Primary water stress corrosion cracking of alloy 600

As United States nuclear reactors have aged, a number of problems have arisen. Among these are primary water cracking (PWSCC) of Alloy 600 in PWRs. Since 1989, when PWSCC was identified to the Nuclear Regulatory Commission (NRC) as an emerging issue, it has been reported in several components, including control rod drive mechanism (CRDM) penetrations. To address PWSCC of CRDM penetrations at U.S. plants, the industry developed a comprehensive inspection, evaluation, repair and mitigation program. Recent pilot inspections that revealed cracking at two of the three U.S. plants inspected indicate the problem is generic. Further, results of stress analyses indicate that an area of high stress exists that could cause cracking that would follow the J-groove weld. Such cracking was identified in a foreign reactor that had a resin intrusion. PWSCC of CRDMs remains an open issue. Proactive NRC/Industry programs for inspection and repair or replacement of affected components are essential for continued operation of nuclear reactors and for license extensions. (author)