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Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs

Description: "The program concerning Acoustic Emission/Flaw Relationships for Inservice Monitoring of LWRs was entitled in FY76 with the objective of validating the application of acoustic emission (AE) to monitor nuclear reactor pressure-containing components during operation to detect cracking."
Date: October 1991
Creator: Hutton, P. H.; Kurtz, R. J.; Friesel, M. A.; Skorpik, J. R. & Dawson, J. F.

[Appendix E. Extended Analysis Microfiche]

Description: Graphical presentations of data from the 1/5-scale Mark I BWR Pressure Suppression Experiment (PSE) air transient tests, including HVLF Characterization Data, Impulse Characterization, Computed Load Cell Response Histories and Frequency Analyses, and Enthalpy Flux Evaluation (see Table E-1. Summary of microfiche descriptions)
Date: June 1980
Creator: Lawrence Livermore National Laboratory

Bouguer Gravity Anomaly Map

Description: Bouguer gravity anomaly map derived from the data set and accompanying the report to document the data sources and the procedures used in the reduction of the data.
Date: October 1980
Creator: Keller, G. Randy; Russell, D. R.; Hinze, William J.; Reed, J. E. & Geraci, Philip J.
Location: None
open access

Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: Seismic Margins Research Program (SSMRP)

Description: A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.
Date: September 1980
Creator: Crouse, C. B.; Hileman, J. A.; Turner, B. E. & Martin, G. R.

[COPS Analysis Tables]

Description: Tables presenting the results of COPS computer model analyses, which has been used to estimate local law enforcement agency (LLEA) officer availability in the neighborhood of 60 selected nuclear reactor sites. The tables show the unrestricted response and restricted response for both state and local police within a given radius for each neighborhood in the study (see page 10 of report).
Date: July 1980
Creator: Sandia Laboratories.

[Dynamic Testing Data]

Description: Dynamic test data from an experiment conducted to determine the puncture resistance of lead- and uranium-backed type AISI 316 stainless steel (SS) plates. The data is presented in line graphs. The parameters that were varied in this investigation were punch diameter, test plate thickness, backing material, and test temperature.
Date: April 1980
Creator: Larder, R. & Arthur, D.
open access

Evaluation of trench subsidence and stabilization at Sheffield low-level radioactive waste disposal facility : Sheffield, Illinois, final report, October 15, 1980-March 30, 1981

Description: "This report presents the results of the evaluation of trench subsidence and possible future stabilization techniques at the Sheffield Low-Level Radioactive Waste Disposal Facility, Sheffield, Illinois."
Date: May 1981
Creator: Kahle, R. & Rowlands, J.
open access

Fault Tree Handbook

Description: Introduction: Since 1975, a short course entitled "System Safety and Reliability Analysis" has been presented to over 200 NRC personnel and contractors. The course has been taught jointly by David F. Haasl, Institute of System Sciences, Professor Norman H. Roberts, University of Washington, and members of the Probabilistic Analysis Staff, NRC, as part of a risk assessment training program sponsored by the Probabilistic Analysis Staff. This handbook has been developed not only to serve as text for the System Safety and Reliability Course, but also to make available to others a set of otherwise undocumented material on fault tree construction and evaluation. The publication of this handbook is in accordance with the recommendations of the Risk Assessment Review Group Report (NUREG/CR-0400) in which it was stated that the fault/event tree methodology both can and should be used more widely by the NRC. It is hoped that this document will help to codify and systematize the fault tree approach to systems analysis.
Date: January 1981
Creator: Roberts, N. H.; Vesely, W. E.; Haasl, D. F. & Goldberg, F. F.
open access

Federal/State Regulatory Permitting Actions in Selected Nuclear Power Station Licensing Cases

