Item B-1: Environmental Technical Specifications
DESCRIPTION
Current NRC regulations and practice require that certain operating requirements (Technical Specifications) be made part of each operating license.
Item A-49: Pressurized Thermal Shock (former USI)
DESCRIPTION
Neutron irradiation of reactor pressure vessel weld and plate materials decreases the fracture toughness of the materials.
Item A-48: Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment
DESCRIPTION
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
Item A-47: Safety Implications of Control Systems (former USI)
DESCRIPTION
Nuclear power plant instrumentation and control systems are composed of safety-related protection systems and non-safety-related control systems.
Item A-46: Seismic Qualification of Equipment in Operating Plants (former USI)
DESCRIPTION
The design criteria and methods for the seismic qualification of mechanical and electrical equipment in nuclear power plants underwent significant change
Item A-45: Shutdown Decay Heat Removal Requirements (former USI)
DESCRIPTION
In March 1981, this issue was identified as a USI in NUREG-0705.[1]A program was initiated to evaluate the safety adequacy o
Item A-44: Station Blackout (former USI)
DESCRIPTION
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
Item A-43: Containment Emergency Sump Performance (former USI)
DESCRIPTION
Historical Background
This issue deals with a concern for the availability of adequate recirculation cooling water following a LOCA when long-ter
Item A-42: Pipe Cracks in Boiling Water Reactors (former USI)
DESCRIPTION
Pipe cracking has occurred in the heat-affected zones of welds in primary system piping in BWRs since mid-1960.