). In the deionized water tests, both monoliths and crushed glass were tested at various ratios of surface area of the sample to volume of water in order to compare leach rates for different sample geometries or leaching times. Effects on the leach rates as a result of the presence of crushed tuff and stainless steel material were also investigated in the tests with J-13 water. 3 refs., 12 figs., 7 tabs

  7. Statistical analysis of the DWPF prototypic sampler

    International Nuclear Information System (INIS)

    Postles, R.L.; Reeve, C.P.; Jenkins, W.J.; Bickford, D.F.

    1991-01-01

    The DWPF process will be controlled using assay measurements on samples of feed slurry. These slurries are radioactive, and thus will be sampled remotely. A Hydraguard trademark pump-driven sampler system will be used as the remote sampling device. A prototype Hydraguard trademark sampler has been studied in a full-scale mock-up of a DWPF process vessel. Two issues were of dominant interest: (1) what accuracy and precision can be provided by such a pump-driven sampler in the face of the slurry rheology; and, if the Hydraguard trademark sample accurately represents the slurry in its local area, (2) is the slurry homogeneous enough throughout for it to represent the entire vessel? To determine Hydraguard trademark Accuracy, a Grab Sampler of simpler mechanism was used as reference. This (Low) Grab Sampler was located as near to the intake port of the Hydraguard trademark as could be arranged. To determine Homogeneity, a second (High) Grab Sampler was located above the first. The data necessary to these determinations comes from the measurement system, so its important variables also affect the results. Thus, the design of the test involved not just Sampling variables, but also some of the Measurement variables as well. However, the main concern was the Sampler and not the Measurement System, so the test design included only such measurement variables as could not be circumvented (Vials, Dissolution Method, and Aliquoting). The test was executed by, or under the direct oversight of, expert technologists. It thus did not explore the many important particulars of ''routine'' plant operations (such as Remote Sample Preparation or Laboratory Shift Operation)

  8. 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

  9. QA [Quality Assurance] role in advanced energy activities: Towards an /open quotes/orthodox/close quotes/ Quality Program: Canonizing the traditions at Fermilab

    International Nuclear Information System (INIS)

    Bodnarczuk, M.W.

    1988-02-01

    After a brief description of the goal of Fermi National Accelerator Laboratory (Fermilab) this paper poses and answers three questions related to Quality Assurance (QA) at the Laboratory. First, what is the difference between 'orthodox' and 'unorthodox' QA and is there a place for 'orthodox' QA at a laboratory like Fermilab? Second, are the deeper philosophical and cultural frameworks of high-energy physics acommodating or antagonistic to an 'orthodox' QA Program? Finally, faced with the task of developing an institutional QA program for Fermilab where does one begin? The paper is based on experience with the on-going development and implementation of an institutional QA Program at Fermilab. 10 refs

  10. 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)

  11. 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

  12. 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.

  13. 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)

  14. Intercomparison programs - a tool for the implementation of a quality assurance program in bioassay

    International Nuclear Information System (INIS)

    Mesquita, Sueli A. de; Sousa, Wanderson O.; Juliao, Ligia M.Q.C.; Santos, Maristela S.; Fernandes, Paulo C.P.

    2009-01-01

    In vitro bioassay laboratories need to have means to demonstrate that they are technically competent, operate an effective quality system, and are able to generate technically valid calibration and test results. The reliability of the results of measurements has a high influence on the reliability of the dose assessment. Inter-laboratory tests are one of the tools for assessing the analytical consistency of in vitro bioassay laboratories. The intercomparison exercises provide an opportunity to compare radiochemistry techniques for in vitro analysis of biological samples. The in vitro Laboratory of the Instituto de Radioprotecao e Dosimetria has therefore participated in the intercomparison exercises sponsored by PROCORAD, ARCAL and IAEA since 1998. The intercomparison exercises comprise measurements of gamma and beta emitters in urine samples and alpha emitters in urine and faecal samples. This paper presents the performance of the IRD in vitro bioassay laboratory in the past intercomparisons. The results demonstrate that in vitro laboratory is able to generate technically valid results, which also guarantee the support for a quality assurance program and accreditation by competent organism in Brazil. (author)

  15. The application of quality assurance

    International Nuclear Information System (INIS)

    Lovatt, G.B.

    1988-01-01

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

  16. 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

  17. 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

  18. 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

  19. QUALITY ASSURANCE IN SECONDARY EDUCATION PROGRAME OF BANGLADESH OPEN UNIVERSITY: Present Status and Challenges

    Directory of Open Access Journals (Sweden)

    Zobaida AKHTER

    2008-04-01

    Full Text Available In the present day in national and international perspectives, quality is the top of most agendas. Quality of education has significant impact and invaluable contribution to the area of development. Recently, the SSC & HSC program of BOU have earned recognition of equivalency with the formal education sector, which has naturally raised the question of quality assurance of these programs By applying the quantitative method, the study has assessed the present status of the quality of SSC & HSC program of BOU and also put some recommendations to meet the challenges for further development.

  20. 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.

  1. 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

  2. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

    Energy Technology Data Exchange (ETDEWEB)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

    2008-11-10

    Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R

  3. 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...

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

    International Nuclear Information System (INIS)

    Rasmussen, T.L.

    1989-01-01

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

  5. 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

  6. 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)

  7. 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.

  8. 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)

  9. 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

  10. 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...

  11. 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

  12. 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.

  13. RECENT PROCESS IMPROVEMENTS TO INCREASE HLW THROUGHPUT AT THE DWPF

    International Nuclear Information System (INIS)

    Herman, C

    2007-01-01

    The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF), the world's largest operating high level waste (HLW) vitrification plant, began stabilizing about 35 million gallons of SRS liquid radioactive waste by-product in 1996. The DWPF has since filled over 2000 canisters with about 4000 pounds of radioactive glass in each canister. In the past few years there have been several process and equipment improvements at the DWPF to increase the rate at which the waste can be stabilized. These improvements have either directly increased waste processing rates or have desensitized the process and therefore minimized process upsets and thus downtime. These improvements, which include glass former optimization, increased waste loading of the glass, the melter heated bellows liner, and glass surge protection software, will be discussed in this paper

  14. Evaluation of vitrification factors from DWPF's macro-batch 1

    International Nuclear Information System (INIS)

    Edwards, T.B.

    2000-01-01

    The Defense Waste Processing Facility (DWPF) is evaluating new sampling and analytical methods that may be used to support future Slurry Mix Evaporator (SME) batch acceptability decisions. This report uses data acquired during DWPF's processing of macro-batch 1 to determine a set of vitrification factors covering several SME and Melter Feed Tank (MFT) batches. Such values are needed for converting the cation measurements derived from the new methods to a ''glass'' basis. The available data from macro-batch 1 were used to examine the stability of these vitrification factors, to estimate their uncertainty over the course of a macro-batch, and to provide a recommendation on the use of a single factor for an entire macro-batch. The report is in response to Technical Task Request HLW/DWPF/TTR-980015

  15. Pilot program to assess proposed basic quality assurance requirements in the medical use of byproduct materials

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, E.; Nelson, K.; Meinhold, C.B. (Brookhaven National Lab., Upton, NY (United States))

    1991-10-01

    In January 1990, the Nuclear Regulatory Commission (NRC) proposed amendments to 10 CFR Part 35 that would require medical licensees using byproduct material to establish and implement a basic quality assurance program. A 60-day real-world trial of the proposed rules was initiated to obtain information beyond that generally found through standard public comment procedures. Volunteers from randomly selected institutions had opportunities to review the details of the proposed regulations and to implement these rules on a daily basis during the trial. The participating institutions were then asked to evaluate the proposed regulations based on their personal experiences. The pilot project sought to determine whether medical institutions could develop written quality assurance programs that would meet the eight performance-based objectives of proposed Section 35.35. In addition, the NRC wanted to learn from these volunteers if they had any recommendations on how the rule could be revised to minimized its cost and to clarify its objectives without decreasing its effectiveness. It was found that licensees could develop acceptable QA programs under a performance-based approach, that most licensee programs did meet the proposed objectives, and that most written QA plans would require consultations with NRC or Agreement State personnel before they would fully meet all objectives of proposed Section 35.35. This report describes the overall pilot program. The methodology used to select and assemble the group of participating licensees is presented. The various workshops and evaluation questionnaires are discussed, and detailed findings are presented. 7 refs.

  16. Quality assurance records system for research and development activities in support of geologic repository programs

    International Nuclear Information System (INIS)

    Smith, J.W.; Ryder, D.E.

    1987-01-01

    The Pacific Northwest Laboratory (PNL), which is operated by Battelle Memorial Institute for the Department of Energy, is conducting site-specific research for all three candidate sites for the first geologic high-level waste repository, as well as generic research for the second repository. In conjunction with this effort, PNL has developed a quality assurance (QA) program that is applicable to all organizations that are performing research and development (R and D) activities in support of the repository programs. This QA program meets the basic and supplemental requirements of ANSI/ASME NQA-1-1983 and the Nuclear Regulatory Commission (NRC) Review Plan for QA Programs for Site Characterization of High Level Nuclear Waste Repositories. A key part of this program is the handling of QA records that may ultimately support the licensing process for the repository. This paper describes a QA records system that is flexible enough to accommodate several types of research, such as paper studies, test method development, site characterization studies, software development, and hardware design. In addition, the QA records system is acceptable to a variety of sponsors who have licensing concerns. The QA procedures and their relation to the requirements are described. Most important is the discussion on the approaches used to assure that the records are organized such that the user can readily recreate or defend data, conclusions, and recommendations resulting from the research

  17. Pilot program to assess proposed basic quality assurance requirements in the medical use of byproduct materials

    International Nuclear Information System (INIS)

    Kaplan, E.; Nelson, K.; Meinhold, C.B.

    1991-10-01

    In January 1990, the Nuclear Regulatory Commission (NRC) proposed amendments to 10 CFR Part 35 that would require medical licensees using byproduct material to establish and implement a basic quality assurance program. A 60-day real-world trial of the proposed rules was initiated to obtain information beyond that generally found through standard public comment procedures. Volunteers from randomly selected institutions had opportunities to review the details of the proposed regulations and to implement these rules on a daily basis during the trial. The participating institutions were then asked to evaluate the proposed regulations based on their personal experiences. The pilot project sought to determine whether medical institutions could develop written quality assurance programs that would meet the eight performance-based objectives of proposed Section 35.35. In addition, the NRC wanted to learn from these volunteers if they had any recommendations on how the rule could be revised to minimized its cost and to clarify its objectives without decreasing its effectiveness. It was found that licensees could develop acceptable QA programs under a performance-based approach, that most licensee programs did meet the proposed objectives, and that most written QA plans would require consultations with NRC or Agreement State personnel before they would fully meet all objectives of proposed Section 35.35. This report describes the overall pilot program. The methodology used to select and assemble the group of participating licensees is presented. The various workshops and evaluation questionnaires are discussed, and detailed findings are presented. 7 refs

  18. SME Acceptability Determination For DWPF Process Control (U)

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-12

    The statistical system described in this document is called the Product Composition Control System (PCCS). K. G. Brown and R. L. Postles were the originators and developers of this system as well as the authors of the first three versions of this technical basis document for PCCS. PCCS has guided acceptability decisions for the processing at the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) since the start of radioactive operations in 1996. The author of this revision to the document gratefully acknowledges the firm technical foundation that Brown and Postles established to support the ongoing successful operation at the DWPF. Their integration of the glass propertycomposition models, developed under the direction of C. M. Jantzen, into a coherent and robust control system, has served the DWPF well over the last 20+ years, even as new challenges, such as the introduction into the DWPF flowsheet of auxiliary streams from the Actinide Removal Process (ARP) and other processes, were met. The purpose of this revision is to provide a technical basis for modifications to PCCS required to support the introduction of waste streams from the Salt Waste Processing Facility (SWPF) into the DWPF flowsheet. An expanded glass composition region is anticipated by the introduction of waste streams from SWPF, and property-composition studies of that glass region have been conducted. Jantzen, once again, directed the development of glass property-composition models applicable for this expanded composition region. The author gratefully acknowledges the technical contributions of C.M. Jantzen leading to the development of these glass property-composition models. The integration of these models into the PCCS constraints necessary to administer future acceptability decisions for the processing at DWPF is provided by this sixth revision of this document.

  19. An update on the quality assurance for the waste vitrification plants

    Energy Technology Data Exchange (ETDEWEB)

    Caplinger, W.H.; Shugars, D.L.; Carlson, M.K.

    1990-01-01

    Immobilization of high-level defense production wastes is an important step in environmental restoration. The best available technology for immobilization of this waste currently is by incorporation into borosilicate glass, i.e., vitrification. Three US sites are active in the design, construction, or operation of vitrification facilities. The status, facility description and Quality Assurance (QA) development for each facility was presented at the 1989 Energy Division Conference. This paper presents the developments since that time. The West Valley Demonstration Project (WVDP) in northwestern New York State has demonstrated the technology. At the Savannah River Site (SRS) in South Carolina the Defense Waste Processing Facility (DWPF) has completed design, construction is essentially complete, and preparation for operation is underway. The Hanford Waste Vitrification Plant (HWVP) in Washington State is in initial Detailed Design. 4 refs.

  20. An update on the quality assurance for the waste vitrification plants

    International Nuclear Information System (INIS)

    Caplinger, W.H.; Shugars, D.L.; Carlson, M.K.

    1990-01-01

    Immobilization of high-level defense production wastes is an important step in environmental restoration. The best available technology for immobilization of this waste currently is by incorporation into borosilicate glass, i.e., vitrification. Three US sites are active in the design, construction, or operation of vitrification facilities. The status, facility description and Quality Assurance (QA) development for each facility was presented at the 1989 Energy Division Conference. This paper presents the developments since that time. The West Valley Demonstration Project (WVDP) in northwestern New York State has demonstrated the technology. At the Savannah River Site (SRS) in South Carolina the Defense Waste Processing Facility (DWPF) has completed design, construction is essentially complete, and preparation for operation is underway. The Hanford Waste Vitrification Plant (HWVP) in Washington State is in initial Detailed Design. 4 refs

  1. 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

  2. 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

  3. Rheological Characterization of Unusual DWPF Slurry Samples

    International Nuclear Information System (INIS)

    Koopman, D. C.

    2005-01-01

    A study was undertaken to identify and clarify examples of unusual rheological behavior in Defense Waste Processing Facility (DWPF) simulant slurry samples. Identification was accomplished by reviewing sludge, Sludge Receipt and Adjustment Tank (SRAT) product, and Slurry Mix Evaporator (SME) product simulant rheological results from the prior year. Clarification of unusual rheological behavior was achieved by developing and implementing new measurement techniques. Development of these new methods is covered in a separate report, WSRC-TR-2004-00334. This report includes a review of recent literature on unusual rheological behavior, followed by a summary of the rheological measurement results obtained on a set of unusual simulant samples. Shifts in rheological behavior of slurries as the wt. % total solids changed have been observed in numerous systems. The main finding of the experimental work was that the various unusual DWPF simulant slurry samples exhibit some degree of time dependent behavior. When a given shear rate is applied to a sample, the apparent viscosity of the slurry changes with time rather than remaining constant. These unusual simulant samples are more rheologically complex than Newtonian liquids or more simple slurries, neither of which shows significant time dependence. The study concludes that the unusual rheological behavior that has been observed is being caused by time dependent rheological properties in the slurries being measured. Most of the changes are due to the effect of time under shear, but SB3 SME products were also changing properties while stored in sample bottles. The most likely source of this shear-related time dependence for sludge is in the simulant preparation. More than a single source of time dependence was inferred for the simulant SME product slurries based on the range of phenomena observed. Rheological property changes were observed on the time-scale of a single measurement (minutes) as well as on a time scale of hours

  4. 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.

  5. Norwegian program of quality assurance in radiotherapy (KVIST) - Organisation, benefits and experience feedback

    International Nuclear Information System (INIS)

    Merete Olerud, H.; Levernes, S.; Hellebust, T.P.; Heikkela, I.E.; Bjerke, H.; Sundqvist, E.; Frykholm, G.

    2009-01-01

    In 2000, the Norwegian Radiation Protection Authority (N.R.P.A.) initiated work to develop a national quality assurance programme in radiotherapy. The program was named K.V.I.S.T.: i.e. Norwegian abbreviation of Quality Assurance in Radiotherapy (KValitetSikring STraleterapi). The programme is performed by the multidisciplinary K.V.I.S.T. Group and aims to stimulate collaboration by focussing on clinical, technical and administrative problems that can be addressed and solved on a national level. An important objective is to establish a positive attitude towards quality assurance and better communication between centres and the various professions and professionals involved in radiotherapy, i.e. the oncologists, medical physicists and radiation therapy technologists. Information is also provided to other stake holders such as health authorities, hospital administrators and patients. In 2007 radiotherapy in Norway represent 10 departments and forty accelerators. Since radiotherapy is given high priority in cancer care good quality assurance is required. The member of the K.V.I.S.T.-group are part time at N.R.P.A. and part time in different radiotherapy departments. Professionals with competencies within radiotherapy (R.T.) have permanent positions in a national public entity. The K.V.I.S.T.-group is multidisciplinary. The K.V.I.S.T.-group acts as a coordinating group for all type of national Q.A. projects. The recommendations/guidelines are developed by national consensus. The work is performed by the radiotherapy community it self, thus creating an atmosphere of ownership. (N.C.)

  6. N Reactor Production Assurance Program blance of plant evaluation: report of findings and conclusions

    International Nuclear Information System (INIS)

    Hurd, E.N.; Bitten, E.J.

    1985-03-01

    Fourteen tasks were identified by UNC Nuclear Industries for evaluating the life expectancy of N Reactor structures, systems and components in the Balance of Plant portion of the Production Assurance Program. A Westinghouse Hanford Company (WHC) evaluation team was assigned to each of these fourteen tasks. A uniform set of criteria was used by all teams in evaluating the problems that may be encountered during the extended plant operating lifetime. The overall conclusion is that extended life to those Balance of Plant components and systems studied can be achieved. Problems with the potential for compromising that conclusion are identified, and feasible solutions are provided

  7. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Quality Assurance Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; R. Nims; K. J. Kvarfordt; C. Wharton

    2008-08-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment using a personal computer running the Microsoft Windows operating system. SAPHIRE is primarily funded by the U.S. Nuclear Regulatory Commission (NRC). The role of the INL in this project is that of software developer and tester. This development takes place using formal software development procedures and is subject to quality assurance (QA) processes. The purpose of this document is to describe how the SAPHIRE software QA is performed for Version 6 and 7, what constitutes its parts, and limitations of those processes.

  8. 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

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. [Standardization in laboratory hematology by participating in external quality assurance programs].

    Science.gov (United States)

    Nazor, Aida; Siftar, Zoran; Flegar-Mestrić, Zlata

    2011-09-01

    Since 1985, Department of Clinical Chemistry and Laboratory Medicine, Merkur University Hospital, Zagreb, has been participating in the International External Quality Assessment Scheme for Hematology (IEQAS-H) organized by the World Health Organization (WHO). Owing to very good results, in 1987 the Department received a certificate of participation in this control scheme. Department has been cooperating in the external quality assessment program in laboratory hematology which has been continuously performed in Croatia since 1986 by the Committee for External Quality Assessment Schemes under the auspices of the Croatian Society of Medical Biochemists and School of Pharmacy and Biochemistry, University of Zagreb. Nowadays, 186 medical biochemical laboratories are included in the National External Quality Assessment program, which is performed three times per year. Our Department has participated in the international projects of the European Committee for External Quality Assurance Programs in Laboratory Medicine (EQALM).

  14. Development and status of data quality assurance program at NASA Langley research center: Toward national standards

    Science.gov (United States)

    Hemsch, Michael J.

