INVESTIGATION AND EVALUATION OF STRESS-CORROSION CRACKING IN PIPING OF LIGHT WATER REACTOR PLANTS

This report covers the investigation of the possible intergranular stress corrosion cracking (IGSCC) of large diameter piping. During 1978, IGSCC was reported for the first time in large diameter piping (greater than 20 in.) in a BWR in Germany. This discovery, together with the reported questions concerning the interpretation of ultrasonic inspections, led to the activation of a new Pipe Crack Study Group (PCSG). The charter of the new PCSG was expanded 1) to review the potential for IGSCC in PWRs and BWRs, 2) to examine operating experiences in foreign reactors relevant to IGSCC, and 3) to specifically address five PCSG charter questions. The specific areas considered by the PCSG and summarized in this report are PWR and BWR cracking experience, metallurgy associated with pipe cracking, reactor coolant chemistry, pipe configuration and stress levels, Duane Arnold safe-end cracking, methods of detecting significance of cracks, and recent developments relevant to control and detection of IGSCC. In the report, conclusions and recommendations by the PCSG are presented.

  • Corporate Authors:

    Nuclear Regulatory Commission

    Pipe Crack Study Group, 1717 H Street, NW
    Washington, DC  United States  20555
  • Publication Date: 1979-2

Media Info

  • Features: References;
  • Pagination: v.p.

Subject/Index Terms

Filing Info

  • Accession Number: 00195820
  • Record Type: Publication
  • Source Agency: Nuclear Regulatory Commission
  • Report/Paper Numbers: NUREG 0531
  • Files: TRIS
  • Created Date: Jul 31 1979 12:00AM