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There are several systems connected to the reactor coolant pressure boundary that have design pressures that are considerably below the reactor coolant system operating pressure.
The methods used to establish safe operating limits for reactor cores were developed about 10 years ago.
This issue was identified in NUREG-0471[1]and addressed the establishment of surveillance test intervals and allowable equi
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 safety-related component.
The majority of the presently operating BWRs and PWRs are designed to operate with less than full reactor coolant flow.
This NUREG-0471[1]task involves a review of valve failure data in a systematic manner to ver
This NUREG-0471[1]task will make a determination as to whether plants should be designed to accommodate a total loss of all AC power for a limited period
This issue was documented in NUREG-0471[1]and resulted from a review of LERs which indicated
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 of the main steam line isolati
This NUREG-0471[1]item deals with two concerns regarding the ice condenser containment desig