    1996-01-01

    As part of a continuing effort to re-engineer the wind tunnel testing process, a comprehensive data quality assurance program is being established at NASA Langley Research Center (LaRC). The ultimate goal of the program is routing provision of tunnel-to-tunnel reproducibility with total uncertainty levels acceptable for test and evaluation of civilian transports. The operational elements for reaching such levels of reproducibility are: (1) statistical control, which provides long term measurement uncertainty predictability and a base for continuous improvement, (2) measurement uncertainty prediction, which provides test designs that can meet data quality expectations with the system's predictable variation, and (3) national standards, which provide a means for resolving tunnel-to-tunnel differences. The paper presents the LaRC design for the program and discusses the process of implementation.

  15. 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

  16. Estimation of Total Error in DWPF Reported Radionuclide Inventories

    International Nuclear Information System (INIS)

    Edwards, T.B.

    1995-01-01

    This report investigates the impact of random errors due to measurement and sampling on the reported concentrations of radionuclides in DWPF's filled canister inventory resulting from each macro-batch. The objective of this investigation is to estimate the variance of the total error in reporting these radionuclide concentrations

  17. DWPF PCCS version 2.0 test case

    International Nuclear Information System (INIS)

    Brown, K.G.; Pickett, M.A.

    1992-01-01

    To verify the operation of the Product Composition Control System (PCCS), a test case specific to DWPF operation was developed. The values and parameters necessary to demonstrate proper DWPF product composition control have been determined and are presented in this paper. If this control information (i.e., for transfers and analyses) is entered into the PCCS as illustrated in this paper, and the results obtained correspond to the independently-generated results, it can safely be said that the PCCS is operating correctly and can thus be used to control the DWPF. The independent results for this test case will be generated and enumerated in a future report. This test case was constructed along the lines of the normal DWPF operation. Many essential parameters are internal to the PCCS (e.g., property constraint and variance information) and can only be manipulated by personnel knowledgeable of the Symbolics reg-sign hardware and software. The validity of these parameters will rely on induction from observed PCCS results. Key process control values are entered into the PCCS as they would during normal operation. Examples of the screens used to input specific process control information are provided. These inputs should be entered into the PCCS database, and the results generated should be checked against the independent, computed results to confirm the validity of the PCCS

  18. Remotely replaceable jumpers and embedded wiring for the DWPF

    International Nuclear Information System (INIS)

    Heckendorn, F.M. II.

    1984-01-01

    The Defense Waste Processing Facility (DWPF) for radioactive waste vitrification at the Savannah River Plant (SRP) is now under construction. Development of specialized electrical/instrument inter-connectors, or jumpers, is now complete. Remote replacement of the associated through-wall wiring using a standard canyon crane has also been demonstrated. 8 figures

  19. KAFEPA-II program users' manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-04-01

    KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

  20. 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.

  1. 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.

  2. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  3. Glass formulation requirements for DWPF coupled operations using crystalline silicotitanates

    International Nuclear Information System (INIS)

    Harbour, J.R.; Andrews, M.K.

    1997-01-01

    The design basis DWPF flowsheet couples the vitrification of two waste streams: (1) a washed sludge and (2) a hydrolyzed sodium tetraphenylborate precipitate product, PHA. The PHA contains cesium-137 which had been precipitated from the tank supernate with sodium tetraphenylborate. Smaller amounts of strontium and plutonium adsorbed on sodium titanate are also present with the PHA feed. Currently, DWPF is running a sludge-only flowsheet while working towards solutions to the problems encountered with In Tank Precipitation (ITP). The sludge loading for the sludge-only flowsheet and for the anticipated coupled operations is 28 wt% on an oxide basis. For the coupled operation, it is essential to balance the treatment of the two waste streams such that no supernate remains after immobilization of all the sludge. An alternative to ITP and sodium titanate is the removal of Cs-137, Sr-90, and plutonium from the tank supernate by ion exchange using crystalline silicotitanate (CST). This material has been shown to effectively sorb these elements from the supernate. It is also known that CST sorbs plutonium. The loaded CST could then be immobilized with the sludge during vitrification. It has recently been demonstrated that CST loadings approaching 70 wt% for a CST-only glass can be achieved using a borosilicate glass formulation which can be processed by the DWPF melter. Initial efforts on coupled waste streams with simulated DWPF sludge show promise that a borosilicate glass formulation can incorporate both sludge and CST. This paper presents the bases for research efforts to develop a glass formulation which will incorporate sludge and CST at loadings appropriate for DWPF operation

  4. The Jefferson Lab Quality Assurance Program for the SNS Superconducting Linac Construction Project

    International Nuclear Information System (INIS)

    Joseph Ozelis

    2003-01-01

    As part of a multi-laboratory collaboration, Jefferson Lab is currently engaged in the fabrication, assembly, and testing of 23 cryomodules for the superconducting linac portion of the Spallation Neutron Source (SNS) being built at Oak Ridge National Laboratory. As with any large accelerator construction project, it is vitally important that these components be built in a cost effective and timely manner, and that they meet the stringent performance requirements dictated by the project specifications. A comprehensive Quality Assurance (QA) program designed to help accomplish these goals has been implemented as an inherent component of JLab's SNS construction effort. This QA program encompasses the traditional spectrum of component performance, from incoming parts inspection, raw materials testing, through to sub-assembly and finished article performance evaluation

  5. Nutrition Program Quality Assurance through a Formalized Process of On-Site Program Review

    Science.gov (United States)

    Paddock, Joan Doyle; Dollahite, Jamie

    2012-01-01

    A protocol for a systematic onsite review of the Expanded Food and Nutrition Education Program and Supplemental Nutrition Assistance Program-Education was developed to support quality programming and ensure compliance with state guidelines and federal regulations. Onsite review of local nutrition program operations is one strategy to meet this…

  6. 40 CFR 239.4 - Narrative description of state permit program.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Narrative description of state permit program. 239.4 Section 239.4 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID... Narrative description of state permit program. The description of a state's program must include: (a) An...

  7. 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

  8. Quality assurance applied to Radiological Protection Program of CPHR - Centro de Proteccion Y Higiene de las Radiaciones

    International Nuclear Information System (INIS)

    Marrero Garcia, M.; Jova Sed, L.; Domenech Nieves, H.; Hernandez Sainz, A.

    2001-01-01

    The quality assurance in establishment that use ionizing radiation sources, is according to international recommendations of radiation protection programs. This work intends to present the experience of the Centro de Proteccion y Higiene de las Radiaciones (CPHR), in the implementation of requirements of quality in their Radiological Protection Program

  9. Defining And Characterizing Sample Representativeness For DWPF Melter Feed Samples

    International Nuclear Information System (INIS)

    Shine, E. P.; Poirier, M. R.

    2013-01-01

    Representative sampling is important throughout the Defense Waste Processing Facility (DWPF) process, and the demonstrated success of the DWPF process to achieve glass product quality over the past two decades is a direct result of the quality of information obtained from the process. The objective of this report was to present sampling methods that the Savannah River Site (SRS) used to qualify waste being dispositioned at the DWPF. The goal was to emphasize the methodology, not a list of outcomes from those studies. This methodology includes proven methods for taking representative samples, the use of controlled analytical methods, and data interpretation and reporting that considers the uncertainty of all error sources. Numerous sampling studies were conducted during the development of the DWPF process and still continue to be performed in order to evaluate options for process improvement. Study designs were based on use of statistical tools applicable to the determination of uncertainties associated with the data needs. Successful designs are apt to be repeated, so this report chose only to include prototypic case studies that typify the characteristics of frequently used designs. Case studies have been presented for studying in-tank homogeneity, evaluating the suitability of sampler systems, determining factors that affect mixing and sampling, comparing the final waste glass product chemical composition and durability to that of the glass pour stream sample and other samples from process vessels, and assessing the uniformity of the chemical composition in the waste glass product. Many of these studies efficiently addressed more than one of these areas of concern associated with demonstrating sample representativeness and provide examples of statistical tools in use for DWPF. The time when many of these designs were implemented was in an age when the sampling ideas of Pierre Gy were not as widespread as they are today. Nonetheless, the engineers and

  10. Defining And Characterizing Sample Representativeness For DWPF Melter Feed Samples

    Energy Technology Data Exchange (ETDEWEB)

    Shine, E. P.; Poirier, M. R.

    2013-10-29

    Representative sampling is important throughout the Defense Waste Processing Facility (DWPF) process, and the demonstrated success of the DWPF process to achieve glass product quality over the past two decades is a direct result of the quality of information obtained from the process. The objective of this report was to present sampling methods that the Savannah River Site (SRS) used to qualify waste being dispositioned at the DWPF. The goal was to emphasize the methodology, not a list of outcomes from those studies. This methodology includes proven methods for taking representative samples, the use of controlled analytical methods, and data interpretation and reporting that considers the uncertainty of all error sources. Numerous sampling studies were conducted during the development of the DWPF process and still continue to be performed in order to evaluate options for process improvement. Study designs were based on use of statistical tools applicable to the determination of uncertainties associated with the data needs. Successful designs are apt to be repeated, so this report chose only to include prototypic case studies that typify the characteristics of frequently used designs. Case studies have been presented for studying in-tank homogeneity, evaluating the suitability of sampler systems, determining factors that affect mixing and sampling, comparing the final waste glass product chemical composition and durability to that of the glass pour stream sample and other samples from process vessels, and assessing the uniformity of the chemical composition in the waste glass product. Many of these studies efficiently addressed more than one of these areas of concern associated with demonstrating sample representativeness and provide examples of statistical tools in use for DWPF. The time when many of these designs were implemented was in an age when the sampling ideas of Pierre Gy were not as widespread as they are today. Nonetheless, the engineers and

  11. Quality assurance program for environmental assessment of Savannah River Plant waste sites: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; King, C.M.; Stephenson, D.E.

    1987-03-01

    Forty-eight locations were identified that received a variety of radioactive and nonradioactive constituents during the past 35 years including surface impoundments and shallow land burial facilities. Detailed environmental assessments of existing waste disposal areas, as well as new waste disposal techniques and disposition of tritiated water, were completed to air in an evaluation of the low level, mixed and hazardous waste management activities. These assessments result in estimation of risk, or residual risk, posed by each disposal area to various receptors as a function of waste management alternative. For example, at existing waste sites, the closure actions evaluated were waste removal and closure, no waste removal and closure, and no action; several pathways/receptors were considered, including groundwater to river, groundwater to well, atmospheric transport, occupational exposure, direct exposure, and contamination followed by ingestion of crops and meat. Modeling of chemical transport in a variety of media was an integral part of the assessment process. The quality of the models used and the application of these models were assured by an explicit quality assurance program

  12. 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

  13. 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

  14. Corrosion impact of reductant on DWPF and downstream facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mickalonis, J. I. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Imrich, K. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Murphy, T. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Wilderman, J. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-12-01

    Glycolic acid is being evaluated as an alternate reductant in the preparation of high level waste for the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). During processing, the glycolic acid is not completely consumed and small quantities of the glycolate anion are carried forward to other high level waste (HLW) facilities. The impact of the glycolate anion on the corrosion of the materials of construction throughout the waste processing system has not been previously evaluated. A literature review had revealed that corrosion data in glycolate-bearing solution applicable to SRS systems were not available. Therefore, testing was recommended to evaluate the materials of construction of vessels, piping and components within DWPF and downstream facilities. The testing, conducted in non-radioactive simulants, consisted of both accelerated tests (electrochemical and hot-wall) with coupons in laboratory vessels and prototypical tests with coupons immersed in scale-up and mock-up test systems. Eight waste or process streams were identified in which the glycolate anion might impact the performance of the materials of construction. These streams were 70% glycolic acid (DWPF feed vessels and piping), SRAT/SME supernate (Chemical Processing Cell (CPC) vessels and piping), DWPF acidic recycle (DWPF condenser and recycle tanks and piping), basic concentrated recycle (HLW tanks, evaporators, and transfer lines), salt processing (ARP, MCU, and Saltstone tanks and piping), boric acid (MCU separators), and dilute waste (HLW evaporator condensate tanks and transfer line and ETF components). For each stream, high temperature limits and worst-case glycolate concentrations were identified for performing the recommended tests. Test solution chemistries were generally based on analytical results of actual waste samples taken from the various process facilities or of prototypical simulants produced in the laboratory. The materials of construction for most vessels

  15. Water Resources Research Grant Program project descriptions, fiscal year 1987

    Science.gov (United States)

    ,

    1987-01-01

    This report contains information on the 34 new projects funded by the United States Geological Survey 's Water Resources Research Grant Program in fiscal year 1987 and on 3 projects completed during the year. For the new projects, the report gives the grant number, project title, performing organization, principal investigator(s), and a project description that includes: (1) identification of water related problems and problem-solution approach (2) contribution to problem solution, (3) objectives, and (4) approach. The 34 projects include 12 in the area of groundwater quality problems, 12 in the science and technology of water quality management, 1 in climate variability and the hydrologic cycle, 4 in institutional change in water resources management, and 5 in surface water management. For the three completed projects, the report furnishes the grant number; project title; performing organization; principal investor(s); starting data; data of receipt of final report; and an abstract of the final report. Each project description provides the information needed to obtain a copy of the final report. The report contains tables showing: (1) proposals received according to area of research interest, (2) grant awards and funding according to area of research interest, (3) proposals received according to type of submitting organization, and (4) awards and funding according to type of organization. (Author 's abstract)

  16. GLYCOLIC-NITRIC ACID FLOWSHEET DEMONSTRATION OF THE DWPF CHEMICAL PROCESSING CELL WITH MATRIX SIMULANTS AND SUPERNATE

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, D.; Stone, M.; Newell, J.; Best, D.

    2012-05-07

    Savannah River Remediation (SRR) is evaluating changes to its current DWPF flowsheet to improve processing cycle times. This will enable the facility to support higher canister production while maximizing waste loading. Higher throughput is needed in the CPC since the installation of the bubblers into the melter has increased melt rate. Due to the significant maintenance required for the DWPF gas chromatographs (GC) and the potential for production of flammable quantities of hydrogen, reducing or eliminating the amount of formic acid used in the CPC is being developed. Earlier work at Savannah River National Laboratory has shown that replacing formic acid with an 80:20 molar blend of glycolic and formic acids has the potential to remove mercury in the SRAT without any significant catalytic hydrogen generation. This report summarizes the research completed to determine the feasibility of processing without formic acid. In earlier development of the glycolic-formic acid flowsheet, one run (GF8) was completed without formic acid. It is of particular interest that mercury was successfully removed in GF8, no formic acid at 125% stoichiometry. Glycolic acid did not show the ability to reduce mercury to elemental mercury in initial screening studies, which is why previous testing focused on using the formic/glycolic blend. The objective of the testing detailed in this document is to determine the viability of the nitric-glycolic acid flowsheet in processing sludge over a wide compositional range as requested by DWPF. This work was performed under the guidance of Task Technical and Quality Assurance Plan (TT and QAP). The details regarding the simulant preparation and analysis have been documented previously.

  17. GLYCOLIC-NITRIC ACID FLOWSHEET DEMONSTRATION OF THE DWPF CHEMICAL PROCESS CELL WITH SLUDGE AND SUPERNATE SIMULANTS

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, D.; Stone, M.; Newell, J.; Best, D.; Zamecnik, J.

    2012-08-28

    Savannah River Remediation (SRR) is evaluating changes to its current Defense Waste Processing Facility (DWPF) flowsheet to improve processing cycle times. This will enable the facility to support higher canister production while maximizing waste loading. Higher throughput is needed in the Chemical Process Cell (CPC) since the installation of the bubblers into the melter has increased melt rate. Due to the significant maintenance required for the DWPF gas chromatographs (GC) and the potential for production of flammable quantities of hydrogen, reducing or eliminating the amount of formic acid used in the CPC is being developed. Earlier work at Savannah River National Laboratory has shown that replacing formic acid with an 80:20 molar blend of glycolic and formic acids has the potential to remove mercury in the SRAT without any significant catalytic hydrogen generation. This report summarizes the research completed to determine the feasibility of processing without formic acid. In earlier development of the glycolic-formic acid flowsheet, one run (GF8) was completed without formic acid. It is of particular interest that mercury was successfully removed in GF8, no formic acid at 125% stoichiometry. Glycolic acid did not show the ability to reduce mercury to elemental mercury in initial screening studies, which is why previous testing focused on using the formic/glycolic blend. The objective of the testing detailed in this document is to determine the viability of the nitric-glycolic acid flowsheet in processing sludge over a wide compositional range as requested by DWPF. This work was performed under the guidance of Task Technical and Quality Assurance Plan (TT&QAP). The details regarding the simulant preparation and analysis have been documented previously.

  18. 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

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

    Science.gov (United States)

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

    2011-10-01

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

  20. Telemedicine spirometry training and quality assurance program in primary care centers of a public health system.

    Science.gov (United States)

    Marina Malanda, Nuria; López de Santa María, Elena; Gutiérrez, Asunción; Bayón, Juan Carlos; Garcia, Larraitz; Gáldiz, Juan B

    2014-04-01

    Forced spirometry is essential for diagnosing respiratory diseases and is widely used across levels of care. However, several studies have shown that spirometry quality in primary care is not ideal, with risks of misdiagnosis. Our objective was to assess the feasibility and performance of a telemedicine-based training and quality assurance program for forced spirometry in primary care. The two phases included (1) a 9-month pilot study involving 15 centers, in which spirometry tests were assessed by the Basque Office for Health Technology Assessment, and (2) the introduction of the program to all centers in the Public Basque Health Service. Technicians first received 4 h of training, and, subsequently, they sent all tests to the reference laboratory using the program. Quality assessment was performed in accordance with clinical guidelines (A and B, good; C-F, poor). In the first phase, 1,894 spirometry tests were assessed, showing an improvement in quality: acceptable quality tests increased from 57% at the beginning to 78% after 6 months and 83% after 9 months (passessed after the inclusion of 36 additional centers, maintaining the positive trend (61%, 87%, and 84% at the same time points; pquality of spirometry tests improved in all centers. (2) The program provides a tool for transferring data that allows monitoring of its quality and training of technicians who perform the tests. (3) This approach is useful for improving spirometry quality in the routine practice of a public health system.

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

    Directory of Open Access Journals (Sweden)

    Robert J Hilsden

    2011-01-01

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

  2. Quality assurance manual for the Department of Energy laboratory accreditation program for personnel dosimetry systems

    International Nuclear Information System (INIS)

    1987-02-01

    The overall purpose of this document is to establish a uniform approach to quality assurance. This will ensure that uniform, high-quality personnel dosimetry practices are followed by the participating testing laboratories. The document presents guidelines for calibrating and maintaining measurement and test equipment (M and TE), calibrating radiation fields, and subsequently irradiating and handling personnel dosimeters in laboratories involved in the DOE dosimetry systems testing program. Radiation energies for which the test procedures apply are photons with approximately 15 keV to 2 MeV, beta particles above 0.3 MeV, neutrons with approximately 1 keV to 2 MeV. 12 refs., 4 tabs

  3. Audit of the informed consent process as a part of a clinical research quality assurance program.

    Science.gov (United States)

    Lad, Pramod M; Dahl, Rebecca

    2014-06-01

    Audits of the informed consent process are a key element of a clinical research quality assurance program. A systematic approach to such audits has not been described in the literature. In this paper we describe two components of the audit. The first is the audit of the informed consent document to verify adherence with federal regulations. The second component is comprised of the audit of the informed consent conference, with emphasis on a real time review of the appropriate communication of the key elements of the informed consent. Quality measures may include preparation of an informed consent history log, notes to accompany the informed consent, the use of an informed consent feedback tool, and the use of institutional surveys to assess comprehension of the informed consent process.

  4. 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

  5. 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

  6. Clinical pharmacology quality assurance program: models for longitudinal analysis of antiretroviral proficiency testing for international laboratories.

