Aging management through condition monitoring of ASCo solenoid valves and NAMCO limit switches
Creators
- 1. Sargent and Lundy, Chicago, IL (United States)
- 2. Baltimore Gas and Electric, Lusby, MD (United States). Calvert Cliffs Nuclear Power Plant
Description
Faced with increasing deregulation in the power industry, competition from independent power producers (IPPs) and aging nuclear power plants, utilities are looking at ways to cut their generation costs to remain competitive. Besides the capital and fuel costs that are fixed, utilities are burdened with the ever escalating operation and maintenance costs and are studying means to control aging of their plants and improve plant performance. This paper presents methods for reducing periodic replacement costs for 2 types of equipment. These methods predict and control aging through baseline material characteristic/performance criteria and periodic condition monitoring. The equipment to which these methods are applied have numerous applications in the plant. The methodologies presented herein can be extended to cover all safety and risk significant components in the plant that are either important to plant safety and operation and/or are expensive to replace
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1347-9
- Imprint Title
- Plant systems/components aging management 1995. PVP-Volume 316
- Imprint Pagination
- 197 p.
- Journal Page Range
- p. 51-57.
Conference
- Title
- Joint ASME/JSME pressure vessels and piping conference.
- Dates
- 23-27 Jul 1995.
- Place
- Honolulu, HI (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27036652
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTUATORS; AGING; CALVERT CLIFFS-1 REACTOR; CALVERT CLIFFS-2 REACTOR; ECONOMICS; ENGINEERED SAFETY SYSTEMS; PERFORMANCE TESTING; PHYSICAL RADIATION EFFECTS; REACTOR SAFETY; RELIABILITY; SERVICE LIFE; SWITCHES; THERMAL DEGRADATION; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; LIFETIME; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950740--.