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NRC plan for cleanup operations at Three Mile Island Unit 2

Description: This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup … more
Date: February 1, 1982
Creator: Lo, R. & Snyder, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DOE role in nuclear policies and programs: official transcript of public briefing. Addendum December 13, 1977, Washington, D. C

Description: A total of 24 questions were read into the official record at the public briefing on nuclear policies and programs. The answers published were researched and written by personnel of DOE's Office of Energy Research, Office of Energy Technology, and the Secretary's Office. A few questions were sent to the Nuclear Regulatory Commission for review and for preparation of answers.
Date: February 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of soil damping techniques used in soil structure interaction analysis of a nuclear power plant

Description: A prediction of dynamic soil properties at the site of a nuclear power plant plays a very important role in the seismic analysis of the facility. Conventional modal analysis procedures can accommodate virtually any range of equivalent elastic soil stiffness which is used to characterize the site. However, high radiation damping associated with energy dissipation in the soil half-space is difficult to accommodate in an elastic modal solution to the dynamic problem. Several methods are available … more
Date: February 24, 1982
Creator: Nelson, T.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Characterization of nuclear reactor containment penetrations. Final report

Description: This report concludes a preliminary report prepared by ANL for Sandia, published as NUREG/CR-3855, in June 1984. The preliminary report, NUREG/CR-3855, presented the results of a survey of nuclear reactor containment penetrations, covering the number of plants surveyed at that time (22 total). Since that time, an additional 26 plants have been included in the survey. This final report serves two purposes: (1) to add the summary data sheets and penetration details for the additional plants now i… more
Date: February 1, 1985
Creator: Shackelford, M. H.; Bump, T. R. & Seidensticker, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some fundamental aspects of fault-tree and digraph-matrix relationships for a systems-interaction evaluation procedure

Description: Recent events, such as Three Mile Island-2, Brown's Ferry-3, and Crystal River-3, have demonstrated that complex accidents can occur as a result of dependent (common-cause/mode) failures. These events are now being called Systems Interactions. A procedure for the identification and evaluation of Systems Interactions is being developed by the NRC. Several national laboratories and utilities have contributed preliminary procedures. As a result, there are several important views of the Systems Int… more
Date: February 28, 1982
Creator: Alesso, H.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of nuclear ownership on utility bond ratings and yields

Description: The major objective of this study was to test the hypothesis that investors have required an additional interest rate premium before purchasing bonds of utilities with large investments in nuclear facilities. The study required several tasks. First, the literature relating to firm bankruptcy and default was reviewed. Second, the failing financial health of the electric utility industry was assessed in terms of construction problems, the impact of federal and state regulations, and the impact of… more
Date: February 1, 1982
Creator: Nesse, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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POPCYCLE: a computer code for calculating nuclear and fossil plant levelized life-cycle power costs

Description: POPCYCLE, a computer code designed to calculate levelized life-cycle power costs for nuclear and fossil electrical generating plants is described. Included are (1) derivations of the equations and a discussion of the methodology used by POPCYCLE, (2) a description of the input required by the code, (3) a listing of the input for a sample case, and (4) the output for a sample case.
Date: February 1, 1982
Creator: Hardie, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

Description: This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and … more
Date: February 14, 2008
Creator: O'Hara, John; Higgins, James C.; Brown, William S. & Fink, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Primer on Durability of Nuclear Power Plant Reinforced Concrete Structures - A Review of Pertinent Factors

Description: The objective of this study was to provide a primer on the environmental effects that can affect the durability of nuclear power plant concrete structures. As concrete ages, changes in its properties will occur as a result of continuing microstructural changes (i.e., slow hydration, crystallization of amorphous constituents, and reactions between cement paste and aggregates), as well as environmental influences. These changes do not have to be detrimental to the point that concrete will not be … more
Date: February 1, 2007
Creator: Naus, Dan J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Load rating and design criteria for pipe snubbers with extension struts

Description: Snubbing devices are used extensively in nuclear power plant piping to prevent seismic shock forces from causing damaging pipe motions. Most seismic snubbers are designed and load rated by the manufacturer without consideration of attaching structure, unless specifically requested to do so by the purchaser. This paper discusses the additional design constraints imposed by the use of extension struts with the seismic snubbers. The constraints evaluated include load rating reduction as a function… more
Date: February 1, 1979
Creator: Entz, R. D. & Anderson, M. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reserve seismic capacity determination of a nuclear power plant braced frame with piping

