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Safety-related equipment inside the containment of a nuclear power plant is qualified for the most severe accident conditions under which it is expected to function.
At the time this issue was identified in NUREG-0371,[1]compliance with NEPA required that alt
At the time this issue was identified in NUREG-0371,[1]trends in the design of nuclear power
Nuclear power plants contain many structures, systems, and components (SSCs), some of which are safety- related.
Prior to May 1978, tests conducted by GE showed that the presence of steam and/or increased pressure in and above the upper core region of BWRs could adve
Operation of a LWR results in slow corrosion of the interior metal surfaces of the primary coolant system. The resulting corrosion products circulate thro
After the 1970 issuance of inspection requirements in Section XI of the ASME Boiler and Pressure Vessel
In May 1978, the ACRS and the staff expressed concern over the substantial number of LERs related to the malfunction of snu
During the course of the licensing action for North Anna Units 1 and 2, a number of questions were raised as to the potential for lamellar tearing and lo