    Science.gov (United States)

    DiFrancesco, Robin; Rosenkranz, Susan L; Taylor, Charlene R; Pande, Poonam G; Siminski, Suzanne M; Jenny, Richard W; Morse, Gene D

    2013-10-01

    Among National Institutes of Health HIV Research Networks conducting multicenter trials, samples from protocols that span several years are analyzed at multiple clinical pharmacology laboratories (CPLs) for multiple antiretrovirals. Drug assay data are, in turn, entered into study-specific data sets that are used for pharmacokinetic analyses, merged to conduct cross-protocol pharmacokinetic analysis, and integrated with pharmacogenomics research to investigate pharmacokinetic-pharmacogenetic associations. The CPLs participate in a semiannual proficiency testing (PT) program implemented by the Clinical Pharmacology Quality Assurance program. Using results from multiple PT rounds, longitudinal analyses of recovery are reflective of accuracy and precision within/across laboratories. The objectives of this longitudinal analysis of PT across multiple CPLs were to develop and test statistical models that longitudinally: (1) assess the precision and accuracy of concentrations reported by individual CPLs and (2) determine factors associated with round-specific and long-term assay accuracy, precision, and bias using a new regression model. A measure of absolute recovery is explored as a simultaneous measure of accuracy and precision. Overall, the analysis outcomes assured 97% accuracy (±20% of the final target concentration of all (21) drug concentration results reported for clinical trial samples by multiple CPLs). Using the Clinical Laboratory Improvement Act acceptance of meeting criteria for ≥2/3 consecutive rounds, all 10 laboratories that participated in 3 or more rounds per analyte maintained Clinical Laboratory Improvement Act proficiency. Significant associations were present between magnitude of error and CPL (Kruskal-Wallis P Kruskal-Wallis P < 0.001).

  7. A quality assurance program for radiotherapy centers in the Republic of Korea

    International Nuclear Information System (INIS)

    Kim, G.Y.; Lee, H.K.; Park, K.J.; Oh, H.J.

    2002-01-01

    Recognizing the importance of quality assurance in radiotherapy and the need to make access to radiation standards traceable to the international measurement system to every radiotherapy center, the KFDA, as a national secondary standard dosimetry laboratory (SSDL), has started a quality assurance program from 1999. This program was initiated by tele-survey to all radiotherapy centers regarding general information about their radiotherapists, medical physicists, type of equipment, dosimeters, etc. This provided the KFDA with a data file and led to links between the KFDA and the clinics. In 1999 a national quality assurance program for ensuring dosimetry accuracy has been performed by on-site dosimetry for 4 60 Co γ ray, 47 high-energy photon beams used in 43 centers. During the audits, the procedure followed by the KFDA was to measure the outputs of the LINAC(6 MV) and Co-60 teletherapy units in terms of absorbed dose to water for fixed dose (2 Gy) in water phantom (only one phantom used in this on-site visit). For all the case, the measurements are carried out in a water phantom according to the IAEA recommended code of practice. The distributions of deviations in total audit are given. The results showed deviations varying between -7.11% and 8.38%. KFDA follow up the large deviated radiotherapy centers. The traceability to SSDL is a major factor of deviation between KFDA measurement dose and clinics quoted dose. The correction for air density (temperature and pressure) is a factor that sometimes introduces errors. Most of the clinics do not calibrate their own barometers and sometimes rely on the air pressure that is quoted during measurements by local metrological offices. In one case, the barometer and thermometer of the clinic were deviating from KFDA instruments by about 10 mmHg and 2, respectively even if the temperature was measured in air. In one case, about 4% of output variation with gantry head angle (horizontal vs. vertical). In the past two years the

  8. Translating DWPF design criteria into an engineered facility design

    International Nuclear Information System (INIS)

    Kemp, J.B.

    1986-01-01

    The Defense Waste Processing Facility (DWPF) takes radioactive defense waste sludge and the radioactive nuclides, cesium and strontium, from the salt solution, and incorporates them in borosilicate glass in stainless steel canisters, for subsequent disposal in a deep geologic repository. The facility was designed by Bechtel National, Inc. under a subcontract from E.I. DuPont de Nemurs and Co., the prime contractor for the Department of Energy, for the design, construction and commissioning of the plant. The design criteria were specified by the DuPont Company, based upon their extensive experience as designer, and operator since the early 1950's, of the existing Savannah River Plant facilities. Some of the design criteria imposed unusual or new requirements on the detailed design of the facilities. This paper describes some of these criteria, encompassing several engineering disciplines, and discusses the solutions and designs which were developed for the DWPF

  9. Program MASTERCALC: an interactive computer program for radioanalytical computations. Description and operating instructions

    International Nuclear Information System (INIS)

    Goode, W.

    1980-10-01

    MASTERCALC is a computer program written to support radioanalytical computations in the Los Alamos Scientific Laboratory (LASL) Environmental Surveillance Group. Included in the program are routines for gross alpha and beta, 3 H, gross gamma, 90 Sr and alpha spectroscopic determinations. A description of MASTERCALC is presented and its source listing is included. Operating instructions and example computing sessions are given for each type of analysis

  10. Copper solubility in DWPF, Batch 1 waste glass: Update report

    International Nuclear Information System (INIS)

    Schumacker, R.F.

    1992-01-01

    The ''Late Washing'' Step in the processing of precipitate will require the use of additional copper formate in the Precipitate Reactor to catalyze the hydrolysis reaction. The increased copper concentration in the melter feed increases the potential for metal precipitation during the vitrification of the melter feed. This report describes recent results with a conservative glass selected from the DWPF acceptable region in the Batch 1 Variability Study

  11. Analysis of the DWPF glass pouring system using neural networks

    International Nuclear Information System (INIS)

    Calloway, T.B. Jr.; Jantzen, C.M.

    1997-01-01

    Neural networks were used to determine the sensitivity of 39 selected Melter/Melter Off Gas and Melter Feed System process parameters as related to the Defense Waste Processing Facility (DWPF) Melter Pour Spout Pressure during the overall analysis and resolution of the DWPF glass production and pouring issues. Two different commercial neural network software packages were used for this analysis. Models were developed and used to determine the critical parameters which accurately describe the DWPF Pour Spout Pressure. The model created using a low-end software package has a root mean square error of ± 0.35 inwc ( 2 = 0.77) with respect to the plant data used to validate and test the model. The model created using a high-end software package has a R 2 = 0.97 with respect to the plant data used to validate and test the model. The models developed for this application identified the key process parameters which contribute to the control of the DWPF Melter Pour Spout pressure during glass pouring operations. The relative contribution and ranking of the selected parameters was determined using the modeling software. Neural network computing software was determined to be a cost-effective software tool for process engineers performing troubleshooting and system performance monitoring activities. In remote high-level waste processing environments, neural network software is especially useful as a replacement for sensors which have failed and are costly to replace. The software can be used to accurately model critical remotely installed plant instrumentation. When the instrumentation fails, the software can be used to provide a soft sensor to replace the actual sensor, thereby decreasing the overall operating cost. Additionally, neural network software tools require very little training and are especially useful in mining or selecting critical variables from the vast amounts of data collected from process computers

  12. 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.

  13. 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

  14. Freeze and restart of the DWPF Scale Glass Melter

    International Nuclear Information System (INIS)

    Choi, A.S.

    1989-01-01

    After over two years of successful demonstration of many design and operating concepts of the DWPF Melter system, the last Scale Glass Melter campaign was initiated on 6/9/88 and consisted of two parts; (1) simulation of noble metal buildup and (2) freeze and subsequent restart of the melter under various scenarios. The objectives were to simulate a prolonged power loss to major heating elements and to examine the characteristics of transient melter operations during a startup with a limited supply of lid heat. Experimental results indicate that in case of a total power loss to the lower electrodes such as due to noble metal deposition, spinel crystals will begin to form in the SRL 165 composite waste glass pool in 24 hours. The total lid heater power required to initiate joule heating was the same as that during slurry-feeding. Results of a radiative heat transfer analysis in the plenum indicate that under the identical operating conditions, the startup capabilities of the SGM and the DWPF Melter are quite similar, despite a greater lid heater to melt surface area ratio in the DWPF Melter

  15. SWiFT Software Quality Assurance Plan.

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-01-01

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

  16. Multicenter Collaborative Quality Assurance Program for the Province of Ontario, Canada: First-Year Results

    International Nuclear Information System (INIS)

    Létourneau, Daniel; McNiven, Andrea; Jaffray, David A.

    2013-01-01

    Purpose: The objective of this work was to develop a collaborative quality assurance (CQA) program to assess the performance of intensity modulated radiation therapy (IMRT) planning and delivery across the province of Ontario, Canada. Methods and Materials: The CQA program was designed to be a comprehensive end-to-end test that can be completed on multiple planning and delivery platforms. The first year of the program included a head-and-neck (H and N) planning exercise and on-site visit to acquire dosimetric measurements to assess planning and delivery performance. A single dosimeter was used at each institution, and the planned to measured dose agreement was evaluated for both the H and N plan and a standard plan (linear-accelerator specific) that was created to enable a direct comparison between centers with similar infrastructure. Results: CQA program feasibility was demonstrated through participation of all 13 radiation therapy centers in the province. Planning and delivery was completed on a variety of infrastructure (treatment planning systems and linear accelerators). The planning exercise was completed using both static gantry and rotational IMRT, and planned-to-delivered dose agreement (pass rates) for 3%/3-mm gamma evaluation were greater than 90% (92.6%-99.6%). Conclusions: All centers had acceptable results, but variation in planned to delivered dose agreement for the same planning and delivery platform was noted. The upper end of the range will provide an achievable target for other centers through continued quality improvement, aided by feedback provided by the program through the use of standard plans and simple test fields

  17. Regulatory research and support program for 1988/89 - project descriptions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-03-15

    Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information.

  18. Regulatory research and support program for 1988/89 - project descriptions

    International Nuclear Information System (INIS)

    1988-01-01

    Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information

  19. Quality assurance

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-06-01

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

  20. Quality assurance

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  1. Implementation of a program of quality assurance of image in an imaging system of flat panel portal

    International Nuclear Information System (INIS)

    Gomez Barrado, A.; Sanchez Jimenez, E.; Benitez, J. A.; Sanchez-Reyes, A.

    2013-01-01

    (IGRT) image-guided radiation therapy is the one in which images are used to locate the area of treatment. Modern irradiation systems are equipped with different modalities for obtaining images, such as flat panel systems, systems conebeam, tomoimagen, etc. This paper describes the start-up and the experience of a quality assurance program based on a flat panel portal Imaging System. (Author)

  2. SoftCopy Display Quality Assurance Program at Texas Children's Hospital.

    Science.gov (United States)

    Ly, Catherine Kim

    2002-01-01

    With growing dependence on picture archiving and communication systems for viewing images, a quality assurance program to monitor the condition of workstation displays has become increasingly important. At present there is no universally accepted program for PACS, but there are groups such as DICOM Working Group 11 of the ACR-NEMA and AAPM Task Group 18 that are working on image quality guidelines for interpretation from soft-copy displays. Texas Children's Hospital (TCH) is developing our own quality assurance program. Data is being collected to determine the appropriate frequency of calibration, the useful life of the displays, appropriate manufacturers, and model-dependent limits on maximum and minimum luminance (black level), symptoms of degradation, and monitor cleanliness. Our system includes a variety of monitors manufactured by Sun, AFP, Siemens, Image Systems, Barco, and Orwin. We are presently collecting data on individual monitor luminance functions but have not yet initiated service calls based on deviation from the DICOM Part 14 Grayscale Display Function (GSDF). The GSDF was intended to produce a grayscale in which driving levels produce changes in luminance that are perceptually equivalent throughout the entire luminance range for a specific test target. Our data is based on measurements of luminance from a digital Society of Motion Picture and Television Engineers (SMPTE) test pattern, which is a standard used by many other institutions. TCH's biomedical engineer measures luminance data each month from the display of the SMPTE pattern and record the results in a spreadsheet. The engineer also makes subjective evaluations of sharpness, geometric distortion, and artifacts. When a monitor's luminance falls outside of arbitrary 10% limits of maximum or minimum luminance, then a service call is placed to the vendor. The luminance check by the biomedical engineer is used to verify both routine and unscheduled calibrations. In addition to the monthly

  3. The AutoBayes Program Synthesis System: System Description

    Science.gov (United States)

    Fischer, Bernd; Pressburger, Thomas; Rosu, Grigore; Schumann, Johann; Norvog, Peter (Technical Monitor)

    2001-01-01

    AUTOBAYES is a fully automatic program synthesis system for the statistical data analysis domain. Its input is a concise description of a data analysis problem in the form of a statistical model; its output is optimized and fully documented C/C++ code which can be linked dynamically into the Matlab and Octave environments. AUTOBAYES synthesizes code by a schema-guided deductive process. Schemas (i.e., code templates with associated semantic constraints) are applied to the original problem and recursively to emerging subproblems. AUTOBAYES complements this approach by symbolic computation to derive closed-form solutions whenever possible. In this paper, we concentrate on the interaction between the symbolic computations and the deductive synthesis process. A statistical model specifies for each problem variable (i.e., data or parameter) its properties and dependencies in the form of a probability distribution, A typical data analysis task is to estimate the best possible parameter values from the given observations or measurements. The following example models normal-distributed data but takes prior information (e.g., from previous experiments) on the data's mean value and variance into account.

  4. Environmental Compliance and Protection Program Description Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Jacobs

    2009-02-26

    The objective of the Environmental Compliance and Protection (EC and P) Program Description (PD) is to establish minimum environmental compliance requirements and natural resources protection goals for the Bechtel Jacobs Company LLC (BJC) Oak Ridge Environmental Management Cleanup Contract (EMCC) Contract Number DE-AC05-98OR22700-M198. This PD establishes the work practices necessary to ensure protection of the environment during the performance of EMCC work activities on the US Department of Energy's (DOE's) Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee, by BJC employees and subcontractor personnel. Both BJC and subcontractor personnel are required to implement this PD. A majority of the decontamination and demolition (D and D) activities and media (e.g., soil and groundwater) remediation response actions at DOE sites on the ORR are conducted under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). CERCLA activities are governed by individual CERCLA decision documents (e.g., Record of Decision [ROD] or Action Memorandum) and according to requirements stated in the Federal Facility Agreement for the Oak Ridge Reservation (DOE 1992). Applicable or relevant and appropriate requirements (ARARs) for the selected remedy are the requirements for environmental remediation responses (e.g., removal actions and remedial actions) conducted under CERCLA.

  5. Implementation of an integral program of quality assurance based on EPID to the IMRT

    International Nuclear Information System (INIS)

    Yannez Ruiz-Labrandera; Emilio; Gonzalez Perez, Y.

    2015-01-01

    We bring forward with this research the implementation of a procedure related to the assurance guaranty in the control of tue quality of IMRT treatment based on the technology of electronic portal images digital (EPID). For the sake of accomplishing quality controls, based in pylic digital images, we used like main tool the System of pylic digital images IviewGT TM with his application software. For the control of positioning of the multi-plates, we implemented a program in MATLAB, which yields the errors of positioning of the plates. For the dosimetric controls, the images obtained for the fields of treatment were climbed with the software ImageJ, and compared with the treatment planning systems (TPS) model Elekta's PrecisePlan ® for it we used the software Verisoft. We managed to implement a comprehensive program of quality control for IMRT. The positioning errors of the multiplates intervening bayouth's test younger errors of positioning under a 1m threw which the requisite is for the IMRT. The rest of the geometric proofs yielded favorable results inmail with them tolerance, same as the test Picket Fence. We verified 2 cases with the technique step and shoot, for it we verified 16 field, where gamma Index varied 85,8 - 98,9. It was checked the possibility to accomplish the quality controls for IMRT using pylic digital images, in our case checked itself himself I apply the Linac Elekta specify on the Ameijeiras. (Author)

  6. The IROC Houston Quality Assurance Program: Potential benefits of 3D dosimetry

    International Nuclear Information System (INIS)

    Followill, D S; Molineu, H A; Lafratta, R; Ibbott, G S

    2017-01-01

    The IROC Houston QA Center has provided QA core support for NCI clinical trials by ensuring that radiation doses delivered to trial patients are accurate and comparable between participating institutions. Within its QA program, IROC Houston uses anthropomorphic QA phantoms to credential sites. It is these phantoms that have the highest potential to benefit from the use of 3D dosimeters. Credentialing is performed to verify that institutions that are using advanced technologies to deliver complex treatment plans that conform to targets. This makes it increasingly difficult to assure the intended calculated dose is being delivered correctly using current techniques that are 2D-based. A 3D dosimeter such as PRESAGE® is able to provide a complete 3D measured dosimetry dataset with one treatment plan delivery. In our preliminary studies, the 3D dosimeters in our H and N and spine phantoms were found to be appropriate for remote dosimetry for relative dose measurements. To implement 3D dosimetry in IROC Houston’s phantoms, the benefit of this significant change to its current infrastructure would have to be assessed and further work would be needed before bringing 3D dosimeters into the phantom dosimetry program. (paper)

  7. A tool to include gamma analysis software into a quality assurance program.

    Science.gov (United States)

    Agnew, Christina E; McGarry, Conor K

    2016-03-01

    To provide a tool to enable gamma analysis software algorithms to be included in a quality assurance (QA) program. Four image sets were created comprising two geometric images to independently test the distance to agreement (DTA) and dose difference (DD) elements of the gamma algorithm, a clinical step and shoot IMRT field and a clinical VMAT arc. The images were analysed using global and local gamma analysis with 2 in-house and 8 commercially available software encompassing 15 software versions. The effect of image resolution on gamma pass rates was also investigated. All but one software accurately calculated the gamma passing rate for the geometric images. Variation in global gamma passing rates of 1% at 3%/3mm and over 2% at 1%/1mm was measured between software and software versions with analysis of appropriately sampled images. This study provides a suite of test images and the gamma pass rates achieved for a selection of commercially available software. This image suite will enable validation of gamma analysis software within a QA program and provide a frame of reference by which to compare results reported in the literature from various manufacturers and software versions. Copyright © 2015. Published by Elsevier Ireland Ltd.

  8. Analysis Of DWPF Sludge Batch 7A (Macrobatch 8) Pour Stream Samples

    International Nuclear Information System (INIS)

    Johnson, F.

    2012-01-01

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7a (SB7a), also referred to as Macrobatch 8 (MB8), in June 2011. SB7a is a blend of the heel of Tank 40 from Sludge Batch 6 (SB6) and the SB7a material that was transferred to Tank 40 from Tank 51. SB7a was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Three pour stream glass samples and two Melter Feed Tank (MFT) slurry samples were collected while processing SB7a. These additional samples were taken during SB7a to understand the impact of antifoam and the melter bubblers on glass redox chemistry. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed. The following conclusions were drawn from the analytical results provided in this report: (1) The sum of oxides for the official SB7a pour stream glass is within the Product Composition Control System (PCCS) limits (95-105 wt%). (2) The average calculated Waste Dilution Factor (WDF) for SB7a is 2.3. In general, the measured radionuclide content of the official SB7a pour stream glass is in good agreement with the calculated values from the Tank 40 dried sludge results from the SB7a Waste Acceptance Program Specification (WAPS) sample. (3) As in previous pour stream samples, ruthenium and rhodium inclusions were detected by Scanning Electron Microscopy-Electron Dispersive Spectroscopy (SEM-EDS) in the official SB7a pour stream sample. (4) The Product Consistency Test (PCT) results indicate that the official SB7a pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.64 g/L, which is an order of magnitude less than the Environmental

  9. 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.)

  10. 24 CFR 92.62 - Review of program description and certifications.

    Science.gov (United States)

    2010-04-01

    ... and Urban Development HOME INVESTMENT PARTNERSHIPS PROGRAM Allocation Formula Insular Areas Program... description unless the insular area has failed to submit information sufficient to allow HUD to make the... projects or activities in its program description. (c) HOME Investment Partnership Agreement. After HUD...

  11. 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

  12. A quality assurance program of simulators in radiotherapy. Pt. 2. Extent and results of long-term quality assurance tests on a therapy simulator

    International Nuclear Information System (INIS)

    Mueller-Sievers, K.; Kober, B.

