NATIONAL ACTION PLAN OF THE FRENCH NUCLEAR SAFETY AUTHORITY - PDF document

COMPLEMENTARY SAFETY ASSESSMENTS FOLLOW-UP TO THE FRENCH NUCLEAR POWER PLANT STRESS TESTS NATIONAL ACTION PLAN OF THE FRENCH NUCLEAR SAFETY AUTHORITY December 2012

TABLE OF CONTENTS Introductio n ________________________________________________________________________ 4 1 Implementation of the recommendations resulting from the european peer review ________________ 8 1.1 Natural hazards __________________________________________________________________ 8 1.1.1 Hazard frequency ______________________________________________________________________ 8 1.1.2 Secondary effects of seismic events ________________________________________________________ 9 1.1.3 Protected volume approach______________________________________________________________ 11 1.1.4 Rapid alert notifications ________________________________________________________________ 12 1.1.5 Seismic instrumentation ________________________________________________________________ 13 1.1.6 Specific inspections and verifications of facilities ____________________________________________ 13 1.1.7 Assessment of margins with respect to the flood risk _________________________________________ 14 1.1.8 Assessment of margins with respect to natural hazards ________________________________________ 15 1.2 Loss of the safety systems__________________________________________________________ 18 1.2.1 Cooling systems and alternate heat sink____________________________________________________ 20 1.2.2 Electrical power sources________________________________________________________________ 21 1.2.3 Electric backup batteries________________________________________________________________ 22 1.2.4 Operational and preparatory actions_______________________________________________________ 23 1.2.5 Instrumentation and measuring___________________________________________________________ 24 1.2.6 Improvement of safety at shutdown and in the different reactor states ____________________________ 25 1.2.7 Reactor primary coolant pump seals_______________________________________________________ 26 1.2.8 Ventilation __________________________________________________________________________ 27 1.2.9 Main and emergency control rooms _______________________________________________________ 28 1.2.10 Spent fuel pool _______________________________________________________________________ 29 1.2.11 Separation and independence of the safety systems___________________________________________ 31 1.2.12 Accessibility _________________________________________________________________________ 32 1.2.13 Mobile equipment_____________________________________________________________________ 33 1.2.14 Protection of the systems _______________________________________________________________ 35 1.2.15 Multiple accidents_____________________________________________________________________ 35 1.2.16 Inspection of equipment and training programmes ___________________________________________ 36 1.2.17 Additional studies in areas where uncertainties remain ________________________________________ 37 1.3 Severe accident management_______________________________________________________ 37 1.3.1 WENRA reference levels _______________________________________________________________ 38 1.3.2 Provisions for ensuring equipment resistance to severe accidents________________________________ 39 1.3.3 Analysis of the provisions for severe accident management further to an extreme external hazard ______ 40 1.3.4 Enhancing the severe accident management guides (SAMG) ___________________________________ 41 1.3.5 Validation of the severe accident management guides (SAMG) _________________________________ 43 1.3.6 Severe accident simulation exercises ______________________________________________________ 43 1.3.7 Severe accident management training _____________________________________________________ 43 1.3.8 Extension of the scope of the severe accident management guides (SAMG) to all reactor states________ 45 1.3.9 Improvement in communication__________________________________________________________ 45 1.3.10 Presence of hydrogen in places where it is not planned for in the design __________________________ 46 STRESS TESTS –NUCLEAR SAFETY AUTHORITY ACTION PLAN – 20.12.2012 2/65

1.3.11 Management of large volumes of contaminated water_________________________________________ 47 1.3.12 Radiation protection ___________________________________________________________________ 47 1.3.13 On-site emergency management premises __________________________________________________ 48 1.3.14 Support to the personnel on site __________________________________________________________ 49 1.3.15 Probabilistic Safety Assessment of level 2 (Level-2 PSA) _____________________________________ 50 1.3.16 Studies relative to severe accidents _______________________________________________________ 51 2 Implementation of the other subjects addressed in the framework of the convention on nuclear safety 52 2.1 National organisations ____________________________________________________________ 52 2.1.1 The main actors involved in a radiological emergency situation in France _________________________ 52 2.1.2 ASN duties in a radiological emergency situation ____________________________________________ 53 2.1.3 Experience feedback to ASN from the Fukushima Daiichi accident ______________________________ 54 2.2 Off-site organisation in post-accident emergency situations______________________________ 56 2.2.1 Principles governing the emergency organisation in France ____________________________________ 56 2.2.2 Identified avenues for improvement_______________________________________________________ 57 2.3 International cooperation__________________________________________________________ 59 2.3.1 International action at European level _____________________________________________________ 59 2.3.2 International actions on the multi-lateral plane (outside Europe) ________________________________ 60 2.3.3 Bilateral actions ______________________________________________________________________ 61 3 Implementation of the additional measures prescribed by asn ________________________________ 62 3.1 Subcontracting __________________________________________________________________ 62 4 General schedule____________________________________________________________________ 62 4.1 Actions mentionned under part 1 ___________________________________________________ 62 4.2 Actions mentionned under part 2 ___________________________________________________ 65 Legend: STRESS TESTS –NUCLEAR SAFETY AUTHORITY ACTION PLAN – 20.12.2012 3/65