The review process for the EDF reactors
In order to benefit fromthe standardisation of the reactors
operated by EDF, these two parts of the revieware first the
subject of a generic design programme for a given plant
series (900 MWe, 1,300 MWe and 1,450 MWe reactors).
The results of this programme are then implemented on
each of the reactors of the plant series on the occasion of
its ten-yearly outage inspection.
In accordance with the provisions of Article L. 593-19 of
the Environment Code, following the ten-yearly outage
inspection, the licensee sends ASNa periodic safety review
conclusions report. In this report, the licensee states its
position on the regulatory conformity of its facility as
well as on the modifications made to remedy deviations
observedor to improve the safety of the facility. The review
report contains information provided for in Article 24 of
Decree 2007-1557 of 2nd November 2007.
The ASN analysis
The guidelines of the generic programmes proposed by
the licensee to verify the status of the facility and reassess
safety are the subject of an ASNposition statement issued
following consultation of the GPR and possibly of the
Advisory Committee for Nuclear Pressure Equipment
(GPESPN). On this basis, EDF carries out safety
reassessment studies and defines modifications.
Following consultation of the GPR at the end of the
periodic safety review generic phase, ASN issues a
position statement on the results of the reassessment
studies and on the modifications envisaged by EDF that
aim to improve safety.
ASN informs theMinister responsible forNuclear Safety of
itsanalysisofthereviewconclusionsreportforeachreactor,
mentionedinArticleL.593-19oftheEnvironmentCodeand
canissuenewprescriptionsregardingitscontinuedoperation.
2.10 The Flamanville 3 EPR reactor
The EPR reactor is a pressurisedwater reactor based on a
designwhich is an evolution of the design of the reactors
currently in service in France, enabling it to comply with
reinforced safety objectives.
After a period of about ten years during which no
nuclear reactors were built in France, EDF submitted
an application inMay 2006 to the Ministers responsible
for Nuclear Safety and Radiation Protection for the
creation of a 1,650 MWe EPR type reactor, called
Flamanville 3, on the Flamanville site, which already
houses two 1,300 MWe reactors.
The Government authorised its creation by Decree 2007-
534 of 10th April 2007, following ASN’s favourable
opinion, subsequent to the inquiry conducted with the
assistance of its technical support organisations.
After issue of this Creation Authorisation Decree and
the building permit, construction of the Flamanville 3
reactor began in September 2007. The first pouring of
concrete for the buildings in the nuclear island began
in December 2007. Since then, the civil engineering
(structural) work has continued and is now almost
completed. In 2015, EDF completed pre-stressing of
the inner containment and the civil engineering work
on the outer containment. Installation of components
(tanks, piping, pumps, cables and electrical and I&C
cubicles, etc.) is now well advanced. In 2015, the last
components of the primary system were installed and
welding of the piping of this system is under way.
According to EDF, fuel loading and start-up of the
Flamanville 3 reactor are scheduled for the end of 2018.
2.10.1 The stages up to commissioning
of the Flamanville 3 reactor
Pursuant to Decree 2007-1557 of 2nd November 2007
(see point 3.1.3 of chapter 3), ASN authorisation is
required to bring nuclear fuel inside the perimeter of the
facility and to start up the NPP. Partial commissioning
corresponds to the reception of nuclear fuel within
the perimeter of the BNI and, for a nuclear reactor,
commissioning of the facility corresponds to the insertion
of nuclear fuel into the reactor vessel.
In accordance with Article 20 of this same Decree and
Article 3 of the Flamanville 3 Creation Authorisation
Decree, the licensee must send ASN a file comprising
the safety analysis report, the general operating rules,
a waste management study for the facility, the on-site
emergency plan, the decommissioning plan and an
update of the facility’s impact assessment, no later than
12 months before the scheduled commissioning date
and no later than six months before fuel is introduced
within the perimeter of the BNI. These requests were
sent by EDF to ASN in March 2015 (see point 3.3) and
ASN expressed its comments and requests for additional
information in letters dated 12th June and 13th July
2015 (available on
www.asn.fr)
.
In parallel with the examination of the commissioning
and partial commissioning authorisation requests, ASN
also checks the construction, the first facility start-up
tests and the preparedness of the teams in charge of
operating the facility following its commissioning.
Finally, ASN assesses the conformity of the nuclear
pressure equipment that is most important for safety with
the requirements set by the regulations. In addition, in
accordance with Article 9 of the Order of 10th November
1999 concerning monitoring of the operation of the
PWR primary and secondary systems, EDF began the
“pre-service inspection” in order to ensure the feasibility
of the scheduled operational maintenance, in particular
before loading of the fuel. ASN checks the performance
386
CHAPTER 12:
EDF NUCLEAR POWER PLANTS (NPPs)
ASN report on the state of nuclear safety and radiation protection in France in 2015




