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Regulatory Requirements and Perspectives on the Use of Inservice Testing Software in the Nuclear Industry PUBLIC ACCESS

[+] Author Affiliations
Jason B. Carneal

U.S. Nuclear Regulatory Commission, Rockville, MD

Paper No. NRC2014-5014, pp. 269-278; 10 pages
doi:10.1115/NRC2014-5014
From:
  • ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium
  • ASME/NRC 2014 12th Valves, Pumps, and Inservice Testing Symposium
  • Rockville, Maryland, USA, June 23–25, 2014
  • Conference Sponsors: ASME
  • ISBN: 978-0-7918-9932-8
  • Compilation Copyright © 2019 ASME

abstract

The American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) establishes the requirements for preservice and inservice testing (IST) and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants. The Code of Federal Regulations (CFR) endorses the use of the ASME OM Code in 10 CFR 50.55a(b)(3) . This paper focuses on applicable regulatory requirements and regulatory perspectives associated with the use of IST software in the nuclear industry.

Paper published with permission.

Compilation Copyright © 2019 ASME
This article is only available in the PDF format.

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