Snubber reduction program at the Byron Station, Unit 1
Creators
Description
Commonwealth Edison Company's (CECo's) Byron Station, unit 1, was originally designed with approximately 1200 snubbers supporting the plant's large- and small-bore piping systems. This relatively large number of snubbers is attributed to excessive conservatism in nuclear piping codes and regulations effective during the original piping design. A recent pilot program at CECo's LaSalle County Station, a boiling water reactor plant, demonstrated that a 50% or greater reduction in total snubber population is achievable in plants of this design vintage. Based on the successful results of the pilot program, CECo initiated a full scale snubber reduction program at Byron, a pressurized water reactor plant of the same vintage at the LaSalle County Station. The benefits from a reduced snubber population are described. To realize the maximum potential benefits, all snubbers in the plant were prioritized in order of desirability for removal. The priority designations are discussed. The major results from phase 1 of the Byron program are summarized. The NRC inspection of the project addressed a variety of issues and is discussed. The conclusions that can be drawn from the phase 1 program are summarized
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 55
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 524-525
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20003850
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BYRON-1 REACTOR; DOCUMENTATION; DYNAMIC LOADS; EDUCATION; FAILURES; INSPECTION; PIPES; RADIATION DOSES; RADIATION PROTECTION; REACTOR SAFETY; REGULATIONS; SEISMIC EFFECTS; SEPARATION PROCESSES; SPECIFICATIONS; SUPPORTS; US NRC
- Descriptors DEC
- ENRICHED URANIUM REACTORS; LAW; MECHANICAL STRUCTURES; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8711195--.