Nuclear Regulatory Commission November 26, 2019 – Federal Register Recent Federal Regulation Documents
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Portland General Electric Company; Eugene Water and Electric Board, and PacifiCorp; Trojan Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) issued a renewed license to Portland General Electric (PGE), Eugene Water and Electric Board, and PacifiCorp (together ``licensee'') for Special Nuclear Materials (SNM) License No. SNM-2509 for the receipt, possession, transfer, and storage of spent fuel from the Trojan Nuclear Plant in the Trojan Independent Spent Fuel Storage Installation (ISFSI), located in Columbia County, Oregon on August 9, 2019. On October 23, 2019, the renewed license and technical specifications were corrected to reflect the current amendment and to remove obsolete pages from the technical specifications.
Nuclear Power Plant License Fees Upon Commencing Commercial Operation
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process one issue raised in a petition for rulemaking, PRM-171-1, dated February 28, 2019, submitted by Dr. Michael D. Meier on behalf of the Southern Nuclear Operating Company (the petitioner), and is denying the remaining issue in PRM-171-1. The petitioner requested that the NRC amend its regulations related to the start of the assessment of annual fees for certain nuclear power plants.
Improved Identification Techniques Against Alkali-Silica Reaction (ASR) Concrete Degradation at Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), PRM-50-109, dated September 25, 2014, submitted by the C-10 Research and Education Foundation (C-10 or the petitioner). The petitioner requests that the NRC amend its regulations to provide improved identification techniques for better protection against concrete degradation due to alkali-silica reaction (ASR) at U.S. nuclear power plants. The petitioner asserts that reliance on visual inspection will not adequately identify ASR, confirm ASR, or provide the current state of ASR damage without petrographic examination. The NRC is denying the petition because existing NRC regulations and NRC oversight activities provide reasonable assurance of adequate protection of public health and safety. Specifically, existing NRC regulations are sufficient to ensure that concrete degradation due to ASR will not result in unacceptable reductions in the structural capacity of safety-related structures at nuclear power plants.
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