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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