Managing Aging PWR Internals

Concerns about aging degradation of PWR internals have become a high priority as nuclear units approach license renewal: renewal applications must consider the effects of aging to meet conditions defined in the NRC's Generic Aging Lessons Learned Report. In response, EPRI® MRP Reactor Internals Focus Group (RI-FG) has prepared draft inspection and evaluation guidelines for managing the effects of aging degradation in PWR internals. The guidelines, to be eventually issued under the NEI 03-08 Materials Initiative, will include developing an Aging Management Program (AMP) and inspection plan for PWR internals. SI, working closely with RI-FG, has beta-tested the draft guidelines for several units. This SI Webinar discusses management of aging PWR internals, RI-FG draft guidelines, and SI technical support for plants considering aging management reviews for license renewal, as well as those considering development of AMPs.

Presented on: April 1, 2009

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Tim Griesbach has a BS and MS in Materials Engineering from Case Western Reserve University, and over 30 years of experience in materials behavior and structural integrity of major nuclear components. His specialty is technical consulting utilizing state-of-the-art technologies for mitigating and resolving material degradation concerns in nuclear reactor vessels, internals, piping, and other major components. Griesbach has led numerous EPRI® projects to develop tools for managing such aging effects as fatigue and reactor vessel embrittlement in nuclear pressure vessels, and he has worked with utilities, NEI, and NRC to resolve such critical industry issues as pressurized thermal shock in PWRs.