Cost effective in situ small bore piping qualification for vintage power plants
Creators
- 1. Stone and Webster Engineering Corp., Cherry Hill, NJ (United States)
Description
Small bore piping for vintage power plants built in the late 60s and early 70s were field routed with minimal documentation. To evaluate the technical adequacy of a piping system, a field walkdown must be first made to identify the configuration. For an operating plant, this is a time consuming and expensive process, not only financially but also in terms of radiation exposure to personnel. Faced with such a substantive task, the plant owner needs to derive a technically sound yet cost effective solution. This paper describes an innovative and cost effective program that was successfully implemented on an early 1970 vintage power plant. The approach relied heavily on the experience and expertise of the engineers performing in situ evaluation and disposition of concerns. It preserved as much as possible the original design practice, but provided sufficient documentation to demonstrate the technical adequacy of the entire population after some modifications
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0815-7
- Imprint Title
- Proceedings of seismic engineering 1991
- Imprint Pagination
- 337 p.
- Journal Page Range
- p. 161-164.
Conference
- Title
- 1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 23-28 Jun 1991.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24035611
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; NUCLEAR POWER PLANTS; PARAMETRIC ANALYSIS; PLANNING; RADIATION DOSES; RADIATION PROTECTION; REACTOR COMPONENTS; REACTOR OPERATORS; REACTOR SAFETY; REACTOR VESSELS; SAFETY ENGINEERING; SAFETY STANDARDS; US NRC; VALVES
- Descriptors DEC
- CONTAINERS; CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; SAFETY; STANDARDS; THERMAL POWER PLANTS; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-910602--.