Reservoir
To preserve a vital part of the St. Louis, Mo. water supply , Stacy Park Reservoir was renovated with a new concrete roof over half its area and new beams in the other half. The new roof...
A Systematic Approach to Conducting Seismic Margin Reviews for Nuclear Power Plants
Deviations from the current codes and standards are considered acceptable in a SMR in areas where the design criteria impose significant conservatism provided the intended function of...
Seismic Evaluation of Non-Seismically Designed Existing Magnox Nuclear Power Plants
Special procedures included on-site testing with a portable shake table, low vibration testing using a structural dynamics analyser, and on-site inspections. The low vibration testing...
A Summary of the Seismic Qualification Utilities Group (SQUG) Program
In 1980, the Nuclear Regulatory Commission (NRC) designated Unresolved Safety Issue (USI) A-46 to address the seismic safety of equipment in operating nuclear power plants. In 1982, the...
Update on Impact Effects in Nuclear Plants Part III?Review of Heavy Object Drop
The consequences of an accidental drop of a heavy component from a lifting device in a nuclear power plant are required to be evaluated even though the device may have been designed using...
Probabilistic Analysis of Impact Loading Conditions
Probabilistic methods are developed for the analysis of random impact loading conditions that arise from oblique, noncollinear, and spinning missile impacts. Models are developed for the...
Behavior of an Operating Floor Subjected to Heavy Load Drops
A structural evaluation of the behavior of a Boiling Water Reactor operating floor subjected to postulated heavy load impact is presented relative to the evaluation of nuclear industry...
Computer-Aided Load Monitoring System for Nuclear Power Plant Steel Framing Structures
The design of nuclear power plant steel framing structures is a long and involved process. It is often complicated by numerous changes in design loads as a result of additions, deletions...
Computer-Aided Design (Seismic Qualification) of Cable Tray Support System ? CADSTrays
A computer system for the analysis and design of cable tray hangers for nuclear power generating plants is discussed. An interactive language for the CADSTrayS was developed. Application...
Sensitivity of Peak Dynamic Responses to Input Factors
Responses have been calculated for the Zion Unit 1 plant, using the SSMRP computer code SMACS, as part of the seismic probabilistic risk assessment performed by the Seismic Safety Margins...
Treatment of Design and Construction Errors in PRA
The risk estimates developed in a PRA should allow for potential design and construction errors. These errors generally modify the component responses and fragilities. Since most design...
Seismic Evaluation of Reinforced Masonry Walls
Masonry walls in operating nuclear plants are in many cases found to be overstressed in terms of allowable stresses when evaluated using current seismic design criteria. However, experimental...
The Use of Joint Reinforcement in Qualifying Masonry Walls in Nuclear Power Plants
Wire joint reinforcement has been traditionally used in block masonry walls for crack control and to provide continuity for multiple wythe walls. In a number of nuclear power plants, vertically...
Probabilistic Seismic Analysis of a Nuclear Power Plant Steel Containment
Concern for the safety of nuclear power plants has motivated efforts to determine the statistical characteristics of the seismic resistance of steel containments under various types of...
Enhancing Quality of Construction on Nuclear Facilities
From the author's viewpoint and the viewpoint of others, the quality of construction on both nuclear projects and many other non-nuclear projects has decreased. The trend...
Techniques for Automating the Process of As-Built Reconciliation
The approach utilizes an electronic digital 'ruler' capable of measuring distances to 100 feet with a resolution of 1/100 of a foot. This ruler interfaces to...
Desin Control for Nuclear Power Plant Modifications
Modifications to operating nuclar power plants which impact structural components must be performed in a manner that is consistent with the licensing basis and technical specifications...
New Developments in Seismic Analysis of Primary and Secondary Systems
This paper presents recent advances made at NCSU in the seismic analysis of these systems. Algorithms are presented by which coupled mode shapes and frequencies can be evaluated without...
Integrated Testing and Analysis
This paper represents a new approach which greatly streamlines the entire process. In those cases where finite element modeling is used without test verification, the procedure consists...
Design Verification of HVAC Duct Turning Vanes in Nuclear Power Plants
HVAC ducts in nuclear power plants utilize short radius elbow construction with turning vanes to minimize the space requirement for duct work and to reduce flow losses in the elbows. Turning...
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