Steam generator tube integrity flaw acceptance criteria
Description
The author discusses the establishment of a flaw acceptance criteria with respect to flaws in steam generator tubing. The problem is complicated because different countries take different approaches to the problem. The objectives in general are grouped in three broad areas: to avoid the unscheduled shutdown of the reactor during normal operation; to avoid tube bursts; to avoid excessive leak rates in the event of an accidental overpressure event. For each degradation mechanism in the tubes it is necessary to know answers to an array of questions, including: how well does NDT testing perform against this problem; how rapidly does such degradation develop; how well is this degradation mechanism understood. Based on the above information it is then possible to come up with a policy to look at flaw acceptance. Part of this criteria is a schedule for the frequency of in-service inspection and also a policy for when to plug flawed tubes. The author goes into a broad discussion of each of these points in his paper
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants
- Imprint Pagination
- 621 p.
- Journal Page Range
- p. 335-357.
- Report number
- NUREG/CP--0154
Conference
- Title
- CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants.
- Dates
- 30 Oct - 2 Nov 1995.
- Place
- Oak Brook, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28068494
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFECTS; EVALUATION; IN-SERVICE INSPECTION; MAINTENANCE; PLUGGING; PWR TYPE REACTORS; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; INSPECTION; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ANL--96/14; NEA/CNRA/R--(96)1; CONF-9510423--.