Review of Industry Efforts to Manage Pressurized Water Reactor Feedwater Nozzle, Piping, and Feedring Cracking and Wall Thinning

摘要

This report presents our review of the nuclear industry efforts to manage thermal fatigue, flow-accelerated corrosion, and water hammer damage to pressurized water reactor (PWR) feedwater nozzles, piping, and feedrings. The review include an evaluation of design modifications, operating procedure changes, augmented inspection and monitoring programs, and mitigation, repair and replacement activities. Four specific actions were taken to perform the evaluation: (1) review of field experience to identify trends of operating events, (2) review of related technical literature, (3) visits to three PWR plants and a PWR vendor, and (4) solicitation of information from eight other countries.