下图(取自NUREG-1032)显示BWR 马克I型核壳电站断电后的事件发展图。资料来源: US NRC G.E. Technology Advanced Manual
t0 = 0, loss of off-plant power and failure of diesel generator t1 = 6 hours, depletion of DC power; HPCI and RCIC inoperable. t2 = 8 hours, primary coolant heatup, release of steam; depletion of primary coolant inventory, loss of makeup. t3 = 10-11 hours, core temperature rises rapidly, resulting in core melt and vessel penetration. t4 > 11 hours, containment failure occurs nearly coincident with vessel penetration, either by loss of electrical penetration integration or by containment overpressure after high pressure core melt ejection.
Event Tree for 1989 Brunswick 2, loss of offsite power. Conditional Core Damage Frequency: 3.6E-5.
BWRs have such a large number of motor driven injection systems that a loss of electrical power implies loss of injection capability. This is why, station blackout is consistently identified by PRAs to be the dominant core melt precursor for BWRs. Operators have to be prepared to deal with
the effects of a loss of and restoration of ac power to plant controls,
instrumentation, and equipment.
Although loss of all ac power is a remote possibility, it is necessary
to address the problem both in training of personnel and equipment
design.