    1997-01-01

    Background: Since 1990 we follow a quality assurance program with periodical tests of functional performance values of a 16-year-old simulator. Material and Method: For this purpose we adopted and modified German standards for quality assurance on linear accelerators and international standards elaborated for simulators (International Electrotechnical Commission). The tests are subdivided into daily visual checks (light field indication, optical distance indicator, isocentre-indicating devices, indication of gantry and collimator angles) and monthly and annually tests of relevant simulator parameters. Some important examples demonstrate the small variation of parameters over 6 years: Position of the light field centre when rotating the collimator, diameter of the isocentre circle when rotating the gantry, accuracy of the isocentre indication device, and coincidence of light field and simulated radiation field. Results: As an important result we can state, that by these rigid periodic tests it was possible to detect and compensate deteriorations of simulators quality rapidly. Conclusions: Technical improvements and specific calling-in of maintenance personnel whenever felt appropriate provided performance characteristics of our old simulator which are required by international recommendations as a basis for modern radiotherapy. (orig.) [de

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

    International Nuclear Information System (INIS)

    Takada, Susumu

    2006-01-01

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

  14. Efficient quality assurance programs in radiology and nuclear medicine in Oestergoetland (Sweden)

    International Nuclear Information System (INIS)

    Sandborg, M.; Althen, J. N.; Gustafsson, A.

    2010-01-01

    Owners of imaging modalities using ionising radiation should have a documented quality assurance (QA) program, as well as methods to justify new radiological procedures to ensure safe operation and adequate clinical image quality. This includes having a system for correcting divergences, written imaging protocols, assessment of patient and staff absorbed doses and a documented education and training program. In this work, how some aspects on QA have been implemented in the County of Oestergoetland in Sweden, and efforts to standardise and automate the process as an integrated part of the radiology and nuclear medicine QA programs were reviewed. Some key performance parameters have been identified by a Swedish task group of medical physicists to give guidance on selecting relevant QA methods. These include low-contrast resolution, image homogeneity, automatic exposure control, calibration of air kerma-area product metres and patient-dose data registration in the radiological information system, as well as the quality of reading stations and of the transfer of images to the picture archive and communication system. IT-driven methods to automatically assess patient doses and other data on all examinations are being developed and evaluated as well as routines to assess clinical image quality by use of European quality criteria. By assessing both patient absorbed doses and clinical image quality on a routine basis, the medical physicists in our region aim to be able to spend more time on imaging optimisation and less time on periodic testing of the technical performance of the equipment, particularly on aspects that show very few divergences. The role of the Medical Physics Expert is rapidly developing towards a person doing advanced data-analysis and giving scientific support rather than one performing mainly routine periodic measurements. It is concluded that both the European Council directive and the rapid development towards more complex diagnostic imaging systems

  15. Quality assurance of HDR prostate plans: program implementation at a community hospital.

    Science.gov (United States)

    Rush, Jennifer B; Thomas, Michael D

    2005-01-01

    Adenocarcinoma of the prostate is currently the most commonly diagnosed cancer in men in the United States, and the second leading cause of cancer mortality. The utilization of radiation therapy is regarded as the definitive local therapy of choice for intermediate- and high-risk disease, in which there is increased risk for extracapsular extension, seminal vesicle invasion, or regional node involvement. High-dose-rate (HDR) brachytherapy is a logical treatment modality to deliver the boost dose to an external beam radiation therapy (EBRT) treatment to increase local control rates. From a treatment perspective, the utilization of a complicated treatment delivery system, the compressed time frame in which the procedure is performed, and the small number of large dose fractions make the implementation of a comprehensive quality assurance (QA) program imperative. One aspect of this program is the QA of the HDR treatment plan. Review of regulatory and medical physics professional publications shows that substantial general guidance is available. We provide some insight to the implementation of an HDR prostate plan program at a community hospital. One aspect addressed is the utilization of the low-dose-rate (LDR) planning system and the use of existing ultrasound image sets to familiarize the radiation therapy team with respect to acceptable HDR implant geometries. Additionally, the use of the LDR treatment planning system provided a means to prospectively determine the relationship between the treated isodose volume and the product of activity and time for the department's planning protocol prior to the first HDR implant. For the first 12 HDR prostate implants, the root-mean-square (RMS) deviation was 3.05% between the predicted product of activity and time vs. the actual plan values. Retrospective re-evaluation of the actual implant data reduced the RMS deviation to 2.36%.

  16. Quality assurance of HDR prostate plans: Program implementation at a community hospital

    International Nuclear Information System (INIS)

    Rush, Jennifer B.; Thomas, Michael D.

    2005-01-01

    Adenocarcinoma of the prostate is currently the most commonly diagnosed cancer in men in the United States, and the second leading cause of cancer mortality. The utilization of radiation therapy is regarded as the definitive local therapy of choice for intermediate- and high-risk disease, in which there is increased risk for extracapsular extension, seminal vesicle invasion, or regional node involvement. High-dose-rate (HDR) brachytherapy is a logical treatment modality to deliver the boost dose to an external beam radiation therapy (EBRT) treatment to increase local control rates. From a treatment perspective, the utilization of a complicated treatment delivery system, the compressed time frame in which the procedure is performed, and the small number of large dose fractions make the implementation of a comprehensive quality assurance (QA) program imperative. One aspect of this program is the QA of the HDR treatment plan. Review of regulatory and medical physics professional publications shows that substantial general guidance is available. We provide some insight to the implementation of an HDR prostate plan program at a community hospital. One aspect addressed is the utilization of the low-dose-rate (LDR) planning system and the use of existing ultrasound image sets to familiarize the radiation therapy team with respect to acceptable HDR implant geometries. Additionally, the use of the LDR treatment planning system provided a means to prospectively determine the relationship between the treated isodose volume and the product of activity and time for the department's planning protocol prior to the first HDR implant. For the first 12 HDR prostate implants, the root-mean-square (RMS) deviation was 3.05% between the predicted product of activity and time vs. the actual plan values. Retrospective re-evaluation of the actual implant data reduced the RMS deviation to 2.36%

  17. Estimation of total error in DWPF reported radionuclide inventories. Revision 1

    International Nuclear Information System (INIS)

    Edwards, T.B.

    1995-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site is required to determine and report the radionuclide inventory of its glass product. For each macro-batch, the DWPF will report both the total amount (in curies) of each reportable radionuclide and the average concentration (in curies/gram of glass) of each reportable radionuclide. The DWPF is to provide the estimated error of these reported values of its radionuclide inventory as well. The objective of this document is to provide a framework for determining the estimated error in DWPF's reporting of these radionuclide inventories. This report investigates the impact of random errors due to measurement and sampling on the total amount of each reportable radionuclide in a given macro-batch. In addition, the impact of these measurement and sampling errors and process variation are evaluated to determine the uncertainty in the reported average concentrations of radionuclides in DWPF's filled canister inventory resulting from each macro-batch

  18. 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

  19. 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

  20. Construction quality assurance program plan for the WIPP project, Carlsbad, NM

    International Nuclear Information System (INIS)

    1987-05-01

    The purpose of this plan is to describe the Quality Assurance (QA) Program to be established and implemented by the US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Project Office (WPO) and by the Major Project Participants: the Architect-Engineer (Bechtel), the Construction Manager (US Army Corps of Engineers), the Scientific Advisor (Sandia National Laboratory), and the Management and Operating Contractor (Westinghouse Electric Corporation). This plan addresses the construction, including site evaluation, design, and turnover phases of WIPP. Other work in progress during the same period is controlled by DOE documents applicable to that work effort. The prime responsibility for ensuring the quality of construction rests with the DOE WIPP Project Office and is implemented through the combined efforts of the Construction Manager, the Construction Contractors, the Management and Operating Contractor, and the Architect-Engineer. Inspection and burden of proof of acceptability rests with the Construction Contractor as defined by the technical provisions of the contract and as otherwise specified by the DOE WIPP Project Office on an individual work-package basis. To the maximum extent possible, acceptance of work will be based upon first-hand witnessing by the Construction Manager and other representatives of the DOE organization

  1. Computer Program for Calculation of Complex Chemical Equilibrium Compositions and Applications II. Users Manual and Program Description. 2; Users Manual and Program Description

    Science.gov (United States)

    McBride, Bonnie J.; Gordon, Sanford

    1996-01-01

    This users manual is the second part of a two-part report describing the NASA Lewis CEA (Chemical Equilibrium with Applications) program. The program obtains chemical equilibrium compositions of complex mixtures with applications to several types of problems. The topics presented in this manual are: (1) details for preparing input data sets; (2) a description of output tables for various types of problems; (3) the overall modular organization of the program with information on how to make modifications; (4) a description of the function of each subroutine; (5) error messages and their significance; and (6) a number of examples that illustrate various types of problems handled by CEA and that cover many of the options available in both input and output. Seven appendixes give information on the thermodynamic and thermal transport data used in CEA; some information on common variables used in or generated by the equilibrium module; and output tables for 14 example problems. The CEA program was written in ANSI standard FORTRAN 77. CEA should work on any system with sufficient storage. There are about 6300 lines in the source code, which uses about 225 kilobytes of memory. The compiled program takes about 975 kilobytes.

  2. Maximum total organic carbon limit for DWPF melter feed

    International Nuclear Information System (INIS)

    Choi, A.S.

    1995-01-01

    DWPF recently decided to control the potential flammability of melter off-gas by limiting the total carbon content in the melter feed and maintaining adequate conditions for combustion in the melter plenum. With this new strategy, all the LFL analyzers and associated interlocks and alarms were removed from both the primary and backup melter off-gas systems. Subsequently, D. Iverson of DWPF- T ampersand E requested that SRTC determine the maximum allowable total organic carbon (TOC) content in the melter feed which can be implemented as part of the Process Requirements for melter feed preparation (PR-S04). The maximum TOC limit thus determined in this study was about 24,000 ppm on an aqueous slurry basis. At the TOC levels below this, the peak concentration of combustible components in the quenched off-gas will not exceed 60 percent of the LFL during off-gas surges of magnitudes up to three times nominal, provided that the melter plenum temperature and the air purge rate to the BUFC are monitored and controlled above 650 degrees C and 220 lb/hr, respectively. Appropriate interlocks should discontinue the feeding when one or both of these conditions are not met. Both the magnitude and duration of an off-gas surge have a major impact on the maximum TOC limit, since they directly affect the melter plenum temperature and combustion. Although the data obtained during recent DWPF melter startup tests showed that the peak magnitude of a surge can be greater than three times nominal, the observed duration was considerably shorter, on the order of several seconds. The long surge duration assumed in this study has a greater impact on the plenum temperature than the peak magnitude, thus making the maximum TOC estimate conservative. Two models were used to make the necessary calculations to determine the TOC limit

  3. DWPF integrated cold runs revised technical bases for precipitate hydrolysis

    International Nuclear Information System (INIS)

    Landon, L.F.

    1992-01-01

    The report defines new precipitate hydrolysis process operating parameters for DWPF Chemical runs assuming the precipitate feed simulants to be processed reflect the decision to implement a final wash of the tetraphenylborate slurry before transfer to DWPF (i.e. the Late Wash Facility). Control of the nitrite content of the tetraphenylborate slurry to 0.01M or less has eliminated the need for hydroxylamine nitrate (HAN) during hydrolysis. Consequently, the oxidant nitrous oxide will not be generated. However, nitric oxide (NO) is expected to be generated (reaction of formic acid with nitrite) and some fraction of the NO can be expected to be oxidized to nitrogen dioxide. The rate of NO generation with low nitrite feed has not been quantified at this time nor is the extent to which the NO is oxidized to NO 2 known. A mass spectrometer is being installed in the Precipitate Hydrolysis Experimental Facility (PHEF) which will enable the NO generation rate to be defined as well as the extent to which the NO is oxidized to NO 2 . There is some undocumented data available for C 6 H 6 /NO and C 6 H 6 /NO 2 with N 2 as the diluent but no similar data for CO 2 . Development of test data in the required time frame is not possible. However, MOC's will be estimated for benzene/NO/NO 2 /CO 2 gas mixtures (the MOC is expected to be approximately 60% less than for the HAN process). Once these data are obtained, and NO/NO 2 concentration profiles are obtained from PHEF hydrolysis process demonstrations, a flammability control strategy for the DWPF Salt Processing Cell will be developed. Implementation of the HAN process purge strategy upon startup of the SPC with the late wash process would be conservative

  4. DWPF Melter No.2 Prototype Bus Bar Test Report

    International Nuclear Information System (INIS)

    Gordon, J.

    2003-01-01

    Characterization and performance testing of a prototype DWPF Melter No.2 Dome Heater Bus Bar are described. The prototype bus bar was designed to address the design features of the existing system which may have contributed to water leaks on Melter No.1. Performance testing of the prototype revealed significant improvement over the existing design in reduction of both bus bar and heater connection maximum temperature, while characterization revealed a few minor design and manufacturing flaws in the bar. The prototype is recommended as an improvement over the existing design. Recommendations are also made in the area of quality control to ensure that critical design requirements are met

  5. 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)

  6. 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)

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

    International Nuclear Information System (INIS)

    1987-12-01

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

  8. 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

  9. The quality assurance program data analysis for diagnostic radiology in government hospitals in southern provinces of Syria

    International Nuclear Information System (INIS)

    Kharita, M. H.; Khedr, M. S.; Wannus, K. M.

    2008-01-01

    This study covered comprehensive evaluation for diagnostic radiography and fluorography equipment used in medicine by applying SAEC quality control rules. The results showed that most of considered x-ray equipment have an acceptable performance but few reached 21.6% in radiography and 36.8% in fluorography need repair and recalibration. Also recommendations and guidance for repair and preventative maintenance are required and quality assurance program should be applied in all diagnostic radiology institutions in Syria.(author)

  10. A Program for Follow-Up and Quality Assurance of Electret Results

    International Nuclear Information System (INIS)

    Sarusi, B.; Levinson, S.; Lavi, N.; German, U.

    2014-01-01

    The most important naturally occurring radio-nuclides in the environment are 40K and 238U and 232Th, which are heads of decay series. Building materials may also contain enhanced levels of naturally occurring radioisotopes which may be sources of external and internal radiation exposure in dwellings. The external exposure is due to the direct radiation from the radioisotopes in the decay series of 238U and 232Th, and among these daughters, two Radon isotopes are produced: 222Rn is a daughter in the chain of decay of 238U and 220Rn is a daughter in the 232Th chain. Radon is a gas, it undergoes diffusion in the building material and exhalation to the surrounding. Besides, radon is emanated also from soil and its concentration can be significant in radon prone areas. Inhalation of air with increased level of Radon causes internal exposure, which is the greatest contribution to the exposure of individuals to natural radiation. Therefore, accurate measurement of radon concentration is of great importance. There are several methods to determine the radon concentration in air. The Israeli regulation for measuring the radioactive content in building materials specifies three methods for radon concentration measurements: applying continuous monitoring, using Electrets and using active charcoal cassettes. Using Electrets is convenient, as a relatively simple stand-alone system can be used. The follow-up and quality assurance of Electrets results is the subject of the present work. For this purpose a computer program was developed which handles the Electrets results database and applies various tools for analysis

  11. Implementation of a lung radiosurgery program: technical considerations and quality assurance in an Australian institution

    International Nuclear Information System (INIS)

    Siva, Shankar; MacManus, Michael; Ball, David; Chesson, Brent; Aarons, Yolanda; Clements, Natalie; Kron, Tomas

    2012-01-01

    The Peter MacCallum Cancer Centre has established a stereotactic lung radiosurgery program for the treatment of isolated lung metastases. The aim of this study was to critically assess the technical feasibility of performing stereotactic lung radiosurgery in an Australian institution. A single 26-Gy fraction of radiotherapy was delivered to patients with positron emission tomography (PET) staged solitary lung metastases. Motion management was addressed using four-dimensional computed tomographic simulation, and cone beam CT (CBCT) online soft-tissue matching. Treatments were with multiple coplanar and non-coplanar asymmetric beams. Patients were immobilised in a dedicated stereotactic body cradle. Quality assurance (QA) of treatment plans with both ion chamber and film measurements was performed accounting for patient-specific respiratory motion. Between February 2010 and February 2011, nine patients received stereotactic lung radiosurgery. One grade 1 toxicity and one grade 2 toxicity were recorded after treatment. The mean planning target volume was 22.6 cc. A median of eight beams were delivered per treatment plan (range 7–10) with a median of two non-coplanar beams (range 0–6). At treatment plan QA, the difference between planned and delivered dose was ≤1.76% in all static and dynamic ion chamber recordings. A mid-treatment CBCT was performed at a median time of 21 min, with the mean displacement discrepancy from initial set-up being 0.4 mm (range 0–2 mm). Stereotactic radiosurgery to the lung was both feasible and tolerable at our institution. Intrafractional immobilisation within 2 mm was reproducible. Excellent concordance between planned and delivered treatments was achieved in the phantom QA.

  12. Implementation of a quality assurance program for computerized treatment planning systems according to TRS 430

    International Nuclear Information System (INIS)

    Camargo, Priscilla Roberta Tavares Leite

    2006-01-01

    This work presents the guidelines and necessary tests tom implement a quality assurance program for Eclipse 7.3.10 from Varian at Hospital das Clinicas, Sao Paulo University School of Medicine - Brazil, in accordance with the new IAEA publication TRS 430. The recommended tests for the TRS 430 air mainly classified into acceptance tests, commissioning (dosimetric and non-dosimetric tests), and routine tests. The IAEA document's recommendations are being implemented at the hospital for two Varian linear accelerators - Clinac 600C e Clinac 2100C. The acceptance tests verified 'hardware', integration of network systems, data transfer and 'software' parameters. The results obtained are in a good agreement with the manufacturer's specifications. Measurements of absolute dose in several set-ups were made for the commissioning dosimetric tests. These data were compared to the absolute doses determined by the TPS. The great majority of the tests showed 90% to 80% of the analyzed data in acceptance levels, with a good agreement between the experimental data and the data determined by the TPS. Only settings with asymmetric fields presented significant discords, showing the need for a more detailed inquiry for these settings. The non-dosimetric commissioning tests have also presented excellent results, with virtually all the system tools and general performance in compliance with TRS 430. The acceptance criteria have been applied for a comparison between the values of MUs generated by TPS and the calculated manually ones. The beams have been characterized for Eclipse with data transferred from CadPlan and with data from recommissioning of accelerators, so for these tests it was found a difference of at least 3% for the conformal field shape for the data originated in the beams of recommissioning and at least 4% for the data proceeded from CadPlan. The tolerance level established by TRS 430 for this setting was 3%. (author)

  13. A pilot scale demonstration of the DWPF process control and product verification strategy

    International Nuclear Information System (INIS)

    Hutson, N.D.; Jantzen, C.M.; Beam, D.C.

    1992-01-01

    The Defense Waste Processing Facility (DWPF) has been designed and constructed to immobilize Savannah River Site high level liquid waste within a durable borosilicate glass matrix for permanent storage. The DWPF will be operated to produce a glass product which must meet a number of product property constraints which are dependent upon the final product composition. During actual operations, the DWPF will control the properties of the glass product by the controlled blending of the waste streams with a glass-forming frit to produce the final melter feed slurry. The DWPF will verify control of the glass product through analysis of vitrified samples of slurry material. In order to demonstrate the DWPF process control and product verification strategy, a pilot-scale vitrification research facility was operated in three discrete batches using simulated DWPF waste streams. All of the DWPF process control methodologies were followed and the glass produce from each experiment was leached according to the Product Consistency Test. Results of the campaign are summarized

  14. A pilot scale demonstration of the DWPF process control and product verification strategy

    International Nuclear Information System (INIS)

    Hutson, N.D.; Jantzen, C.M.; Beam, D.C.