Description: A typical diagonal braced steel frame was developed to determine the amount of reserve capacity that is available beyond elastic design levels. The frame was analyzed first using elastic static and dynamic analyses. The loadings included dead and live load, an equivalent static lateral earthquake load, two response spectra and a suite of eight earthquake time history records. The response spectra used were the Housner and Regulatory Guide 1.60. The time histories represented different site cond… more
Date: February 27, 1979
Creator: Nelson, T.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Engineering Physics and Mathematics Division progress report for period ending June 30, 1985

Description: The report is divided into eight sections: (1) nuclear data measurements and evaluation; (2) systems analysis and shielding; (3) applied physics and fusion reactor analysis; (4) mathematical modeling and intelligent control; (5) reliability and human factors research; (6) applied risk and decision analysis; (7) information analysis and data management; and (8) mathematical sciences. Each section then consists of abstracts of presented or published papers. (WRF)
Date: February 1, 1986
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of local soil conditions on site amplification

Description: The Seismic Safety Margins Research Program (SSMRP) is developing a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly accounts for uncertainties inherent in such a process. In Phase I, the seismic input, the soil-structure inte… more
Date: February 18, 1983
Creator: Chen, J. C.; Bernreuter, D. L. & Johnson, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Computer-based diagnostic monitoring to enhance the human-machine interface of complex processes

Description: There is a growing interest in introducing an automated, on-line, diagnostic monitoring function into the human-machine interfaces (HMIs) or control rooms of complex process plants. The design of such a system should be properly integrated with other HMI systems in the control room, such as the alarms system or the Safety Parameter Display System (SPDS). This paper provides a conceptual foundation for the development of a Plant-wide Diagnostic Monitoring System (PDMS), along with functional req… more
Date: February 1, 1992
Creator: Kim, I.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Subsystem response determination for the US NRC Seismic Safety Margins Research Program

Description: The initial portion of the task described deals with a definition of the state-of-the-art of seismic qualification methods for subsystems. Too facilitate treatment of this broad class of subsystems, three classifications have been identified: multiply supported subsystems (e.g., piping systems); mechanical components (e.g., valves, pumps, control rod drives, hydraulic systems, etc.); and electrical components (e.g., electrical control panels). Descriptions of the available analysis and/or testi… more
Date: February 22, 1979
Creator: Johnson, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Seismic Safety Margins Research Program (Phase I). Project VII. Systems analysis specification of computational approach

Description: An initial specification is presented of a computation approach for a probabilistic risk assessment model for use in the Seismic Safety Margin Research Program. This model encompasses the whole seismic calculational chain from seismic input through soil-structure interaction, transfer functions to the probability of component failure, integration of these failures into a system model and thereby estimate the probability of a release of radioactive material to the environment. It is intended tha… more
Date: February 1, 1979
Creator: Wall, I.B.; Kaul, M.K.; Post, R.I.; Tagart, S.W. Jr. & Vinson, T.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Seismic fragility test of a 6-inch diameter pipe system

Description: This report contains the test results and assessments of seismic fragility tests performed on a 6-inch diameter piping system. The test was funded by the US Nuclear Regulatory Commission (NRC) and conducted by ETEC. The objective of the test was to investigate the ability of a representative nuclear piping system to withstand high level dynamic seismic and other loadings. Levels of loadings achieved during seismic testing were 20 to 30 times larger than normal elastic design evaluations to ASME… more
Date: February 1, 1987
Creator: Chen, W. P.; Onesto, A. T. & DeVita, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary analysis of the postulated changes needed to achieve rail cask handling capabilities at selected light water reactors

Description: Reactor-specific railroad and crane information for all LWRs in the US was extracted from current sources of information. Based on this information, reactors were separated into two basic groups consisting of reactors with existing, usable rail cask capabilities and those without these capabilities. The latter group is the main focus of this study. The group of reactors without present rail cask handling capabilities was further separated into two subgroups consisting of reactors considered ess… more
Date: February 1, 1986
Creator: Konzek, G.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic testing of nuclear power plant structures: an evaluation

Description: Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes … more
Date: February 1, 1980
Creator: Weaver, H.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactive materials released from nuclear power plants. Annual report, 1982. Volume 3

Description: Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1982 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1982 release data are summarized in tabular form. Data covering specific radionuclides are summarized.
Date: February 1, 1986
Creator: Tichler, J. & Norden, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MELCOR Accident Consequence Code System (MACCS)

Description: This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previous CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by … more
Date: February 1, 1990
Creator: Chanin, D. I.; Sprung, J. L.; Ritchie, L. T. & Jow, Hong-Nian
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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[Development of a semi-autonomous mobile robot for reactor containments]

Description: The University of Michigan reports its progress on this project on a bimonthly or quarterly reporting frequency. As a result, the detailed annual summary of activity is derived from the integration of these progress reports. They are attached here to form a permanent record of the University's contribution to this program.
Date: February 10, 1993
Creator: Wehe, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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