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Acceptance sampling plans

Description: A compilation is presented of attributes and variables acceptance sampling plans and procedures which may be used as a ready reference to provide protection to both supplier and purchaser whenever sampling inspection is involved. Some of the basic and underlying principles involved in these plans and procedures are discussed. The plans and procedures provide for selection of adequate sample quantities and evaluation of inspection data for the purpose of determining conformance to the specified lot tolerance percent defective (LTPD) and BETA error acceptance criteria. (auth)
Date: November 1, 1973
Partner: UNT Libraries Government Documents Department

Evaluation of the computer program CREEP--PLAST (CDC version)

Description: From ASME annual winter meeting; Detroit, Michigan, USA (Dec 1973). The results of an evaluation of the CREEP-PLAST Program are reported. The assumptions in the formulation of the Program are reviewed. Program operations and user oriented features that were added to the Program are discussed. Selected benchmark problems are then solved and the results are compared with known solutions. (10 references) (auth)
Date: January 1, 1973
Creator: Hsu, M.B.; Berman, I. & Pai, D.H.
Partner: UNT Libraries Government Documents Department

An Assessment of Visual Testing

Description: In response to increasing interest from nuclear utilities in replacing some volumetric examinations of nuclear reactor components with remote visual testing, the Pacific Northwest National Laboratory has examined the capabilities of remote visual testing for the Nuclear Regulatory Commission. This report describes visual testing and explores the visual acuities of the camera systems used to examine nuclear reactor components. The types and sizes of cracks typically found in nuclear reactor components are reviewed. The current standards in visual testing are examined critically, and several suggestions for improving these standards are proposed. Also proposed for future work is a round robin test to determine the effectiveness of visual tests and experimental studies to determine the values for magnification and resolution needed to reliably image very tight cracks.
Date: November 1, 2004
Creator: Cumblidge, Stephen E.; Anderson, Michael T. & Doctor, Steven R.
Partner: UNT Libraries Government Documents Department

Preparation of system design descriptions

Description: A standard is presented which prescribes the purpose, scope, organization, and content of system design descriptions (SSD's), in order to promulgate a unified approach to their preparation and use by a project as the principal means to establish, describe, and control the individual system designs from conception and throughout the lifetime of the system. SDD's are comprehensive technical documents that specifically and completely define the design, including operation, maintenance, and reliability requirements, of individual systems which comprise a nuclear power plant or test facility. SDD's are prepared and maintained current by the responsible system designer and are the principal means of system design definition and control common to the designer and the other participating organizations responsible for the project. (auth)
Date: December 1, 1975
Partner: UNT Libraries Government Documents Department

Transportation of critical components and equipment

Description: A standard is presented which covers recommended practices in the planning, coordination, and administration of shipments of critical components and equipment for nuclear facilities. The standard supplements and is additive to the rules and regulations of freight classifications and tariffs governing carriers and shipping, and has the purpose of minimizing the liklihood of physical damage or deterioration of critical components and equipment due to collision, upset, shock, vibration, corrosion, or other conditions of the transport environment. (auth)
Date: January 1, 1976
Partner: UNT Libraries Government Documents Department

In-place HEPA filter penetration test

Description: We have demonstrated the feasibility of conducting penetration tests on high efficiency particulate air (HEPA) filters as installed in nuclear ventilation systems. The in-place penetration test, which is designed to yield equivalent penetration measurements as the standard DOP efficiency test, is based on measuring the aerosol penetration of the filter installation as a function of particle size using a portable laser particle counter. This in-place penetration test is compared to the current in-place leak test using light scattering photometers for single HEPA filter installations and for HEPA filter plenums using the shroud method. Test results show the in-place penetration test is more sensitive than the in-place leak test, has a similar operating procedure, but takes longer to conduct. Additional tests are required to confirm that the in-place penetration test yields identical results as the standard dioctyl phthalate (DOP) penetration test for HEPA filters with controlled leaks in the filter and gasket and duct by-pass leaks. Further development of the procedure is also required to reduce the test time before the in- place penetration test is practical.
Date: January 1, 1997
Creator: Bergman, W.; Wilson, kK.; Elliott, J.; Bettencourt, B. & Slawski, J.W.
Partner: UNT Libraries Government Documents Department

Plant maintenance and aging management: Are they the same?

Description: As part of the NRC`s Nuclear Plant Aging Research Program, a number of aging studies were performed on safety-related systems and components which found that, even with current maintenance and monitoring practices in place, a large number of the reported failures are related to aging. This suggests that current practices are not sufficient to completely manage aging degradation, and other factors need to be considered. This paper examines the aging management process and the degree to which maintenance plays a part in it. Component failures and degradation mechanisms identified in aging studies of several different safety systems are summarized and evaluated, then con-elated with the components most frequently failed. This information, along with an analysis of failure causes, is then used to determine the extent to which aging is managed by current maintenance practices. Conclusions and recommendations for proper aging management arc also presented.
Date: June 1, 1995
Creator: Lofaro, R.J.
Partner: UNT Libraries Government Documents Department