Abstracts ASN Report 2019

Management of the condition of the evaporation concentration containers ASN continued its verification of implementation of the ȵȸȒɮǣɀǣȒȇɀ Ȓǔ ³z ȸƺɀȒǼɖɎǣȒȇ א ׎׏ ٮ!(ٮה ׎ ژחדד Ȓǔ ژבא hɖȇƺ א ׎׏ ה relative to the fission product evaporators, issued further to the finding of a rate of corrosion of these equipment items exceeding that considered in their design. ASN conducted a five-day tightened inspection focusing on the non-destructive tests performed by the licensee on the ƺɮƏȵȒȸƏɎȒȸɀ Ȓǔ Ɏǝƺ Á ژא ǔƏƬǣǼǣɎɵ ƳɖȸǣȇǕ ǣɎɀ ȅƏǣȇɎƺȇƏȇƬƺ ȒɖɎƏǕƺِ ASN considers that these inspections were prepared and carried out under satisfactory conditions. Nevertheless, the ȸƺɀɖǼɎɀ ɀǝȒɯ ɎǝƏɎ Ɏǝƺ ɎǝǣƬǸȇƺɀɀ Ȓǔ Ɏǝƺ Á ژא ǔƏƬǣǼǣɎɵ ƺɮƏȵȒȸƏɎȒȸ 4120-23, identified as being the most affected by the corrosion, is close to the minimum thickness. Before restarting the facility, the licensee undertook to continue to reduce the utilisation of this evaporator and to conduct another measurement campaign in 2020. ASN will be particularly attentive to the monitoring of these evaporators until the new replacement evaporators are commissioned. “New Fission Products Concentration” project (NCPF) ASN continued its examination of the NCPF project relative to the commissioning of new fission product evaporator concentrators to replace the old ones, the introduction of ɯǝǣƬǝ ƫƺǕƏȇ ǣȇ ɖǕɖɀɎ א ׎׏ ژח ƏȇƳ ƺȇƳƺƳ ǣȇ zȒɮƺȅƫƺȸ א ׎׏ ژח ٢ɀƺƺ ƬǝƏȵɎƺȸ ׏׏٣ِ ȇ ǣȇɀȵƺƬɎǣȒȇ ɯƏɀ ƬƏȸȸǣƺƳ ȒɖɎ ǣȇ…ƬɎȒƫƺȸ א ׎׏ ژח Ȓȇ the construction worksites of the buildings for these six new evaporators. The organisation for managing this worksite was found to be rigorous. Another ASN inspection on these worksites is scheduled in 2020. Áǝƺ ǣȇɀɎƏǼǼƏɎǣȒȇɀ ƏɎ nƏ RƏǕɖƺ ³RÈÁ (…áz Xz³Á nn ÁX…z³ ژ Èz(0«J…XzJ DECOMMISSIONING: ཛྷ zX זژ ׎ …٫ژ ɴǣƳƺ RǣǕǝ ƬɎǣɮǣɎɵ ǔƏƬǣǼǣɎɵ ٢R…٣ ي ٫ R…ٖzȒȸɎǝ ي facility for “under water” unloading and storage of spent fuel elements, ٫ R…ٖ³ȒɖɎǝ ي Facility for shearing and dissolving spent fuel elements; ཛྷ zX ٫ژבבژ Ȩ גٮא ׎׎ ژ ȵǼƏȇɎً ǔǣȸɀɎ ȸƺȵȸȒƬƺɀɀǣȇǕ ɖȇǣɎ ي ٫ R ٖ(0 ي Facility for separating uranium and plutonium from fission products, ٫ R ¨Iٖ³¨I ٢׏ ژ ɎȒ ב ٣ ي Facility for fission product concentration and storage, ٫ x È ي Facility for separating uranium and plutonium, uranium purification and storage as uranyl nitrate, ٫ x ¨ɖ ي Facility for purification, conversion to oxide and initial packaging of plutonium oxide, ٫ n!! ي Central product quality control laboratory, ٫ ي«! Resin conditioning facility; ཛྷ zX ٫ژזבژ ³Á0 ژא ǔƏƬǣǼǣɎɵ ي 0ǔǔǼɖƺȇɎ ƬȒǼǼƺƬɎǣȒȇ ƏȇƳ ɎȸƺƏɎȅƺȇɎ ƏȇƳ ɀɎȒȸƏǕƺ Ȓǔ ȵȸƺƬǣȵǣɎƏɎǣȒȇ ɀǼɖƳǕƺً ƏȇƳ Á׏ ژ ǔƏƬǣǼǣɎɵً ȵȸȒɎȒɎɵȵƺ ǔƏƬǣǼǣɎɵ ƬɖȸȸƺȇɎǼɵ ƫƺǣȇǕ ƳƺƬȒȅȅǣɀɀǣȒȇƺƳٕ ཛྷ zX ٫ژוגژ 0n z XX ǔƏƬǣǼǣɎɵً ȸƺɀƺƏȸƬǝ ǣȇɀɎƏǼǼƏɎǣȒȇ ƬɖȸȸƺȇɎǼɵ ƫƺǣȇǕ ƳƺƬȒȅȅǣɀɀǣȒȇƺƳِ INSTALLATIONS IN OPERATION: ཛྷ zX ژ ׏׏ ٫ژה Ȩ ٮב ȵǼƏȇɎ ي ٫ Á׎ ي Facility for dry unloading of spent fuel elements, ٫ ¨ȒȒǼɀ ( ƏȇƳ 0 ي Pools for storing spent fuel elements, ٫ Á׏ ي Facility for shearing fuel elements, dissolving and clarification of the resulting solutions, ٫ Á يא Facility for separating uranium, plutonium and fission products and concentrating/storing fission product solutions, ٫ Á ב ٖÁ يד Facilities for purification and storage of uranyl nitrate, ٫ Á يג Facility for purification, conversion to oxide and packaging of plutonium, ٫ Á يו Fission product vitrification facility, ٫ ³X ي Plutonium oxide storage facility, ٫ ي! Plant control room, reagent distribution facility and process control laboratories, ٫ ي!! Hull and end-piece compaction facility, ٫ يא( Technological waste packaging facility, ٫ (Á ي Waste transit area, ٫ 0(³ ي Sold waste storage area, ٫ (ٖ0 0(³ ي Solid waste storage/removal from storage, ٫ 0!! ي Facilities for storage and retrieval of technological waste and packaged structures, ٫ 0ٖ0à ³ȒɖɎǝ ٮ 0ƏɀɎ ي Vitrified residues storage facility, ٫ 0ٖ0àٖnR ƏȇƳ 0ٖ0àٖnR يא Vitrified residues storage facility extensions; ཛྷ zX ژ ׏׏ ٫ژו Ȩ זٮא ׎׎ ژ ȵǼƏȇɎ ي ٫ z¨R ي Facility for “under water” unloading and storage of spent fuel elements in pool, ٫ ¨ȒȒǼ ! ي Spent fuel element storage pool, ٫ «׏ ي Facility for shearing and dissolving fuel elements and clarification of the resulting solutions (including the URP: Plutonium Redissolution Facility), ٫ يא« Facility for separating uranium, plutonium and fission products and concentrating the fission product solutions (including the UCD: centralised alpha waste conditioning unit), ٫ ³¨I ٢ ג ً ד ً ה ٣ ي Fission product storage facilities, ٫ يג« Facility for purification, conversion to oxide and initial packaging of plutonium oxide, ٫ ³Á׏ ي Facility for secondary packaging and storage of plutonium oxide, ٫ يו« Fission products vitrification facility, ٫ xn ٮ x0! ي Packaging reception and maintenance facility; ཛྷ zX ژ ׏׏ ٫ژז ³Á0 ژב ǔƏƬǣǼǣɎɵ ي 0ǔǔǼɖƺȇɎ ƬȒǼǼƺƬɎǣȒȇ ƏȇƳ ɎȸƺƏɎȅƺȇɎ ƏȇƳ ɀɎȒȸƏǕƺ Ȓǔ ƫǣɎɖȅǣȇǣɀƺƳ ɯƏɀɎƺ ȵƏƬǸƏǕƺɀ ي ٫ (ٖ0 0 ي Storage of alpha waste, ٫ x(³ٖ ي Mineralisation of solvent waste. 74 ASN Report on the state of nuclear safety and radiation protection in France in 2019 REGIONAL OVERVIEWOF NUCLEAR SAFETY AND RADIATION PROTECTION NORMANDIE