Abstracts ASN Report 2019

א ِ׏׎ !ȒȇɎǣȇɖƺƳ ȒȵƺȸƏɎǣȒȇ Ȓǔ Ɏǝƺ z¨¨ɀ א ِ׏׎ِ׏ Áǝƺ ƏǕƺ Ȓǔ Ɏǝƺ z¨¨ɀ Ļĸ ņ ĶňŅŅĸŁŇĿŌ ļŁ ņĸŅʼnļĶĸ ļŁ ŅĴŁĶĸ ŊĸŅĸ ĵňļĿŇ łʼnĸŅ Ĵ ŅĸĿĴŇļʼnĸĿŌ ņĻłŅŇ ŃĸŅļłķ łĹ Ňļŀĸѓ ӇӈׇŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņ ŅĸŃŅĸņĸŁŇļŁĺ ŁĸĴŅĿŌ ӈӃёӃӃӃ ĸё łŅ ŇĻŅĸĸіńňĴŅŇĸŅņ łĹ ŇĻĸ ŃłŊĸŅ łňŇŃňŇ ĵŌ ĴĿĿ ŇĻĸ ŅĸŁĶĻ ŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņё ŊĸŅĸ ĶłŀŀļņņļłŁĸķ ĵĸŇŊĸĸŁ ӄӌӋӃׇĴŁķ ӄӌӌӃё ĴŁķ ņĸʼnĸŁ ŅĸĴĶŇłŅņё ŅĸŃŅĸņĸŁŇļŁĺ ӄӃёӃӃӃ ĸё ĵĸŇŊĸĸŁ ӄӌӌӄׇĴŁķ ӅӃӃӃє Ł ĸĶĸŀĵĸŅ ӅӃӄӌё ŇĻĸ ĴʼnĸŅĴĺĸ Ĵĺĸ łĹ the reactors, calculated from the dates of first divergence, can be broken down as follows: Ҋ ӆӋׇŌĸĴŅņ ĹłŅ ŇĻĸ ӆӇׇŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņ łĹ ӌӃӃׇ ĸђ Ҋ ӆӅׇŌĸĴŅņ ĹłŅ ŇĻĸ ӅӃׇŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņ łĹ ӄёӆӃӃׇ ĸђ Ҋ ӅӅׇŌĸĴŅņ ĹłŅ ŇĻĸ ĹłňŅ ŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņ łĹ ӄёӇӈӃׇ ĸє א ِ׏׎ِ א Áǝƺ ȵƺȸǣȒƳǣƬ ɀƏǔƺɎɵ ȸƺɮǣƺɯ • Áǝƺ ȵȸǣȇƬǣȵǼƺ Ȓǔ Ɏǝƺ ȵƺȸǣȒƳǣƬ ɀƏǔƺɎɵ ȸƺɮǣƺɯ The periodic safety reviews of nuclear power reactors comprise the following two parts: ҄ A check on the condition and conformity of the facility: this step aims to assess the situation of the facility with respect to the rules applicable to it. It is based on a range of inspections and tests in addition to those performed in real- time. These verifications can comprise checks on the initial design studies as well as field inspections of the equipment, or even ten-yearly tests such as the containment hydrotests. Any deviations detected during these investigations are then restored to conformity within a time-frame commensurate with their potential consequences. Ageing management is also incorporated into this part of the review. ҄ The safety reassessment: this step aims to improve the level of safety, notably taking account of the experience acquired during operation, changing knowledge, the requirements applicable to the more recent facilities and international ĵĸņŇ ŃŅĴĶŇļĶĸņє łĿĿłŊļŁĺ ŇĻĸņĸ ŅĸĴņņĸņņŀĸŁŇ ņŇňķļĸņё identifies the changes it intends to make to its facilities in order to enhance safety. • Áǝƺ ȸƺɮǣƺɯ ȵȸȒƬƺɀɀ ǔȒȸ Ɏǝƺ 0(I ȇɖƬǼƺƏȸ ȵȒɯƺȸ ȸƺƏƬɎȒȸɀ In order to fully benefit from the standardisation of the ŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅņ łŃĸŅĴŇĸķ ĵŌ ё ŇĻĸņĸ ŇŊł ŃĴŅŇņ łĹ ŇĻĸ periodic safety review are first of all covered by a generic studies ŃŅłĺŅĴŀŀĸ ĹłŅ Ĵ ĺļʼnĸŁ ŇŌŃĸ łĹ ŅĸĴĶŇłŅ ҎӌӃӃ ĸё ӄёӆӃӃ ĸ łŅ ӄёӇӈӃ ĸ ŅĸĴĶŇłŅņҏє Ļĸ ŅĸņňĿŇņ łĹ ŇĻļņ ŃŅłĺŅĴŀŀĸ ĴŅĸ ŇĻĸŁ applied to each nuclear power reactor on the occasion of its ŃĸŅļłķļĶ ņĴĹĸŇŌ ŅĸʼnļĸŊє ŀłŅĸ ŃĴŅŇļĶňĿĴŅĿŌ ĶĴŅŅļĸņ łňŇ Ĵ ĿĴŅĺĸ part of the checks and modifications related to the periodic safety reviews during the ten-yearly inspections of its reactors. Ł ĴĶĶłŅķĴŁĶĸ ŊļŇĻ ŇĻĸ ŃŅłʼnļņļłŁņ łĹ ŅŇļĶĿĸ є ӈӌӆіӄӌׇłĹ ŇĻĸ Environment Code, following this periodic safety review, the licensee sends ASN a periodic safety review conclusions report. In this report, the licensee gives its position on the regulatory compliance of its facility as well as on the modifications made to remedy the deviations observed or improve the safety of the facility and, as necessary, proposes implementing additional improvements. The periodic safety review report comprises parts specified in the Environment Code. • ASN analysis Ļĸ ĺňļķĸĿļŁĸņ łĹ ŇĻĸ ĺĸŁĸŅļĶ ŃŅłĺŅĴŀŀĸņ ŃŅłŃłņĸķ ĵŌ for verification of the status of the facility and reassessment of safety are the subject of an ASN position statement issued following consultation of the GPR and possibly of the GPESPN. Ł ŇĻļņ ĵĴņļņё ĶĴŅŅļĸņ łňŇ ņĴĹĸŇŌ ŅĸĴņņĸņņŀĸŁŇ ņŇňķļĸņ and defines the modifications to be made. łĿĿłŊļŁĺ ĶłŁņňĿŇĴŇļłŁ łĹ ŇĻĸ ķʼnļņłŅŌ łŀŀļŇŇĸĸņ ĴŇ ŇĻĸ ĸŁķ łĹ the periodic safety review generic phase, ASN issues a position statement on the results of the reassessment studies and on the ŀłķļĹļĶĴŇļłŁņ Ňł ĴĿĿłŊ ŇĻĸ ņĴĹĸŇŌ ļŀŃŅłʼnĸŀĸŁŇņ ĸŁʼnļņĴĺĸķ ĵŌ є ASN then informs the Minister responsible for nuclear safety of its analysis of the review conclusions report for each nuclear ŃłŊĸŅ ŅĸĴĶŇłŅё ŀĸŁŇļłŁĸķ ļŁ ŅŇļĶĿĸ є ӈӌӆіӄӌׇłĹ ŇĻĸ ŁʼnļŅłŁŀĸŁŇ Code, and can issue new binding requirements regarding its continued operation. Ļĸ ŁĸŅĺŌ ŅĴŁņļŇļłŁ ĹłŅ ŅĸĸŁ ŅłŊŇĻ ĶŇ ӅӃӄӈіӌӌӅׇłĹ ӄӊׇ ňĺňņŇ ӅӃӄӈׇņňŃŃĿĸŀĸŁŇĸķ ŇĻĸ ĹŅĴŀĸŊłŅľ ĴŃŃĿļĶĴĵĿĸ Ňł the periodic safety reviews on nuclear power reactors. It more specifically requires ASN authorisation, following a public inquiry, of the provisions proposed by the licensee during the periodic safety reviews beyond the 35th year of operation of a ŁňĶĿĸĴŅ ŃłŊĸŅ ŅĸĴĶŇłŅє ļʼnĸ ŌĸĴŅņ ĴĹŇĸŅ ņňĵŀļŇŇļŁĺ ŇĻĸ ŃĸŅļłķļĶ safety review report, the licensee also submits an interim report on the condition of the equipment, in the light of which ASN may supplement its binding requirements. GRAPH 5 Mean collective dose per reactor (Man.Sv/reactor) 0.00 0.25 0.50 0.75 1.00 2019 2018 2017 2016 2015 2014 2013 2012 2011 2010 2009 0.69 0.62 0.71 0.67 0.79 0.72 0.71 0.76 0.61 0.67 0.74 Source: EDF. ASN Report on the state of nuclear safety and radiation protection in France in 2019 303 ׏׎ ٲ THE EDF NUCLEAR POWER PLANTS 10