Attachment ３

March 13, 2011
References
1. Act on Special Measures Concerning Nuclear Emergency Preparedness(hereafter referred to as “Nuclear Emergency Preparedness Act”)(1) Specific events (related to light water reactors) under Article 10 of the
Nuclear Emergency Preparedness Act● When a radiation dose of 5µSv/h or higher is detected by a radiologicalsurvey instrument located near the boundary of the nuclear site;● When radioactive material equivalent to 5µSv/h is detected at a usual
release point, such as a stack, while the level of diffusion and otherfactors are taken into consideration;● When a radiation dose of 50µSv/h or radioactive material equivalent to5µSv/h is detected at a place outside the controlled area;● When a radiation dose of 100µSv/h is detected at a point one (1) meteraway from a transport container or cask;● The reactor cannot be shut down with the normal shutdown method
when a reactor scram is required;● In the event of loss of reactor coolant, which requires the operation of
the emergency core cooling system during reactor operation(Fukushima Daini Unit 1);● When the emergency core cooling system is inoperable following loss ofthe function to feed water to the reactor during reactor operation;● Loss of all functions to feed water to the steam generator during reactor
operation (pressurized water reactors);● Loss of the function to remove residual heat from the reactor following
loss of the function to remove heat from the reactor with the maincondenser during reactor operation (excluding pressurized waterreactors) (Fukushima Daini, Units 2 and 4);● When electricity supply from all AC power supplies stops during reactor
operation and such a state continues for more than five (5) minutes(Fukushima Daiichi, Units 1, 2, and 3);● In the event of only a single emergency DC bus being available during
reactor operation, the condition in which only a single power supply isavailable to supply electricity to said DC bus continues for more than
five (5) minutes;● When irradiated fuel assemblies are inside the reactor vessel during
reactor shutdown and the level of water within such a reactor vessel
lowers to the level at which the emergency core cooling system is
activated (or, during shutdown of a pressurized water reactor, to the1level at which the function to remove residual heat from the reactor islost);● The level of the irradiate fuel assembly storage tank lowers to the levelat which such fuel assemblies are exposed; and● Loss of the function to shut down the reactor or the function to remove
residual heat of the reactor from the main control room due to theunavailability of the main control room(2) Nuclear emergency criteria (related to light water reactors) under Article
15 of the Nuclear Emergency Preparedness Act● When a radiation dose of 500µSv/h or higher is detected near theboundary of the nuclear site by a radiological survey instrument
belonging to said nuclear site or a relevant prefectural government(Fukushima Daiichi);● When radioactive material equivalent to 500µSv/h is detected at a usual
release point, such as a stack, or at a place outside the controlled area;● When a radiation dose of 5mSv/h is detected at a place outside thecontrolled area;● When a radiation dose of 10mSv/h is detected at a point one (1) meteraway from a transport container or cask;● When nuclear fuel material is in a critical sate (meaning a state in whichchain reaction of atomic fission continues) inside the facility for reactor
operation, etc. (excluding the interior of the reactor) ;● When reactor operation cannot be shut down even by injecting
emergency neutron absorbers;● Loss of all the functions to shutdown the reactor when a reactor scramis required;● In the event of a reactor coolant leak requiring the operation of theemergency core cooling system during operation, or loss of all thefunctions to feed water to the reactor if it is a boiling water reactor, orloss of all the functions to feed water to the steam generator if it is apressurized water reactor, and inability to flood said reactor with all of
the emergency core cooling systems (Fukushima Daiichi, Units 1, 2, and3);● In the event of a reactor coolant leak, the pressure inside thecontainment vessel reaches the maximum design operating pressure ofsaid containment vessel;● Loss of the function to suppress the pressure of the containment vessel
following loss of the function to remove residual heat from the reactor in
the event of loss of the function to remove heat from the reactor with2the main condenser during reactor operation (limited to boiling waterreactors) (Fukushima Daini, Units 1, 2, and 4);● Loss of all the functions to cool down the reactor (or, if it is a pressurizedwater reactor, to feed water to the steam generator) during reactor
operation (for boiling water reactors and pressurized water reactors,
only when electricity supply from all AC power supplies stops):● When electricity supply from all AC power supplies stops during reactor
operation and such a state continues for more than five (5) minutes;● When a radiation dose within the containment vessel or a temperature
within the reactor vessel indicating a core melt is detected;● When any change of the water level within the reactor vessel or any
other event is detected, indicating that irradiated fuel assemblies are
exposed within the reactor vessel during reactor shutdown;● When irradiated fuel assemblies are inside the reactor vessel during
reactor shutdown (limited to pressurized water reactors) and the levelof water lowers to the level at which the function to remove residual
heat from the reactor is lost and such a state continues for more thanone (1) hour; and● Loss of the function to shut down the reactor or to remove residual heatfrom the main control room or by other means.
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