Item B-4: ECCS Reliability
DESCRIPTION
Numerical reliability goals and methods of analysis have not been established by the NRC.
Numerical reliability goals and methods of analysis have not been established by the NRC.
There are several inconsistencies in event categorization between the GDC, SRP, Standard Format, and applicant submissions.
Current NRC regulations and practice require that certain operating requirements (Technical Specifications) be made part of each operating license.
Neutron irradiation of reactor pressure vessel weld and plate materials decreases the fracture toughness of the materials.
Following a LOCA in an LWR, combustible gases, principally hydrogen, may accumulate inside the primary reactor containment as a result of: (1) metal-water reaction involving the fuel e
Nuclear power plant instrumentation and control systems are composed of safety-related protection systems and non-safety-related control systems.
The design criteria and methods for the seismic qualification of mechanical and electrical equipment in nuclear power plants underwent significant change
In March 1981, this issue was identified as a USI in NUREG-0705.[1]A program was initiated to evaluate the safety adequacy o
The complete loss of AC electrical power to the essential and nonessential switchgear buses in a nuclear power plant is referred to as a "Station Blackout." Because many safety systems
This issue deals with a concern for the availability of adequate recirculation cooling water following a LOCA when long-ter