    1992-01-01

    The Defense Waste Processing Facility (DWPF) has been designed and constructed to immobilize Savannah River Site high level liquid waste within a durable borosilicate glass matrix for permanent storage. The DWPF will be operated to produce a glass product which must meet a number of product property constraints which are dependent upon the final product composition. During actual operations, the DWPF will control the properties of the glass product by the controlled blending of the waste streams with a glass-forming frit to produce the final melter feed slurry. The DWPF will verify control of the glass product through analysis of vitrified samples of slurry material. In order to demonstrate the DWPF process control and product verification strategy, a pilot-scale vitrification research facility was operated in three discrete batches using simulated DWPF waste streams. All of the DWPF process control methodologies were followed and the glass product from each experiment was leached according to the Product Consistency Test. In this paper results of the campaign are summarized

  15. 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)

  16. 13 CFR 108.10 - Description of the New Markets Venture Capital Program.

    Science.gov (United States)

    2010-01-01

    ... Venture Capital Program. 108.10 Section 108.10 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW MARKETS VENTURE CAPITAL (âNMVCâ) PROGRAM Introduction to Part 108 § 108.10 Description of the New Markets Venture Capital Program. The New Markets Venture Capital (“NMVC”) Program is a...

  17. GGP Program Description, 2006-2011 | IDRC - International ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    2010-12-22

    Dec 22, 2010 ... This document explains the context and orientation of the IDRC's Globalization, Growth and Poverty (GGP) program initiative for the 2006-11 period, detailing the GGP program's objectives, research areas, cross-cutting themes, and programming approach.Download the PDF : Globalization, Growth and ...

  18. World Perspective Case Descriptions on Educational Programs for Adults: India.

    Science.gov (United States)

    Jayagopal, R.; Burns, E. P.

    Four adult education programs being conducted in India are described in the case studies in this packet. Two of the projects involve literacy; the third promotes literacy as one part of its community development program, and the fourth trains workers in hotel management and catering technology. The literacy programs are (1) development of a…

  19. Burst Test Qualification Analysis of DWPF Canister-Plug Weld

    International Nuclear Information System (INIS)

    Gupta, N.K.; Gong, Chung.

    1995-02-01

    The DWPF canister closure system uses resistance welding for sealing the canister nozzle and plug to ensure leak tightness. The welding group at SRTC is using the burst test to qualify this seal weld in lieu of the shear test in ASME B ampersand PV Code, Section IX, paragraph QW-196. The burst test is considered simpler and more appropriate than the shear test for this application. Although the geometry, loading and boundary conditions are quite different in the two tests, structural analyses show similarity in the failure mode of the shear test in paragraph QW-196 and the burst test on the DWPF canister nozzle Non-linear structural analyses are performed using finite element techniques to study the failure mode of the two tests. Actual test geometry and realistic stress strain data for the 304L stainless steel and the weld material are used in the analyses. The finite element models are loaded until failure strains are reached. The failure modes in both tests are shear at the failure points. Based on these observations, it is concluded that the use of a burst test in lieu of the shear test for qualifying the canister-plug weld is acceptable. The burst test analysis for the canister-plug also yields the burst pressures which compare favorably with the actual pressure found during burst tests. Thus, the analysis also provides an estimate of the safety margins in the design of these vessels

  20. Lot No. 1 of Frit 202 for DWPF cold runs

    International Nuclear Information System (INIS)

    Schumacher, R.F.

    1993-01-01

    This report was prepared at the end of 1992 and summarizes the evaluation of the first lot sample of DWPF Frit 202 from Cataphote Inc. Publication of this report was delayed until the results from the carbon analyses could be included. To avoid confusion the frit specifications presented in this report were those available at the end of 1992. The specifications were slightly modified early in 1993. The frit was received and evaluated for moisture, particle size distribution, organic-inorganic carbon and chemical composition. Moisture content and particle size distribution were determined on a representative sample at SRTC. These properties were within the DWPF specifications for Frit 202. A representative sample was submitted to Corning Engineering Laboratory Services for chemical analyses. The sample was split and two dissolutions prepared. Each dissolution was analyzed on two separate days. The results indicate that there is a high probability (>95%) that the silica content of this frit is below the specification limit of 77.0 ± 1.0 wt %. The average of the four analyzed values was 75.1 wt % with a standard deviation of 0.28 wt %. All other oxides were within the elliptical two sigma limits. Control standard frit samples were submitted and analyzed at the same time and the results were very similar to previous analyses of these materials

  1. The integrated performance evaluation program quality assurance guidance in support of EM environmental sampling and analysis activities

    International Nuclear Information System (INIS)

    1994-05-01

    EM's (DOE's Environmental Restoration and Waste Management) Integrated Performance Evaluation Program (IPEP) has the purpose of integrating information from existing PE programs with expanded QA activities to develop information about the quality of radiological, mixed waste, and hazardous environmental sample analyses provided by all laboratories supporting EM programs. The guidance addresses the goals of identifying specific PE sample programs and contacts, identifying specific requirements for participation in DOE's internal and external (regulatory) programs, identifying key issues relating to application and interpretation of PE materials for EM headquarters and field office managers, and providing technical guidance covering PE materials for site-specific activities. (PE) Performance Evaluation materials or samples are necessary for the quality assurance/control programs covering environmental data collection

  2. Impact of Spherical Frit Beads on Simulated DWPF Slurries

    International Nuclear Information System (INIS)

    SMITH, MICHAEL

    2005-01-01

    It has been shown that the rheological properties of simulated Defense Waste Processing Facility (DWPF) melter feed with the glass former frit as mostly (90 weight percent) solid spherical particles (referred to as beads) were improved as the feed was less viscous as compared to DWPF melter feed that contained the normal irregular shaped frit particles. Because the physical design of the DWPF Slurry Mix Evaporator (SME), Melter Feed Tank (MFT), and melter feed loop are fixed, the impact of changing the rheology might be very beneficial. Most importantly, higher weight percent total solids feed might be processed by reducing the rheological properties (specifically yield stress) of the feed. Additionally, if there are processing problems, such as air entrainment or pumping, these problems might be alleviated by reducing the rheological properties, while maintaining targeted throughputs. Rheology modifiers are chemical, physical, or a combination of the two and can either thin or thicken the rheology of the targeted slurry. The beads are classified as a physical rheological modifier in this case. Even though the improved rheological properties of the feed in the above mentioned DWPF tanks could be quite beneficial, it is the possibility of increased melt rate that is the main driver for the use of beaded glass formers. By improving the rheological properties of the feed, the weight percent solids of the feed could be increased. This higher weight percent solids (less water) feed could be processed faster by the melter as less energy would be required to evaporate the water, and more would be available for the actual melting of the waste and the frit. In addition, the use of beads to thin the feed could possibly allow for the use of a lower targeted acid stoichiometry in the feed preparation process (if in fact acid stoichiometry is being driven by feed rheology as opposed to feed chemistry). Previous work by the Savannah River National Laboratory (SRNL) with the lab

  3. Lot quality assurance sampling (LQAS) for monitoring a leprosy elimination program.

    Science.gov (United States)

    Gupte, M D; Narasimhamurthy, B

    1999-06-01

    In a statistical sense, prevalences of leprosy in different geographical areas can be called very low or rare. Conventional survey methods to monitor leprosy control programs, therefore, need large sample sizes, are expensive, and are time-consuming. Further, with the lowering of prevalence to the near-desired target level, 1 case per 10,000 population at national or subnational levels, the program administrator's concern will be shifted to smaller areas, e.g., districts, for assessment and, if needed, for necessary interventions. In this paper, Lot Quality Assurance Sampling (LQAS), a quality control tool in industry, is proposed to identify districts/regions having a prevalence of leprosy at or above a certain target level, e.g., 1 in 10,000. This technique can also be considered for identifying districts/regions at or below the target level of 1 per 10,000, i.e., areas where the elimination level is attained. For simulating various situations and strategies, a hypothetical computerized population of 10 million persons was created. This population mimics the actual population in terms of the empirical information on rural/urban distributions and the distribution of households by size for the state of Tamil Nadu, India. Various levels with respect to leprosy prevalence are created using this population. The distribution of the number of cases in the population was expected to follow the Poisson process, and this was also confirmed by examination. Sample sizes and corresponding critical values were computed using Poisson approximation. Initially, villages/towns are selected from the population and from each selected village/town households are selected using systematic sampling. Households instead of individuals are used as sampling units. This sampling procedure was simulated 1000 times in the computer from the base population. The results in four different prevalence situations meet the required limits of Type I error of 5% and 90% Power. It is concluded that

  4. DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 4 MACROBATCH 5

    International Nuclear Information System (INIS)

    Bannochie, C; Ned Bibler, N; David Diprete, D

    2008-01-01

    the inputs for the development of the Production Records that relate to the radionuclide inventory. This work was initiated through Task Technical Request HLW/DWPF/TTR-2005-0034; Rev. 0 entitled Sludge Batch 4 SRNL Shielded Cells Testing4. Specifically, this report details results from performing, in part, Subtask 3 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Technical Task and Quality Assurance Plan (TTQAP), WSRC-RP-2006-00310, Rev. 15 and Analytical Study Plan (ASP), WSRC-RP-2006-00458, Rev. 16. In order to determine the reportable radionuclides for Sludge Batch 4 (SB4) (Macro Batch 5 (MB5)), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes excluded from the projection calculations. Based on measurements and analytical detection limits, twenty-nine radionuclides have been identified as reportable for DWPF SB4 (MB5) as specified by WAPS 1.2. The 29 reportable nuclides are: Ni-59; Ni-63; Se-79; Sr-90; Zr-93; Nb-93m; Tc-99; Sn-126; Cs-137; Sm-151; U-233; U-234; Np-237; U-238; Pu-238; Pu-239; Pu-240; Am-241; Pu-241; Pu-242; Am-242m; Am-243; Cm-244; Cm-245; Cm-246; Cm-247; Bk-247; Cm-248; and Cf-251. The WCP and WQR require that all of radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB4 (MB5), all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time through the calendar year 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list

  5. Integrated Data Collection Analysis (IDCA) Program: FY2011 Project Descriptions

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Whinnery, LeRoy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shelley, Timothy J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Reyes, Jose A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2012-02-03

    This document provides brief descriptions of research topics for consideration by the IDCA for potential funding in funding in FY 2011. The topics include the utilization of the results from the Proficiency Test developed during FY 2010 to start populating the small-scale safety and thermal testing (SSST) Testing Compendium and revising results from methods modifications. Other research topics were also developed for FY 2011 from issues that arose in the Proficiency Test.

  6. The ASSURE Summer REU Program: Introducing research to first-generation and underserved undergraduates through space sciences and engineering projects

    Science.gov (United States)

    Barron, Darcy; Peticolas, Laura; Multiverse Team at UC Berkeley's Space Sciences Lab

    2018-01-01

    The Advancing Space Science through Undergraduate Research Experience (ASSURE) summer REU program is an NSF-funded REU site at the Space Sciences Lab at UC Berkeley that first started in summer 2014. The program recruits students from all STEM majors, targeting underserved students including community college students and first-generation college students. The students have little or no research experience and a wide variety of academic backgrounds, but have a shared passion for space sciences and astronomy. We will describe our program's structure and the components we have found successful in preparing and supporting both the students and their research advisors for their summer research projects. This includes an intensive first week of introductory lectures and tutorials at the start of the program, preparing students for working in an academic research environment. The program also employs a multi-tiered mentoring system, with layers of support for the undergraduate student cohort, as well as graduate student and postdoctoral research advisors.

  7. 47 CFR 79.3 - Video description of video programming.

    Science.gov (United States)

    2010-10-01

    ... television audience measurement service, based on television viewership in the counties that make up each DMA... other distributor of video programming for residential reception that delivers such programming directly... the national audience share during prime time of nonbroadcast networks, as determined by Nielsen Media...

  8. 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

  9. 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.

  10. Quality Assurance Audit of Technique Failure and 90-Day Mortality after Program Discharge in a Canadian Home Hemodialysis Program.

    Science.gov (United States)

    Shah, Nikhil; Reintjes, Frances; Courtney, Mark; Klarenbach, Scott W; Ye, Feng; Schick-Makaroff, Kara; Jindal, Kailash; Pauly, Robert P

    2017-07-24

    Little is known about patients exiting home hemodialysis. We sought to characterize the reasons, clinical characteristics, and pre-exit health care team interactions of patients on home hemodialysis who died or underwent modality conversion (negative disposition) compared with prevalent patients and those who were transplanted (positive disposition). We conducted an audit of all consecutive patients incident to home hemodialysis from January of 2010 to December of 2014 as part of ongoing quality assurance. Records were reviewed for the 6 months before exit, and vital statistics were assessed up to 90 days postexit. Ninety-four patients completed training; 25 (27%) received a transplant, 11 (12%) died, and 23 (25%) were transferred to in-center hemodialysis. Compared with the positive disposition group, patients in the negative disposition group had a longer mean dialysis vintage (3.15 [SD=4.98] versus 1.06 [SD=1.16] years; P =0.003) and were performing conventional versus a more intensive hemodialysis prescription (23 of 34 versus 23 of 60; P <0.01). In the 6 months before exit, the negative disposition group had significantly more in-center respite dialysis sessions, had more and longer hospitalizations, and required more on-call care team support in terms of phone calls and drop-in visits (each P <0.05). The most common reason for modality conversion was medical instability in 15 of 23 (65%) followed by caregiver or care partner burnout in three of 23 (13%) each. The 90-day mortality among patients undergoing modality conversion was 26%. Over a 6-year period, approximately one third of patients exited the program due to death or modality conversion. Patients who die or transfer to another modality have significantly higher health care resource utilization ( e.g. , hospitalization, respite treatments, nursing time, etc. ). Copyright © 2017 by the American Society of Nephrology.

  11. Simulation model for wind energy storage systems. Volume III. Program descriptions. [SIMWEST CODE

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume III, the SIMWEST program description contains program descriptions, flow charts and program listings for the SIMWEST Model Generation Program, the Simulation program, the File Maintenance program and the Printer Plotter program. Volume III generally would not be required by SIMWEST user.

  12. Summary of development and recommendations for a quality assurance program for the procurement and manufacture of urban mass transit operating equipment and systems

    Science.gov (United States)

    Witkin, S. A.

    1976-01-01

    A viable quality program for the urban mass transit industry, and a management approach to ensure compliance with the program are outlined. Included are: (1) a set of guidelines for quality assurance to be imposed on transit authorities, and a management approach to ensure compliance with them; (2) a management approach to be used by the transit authorities (properties) for assuring compliance with the QA guidelines; and (3) quality assurance guidelines to be imposed by properties and umta for procurement of hardware and systems.

  13. HIGHWAY, a transportation routing model: program description and users' manual

    International Nuclear Information System (INIS)

    Joy, D.S.; Johnson, P.E.; Gibson, S.M.

    1982-12-01

    A computerized transportation routing model has been developed at the Oak Ridge National Laboratory to be used for predicting likely routes for shipping radioactive materials. The HIGHWAY data base is a computerized road atlas containing descriptions of the entire interstate highway system, the federal highway system, and most of the principal state roads. In addition to its prediction of the most likely commercial route, options incorporated in the HIGHWAY model can allow for maximum use of interstate highways or routes that will bypass urbanized areas containing populations > 100,000. The user may also interactively modify the data base to predict routes that bypass any particular state, city, town, or specific highway segment

  14. 15 CFR 16.2 - Description and goal of program.

    Science.gov (United States)

    2010-01-01

    ... particular advantages of their products. These objectives are accomplished by: (1) Selecting or developing.... (c) For selected categories of consumer products, the program includes advertising guidelines covering situations where quantitative performance values are stated in advertising or where qualitative...

  15. DWPF GLASS BEADS AND GLASS FRIT TRANSPORT DEMONSTRATION

    Energy Technology Data Exchange (ETDEWEB)

    Adamson, D; Bradley Pickenheim, B

    2008-11-24

    DWPF is considering replacing irregularly shaped glass frit with spherical glass beads in the Slurry Mix Evaporator (SME) process to decrease the yield stress of the melter feed (a non-Newtonian Bingham Plastic). Pilot-scale testing was conducted on spherical glass beads and glass frit to determine how well the glass beads would transfer when compared to the glass frit. Process Engineering Development designed and constructed the test apparatus to aid in the understanding and impacts that spherical glass beads may have on the existing DWPF Frit Transfer System. Testing was conducted to determine if the lines would plug with the glass beads and the glass frit slurry and what is required to unplug the lines. The flow loop consisted of vertical and horizontal runs of clear PVC piping, similar in geometry to the existing system. Two different batches of glass slurry were tested: a batch of 50 wt% spherical glass beads and a batch of 50 wt% glass frit in process water. No chemicals such as formic acid was used in slurry, only water and glass formers. The glass beads used for this testing were commercially available borosilicate glass of mesh size -100+200. The glass frit was Frit 418 obtained from DWPF and is nominally -45+200 mesh. The spherical glass beads did not have a negative impact on the frit transfer system. The transferring of the spherical glass beads was much easier than the glass frit. It was difficult to create a plug with glass bead slurry in the pilot transfer system. When a small plug occurred from setting overnight with the spherical glass beads, the plug was easy to displace using only the pump. In the case of creating a man made plug in a vertical line, by filling the line with spherical glass beads and allowing the slurry to settle for days, the plug was easy to remove by using flush water. The glass frit proved to be much more difficult to transfer when compared to the spherical glass beads. The glass frit impacted the transfer system to the point

  16. Development Of Remote Hanford Connector Gasket Replacement Tooling For DWPF

    International Nuclear Information System (INIS)

    Krementz, D.; Coughlin, Jeffrey

    2009-01-01

    The Defense Waste Processing Facility (DWPF) requested the Savannah River National Laboratory (SRNL) to develop tooling and equipment to remotely replace gaskets in mechanical Hanford connectors to reduce personnel radiation exposure as compared to the current hands-on method. It is also expected that radiation levels will continually increase with future waste streams. The equipment is operated in the Remote Equipment Decontamination Cell (REDC), which is equipped with compressed air, two master-slave manipulators (MSM's) and an electro-mechanical manipulator (EMM) arm for operation of the remote tools. The REDC does not provide access to electrical power, so the equipment must be manually or pneumatically operated. The MSM's have a load limit at full extension of ten pounds, which limited the weight of the installation tool. In order to remotely replace Hanford connector gaskets several operations must be performed remotely, these include: removal of the spent gasket and retaining ring (retaining ring is also called snap ring), loading the new snap ring and gasket into the installation tool and installation of the new gasket into the Hanford connector. SRNL developed and tested tools that successfully perform all of the necessary tasks. Removal of snap rings from horizontal and vertical connectors is performed by separate air actuated retaining ring removal tools and is manipulated in the cell by the MSM. In order install a new gasket, the snap ring loader is used to load a new snap ring into a groove in the gasket installation tool. A new gasket is placed on the installation tool and retained by custom springs. An MSM lifts the installation tool and presses the mounted gasket against the connector block. Once the installation tool is in position, the gasket and snap ring are installed onto the connector by pneumatic actuation. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and

  17. DWPF GLASS BEADS AND GLASS FRIT TRANSPORT DEMONSTRATION

    International Nuclear Information System (INIS)

    Adamson, D.; Pickenheim, Bradley

    2008-01-01

    DWPF is considering replacing irregularly shaped glass frit with spherical glass beads in the Slurry Mix Evaporator (SME) process to decrease the yield stress of the melter feed (a non-Newtonian Bingham Plastic). Pilot-scale testing was conducted on spherical glass beads and glass frit to determine how well the glass beads would transfer when compared to the glass frit. Process Engineering Development designed and constructed the test apparatus to aid in the understanding and impacts that spherical glass beads may have on the existing DWPF Frit Transfer System. Testing was conducted to determine if the lines would plug with the glass beads and the glass frit slurry and what is required to unplug the lines. The flow loop consisted of vertical and horizontal runs of clear PVC piping, similar in geometry to the existing system. Two different batches of glass slurry were tested: a batch of 50 wt% spherical glass beads and a batch of 50 wt% glass frit in process water. No chemicals such as formic acid was used in slurry, only water and glass formers. The glass beads used for this testing were commercially available borosilicate glass of mesh size -100+200. The glass frit was Frit 418 obtained from DWPF and is nominally -45+200 mesh. The spherical glass beads did not have a negative impact on the frit transfer system. The transferring of the spherical glass beads was much easier than the glass frit. It was difficult to create a plug with glass bead slurry in the pilot transfer system. When a small plug occurred from setting overnight with the spherical glass beads, the plug was easy to displace using only the pump. In the case of creating a man made plug in a vertical line, by filling the line with spherical glass beads and allowing the slurry to settle for days, the plug was easy to remove by using flush water. The glass frit proved to be much more difficult to transfer when compared to the spherical glass beads. The glass frit impacted the transfer system to the point

  18. 76 FR 26341 - Medicaid Program; Methods for Assuring Access to Covered Medicaid Services

    Science.gov (United States)

    2011-05-06

    ... as part of their broader efforts to ``assure that payments are consistent with efficiency, economy... but not limited to, the beneficiaries' health care needs and characteristics, State or local service... care case management). Increasingly, States are developing service delivery models that emphasize...

