Published 1986 | Version v1
Journal article

United States criteria for repair and replacement of BWR piping and steam generator tubing

Creators

  • 1. Nuclear Regulatory Commission, Washington, DC (USA). Office of Inspection and Enforcement

Description

The criteria currently used by the US Nuclear Regulatory Commission in dealing with repairs and replacement of BWR piping and steam generator tubing are discussed and the bases for these criteria are provided. As a result of extensive cracking in BWR pipes caused by intergranular stress corrosion, a program of augmented inspection and leak testing has been instituted. Emphasis is placed on returning such piping to original design conformance either by replacement with non-susceptible material or by a combination of stress improvement and environmental control. As a result of a number of degradation mechanisms in steam generator tubes, inspection and criteria for plugging or sleeving have been instituted along with broad recommendations aimed at an integrated program for resolving steam generator tube problems. (author)

Additional details

Publishing Information

Journal Title
Int. J. Press. Vessels Piping
Journal Volume
25
Journal Issue
1-4
Series
Int. J. Press. Vessels Piping.
Journal Page Range
231-238
ISSN
0308-0161
CODEN
PRVPA

Conference

Title
4. International Seminar on Assuring Structural Integrity of Steel Reactor Pressure Boundary Components.
Dates
26-27 Aug 1985.
Place
Ispra (Italy).

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
18065791
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; INSPECTION; PIPES; REPAIR; STEAM GENERATORS; TUBES
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS