Item B-53: Load Break Switch
DESCRIPTION
Historical Background
This NUREG-0471[1]item arose in the course of the NRC review of the McGuire application, whe
This NUREG-0471[1]item arose in the course of the NRC review of the McGuire application, whe
The fuel assembly is a highly nonlinear structure which can be subjected to substantial loadings during seismic excitations and LOCA transients. The integrity of this assembly is critical for plant safety.
In the design of nuclear power plants, inelastic response of equipment and components due to severe transients from low probability events is permitted in the ASME Boiler and Pressure Vessel Code, Section III, Sub
Appendix A of CFR 10 Part 100 specifies that the operating basis earthquake (OBE) shall be defined by response spectra and that the maximum vibratory gr
GDC-53, "Provisions for Containment Testing and Inspection," requires in part that the reactor containment be designed to permit: (1) periodic inspection of all important areas, and
Surface cracks have been discovered in control rod drive internal parts at some operating BWR plants.
According to NUREG-0471,[1]the safety concern in this issue relates to results from inspections of various structural components in the torus support sys
Frequently, regulatory changes are made in the applicant's proposal for design and/or operation of systems or subsystems based on perceived needs to mitigate impacts on the environment. Also, differences in design
This NUREG-0471[1]task is included in Item B-2.
This Environmental issue is covered in Item B-2.
In the performance of NEPA obligations to evaluate alternatives to the proposed action, the staff must reach a conclusion as to the comparative costs of generating power among the feasible alternatives.