Prior to 1982, pipe damping values in nuclear plants were prescribed by Regulatory Guide 1.61 and Appendix N to Section III of the ASME Boiler and Pressure Vessel Code. In the early 1980s, it became clear that piping design was too conservative resulting in systems that had far too many supports, particularly snubbers. These supports were costly to design, install, and inspect; contributed to increased worker radiation exposure; and since snubbers sometimes lock when unloaded causing higher fatigue usage in piping, the safety margin of the systems was reduced. A series of steps was undertaken by the Pressure Vessel Research Committee (PVRC) to propose new damping limits, which culminated in alternate damping allowable values, called PVRC damping. This damping was later adopted as Code Case N-411 to the ASME Code. Code Case N-411 has enabled several utilities to make significant reductions in the number of snubbers on their plants, resulting in lower maintenance costs, lower worker radiation exposure, and greater reliability (since the consequences of snubber malfunction are reduced). More recently, the Electric Power Research Institute sponsored a project by Bechtel to review the damping data, perform a regression analysis, and recommend a permanent change to the ASME Code to replace Code Case N-411.
Skip Nav Destination
Article navigation
Research Papers
The History of Allowable Damping Values for U.S. Nuclear Plant Piping
A. G. Ware
A. G. Ware
Idaho National Engineering Laboratory, EG&G Idaho, Inc., Idaho Falls, ID 83415
Search for other works by this author on:
A. G. Ware
Idaho National Engineering Laboratory, EG&G Idaho, Inc., Idaho Falls, ID 83415
J. Pressure Vessel Technol. May 1991, 113(2): 284-290 (7 pages)
Published Online: May 1, 1991
Article history
Received:
December 3, 1990
Online:
June 17, 2008
Citation
Ware, A. G. (May 1, 1991). "The History of Allowable Damping Values for U.S. Nuclear Plant Piping." ASME. J. Pressure Vessel Technol. May 1991; 113(2): 284–290. https://doi.org/10.1115/1.2928756
Download citation file:
Get Email Alerts
Cited By
Surface Strain Measurement for Non-Intrusive Internal Pressure Evaluation of A Cannon
J. Pressure Vessel Technol
The Upper Bound of the Buckling Stress of Axially Compressed Carbon Steel Circular Cylindrical Shells
J. Pressure Vessel Technol (December 2024)
Crack Growth Prediction Based on Uncertain Parameters Using Ensemble Kalman Filter
J. Pressure Vessel Technol (December 2024)
Defect Detection of Polyethylene Gas Pipeline Based on Convolutional Neural Networks and Image Processing
J. Pressure Vessel Technol
Related Articles
Overview of the Impact of Ultrasonic Examination Performance Demonstration on the ASME Boiler and Pressure Vessel Code
J. Pressure Vessel Technol (August,2002)
Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
J. Pressure Vessel Technol (June,2016)
An Ability to Adapt and Change
Mechanical Engineering (November,2014)
Performance-Based Reliability of ASME Piping Design Equations
J. Pressure Vessel Technol (June,2017)
Related Proceedings Papers
Related Chapters
Part 2, Section II—Materials and Specifications
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Part 2, Section II—Materials and Specifications
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Global Harmonization of Flaw Modeling/Characterization
Global Applications of the ASME Boiler & Pressure Vessel Code