Becht Engineering Blog

In this section of the site contributing authors submit interesting articles relating to the various services, industries and research & development efforts of Becht Engineering.

EPRI Publishes "Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping"

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EPRI has just published the report “Roadmap to Integrity Evaluation and Repair of Nuclear Plant Piping” EPRI report number 3002013156, dated December 2018, prepared by Becht Nuclear Services, under EPRI Project Manager T. Eckert. The methods and criteria for the evaluation of degraded and non-conforming conditions in piping systems in nuclear power plants are dispersed among a number of ASME XI Code sections, Appendices, Code Cases, and US NRC regulatory requirements, generic letters, and inspection manual sections. This multitude of requirements makes it necessary to have this roadmap to help the engineer make the right fitness-for-service evaluation and the right repair decision. The EPRI road map addresses the fitness-for-service evaluation methods and criteria for the two most common damage mechanisms in nuclear power plant piping systems: Wall thinning, and cracking. The roadmap also addresses non-conformance caused by overloads, i.e. operating loads that exceed the design loads. Regarding repairs of nuclear...
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Repair of Pressure Equipment and Piping in Nuclear Power Plants- Navigating ASME XI Repairs with PCC-2 as a Roadmap

Repair of Pressure Equipment and Piping in Nuclear Power Plants-
Navigating ASME XI Repairs with PCC-2 as a Roadmap
Download/View as PDF Summary - This article assists engineers in selecting ASME XI options for the repair of ASME III nuclear components. In summary, the repair options in ASME XI are dispersed throughout Section XI and Code Cases, while, in contrast, the ASME PCC-2 repair standard (for non-safety related components) lists repair options in a well-structured manner. So, we are going to use the structure of ASME PCC-2 as a road map to cross-correlate the equivalent ASME XI repair, where it exists. Therefore, the Table can be used as a checklist to remind engineers of the many repair options. On one hand …. ASME XI : The repair of safety-related Class 1, 2, and 3 nuclear components is addressed in ASME Boiler & Pressure Vessel Code Section XI and in a series of ASME XI Code Cases. The use of ASME XI and its Code Cases to select a repair...
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