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There are several inconsistencies in event categorization between the GDC, SRP, Standard Format, and applicant submissions.

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Current NRC regulations and practice require that certain operating requirements (Technical Specifications) be made part of each operating license.

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Neutron irradiation of reactor pressure vessel weld and plate materials decreases the fracture toughness of the materials.

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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 element cladding; (2) the radi

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Nuclear power plant instrumentation and control systems are composed of safety-related protection systems and non-safety-related control systems.

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The design criteria and methods for the seismic qualification of mechanical and electrical equipment in nuclear power plants underwent significant changes during the course of the li

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In March 1981, this issue was identified as a USI in NUREG-0705.[1]A program was initiated to evaluate the safety adequacy of the decay heat removal (DHR

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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 required for reactor core de

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Historical Background

This issue deals with a concern for the availability of adequate recirculation cooling water following a LOCA when long-term recirculation of cooling wa

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Pipe cracking has occurred in the heat-affected zones of welds in primary system piping in BWRs since mid-1960. These cracks have occurred mainly in Type 304 stainless steel which is the type used in most