In the regulatory realm, this term applies to systems, structures, components, procedures and controls (of a facility or process) that are relied upon to remain functional during and after design-based events. The NRC is primarily focused on preserving the health and safety of the public. Tag “security-related” any system, structure, or component that is critical to doing so. This term is intended to focus our attention on the seriousness of our responsibilities when developing modifications and replacing equipment.
Whenever any aspect of a modification interacts with any safety-related SSC, plant procedures automatically demand the most intense levels of rigor and scrutiny due to the importance placed on them by the NRC. In 2003, the United States Nuclear Regulatory Commission (NRC) developed mandates on improving safety in nuclear power plants. Principal radioactive components means, for a nuclear power reactor installation, the reactor vessel and internal components, steam generators, pressurizers, large-caliber reactor coolant system piping and other large components that are radioactive to a comparable degree. Parties' obligations are largely based on the principles contained in the IAEA Safety Fundamentals document The Safety of Nuclear Installations.
The plan emerged from intensive consultations with Member States, but not with industry, and was described as a meeting point and plan to strengthen nuclear safety worldwide. EDF's Blayais nuclear power plant in western France uses seawater for cooling and the plant itself is protected from storm surges by dams. Volcanic hazards are minimal for virtually all nuclear plants, but IAEA has developed a new Safety Guide in this regard. Several problems arise in extending the life of nuclear plants that were originally designed for a nominal operating life of 30 or 40 years.
The report was quoted in a 2004 statement from the Japan Nuclear and Industrial Safety Agency, but it appears that TEPCO did not take adequate steps to address the risk. Analysis of the aftermath of next-generation reactors (SOARCA) showed that a serious accident at a United States nuclear power plant (PWR or BWR) would likely cause no immediate death, and that the risks of fatal cancer would be much lower than the overall risks of cancer. Nuclear reactors have three unique characteristics that affect their safety, compared to other power plants. Nuclear DKM can focus on the creation, identification, exchange, transfer, protection, validation, storage, dissemination, preservation or use of knowledge.
The CNRA is responsible for the NEA program and its activities related to the regulation, licensing and inspection of nuclear facilities with respect to safety. IAEA safety standards, applied in the DSR and GRSR at the fundamental and requirements levels, are generic and apply to all nuclear installations. Nuclear fuel is a strategic resource whose continuous supply must be ensured to avoid plant interruptions. The study involved identifying and modeling a large atmospheric release of radionuclides from a hypothetical serious nuclear accident at the four-unit Darlington power plant; estimating doses to individuals at various distances from the plant, after taking into account protective actions such as evacuation would carry out in response to that emergency and, finally, determine the consequences for human health and the environment of the resulting radiation exposure.