  19. 77 FR 14955 - DoD Information Assurance Scholarship Program (IASP)

    Science.gov (United States)

    2012-03-14

    ... point of contact at each CAE, responsible for publicizing the DoD IASP to potential recruitment students... college or university to NSA. Centers of Academic Excellence in Information Assurance Education and... proposal, and all colleges and universities subsequently receiving grants must provide documentation on how...

  20. 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

    It is widely acknowledged that the culture of medical group practices greatly influences the quality of care, but little is known about how cultures are translated into specific types of programs focused on quality. This study explores this issue by assessing the influence of the organizational culture on these types of programs in medical group practices in the upper Midwest. Data were obtained from two surveys of medical group practices. The first survey was designed to assess the culture of the practice using a nine-dimension instrument developed previously. The second survey was designed to obtain organizational structure data including the programs identified by the literature as important to the quality of care in medical practices. Completed surveys were obtained from eighty-eight medical groups. The relationship of the group practice culture to structural programs focused on quality of care was analyzed using logistic regression equations. Several interesting patterns emerged. As expected, practices with a strong information culture favor electronic data systems and formal programs that provide comparative or evidence-based data to enhance their clinical practices. However, those with a quality-centered culture appear to prefer patient satisfaction surveys to assess the quality of their care, while practices that are more business-oriented rely on bureaucratic strategies such as benchmarking and physician profiling. Cultures that emphasize the autonomy of physician practice were negatively (but not at a statistically significant level) associated with all the programs studied. Practices with a highly collegial culture appear to rely on informal peer review mechanisms to assure quality rather than any of the structural programs included in this analysis. This study suggests that the types of quality programs that group practices develop differ according to their cultures. Consequently, it is important for practice administrators and medical directors to

  1. 77 FR 48102 - Closed Captioning and Video Description of Video Programming

    Science.gov (United States)

    2012-08-13

    ... Captioning and Video Description of Video Programming AGENCY: Federal Communications Commission. [[Page 48103... show that providing captions on their programming would be economically burdensome. DATES: Effective...) establishing requirements for closed captioning on video programming to ensure access by persons with hearing...

  2. Implementation of quality assurance in the manufacture of radiation measuring instruments

    International Nuclear Information System (INIS)

    Erath, W.; Maushart, R.

    1993-01-01

    Contrary to a general belief, quality assurance in an instrument manufacturing plant comprises considerably more than the testing of instruments and components. Quality assurance programs according to the ISO 9000 standards are part of the general quality policy of a company, comprising management, manufacturing, sales, and service. A description of the quality assurance research and development is given, and the practical execution with regard to calibration of contamination monitors is pointed out in detail. (orig.) [de

  3. Influence of department volume on survival for ovarian cancer: results from a prospective quality assurance program of the Austrian Association for Gynecologic Oncology.

    Science.gov (United States)

    Marth, Christian; Hiebl, Sonja; Oberaigner, Willi; Winter, Raimund; Leodolter, Sepp; Sevelda, Paul

    2009-01-01

    The Austrian Association for Gynecologic Oncology initiated in 1998 a prospective quality assurance program for patients with ovarian cancer. The aim of this study was to evaluate factors predicting overall survival especially under consideration of department volume. All Austrian gynecological departments were invited to participate in the quality assurance program. A questionnaire was sent out that included birth date, histology, date of diagnosis, stage, and basic information on primary treatment. Description of comorbidity was not requested. Patient life status was assessed in a passive way. We did record linkage between each patient's name and birth date and the official mortality data set collected by Statistics Austria. No data were available on progression-free survival. Patients treated between January 1, 1999 and December 31, 2004 were included in the analysis. Mortality dates were available to December 31, 2006. Data were analyzed by means of classical statistical methods. Cut-off point for departments was 24 patients per year. A total of 1948 patients were evaluable. Approximately 75% of them were treated at institutions with fewer than 24 new patients per year. Patient characteristics were grossly similar for both department types. Multivariate analysis confirmed established prognostic factors such as International Federation of Gynecologists and Obstetricians (FIGO) stage, lymphadenectomy, age, grading, and residual disease. In addition, we found small departments (<24 patients per year) to have a negative effect on overall survival (hazards ratio, 1.38: 95% confidence interval, 1.2-1.7; and P < 0.001). The results indicate that in Austria, rules prescribing minimum department case load can further improve survival for patients with ovarian cancer.

  4. INTERLINE, a railroad routing model: program description and user's manual

    International Nuclear Information System (INIS)

    Peterson, B.E.

    1985-11-01

    INTERLINE is an interactive computer program that finds likely routes for shipments over the US railroad system. It is based on a shortest path algorithm modified both to reflect the nature of railroad company operations and to accommodate computer resource limitations in dealing with a large transportation network. The first section of the report discusses the nature of railroad operations and routing practices in the United States, including the tendency to concentrate traffic on a limited number of mainlines, the competition for traffic by different companies operating in the same corridors, and the tendency of originating carriers to retain traffic on their systems before transferring it to terminating carriers. The theoretical foundation and operation of shortest path algorithms are described, as well as the techniques used to simulate actual operating practices within this framework. The second section is a user's guide that describes the program operation and data structures, program features, and user access. 11 refs., 11 figs

  5. Description of the thermoelastic/plastic computer program TEPCO. Memorandum report RSI-0040

    International Nuclear Information System (INIS)

    Pariseau, W.G.

    1975-01-01

    Presented is a description of the two-dimensional (plane strain, axial symmetry) thermoelastic/plastic computer program TEPCO used by RE/SPEC Inc. in conjunction with an investigation of rock mechanics of underground radioactive waste disposal

  6. DWPF upgrade, immobilization Programmatic Environmental Impact Statement input. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, I.K.; Bignell, D.

    1994-01-01

    This Programmatic Environmental Impact Statement (PEIS) addresses the immobilization of plutonium by vitrification. Existing engineering documents, analyses, EIS, and technical publications were used and incorporated wherever possible to provide a timely response to this support effort. Although the vitrification technology is proven for the immobilization of high-level radioactive waste, more study and technical detail will be necessary to provide a comprehensive EIS that fully addresses all aspects of introduction of plutonium to the vitrification process. This document describes the concept(s) of plutonium processing as it relates to the upgrade of the DWPF and is therefore conceptual in nature. These concepts are based on technical data and experience at the Savannah River Site and will be detailed and finalized to support execution of this immobilization option

  7. Dew point, internal gas pressure, and chemical composition of the gas within the free volume of DWPF canistered waste forms

    International Nuclear Information System (INIS)

    Harbour, J.R.; Herman, D.T.; Crump, S.; Miller, T.J.; McIntosh, J.

    1996-01-01

    The Defense Waste Processing Facility (DWPF) produced 55 canistered waste forms containing simulated waste glass during the four Waste Qualification campaigns of the DWPF Startup Test Program. Testing of the gas within the free volume of these canisters for dew point, internal gas pressure, and chemical composition was performed as part of a continuing effort to demonstrate compliance with the Waste Acceptance Product Specifications. Results are presented for six glass-filled canisters. The dew points within the canisters met the acceptance criterion of < 20 degrees C for all six canisters. Factors influencing the magnitude of the dew point are presented. The chemical composition of the free volume gas was indistinguishable from air for all six canisters. Hence, no foreign materials were present in the gas phase of these canisters. The internal gas pressures within the sealed canisters were < 1 atm at 25 degrees C for all six canisters which readily met the acceptance criterion of an internal gas pressure of less than 1.5 atm at 25 degrees C. These results provided the evidence required to demonstrate compliance with the Waste Acceptance Product Specifications

  8. 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

  9. Coca-Cola Hispanic Education Fund: Los Angeles Program Description.

    Science.gov (United States)

    Coca Cola Bottling Co. of Los Angeles, CA.

    The Coca-Cola Hispanic Education Fund was created in response to the high school dropout problem in Los Angeles. The Fund enables the Coca-Cola Bottling Company of Los Angeles to build upon the successful relationship it has developed in the Hispanic community and maximizes the effectiveness of existing student support programs by directing needy…

  10. Program Description: Physical Therapy in a Heart Failure Clinic

    OpenAIRE

    Knocke, Ann

    2012-01-01

    Aerobic exercise and resistance training have been proven to be beneficial for patients with heart failure. Current reimbursement guidelines exclude these patients from our traditional cardiac rehabilitation program, so at Newton Wellesley Hospital a clinic model was developed for the disease management and exercise of heart failure patients.

  11. Isochronous cyclotron closed equilibrium orbit calculation program description

    International Nuclear Information System (INIS)

    Kiyan, I.N.; Vorozhtsov, S.B.; Tarashkevich, R.

    2003-01-01

    The Equilibrium Orbit Research Program - EORP, written in C++ with the use of Visual C++ is described. The program is intended for the calculation of the particle rotation frequency and particle kinetic energy in the closed equilibrium orbits of an isochronous cyclotron, where the closed equilibrium orbits are described through the radius and particle momentum angle: r eo (θ) and φ p (θ). The program algorithm was developed on the basis of articles, lecture notes and original analytic calculations. The results of calculations by the EORP were checked and confirmed by using the results of calculations by the numerical methods. The discrepancies between the EORP results and the numerical method results for the calculations of the particle rotation frequency and particle kinetic energy are within the limits of ±1·10 -4 . The EORP results and the numerical method results for the calculations of r eo (θ) and φ p (θ) practically coincide. All this proves the accuracy of calculations by the EORP for the isochronous cyclotrons with the azimuthally varied fields. As is evident from the results of calculations, the program can be used for the calculations of both straight - sector and spiral-sector isochronous cyclotrons. (author)

  12. 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)

  13. [Laparoscopic "fast-track" sigmoidectomy for diverticulitis disease in Germany. Results of a prospective quality assurance program].

    Science.gov (United States)

    Tsilimparis, N; Haase, O; Wendling, P; Kipfmüller, K; Schmid, M; Engemann, R; Schwenk, W

    2010-09-01

    The natural course of sigmoid colon diverticulitis during conservative therapy and the assessment of the perioperative morbidity after sigmoid colon resection are differently evaluated by surgeons and gastroenterologists. The "fast-track" rehabilitation accelerates the reconvalescence and reduces the rate of postoperative general complications after colorectal surgery. The results of the laparoscopic "Fast-track" sigmoidectomy should be examined within a quality assurance program to better evaluate the perioperative risks following surgical management of diverticulitis. A prospective data collection within the voluntary quality assurance program "fast-track" Kolon II was performed. All participating clinics agreed on a multimodal, evidence-based standard perioperative treatment in terms of a "fast-track" rehabilitation for elective operations for sigmoid diverticulitis. Data from 846 patients undergoing laparoscopic "fast-track" sigmoid colon resection in 23 surgical departments in Germany were collected and evaluated. The mean age of the patients was 63 years (range 23 - 91). 203 patients (24 %) had severe co-morbidities (ASA classification III - IV). A conversion to conventional open surgery was necessary in 51 cases (6 %). Complications occurred in 93 patients (11 %). 76 patients suffered a surgical complication (8.9 %) and 32 patients (3.8 %) a general complication. Two patients died postoperatively due to multi-organ failure following anastomotic leaks. The patients took solid food in median on day 1 after surgery (range, 0 - 5) and passed stool on day 2 (range, 0 - 22). Predefined discharge criteria (free of pain on oral medication, normal oral feeding, stool) were met on day 4 (range, 1 - 58) and the patients were discharged on day 7 (range, 3 - 72). The 30-day re-admission rate was 3.9 %. Patients undergoing laparoscopic "fast-track" sigmoidectomy had a low rate of general complications and had a rapid reconvalescence with a short postoperative in

  14. Quality Assurance Source Requirements Traceability Database

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  15. 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

  16. Program description and summaries of fiscal year 1981 activities

    International Nuclear Information System (INIS)

    1981-10-01

    This Division supports exploratory research on novel concepts related to energy. The research is usually aimed at establishing the scientific feasibility of a concept and, where appropriate, also at estimating its economic viability. Because projects supported inevitably involve a high degree of risk, an indication of a high potential payoff is required. An immediate, specific application of the concept is not an absolute prerequisite for consideration; thus, for example, proposers of schemes leading to the development of x-ray lasers are not required to justify their proposals by discussing potential applications of such lasers. The concepts supported are typically at too early a stage of scientific verification to qualify for funding by DOE programs responsible for technology development. Where doubt exists, such programs are consulted, prior to proposal consideration by AEP, in order to establish their possible interest in the project

  17. Full-scale mark II CRT program facility description report

    International Nuclear Information System (INIS)

    Namatame, Ken; Kukita, Yutaka; Ito, Hideo; Yamamoto, Nobuo; Shiba, Masayoshi

    1980-03-01

    Started in fiscal year 1977, the Full-Scale Mark II CRT (Containment Response Test) Program is proceeding for the period of five years. The primary objective of the CRT Program is to provide a data base for evaluation of the pressure suppression pool hydrodynamic loads associated with a postulated loss-of-coolant accident in the BWR Mark II containment system. The test facility was designed and constructed from fiscal year 1977 to 1978, and completed in March 1979. It is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report describes design concepts, dimensions and constructions of the test facility, as well as specifications, locations and installation schemes of the measuring equipments. Results of soil structure inspection, vacuum breaker test and shaker test of the containment shell are given in the appendices. (author)

  18. Description of an ethics curriculum for a medicine residency program.

    OpenAIRE

    Silverman, H J

    1999-01-01

    This paper examines the attempts to develop and implement an ethics curriculum for the Internal Medicine Residency Program at the University of Maryland Medical Center. The objectives of the curriculum were to enhance moral reasoning skills and to promote humanistic attitudes and behavior among the residents. The diverse methodologies used to achieve these objectives included case discussions, literature reading, role playing, writing, and videos. These activities occurred predominantly withi...

  19. Isochronous Cyclotron Closed Equilibrium Orbit Calculation Program Description

    CERN Document Server

    Kian, I N; Tarashkevich, R

    2003-01-01

    The Equilibrium Orbit Research Program - EORP, written in C++ with the use of Visual C++ is described. The program is intended for the calculation of the particle rotation frequency and particle kinetic energy in the closed equilibrium orbits of an isochronous cyclotron, where the closed equilibrium orbits are described through the radius and particle momentum angle: r_{eo}(\\theta) and \\varphi_{p}(\\theta). The program algorithm was developed on the basis of articles, lecture notes and original analytic calculations. The results of calculations by the EORP were checked and confirmed by using the results of calculations by the numerical methods. The discrepancies between the EORP results and the numerical method results for the calculations of the particle rotation frequency and particle kinetic energy are within the limits of \\pm1\\cdot10^{-4}. The EORP results and the numerical method results for the calculations of r_{eo}(\\theta) and \\varphi_{p}(\\theta) practically coincide. All this proves the accuracy of ca...

  20. Office of radiation and indoor air: Program description

    International Nuclear Information System (INIS)

    1993-06-01

    The goal of the Environmental Protection Agency's (EPA) Office of Radiation and Indoor Air is to protect the public and the environment from exposures to radiation and indoor air pollutants. The Office develops protection criteria, standards, and policies and works with other programs within EPA and other agencies to control radiation and indoor air pollution exposures; provides technical assistance to states through EPA's regional offices and other agencies having radiation and indoor air protection programs; directs an environmental radiation monitoring program; responds to radiological emergencies; and evaluates and assesses the overall risk and impact of radiation and indoor air pollution. The Office is EPA's lead office for intra- and interagency activities coordinated through the Committee for Indoor Air Quality. It coordinates with and assists the Office of Enforcement in enforcement activities where EPA has jurisdiction. The Office disseminates information and works with state and local governments, industry and professional groups, and citizens to promote actions to reduce exposures to harmful levels of radiation and indoor air pollutants

  1. Use of alumni and employer surveys for internal quality assurance of the DVM program at the University of Montreal.

    Science.gov (United States)

    Doucet, Michèle Y; Vrins, André

    2010-01-01

    Annual alumni and employer surveys, initially designed as outcomes assessment tools, were integrated into a new internal quality assurance strategy to improve the doctor of veterinary medicine program at the University of Montreal's Faculté de Médecine Vétérinaire. Data collected annually from the classes of 2004-2007 indicated that alumni and their employers were generally satisfied with their level of preparation after one year of professional activity. Specific weaknesses were found in non-technical skills such as communication and resource management. These data were used in support of other forms of feedback to guide curricular reform.

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

    International Nuclear Information System (INIS)

    Pickering, S.Y.

    1999-01-01

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

  3. GetData Digitizing Program Code: Description, Testing, Training

    International Nuclear Information System (INIS)

    Taova, S.

    2013-01-01

    90 percents of compilation in our center is obtained by data digitizing. So we are rather interested in the development of different techniques of data digitizing. Plots containing a great amount of points and solid lines are most complicated for digitizing. From our point of view including to the Exfor-Digitizer procedures of automatic or semi-automatic digitizing will allow to simplify significantly this process. We managed to test some free available program codes. Program GETDATA Graph Digitizer (www.getdata- graph-digitizer.com) looks more suitable for our purposes. GetData Graph Digitizer is a program for digitizing graphs, plots and maps. Main features of GetData Graph Digitizer are: - supported graphics formats are TIFF, JPEG, BMP and PCX; - two algorithms for automatic digitizing; - convenient manual digitizing; - reorder tool for easy points reordering; - save/open workspace, which allows to save the work and return to it later; - obtained data can be exported to the clipboard; - export to the formats: TXT (text file), XLS (MS Excel), XML, DXF (AutoCAD) and EPS (PostScript). GetData Graph Digitizer includes two algorithms for automatic digitizing. Auto trace lines: This method is designed to digitize solid lines. Choose the starting point, and the program will trace the line, stopping at it's end. To trace the line use Operations =>Auto trace lines menu or context menu ('Auto trace lines' item). To choose starting point click left mouse button, or click right mouse button to additionally choose direction for line tracing. Digitize area: The second way is to set digitizing area. This method works for any type of lines, including dashed lines. Data points are set at the intersection of grid with the line. You can choose the type of grid (X grid or Y grid), and set the distance between grid lines. You can also make the grid be shifted in such a way, that it will pass through a specific X (or Y) value. To digitize area use Operations →Digitize area menu

  4. Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

    International Nuclear Information System (INIS)

    1988-12-01

    This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

  5. Development of an IMRT quality assurance program using an amorphous silicon electronic portal imaging device

    International Nuclear Information System (INIS)

    Hunt, P.; Oliver, L.; Mallik, A.

