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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Ho Nieh nominated to the NRC
Nieh
President Trump recently nominated Ho Nieh for the role of commissioner in the Nuclear Regulatory Commission through the remainder of a term that will expire June 30, 2029.
Nieh has been the vice president of regulatory affairs at Southern Nuclear since 2021, though he is currently working as a loaned executive at the Institute of Nuclear Power Operations, where he has been for more than a year.
Nieh’s experience: Nieh started his career at the Knolls Atomic Power Laboratory, where he worked primarily as a nuclear plant engineer and contributed as a civilian instructor in the U.S. Navy’s Nuclear Power Program.
From there, he joined the NRC in 1997 as a project engineer. In more than 19 years of service at the organization, he served in a variety of key leadership roles, including division director of Reactor Projects, division director of Inspection and Regional Support, and director of the Office of Nuclear Reactor Regulation.
Truong V. Vo, Michael S. Harris, Bryan F. Gore
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 14-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34192
Articles are hosted by Taylor and Francis Online.
Probabilistic risk assessment (PRA) based inspection guidance has been developed using information from the PRA for Arkansas Nuclear One Unit 1 (ANO-1). This information will be used in conjunction with the U.S. Nuclear Regulatory Commission (NRC) Inspection and Enforcement Manual and has been prepared in the form of a plant-specific appendix for incorporation into this manual. An analytical method was developed for calculating risk importance for affected plant systems. This was used to prioritize the ANO-1 plant systems using the Fussel- Vesely importance measure on the basis of core melt probability. System fault trees were reanalyzed to identify and rank the risk significant components in each system. The product of this effort is a prioritized listing of systems and components associated with 98% of the inspectable portion of the risk from ANO-1. This compilation will subsequently be used by NRC inspectors in the preparation of inspection plans addressing risk-important systems and components at the ANO-1 power plant.
