Item A-31: RHR Shutdown Requirements (former USI)
DESCRIPTION
The safe shutdown of a nuclear power plant following an accident not related to a LOCA has been typically interpreted as achieving a "hot-standby" condition (i.e., the reactor is shu
Item A-30: Adequacy of Safety-Related DC Power Supplies
DESCRIPTION
Historical Background
This issue is documented in NUREG-0371[1]and addresses the adequacy of safety-related DC pow
Item A-29: Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage
DESCRIPTION
Historical Background
The safety concern of this NUREG-0371[1]item deals with the consideration of alternatives to the basic design of nuclear po
Item A-28: Increase in Spent Fuel Pool Storage Capacity
DESCRIPTION
Historical Background
This NUREG-0371[1]item involves the development of consistent and formalized acceptance criteria regarding the conversion t
Item A-27: Reload Applications
DESCRIPTION
By letter dated June 18, 1975, licensees of operating reactor facilities were sent a preliminary copy of a staff paper, "Guidance for Proposed License Amendments Relating to Refuelin
Item A-25: Non-Safety Loads on Class 1E Power Sources
DESCRIPTION
Historical Background
The Class 1E power sources provide the electric power for the plant systems that are essential to reactor shutdown, containment isolation, reactor core
Item A-24: Qualification of Class 1E Safety-Related Equipment (former USI)
DESCRIPTION
CP applicants for which SERs were issued after July 1, 1974, were required by the NRC to qualify all safety-
Item A-23: Containment Leak Testing
DESCRIPTION
Historical Background
Since the issuance of Appendix J to 10 CFR Part 50 in February 1973, certain requirements of the appendix have been found to be conflicting, impractical
Item A-22: PWR Main Steamline Break - Core, Reactor Vessel and Containment Building Response
DESCRIPTION
Historical Background
Several aspects of the MSLB analyses as currently provided by applicants and accepted by the NRC have been questioned.
Item A-21: Main Steamline Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification
DESCRIPTION
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.