Item B-64: Decommissioning of Reactors
DESCRIPTION
Decommissioning is defined as the orderly retirement of a nuclear facility from service and the safe disposition of the remaining radioactivity.
Item B-63: Isolation of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary
DESCRIPTION
There are several systems connected to the reactor coolant pressure boundary that have design pressures that are considerably below the reactor coolant s
Item B-62: Reexamination of Technical Bases for Establishing SLs, LSSSs, and Reactor Protection System Trip Functions
DESCRIPTION
The methods used to establish safe operating limits for reactor cores were developed about 10 years ago.
Item B-61: Allowable ECCS Equipment Outage Periods
DESCRIPTION
Historical Background
This issue was identified in NUREG-0471[1]and addressed the establishment of surveillance test
Item B-60: Loose Parts Monitoring Systems
DESCRIPTION
The presence of a loose (i.e., disengaged and/or drifting) object in the primary coolant system can be indicative of degraded reactor safety resulting from failure or weakening of a sa
Item B-59: (N-1) Loop Operation in BWRs and PWRs
DESCRIPTION
Historical Background
The majority of the presently operating BWRs and PWRs are designed to operate with less than full reactor coolant flow.
Item B-57: Station Blackout
DESCRIPTION
This NUREG-0471[1]task will make a determination as to whether plants should be designed to accommodate a total loss of all
Item B-55: Improved Reliability of Target Rock Safety Relief Valves
DESCRIPTION
The BWR pressure relief system is designed to prevent overpressurization of the reactor coolant pressure boundary (RCPB) under the most severe abnormal operational transient: closure o