    2000-01-01

    Full text: Quality Assurance (QA) for an intensity modulated radiotherapy (IMRT) megavoltage beam is a complex task. The positional accuracy of the MLC; its radiation leakage; the overall distribution of the dose delivered as compared to the treatment plan and; the accuracy of the calculated monitor units to deliver this dose, are all important parameters to clinically monitor. We are presently assessing the Varian version 6 software package with CadPlan, Helios with IMRT and inverse planning, VARiS Vision and the linear accelerator DMLC controller. Whilst conventional QA tools such as ionisation chamber and film measurements are used, these methods are inconvenient for directly monitoring an IMRT patient treatment. Varian Medical Systems has developed an improved electronic portal imaging device (EPID) with an amorphous silicon (a-Si) detector array. The A-Si has a sensitive area of 40x30cm and an improved image resolution of 512x384 pixels. Images are recorded at approximately 7-10 frames per second for an exposure rate of 100-600 MU/minute. Although the A-Si was designed as an EPID for a static treatment field, this new device could be a valuable IMRT QA tool for a range of different tests. Measurements taken on the RNSH and Varian prototype A-Si EPI devices showed a linear dose response for 6-18MeV X-ray energy. In addition to the Varian IAS2 internal software handlers, we have developed some image data handling programs to view and analyse these images in more detail. The software is primarily used to view the images; measure the reading in a region of interest or profile; or merge, overlay, add or subtract images during the analysis. The small pixel resolution provides a reliable, highly accurate means of measuring beam size, leaf position, MLC radiation leakage or profile intensity curves with a positional accuracy of 0.8mm. The images produced by an IMRT exposure is clearly discernible and appears consistent with the result expected. Step wedge images

  6. IMPACT OF IRRADIATION AND THERMAL AGING ON DWPF SIMULATED SLUDGE PROPERTIES

    International Nuclear Information System (INIS)

    Eibling, R; Michael Stone, M

    2006-01-01

    The research and development programs in support of the Defense Waste Processing Facility (DWPF) and other high-level waste vitrification processes require the use of both nonradioactive waste simulants and actual waste samples. While actual waste samples are the ideal materials to study, acquiring large quantities of actual waste is difficult and expensive. Tests utilizing actual high-level waste require the use of expensive shielded cells facilities to provide sufficient shielding for the researchers. Nonradioactive waste simulants have been used for laboratory testing, pilot-scale testing and full-scale integrated facility testing. These waste simulants were designed to reproduce the chemical and, if possible, the physical properties of the actual high-level waste. This technical report documents a study on the impact of irradiating a Sludge Batch 3 (SB3) simulant and of additional tests on aging a SB3 simulant by additional thermal processing. Prior simulant development studies examined methods of producing sludge and supernate simulants and processes that could be used to alter the physical properties of the simulant to more accurately mimic the properties of actual waste. Development of a precipitated sludge simulant for the River Protection Project (RPP) demonstrated that the application of heat for a period of time could significantly alter the rheology of the sludge simulant. The RPP precipitated simulant used distillation to concentrate the sludge solids and produced a reduction in sludge yield stress of up to 80% compared to the initial sludge properties. Observations at that time suggested that a substantial fraction of the iron hydroxide had converted to the oxide during the distillation. DWPF sludge simulant studies showed a much smaller reduction in yield stress (∼10%), demonstrated the impact of shear on particle size, and showed that smaller particle sizes yielded higher yield stress products. The current study documented in this report focuses

  7. Description of the Formerly Utilized Sites Remedial Action Program

    International Nuclear Information System (INIS)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed

  8. Department of Energy WindSentinel Loan Program Description

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sturges, Mark H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-12-01

    The U.S. Department of Energy (DOE) currently owns two AXYS WindSentinel buoys that collect a comprehensive set of meteorological and oceanographic data to support resource characterization for wind energy offshore. The two buoys were delivered to DOE’s Pacific Northwest National Laboratory (PNNL) in September, 2014. After acceptance testing and initial performance testing and evaluation at PNNL’s Marine Sciences Laboratory in Sequim, Washington, the buoys have been deployed off the U.S. East Coast. One buoy was deployed approximately 42 km east of Virginia Beach, Virginia from December, 2014 through June, 2016. The second buoy was deployed approximately 5 km off Atlantic City, New Jersey in November, 2015. Data from the buoys are available to the public. Interested parties can create an account and log in to http://offshoreweb.pnnl.gov. In response to a number of inquiries and unsolicited proposals, DOE’s Wind Energy Technologies Office is implementing a program, to be managed by PNNL, to lend the buoys to qualified parties for the purpose of acquiring wind resource characterization data in areas of interest for offshore wind energy development. This document describes the buoys, the scope of the loans, the process of how borrowers will be selected, and the schedule for implementation of this program, including completing current deployments.

  9. Description of the Formerly Utilized Sites Remedial Action Program

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

  10. A summary description of the flammable gas tank safety program

    International Nuclear Information System (INIS)

    Johnson, G.D.; Sherwood, D.J.

    1994-10-01

    Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks

  11. Poster - 09: A MATLAB-based Program for Automated Quality Assurance of a Prostate Brachytherapy Ultrasound System

    Energy Technology Data Exchange (ETDEWEB)

    Poon, Justin; Sabondjian, Eric; Sankreacha, Raxa [University of British Columbia, Dept. of Physics and Astronomy, Vancouver, BC (Canada); Trillium Health Partners – Credit Valley Hospital, Peel Regional Cancer Centre, Mississauga, ON, Trillium Health Partners – Credit Valley Hospital, Peel Regional Cancer Centre, Mississauga, ON, Trillium Health Partners – Credit Valley Hospital, Peel Regional Cancer Centre, Mississauga, ON (Canada); University of Toronto, Dept. of Radiation Oncology, Toronto, ON (Canada)

    2016-08-15

    Purpose: A robust Quality Assurance (QA) program is essential for prostate brachytherapy ultrasound systems due to the importance of imaging accuracy during treatment and planning. Task Group 128 of the American Association of Physicists in Medicine has recommended a set of QA tests covering grayscale visibility, depth of penetration, axial and lateral resolution, distance measurement, area measurement, volume measurement, and template/electronic grid alignment. Making manual measurements on the ultrasound system can be slow and inaccurate, so a MATLAB program was developed for automation of the described tests. Methods: Test images were acquired using a BK Medical Flex Focus 400 ultrasound scanner and 8848 transducer with the CIRS Brachytherapy QA Phantom – Model 045A. For each test, the program automatically segments the inputted image(s), makes the appropriate measurements, and indicates if the test passed or failed. The program was tested by analyzing two sets of images, where the measurements from the first set were used as baseline values. Results: The program successfully analyzed the images for each test and determined if any action limits were exceeded. All tests passed – the measurements made by the program were consistent and met the requirements outlined by Task Group 128. Conclusions: The MATLAB program we have developed can be used for automated QA of an ultrasound system for prostate brachytherapy. The GUI provides a user-friendly way to analyze images without the need for any manual measurement, potentially removing intra- and inter-user variability for more consistent results.

  12. Poster - 09: A MATLAB-based Program for Automated Quality Assurance of a Prostate Brachytherapy Ultrasound System

    International Nuclear Information System (INIS)

    Poon, Justin; Sabondjian, Eric; Sankreacha, Raxa

    2016-01-01

    Purpose: A robust Quality Assurance (QA) program is essential for prostate brachytherapy ultrasound systems due to the importance of imaging accuracy during treatment and planning. Task Group 128 of the American Association of Physicists in Medicine has recommended a set of QA tests covering grayscale visibility, depth of penetration, axial and lateral resolution, distance measurement, area measurement, volume measurement, and template/electronic grid alignment. Making manual measurements on the ultrasound system can be slow and inaccurate, so a MATLAB program was developed for automation of the described tests. Methods: Test images were acquired using a BK Medical Flex Focus 400 ultrasound scanner and 8848 transducer with the CIRS Brachytherapy QA Phantom – Model 045A. For each test, the program automatically segments the inputted image(s), makes the appropriate measurements, and indicates if the test passed or failed. The program was tested by analyzing two sets of images, where the measurements from the first set were used as baseline values. Results: The program successfully analyzed the images for each test and determined if any action limits were exceeded. All tests passed – the measurements made by the program were consistent and met the requirements outlined by Task Group 128. Conclusions: The MATLAB program we have developed can be used for automated QA of an ultrasound system for prostate brachytherapy. The GUI provides a user-friendly way to analyze images without the need for any manual measurement, potentially removing intra- and inter-user variability for more consistent results.

  13. A Review of Research and Practice on Professional Development School : Quality Assurance regarding to Development of Program for Advanced Teacher Education

    OpenAIRE

    小柳, 和喜雄

    2014-01-01

    Currently, studies have been made on quality assurance regarding to development of program for advanced teacher education, including in-service training and teacher training in Japan. If the enhancement of teaching practical skills training is requested at the graduate level, effective coordination between the local government and schools and universities to be a place for the practice becomes more and more important. In the flow of quality assurance of school education and teacher training, ...

  14. Yield Stress Reduction of DWPF Melter Feed Slurries

    International Nuclear Information System (INIS)

    Stone, M.E.; Smith, M.E.

    2007-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site vitrifies High Level Waste for repository internment. The process consists of three major steps: waste pretreatment, vitrification, and canister decontamination/sealing. The HLW consists of insoluble metal hydroxides and soluble sodium salts. The pretreatment process acidifies the sludge with nitric and formic acids, adds the glass formers as glass frit, then concentrates the resulting slurry to approximately 50 weight percent (wt%) total solids. This slurry is fed to the joule-heated melter where the remaining water is evaporated followed by calcination of the solids and conversion to glass. The Savannah River National Laboratory (SRNL) is currently assisting DWPF efforts to increase throughput of the melter. As part of this effort, SRNL has investigated methods to increase the solids content of the melter feed to reduce the heat load required to complete the evaporation of water and allow more of the energy available to calcine and vitrify the waste. The process equipment in the facility is fixed and cannot process materials with high yield stresses, therefore increasing the solids content will require that the yield stress of the melter feed slurries be reduced. Changing the glass former added during pretreatment from an irregularly shaped glass frit to nearly spherical beads was evaluated. The evaluation required a systems approach which included evaluations of the effectiveness of beads in reducing the melter feed yield stress as well as evaluations of the processing impacts of changing the frit morphology. Processing impacts of beads include changing the settling rate of the glass former (which effects mixing and sampling of the melter feed slurry and the frit addition equipment) as well as impacts on the melt behavior due to decreased surface area of the beads versus frit. Beads were produced from the DWPF process frit by fire polishing. The frit was allowed to free fall through a flame

  15. An anaesthesia information management system as a tool for a quality assurance program: 10years of experience.

    Science.gov (United States)

    Motamed, Cyrus; Bourgain, Jean Louis

    2016-06-01

    Anaesthesia Information Management Systems (AIMS) generate large amounts of data, which might be useful for quality assurance programs. This study was designed to highlight the multiple contributions of our AIMS system in extracting quality indicators over a period of 10years. The study was conducted from 2002 to 2011. Two methods were used to extract anaesthesia indicators: the manual extraction of individual files for monitoring neuromuscular relaxation and structured query language (SQL) extraction for other indicators which were postoperative nausea and vomiting (PONV), pain, sedation scores, pain-related medications, scores and postoperative hypothermia. For each indicator, a program of information/meetings and adaptation/suggestions for operating room and PACU personnel was initiated to improve quality assurance, while data were extracted each year. The study included 77,573 patients. The mean overall completeness of data for the initial years ranged from 55 to 85% and was indicator-dependent, which then improved to 95% completeness for the last 5years. The incidence of neuromuscular monitoring was initially 67% and then increased to 95% (Psystem permitted the follow-up of certain indicators through manual sampling and many more via SQL extraction in a sustained and non-time-consuming way across years. However, it requires competent and especially dedicated resources to handle the database. Copyright © 2016 Société française d'anesthésie et de réanimation (Sfar). Published by Elsevier Masson SAS. All rights reserved.

  16. 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

  17. Quality assurance in radiodiagnosis

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  18. DWPF SB6 Initial CPC Flowsheet Testing SB6-1 TO SB6-4L Tests Of SB6-A And SB6-B Simulants

    International Nuclear Information System (INIS)

    Lambert, D.; Pickenheim, B.; Best, D.

    2009-01-01

    The Defense Waste Processing Facility (DWPF) will transition from Sludge Batch 5 (SB5) processing to Sludge Batch 6 (SB6) processing in late fiscal year 2010. Tests were conducted using non-radioactive simulants of the expected SB6 composition to determine the impact of varying the acid stoichiometry during the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) processes. The work was conducted to meet the Technical Task Request (TTR) HLW/DWPF/TTR-2008-0043, Rev.0 and followed the guidelines of a Task Technical and Quality Assurance Plan (TT and QAP). The flowsheet studies are performed to evaluate the potential chemical processing issues, hydrogen generation rates, and process slurry rheological properties as a function of acid stoichiometry. These studies were conducted with the estimated SB6 composition at the time of the study. This composition assumed a blend of 101,085 kg of Tank 4 insoluble solids and 179,000 kg of Tank 12 insoluble solids. The current plans are to subject Tank 12 sludge to aluminum dissolution. Liquid Waste Operations assumed that 75% of the aluminum would be dissolved during this process. After dissolution and blending of Tank 4 sludge slurry, plans included washing the contents of Tank 51 to ∼1M Na. After the completion of washing, the plan assumes that 40 inches on Tank 40 slurry would remain for blending with the qualified SB6 material. There are several parameters that are noteworthy concerning SB6 sludge: (1) This is the second batch DWPF will be processing that contains sludge that has had a significant fraction of aluminum removed through aluminum dissolution; (2) The sludge is high in mercury, but the projected concentration is lower than SB5; (3) The sludge is high in noble metals, but the projected concentrations are lower than SB5; and(4) The sludge is high in U and Pu - components that are not added in sludge simulants. Six DWPF process simulations were completed in 4-L laboratory-scale equipment using

  19. 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

  20. 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

  1. Quality assurance program on the individual monitory service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil): preliminary results

    International Nuclear Information System (INIS)

    Antonino, Paulo H.D.; Filho, Joao A.; Silveira, Sueldo V.

    1996-01-01

    The current stage of the quality assurance program on the individual monitoring service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil) is presented. The program emphasizes the personnel training and its development is focused to meet national and international standards requirements

  2. 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

  3. Methodology for establishing of a control and assurance program on a Radiology Department of a university hospital

    International Nuclear Information System (INIS)

    Almeida, Carlos Domingues de; Almeida, Carlos Eduardo de

    1995-01-01

    The purpose of this work is to present a proposal of a quality assurance program developed for a typical diagnostic radiology department of a University Hospital. The aim of this program is to reduce the number of films lost due to several kinds of problems, equipment malfunction, incorrect selection of the physical parameters of the X-ray equipment, poor conditions of the film ecrans and chassis, excessive temperature fluctuations on the processor, personnel training and organizational related aspects. The preliminary results shows that the main causes of problems are film overexposure, film under exposure, unexposed films taken back to the dark room, inadequate positioning of the film in the couch, inadequate positioning of the patient and the X-ray processor in addition to others of minor importance. It is very important to emphasize that the data acquisition methodology must contemplate a professional posture of respect for those involved in the procedures and as result of this one would expect their active participation in the program. As result of the first year of study, this program has demonstrated that the annual losses in the department studied are over US$ 125.000,00 and the goal of this program now is to reduce this figure to an acceptable number, US$40.000,00 a reasonable value for a large diagnostic radiology facility. (author). 6 refs., 4 figs

  4. [Implementation of quality assurance program ISO 9001 in a department of paediatric oncology].

    Science.gov (United States)

    Kanold, J; Halle, P; Paillard, C; Merlin, E; David, A; Levallois, S; Roudeix, D; Dugué, F; Lacaze, C; Morisset, C; Souquiere, V; Deméocq, F

    2008-02-01

    Our objective was to improve the organization and management of care facilities for children suffering from cancer or leukaemia and to be aligned with the legislation in force in France. Our report is on the successive steps for the implementation of a quality assurance system, methods used, motivations, cost, difficulties encountered as well as the advantages obtained. In the Regional Centre for Paediatric Oncology (CRCP) at the CHU in Clermont-Ferrand, we launched a quality programme based on ISO9001/2000 standards. The implementation of the quality assurance system was conducted as a research project and an established medical project with the support of the Management Team. The mission was divided into several "processes", an approach consisting of considering the clinical service in terms of flow and successions of transformations (reception, care, support, accompaniment, etc.) which produce added-value (services and products adapted to the needs of the "customers": children, families, correspondents). We singled out ten physical processes or "job specializations" such as "diagnosis", "care" or "project for the child". The cartography which is the systematic representation of the processes and the interactions between them made it possible to draw up a global vision of the CRCP "care" activity. The ISO9001/2000 standard is a tool designed to help organization and management. The benefit obtained in implementing it in a clinic was perceived in organisational terms and lead to a true team spirit, a standardization of the professional practices and the enhancement of the role of each person. The advantages appear at three levels: the child and his/her family, the medical and paramedical teams, and the administrative supervisory bodies.

  5. Quality assurance

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  6. Durability of glasses from the Hg-doped Integrated DWPF Melter System (IDMS) campaign

    International Nuclear Information System (INIS)

    Jantzen, C.M.

    1992-01-01

    The Integrated DWPF Melter System (IDMS) for the vitrification of high-level radioactive wastes is designed and constructed to be a 1/9th scale prototype of the full scale Defense Waste Processing Facility (DWPF) melter. The IDMS facility is the first engineering scale melter system capable of processing mercury, and flowsheet levels of halides and noble metals. In order to determine the effects of mercury on the feed preparation process, the off-gas chemistry, glass melting behavior, and glass durability, a three-run mercury (Hg) campaign was conducted. The glasses produced during the Hg campaign were composed of Batch 1 sludge, simulated precipitate hydrolysis aqueous product (PHA) from the Precipitate Hydrolysis Experimental Facility (PHEF), and Frit 202. The glasses were produced using the DWPF process/product models for glass durability, viscosity, and liquidus. The durability model indicated that the glasses would all be more durable than the glass qualified in the DWPF Environmental Assessment (EA). The glass quality was verified by performing the Product Consistency Test (PCT) which was designed for glass durability testing in the DWPF

  7. The DWPF: Results of full scale qualification runs leading to radioactive operations

    International Nuclear Information System (INIS)

    Marra, S.L.; Elder, H.H.; Occhipinti, J.H.; Snyder, D.E.

    1996-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC will immobilize high-level radioactive liquid waste, currently stored in underground carbon steel tanks, in borosilicate glass. The radioactive waste is transferred to the DWPF in two forms: precipitate slurry and sludge slurry. The radioactive waste is pretreated and then combined with a borosilicate glass frit in the DWPF. This homogeneous slurry is fed to a Joule-heated melter which operates at approximately 1150 degrees C. The glass is poured into stainless steel canisters for eventual disposal in a geologic repository. The DWPF product (i.e. the canistered waste form) must comply with the Waste Acceptance Product Specifications (WAPS) in order to be acceptable for disposal. The DWPF has completed Waste Qualification Runs which demonstrate the facility's ability to comply with the waste acceptance specifications. During the Waste Qualification Runs seventy-one canisters of simulated waste glass were produced in preparation for Radioactive Operations. These canisters of simulated waste glass were produced during five production campaigns which also exercised the facility prior to beginning Radioactive Operations. The results of the Waste Qualification Runs are presented

  8. [Impact of a quality assurance program on the use of neuromuscular monitoring and reversal of muscle relaxants].

    Science.gov (United States)

    Motamed, C; Bourgain, J-L

    2009-04-01

    As part of a quality assurance in the anaesthesia department, this study was designed to enhance the rate of neuromuscular blockade monitoring for patients receiving muscle relaxant during anaesthesia. After approval of our local ethical committee, we assessed 200 computerized anaesthesia records in which neuromuscular relaxants were used. The following data were collected: demographic characteristics, durations of anaesthesia and surgery, use of neuromuscular monitoring, reversal agents and the quality of neuromuscular monitoring. The results were discussed with all anaesthesia providers of the department and an internal guideline was elaborated with the endpoint that all patients having muscle relaxants should have quantitative neuromuscular monitoring. Six months later, another assessment of 200 consecutive records collected the same data to check the efficiency of the elaborated guideline. The monitoring rate was of 67% at the first assessment and increased to 94% (passessment and was stable at the second assessment (50%). The rate of patients not monitored and not reversed decreased from 5 to 2% (pquality assurance program systematic quantitative monitoring of neuromuscular blockade can be significantly increased.

