Item B-72: Health Effects and Life Shortening from Uranium and Coal Fuel Cycles
DESCRIPTION
Practice in health impact assessments at the time of identification of this issue was to convert radiation exposure estimates into estimates of health ef
Item B-71: Incident Response
DESCRIPTION
Present NRC actions taken in response to a serious incident are directed from an Incident Response Center (IRC).
Item B-70: Power Grid Frequency Degradation and Effect on Primary Coolant Pumps
DESCRIPTION
Offsite power system frequency decay, depending on the rate of decay, could provide an electrical brake on the reactor coolant pump motors that could slo
Item B-69: ECCS Leakage Ex-Containment
DESCRIPTION
Following a plant transient or accident, provisions are required for long-term decay heat removal. Redundancy of components is required as necessary to assure that a failure in the RHR
Item B-68: Pump Overspeed During LOCA
DESCRIPTION
Historical Background
This NUREG-0471[1]item, as presently formulated, involves the conduct of analytical and experi
Item B-67: Effluent and Process Monitoring Instrumentation
DESCRIPTION
According to NUREG-0471,[1]the nature of this problem is described as follows:
Item B-66: Control Room Infiltration Measurements
DESCRIPTION
The control room area ventilation systems and control building layout and structures are reviewed to assure that plant operators are adequately protected
Item B-65: Iodine Spiking
DESCRIPTION
Historical Background
This NUREG-0471[1]task is to develop and confirm a model for the iodine spiking phenomenon, in
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