Item D-2: Emergency Core Cooling System Capability for Future Plants
DESCRIPTION
This issue was documented in NUREG-0471[1]and stemmed from an ACRS recommendation that the staff explore diverse means of ob
This issue was documented in NUREG-0471[1]and stemmed from an ACRS recommendation that the staff explore diverse means of ob
There are no current criteria for acceptability of solidification agents.
Interpretations of NEPA require the environmental impact assessment include land use impacts and alternatives in nuclear power plant licensing cases.
SRP[1]Section 15.7.3 requires an analysis of the consequences of failure of tanks containing
Licensees are required to estimate the design-basis flood levels for each nuclear power plant site consistent with the requirements in General Design Cri
This NUREG-0471[1]item was an ACRS generic concern that initially addressed the common mode failure of identical components
Structural damage to the primary system, including the reactor pressure vessel and internals, associated piping and steam g
The operating experience of nuclear power plants indicates that a number of valves, valve operators, and pumps fail to oper
This NUREG-0471[1]task will respond to a concern of the ACRS about the effectiveness of vario