Snubber reduction for enhanced plant reliability
- 1. Quadrex Energy Services Corp., Campbell, CA
Description
Nuclear power plants coming on line since the late 1970s tend to have a large number of snubbers and struts on piping systems to provide protection against seismic and other dynamic loads. Considerable effort has been expended by industry to reexamine ASME code requirements, regulatory standards, and design practices for piping to identify those items that could lead to the identification and removal of unnecessary snubbers. This paper provides a summary of three related efforts in snubber reduction. The first study consisted of a pilot program of snubber reduction of three typical lines from a recently operating boiling water reactor (BWR) plant. The second effort consisted of developing and obtaining approval for a licensing application that identifies methods and criteria to be used for a snubber reduction evaluation of an operating plant. The third effort consisted of developing generic industry guidelines for snubber reduction of operating power plants. This work has also identified recommendations for industry activities to justify code and regulatory changes that will allow snubber removal beyond the guidelines presented
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 52
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 599
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 15-20 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080441
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALARA; BWR TYPE REACTORS; DYNAMIC LOADS; IN-SERVICE INSPECTION; PIPES; RADIATION PROTECTION; REACTOR COOLING SYSTEMS; REACTOR LICENSING; REACTOR OPERATION; RELIABILITY; SAFETY ENGINEERING; SEISMIC EFFECTS; SHOCK ABSORBERS; SPECIFICATIONS; SUPPORTS; THERMAL STRESSES; US NRC; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; INSPECTION; LICENSING; MECHANICAL STRUCTURES; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STRESSES; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-860610--.