Description: Abstract: This report documents the Federal/State regulatory permitting actions in 12 case histories of nuclear power station licensing in nine different states. General observations regarding Federal/State siting roles in the siting process include: new regulations, with the exceptions of those imposed by NEPA, were not found to be the source of significant delay; interventions were the sources of significant delay in only two cases; in only two cases was a local agency a source of delay; no one factor was found to be a source of delay, rather several factors often combined to cause delay; it is still too early to assess the influence of State power plant siting laws on the licensing process; clarification of the word "delay" is needed; water related issues predominate in State permitting requirements associated with delay; generalizations on the sources and nature of delay in the licensing process are difficult to make because of site specific characteristics; and frequently problems outside the Federal/State realm have had, or can have, a delaying effect on the process. Eleven of the case histories are illustrated with a logic network that gives the actions of the utilities in addition to the Federal/State permits.
Date: June 1977
Creator: U.S. Nuclear Regulatory Commission. Office of State Programs.
open access

Final Environmental Statement by the U.S. Nuclear Regulatory Commission for Greene County Nuclear Power Plant

Description: Abstract: A Final Environmental Statement for the Power Authority of the State of New York for the construction of the Greene County Nuclear Power Plant (Docket No. 50-549) located in Greene County, New York, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission (NRC). This statement provides (1) a summary of environmental impact and adverse effects of the proposed facility, and (2) a consideration of principal alternatives. Also included are comments of governmental agencies and other organizations on the Draft Environmental Statement for the project and staff responses to these comments. The NRC staff has concluded, based on a weighing of environmental, economic, technical, and other benefit against environmental costs and available alternatives, that a construction permit should be denied because the alternative sites available to the applicant are environmentally preferable. If the permit is granted, the applicant will be required to take the necessary mitigating actions to decrease the aesthetic impact by using alternative closed cycle cooling systems and to undertake monitoring programs to identify, evaluate and mitigate construction related community and public services impacts in the immediate three-county impact area.
Date: January 1979
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
open access

Final Environmental Statement by the U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation for Montague Nuclear Power Station, Units 1 and 2

Description: The proposed project: Pursuant to the Atomic Energy Act, as amended, the U.S. Nuclear Regulatory Commission's regulations in Title 10, Code of Federal Regulations, an application with an accompanying Environmental Report, was filed by Northeast Utilities (hereinafter referred to as the applicant) for construction permits for two generating units designated as the Montague Nuclear Power Station, Units 1 and 2 (Docket Nos. 50-496 and 50-497), each of which is powered by a boiling water reactor (BWR) and is designed for initial operation at approximately 3579 megawatts thermal (MWt) with a net electrical output of 1150 megawatts electric (MWe). A safety design rating of 3759 (MWt) has been used in assessing the impact in this report. Condenser cooling will be accomplished through the use of natural-draft cooling towers. Makeup water for the cooling towers will be obtained from the Connecticut River, and the tower discharge (blowdown) will be returned to the Connecticut River. The proposed facilities will be located on the 1900-acre Montague Plain in the Town of Montague, Franklin County, in northwestern Massachusetts about 1.8 miles east of the Connecticut River and about 3.5 miles east-southeast of the Town of Greenfield, Massachusetts, the largest community within 10 miles with a population of about 15,000. Integration of the power from the Montague Nuclear Power Station will be accomplished by individual routes for each unit, requiring the construction of approximately 118 miles of 345-kV circuit transmission lines into existing electrical systems. A 345-kV switchyard will be located on the Montague site in proximity to the generating units and will constitute the terminus of the 345-kV circuits over which the output of the station will be delivered to the load centers. The route for Unit 1 will terminate at the Ludlow, Massachusetts, substation, and the route for Unit 2 will terminate at the …
Date: February 1977
Creator: U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
open access

FRAPCON-2 : A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

Description: FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d) fission gas release, (e} fuel rod internal gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, and (h) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat transfer correlations. FRAPCON-2 is programmed for use on the CDC Cyber 175 and 176 computers. The FRAPCON-2 code Is designed to generate initial conditions for transient fuel rod analysis by either the FRAP-T6 computer code or the thermal-hydraulic code, RELAP4/MOD7 Version 2.
Date: January 1981
Creator: Berna, Gary A.; Bohn, Michael P.; Rausch, W. N.; Williford, R. E. & Lanning, D. D.
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