The termination of electrical power generation by
the plant corresponds to the last time the control rods of the reactor
are inserted into the reactor core.
The operations leading to the termination of electric
power generation are carried out by the operating organization in
accordance with the General Operating Rules and the Safety Analysis
Report on the initial installation. The operations include defuelling
and the removal of spent nuclear fuel and normal operating waste.
A safety dossier regarding these operations must be submitted by
the operating organization to the Safety Authority six months before
terminating electrical power generation.
Removing the equipment outside of the
nuclear island that is not necessary to be kept under surveillance
for safety reasons
Maintaining or reinforcing
the containment barriers
Producing a radioactivity balance
These operations enable stage 1 decommissioning to
be initiated (the stages of decommissioning are defined below).
The dismantling work may start just after the final
shutdown or be deferred to benefit from radioactive decay. Dismantling
can lead to stage 2 of decommissioning or possibly stage 3 depending
on the final state required.
The final shutdown operations and subsequent dismantling
work require a license in the form of a decree. These activities
should start after examination and approval by the Safety Authority
of a dossier prepared by the operating organization. This dossier
justifies the planned final state of the installation and indicates
the different dismantling stages.
Upon completion of the dismantling work, there are
three possible outcomes:
The installation is entirely dismantled
and, as such, is removed from the list of Basic Nuclear Installations
The final state is that of an installation
classified for environmental protection. If
the residual activity is less than 370*1012 Bq; an
installation classified for environmental
protection may be licensed or
simply declared, depending on the procedures provided for the
type of installation
The final state is that of a new Basic
Nuclear Installation if the residual activity
is greater than 370*1012 Bq. This new Basic Nuclear
Installation must be licensed by decree after a public inquiry,
in accordance with the procedures established by the decree
Produced for the Nuclear Installation Safety Division
of the IAEA
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