  9. Description of a program for steam generators; Descripcion de un programa de generadores de vapor

    Energy Technology Data Exchange (ETDEWEB)

    Campana, F. J.

    2014-10-01

    Steam Generators (SGs) are a key component of PWR nuclear power plants, maintaining their structural integrity throughout their life time is necessary to allow for long term operation (LTD) of PWR plants. NEI 97-06 provides the fundamental elements to be included in a SG Program. In addiction it describes performance criteria that SG tubes have to meet in order to provide reasonable assurance that the tubes are still able to maintain specific safety function. Hence, it is mandatory for plants with SGs to have defined a SG program consistent with NEI 97-06 and contains the elements which are described by it. This Program must contain some elements such as, Degradation Assessment, inspection and Integrity Assessment, among other. (Author)

  10. Directory of certificates of compliance for radioactive materials packages. Volume 3, Revision 14: Report of NRC approved quality assurance programs for radioactive materials packages

    International Nuclear Information System (INIS)

    1994-10-01

    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

  11. Hanford Tanks Initiative quality assurance implementation plan

    International Nuclear Information System (INIS)

    Huston, J.J.

    1998-01-01

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

  12. Dissolution rates of DWPF glasses from long-term PCT

    International Nuclear Information System (INIS)

    Ebert, W.L.; Tam, S.W.

    1996-01-01

    We have characterized the corrosion behavior of several Defense Waste Processing Facility (DWPF) reference waste glasses by conducting static dissolution tests with crushed glasses. Glass dissolution rates were calculated from measured B concentrations in tests conducted for up to five years. The dissolution rates of all glasses increased significantly after certain alteration phases precipitated. Calculation of the dissolution rates was complicated by the decrease in the available surface area as the glass dissolves. We took the loss of surface area into account by modeling the particles to be spheres, then extracting from the short-term test results the dissolution rate corresponding to a linear decrease in the radius of spherical particles. The measured extent of dissolution in tests conducted for longer times was less than predicted with this linear dissolution model. This indicates that advanced stages of corrosion are affected by another process besides dissolution, which we believe to be associated with a decrease in the precipitation rate of the alteration phases. These results show that the dissolution rate measured soon after the formation of certain alteration phases provides an upper limit for the long-term dissolution rate, and can be used to determine a bounding value for the source term for radionuclide release from waste glasses. The long-term dissolution rates measured in tests at 20,000 per m at 90 degrees C in tuff groundwater at pH values near 12 for the Environmental Assessment glass and glasses made with SRL 131 and SRL 202 frits, respectively

  13. Erosion Modeling Analysis For Modified DWPF SME Tank

    International Nuclear Information System (INIS)

    LEE, SI

    2004-01-01

    In support of an erosion evaluation for the modified cooling coil guide and its supporting structure in the DWPF SME vessel, a computational model was developed to identify potential sites of high erosion using the same methodology established by previous work. The erosion mechanism identified in the previous work was applied to the evaluation of high erosion locations representative of the actual flow process in the modified coil guide of the SME vessel, abrasive erosion which occurs by high wall shear of viscous liquid. The results show that primary locations of the highest erosion due to the abrasive wall erosion are at the leading edge of the guide, external surface of the insert plate, the tank floor next to the insert plate of the coil guide support, and the upstream lead-in plate. The present modeling results show a good comparison between the original and the modified cases in terms of high erosion sites, as well as the degree of erosion and the calculated shear stress. Wall she ar of the tank floor is reduced by about 30 per cent because of the new coil support plate. Calculations for the impeller speed lower than 103 rpm in the SME showed similar erosion patterns but significantly reduced wall shear stresses and reduced overall erosion. Comparisons of the 103 rpm results with SME measurements indicated that no significant erosion of the tank floor in the SME is to be expected. Thus, it is recommended that the agitator speed of SME does not exceed 103 rpm

  14. Preliminary Analysis of Species Partitioning in the DWPF Melter

    Energy Technology Data Exchange (ETDEWEB)

    Choi, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kesterson, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Johnson, F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-07-15

    The work described in this report is preliminary in nature since its goal was to demonstrate the feasibility of estimating the off-gas entrainment rates from the Defense Waste Processing Facility (DWPF) melter based on a simple mass balance using measured feed and glass pour stream compositions and timeaveraged melter operating data over the duration of one canister-filling cycle. The only case considered in this study involved the SB6 pour stream sample taken while Canister #3472 was being filled over a 20-hour period on 12/20/2010, approximately three months after the bubblers were installed. The analytical results for that pour stream sample provided the necessary glass composition data for the mass balance calculations. To estimate the “matching” feed composition, which is not necessarily the same as that of the Melter Feed Tank (MFT) batch being fed at the time of pour stream sampling, a mixing model was developed involving three preceding MFT batches as well as the one being fed at that time based on the assumption of perfect mixing in the glass pool but with an induction period to account for the process delays involved in the calcination/fusion step in the cold cap and the melter turnover.

  15. Remote process cell mercury transfer pumps for DWPF

    International Nuclear Information System (INIS)

    Nielsen, M.G.; Vaughn, V.G.

    1986-01-01

    Final design and the results of the testing performed thus far show that the water displacement of mercury to a height of 40 feet is feasible with just 6 gallons of motive water. Control of the transfer is achieved by monitoring the pump discharge pressure. An air actuated plug valve configuration successfully contained the required discharge pressure of 260 psi. The requirements of low flow and maximum separation of mercury from particulates are achieved due to the configuration of the pressure canister. The pump is capable of transferring a discrete amount of mercury with little additional slurry particulates. The success of this new pumping configuration is highlighted by the fact that it was the inspiration for other remote transfer applications tested at SRP. These application include the dual canister sample pump shown in Figure 7, as well as a successful prototype pump designed at Pacific Northwest Laboratories (PNL). The PNL pump was designed for the purpose of metering waste slurries to an electric melter. Upon completion of final pump fabrication, the Defense Waste Processing facility (DWPF) facility will have a simple and highly reliable method of remotely transferring small discrete batches of mercury as required from radioactive process vessels. 3 refs., 7 figs., 1 tab

  16. FURNACE; a toroidal geometry neutronic program system method description and users manual

    International Nuclear Information System (INIS)

    Verschuur, K.A.

    1984-12-01

    The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor-design purposes, at acceptable calculational costs. A short description is given of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER is presented

  17. 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...

  18. Quality Assurance Program: Argonne peer review activities for the salt host-rock portion of the Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    Edgar, D.E.

    1986-01-01

    This Quality Assurance (QA) Program sets forth the methods, controls, and procedures used to ensure that the results of Argonne National Laboratory's peer review activities are consistently of the highest quality and responsive to Salt Repository Project Office's needs and directives. Implementation of the QA procedures described herein establishes an operational framework so that task activities are traceable and the activities and decisions that influence the overall quality of the peer review process and results are fully documented. 56 refs., 5 figs., 6 tabs

  19. A quality assurance program for environmental data operations involving waste management processes

    International Nuclear Information System (INIS)

    Johnson, G.L.; Blacker, S.M.

    1990-01-01

    This paper describes the 'core' elements needed in an effective Quality Program for environmental data operations involving nuclear, mixed, or non-nuclear wastes. For each core element, this paper examines the minimum components needed for an effective Quality Program for EDOs, and compares approaches to Quality Programs currently required by the U.S. DOE and the U.S. EPA. The comparison suggests how the Quality Program requirements used at DOE, and defined by NQA-1 and its supplements, and those used by EPA through its QAMS program guidance, may provide a basis for developing a harmonized Quality Program for EDOs involving any waste management processes, nuclear, non-nuclear, or mixed. (orig./DG)

  20. Need of patient-specific quality assurance and pre-treatment verification program for special plans in radiotherapy

    International Nuclear Information System (INIS)

    Ravichandran, Ramamoorthy; Bhasi, Saju; Binukumar, J.P.; Davis, C.A.

    2011-01-01

    Accuracy in planned radiation dose delivery in cancer treatments becomes necessary in the advent of complex treatment delivery options with newer technology using medical linear accelerators, which makes patient management very crucial. Treatment outcome in an individual patient therefore depends on the professional involvement of staff and execution accuracy of planned procedure. Therefore, this article has addressed an important problem. International Atomic Energy Agency (IAEA) and International Commission on Radiological Protection (ICRP) reported mis-administrations of radiation dose, the nature of their occurrence and complexity of situations. Lack of adequate quality assurance (QA) program or failure in their routine applications, complacency in attention, lack of knowledge, overconfidence, pressures of time, lack of resources and failures in communication are some of the general human causes of errors. A recent report enumerated misadministration of radiation doses under the heading 'harming instead of healing' delivery of wrong doses in small field treatment plans with stereotactic equipment' was mostly highlighted

  1. Analysis of high-level radioactive slurries as a method to reduce DWPF turnaround times

    International Nuclear Information System (INIS)

    Coleman, C.J.; Bibler, N.E.; Ferrara, D.M.; Hay, M.S.

    1996-01-01

    Analysis of Defense Waste Processing Facility (DWPF) samples as slurries rather than as dried or vitrified samples is an effective way to reduce sample turnaround times. Slurries can be dissolved with a mixture of concentrated acids to yield solutions for elemental analysis by inductively coupled plasma-atomic emission spectroscopy (ICP-AES). Slurry analyses can be performed in eight hours, whereas analyses of vitrified samples require up to 40 hours to complete. Analyses of melter feed samples consisting of the DWPF borosilicate frit and either simulated or actual DWPF radioactive sludge were typically within a range of 3--5% of the predicted value based on the relative amounts of sludge and frit added to the slurry. The results indicate that the slurry analysis approach yields analytical accuracy and precision competitive with those obtained from analyses of vitrified samples. Slurry analyses offer a viable alternative to analyses of solid samples as a simple way to reduce analytical turnaround times

  2. Fabrication of remote steam atomized scrubbers for DWPF off-gas system

    International Nuclear Information System (INIS)

    Nielsen, M.G.; Lafferty, J.D.

    1988-01-01

    The defense waste processing facility (DWPF) is being constructed for the purpose of processing high-level waste from sludge to a vitrified borosilicate glass. In the operation of continuous slurry-fed melters, off-gas aerosols are created by entrainment of feed slurries and the vaporization of volatile species from the molten glass mixture. It is necessary to decontaminate these aerosols in order to minimize discharge of airborne radionuclide particulates. A steam atomized scrubber (SAS) has been developed for DWPF which utilizes a patented hydro- sonic system gas scrubbing method. The Hydro-Sonic System utilizes a steam aspirating-type venturi scrubber that requires very precise fabrication tolerances in order to obtain acceptable decontamination factors. In addition to the process-related tolerances, precision mounting and nozzle tolerances are required for remote service at DWPF

  3. Preliminary analysis of species partitioning in the DWPF melter. Sludge batch 7A

    Energy Technology Data Exchange (ETDEWEB)

    Choi, A. S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith III, F. G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-01-01

    The work described in this report is preliminary in nature since its goal was to demonstrate the feasibility of estimating the off-gas carryover from the Defense Waste Processing Facility (DWPF) melter based on a simple mass balance using measured feed and glass pour stream (PS) compositions and time-averaged melter operating data over the duration of one canister-filling cycle. The DWPF has been in radioactive operation for over 20 years processing a wide range of high-level waste (HLW) feed compositions under varying conditions such as bubbled vs. non-bubbled and feeding vs. idling. So it is desirable to find out how the varying feed compositions and operating parameters would have impacted the off-gas entrainment. However, the DWPF melter is not equipped with off-gas sampling or monitoring capabilities, so it is not feasible to measure off-gas entrainment rates directly. The proposed method provides an indirect way of doing so.

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  5. ELESTRES.M11K program users'manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-12-01

    ELESTRES.M11K is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computers the one-dimensional temperature distribution and thermal expansion of the fuel pellets, and computes two-dimensional pellet deformation using FEM. The amount of fission gas released and sheath strain/stress are also computed. This document is intended as a users' manual and description for ELESTRES.M11K program. (Author)

  6. US Department of Energy, Richland Operations Office Integrated Safety Management System Program Description

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    2000-01-01

    The purpose of this Integrated Safety Management System (ISMS) Program Description (PD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This PD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this PD contains some information on contractor processes and procedures which then require RL approval or oversight

  7. Mathematical description and program documentation for CLASSY, an adaptive maximum likelihood clustering method

    Science.gov (United States)

    Lennington, R. K.; Rassbach, M. E.

    1979-01-01

    Discussed in this report is the clustering algorithm CLASSY, including detailed descriptions of its general structure and mathematical background and of the various major subroutines. The report provides a development of the logic and equations used with specific reference to program variables. Some comments on timing and proposed optimization techniques are included.

  8. 78 FR 40421 - Inquiry Regarding Video Description in Video Programming Distributed on Television and on the...

    Science.gov (United States)

    2013-07-05

    ... description services for television are provided on a secondary audio stream, and typically a consumer can... box. The Commission recently adopted rules requiring apparatus that is designed to receive, play back, or record video programming transmitted simultaneously with sound to make secondary audio streams...

  9. Windows Calorimeter Control (WinCal) program computer software design description

    International Nuclear Information System (INIS)

    Pertzborn, N.F.

    1997-01-01

    The Windows Calorimeter Control (WinCal) Program System Design Description contains a discussion of the design details for the WinCal product. Information in this document will assist a developer in maintaining the WinCal system. The content of this document follows the guidance in WHC-CM-3-10, Software Engineering Standards, Standard for Software User Documentation

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-06-15

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  12. Quality assurance for geologic investigations

    International Nuclear Information System (INIS)

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

    1983-01-01

    A quality assurance handbook was written to provide guidance in the application of quality assurance to geologic work activities associated with the National Waste Terminal Storage (NWTS) Program. It is intended to help geoscientists and NWTS program managers in applying quality assurance to their work 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

  13. 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

  14. Assessment of combustion and related issues in the DWPF and ITP waste tanks

    International Nuclear Information System (INIS)

    Ginsberg, T.

    1994-04-01

    This report presents a review of the safety analyses described in the DWPF Safety Analysis Report, the combustion analysis of the ITP Tanks 48 and 49, and presents conclusions drawn from interviews staff on issues related to accident analysis, in particular on issues related to combustion phenomena. The major objectives of this report are to clarify the issues related to the modes of combustion and expected loads on process vessels and structures and, in addition, to offer recommendations which would improve the defense-in-depth posture of the DWPF

  15. Material compatibility evaluation for DWPF nitric-glycolic acid-literature review

    Energy Technology Data Exchange (ETDEWEB)

    Mickalonis, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Skidmore, E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2013-06-01

    Glycolic acid is being evaluated as an alternative for formic and nitric acid in the DWPF flowsheet. Demonstration testing and modeling for this new flowsheet has shown that glycolic acid and glycolate has a potential to remain in certain streams generated during the production of the nuclear waste glass. A literature review was conducted to assess the impact of glycolic acid on the corrosion of the materials of construction for the DWPF facility as well as facilities downstream which may have residual glycolic acid and glycolates present. The literature data was limited to solutions containing principally glycolic acid.

  16. Discrete event simulation of the Defense Waste Processing Facility (DWPF) analytical laboratory

    International Nuclear Information System (INIS)

    Shanahan, K.L.

    1992-02-01

    A discrete event simulation of the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) analytical laboratory has been constructed in the GPSS language. It was used to estimate laboratory analysis times at process analytical hold points and to study the effect of sample number on those times. Typical results are presented for three different simultaneous representing increasing levels of complexity, and for different sampling schemes. Example equipment utilization time plots are also included. SRS DWPF laboratory management and chemists found the simulations very useful for resource and schedule planning

  17. 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

  18. Implementation of Good Clinical Laboratory Practice (GCLP) guidelines within the External Quality Assurance Program Oversight Laboratory (EQAPOL).

    Science.gov (United States)

    Todd, Christopher A; Sanchez, Ana M; Garcia, Ambrosia; Denny, Thomas N; Sarzotti-Kelsoe, Marcella

    2014-07-01

    The EQAPOL contract was awarded to Duke University to develop and manage global proficiency testing programs for flow cytometry-, ELISpot-, and Luminex bead-based assays (cytokine analytes), as well as create a genetically diverse panel of HIV-1 viral cultures to be made available to National Institutes of Health (NIH) researchers. As a part of this contract, EQAPOL was required to operate under Good Clinical Laboratory Practices (GCLP) that are traditionally used for laboratories conducting endpoint assays for human clinical trials. EQAPOL adapted these guidelines to the management of proficiency testing programs while simultaneously incorporating aspects of ISO/IEC 17043 which are specifically designed for external proficiency management. Over the first two years of the contract, the EQAPOL Oversight Laboratories received training, developed standard operating procedures and quality management practices, implemented strict quality control procedures for equipment, reagents, and documentation, and received audits from the EQAPOL Central Quality Assurance Unit. GCLP programs, such as EQAPOL, strengthen a laboratory's ability to perform critical assays and provide quality assessments of future potential vaccines. © 2013.

  19. Implementation of the first worldwide quality assurance program for cystic fibrosis multiple mutation detection in population-based screening.

    Science.gov (United States)

    Earley, Marie C; Laxova, Anita; Farrell, Philip M; Driscoll-Dunn, Rena; Cordovado, Suzanne; Mogayzel, Peter J; Konstan, Michael W; Hannon, W Harry

    2011-07-15

    CDC's Newborn Screening Quality Assurance Program collaborated with several U.S. Cystic Fibrosis Care Centers to collect specimens for development of a molecular CFTR proficiency testing program using dried-blood spots for newborn screening laboratories. Adult and adolescent patients or carriers donated whole blood that was aliquoted onto filter paper cards. Five blind-coded specimens were sent to participating newborn screening laboratories quarterly. Proficiency testing results were evaluated based on presumptive clinical assessment. Individual evaluations and summary reports were sent to each participating laboratory and technical consultations were offered if incorrect assessments were reported. The current CDC repository contains specimens with 39 different CFTR mutations. Up to 45 laboratories have participated in the program. Three years of data showed that correct assessments were reported 97.7% of the time overall when both mutations could be determined. Incorrect assessments that could have lead to a missed case occurred 0.9% of the time, and no information was reported 1.1% of the time due to sample failure. Results show that laboratories using molecular assays to detect CFTR mutations are performing satisfactorily. The programmatic results presented demonstrate the importance and complexity of providing proficiency testing for DNA-based assays. Published by Elsevier B.V.

  20. Loch Vale Watershed Long-Term Ecological Research and Monitoring Program: Quality Assurance Report, 2003-09

    Science.gov (United States)

    Richer, Eric E.; Baron, Jill S.

    2011-01-01

    The Loch Vale watershed project is a long-term research and monitoring program located in Rocky Mountain National Park that addresses watershed-scale ecosystem processes, particularly as they respond to atmospheric deposition and climate variability. Measurements of precipitation depth, precipitation chemistry, discharge, and surface-water quality are made within the watershed and elsewhere in Rocky Mountain National Park. As data collected for the program are used by resource managers, scientists, policy makers, and students, it is important that all data collected in Loch Vale watershed meet high standards of quality. In this report, data quality was evaluated for precipitation, discharge, and surface-water chemistry measurements collected during 2003-09. Equipment upgrades were made at the Loch Vale National Atmospheric Deposition Program monitoring site to improve precipitation measurements and evaluate variability in precipitation depth and chemistry. Additional solar panels and batteries have been installed to improve the power supply, and data completeness, at the NADP site. As a result of equipment malfunction, discharge data for the Loch Outlet were estimated from October 18, 2005, to August 17, 2006. Quality-assurance results indicate that more than 98 percent of all surface-water chemistry measurements were accurate and precise. Records that did not meet quality criteria were removed from the database. Measurements of precipitation depth, precipitation chemistry, discharge, and surface-water quality were all sufficiently complete and consistent to support project data needs.