SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY Role of the TSO in Public Information/ Debate Openness, Transparency.

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Presentation transcript:

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY Role of the TSO in Public Information/ Debate Openness, Transparency Technical support to regulatory body for the new NPP (OL3) project Keijo Valtonen International Conference on the Challenges Faced by Technical and Scientific Support Organizations in Enhancing Nuclear Safety Aix-en-Provence

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 2 PVM/NN Olkiluoto 3 licensing phases Decision in Principle Construction Permit Environmental Impact Assessment Operating License Feasibility study Preparatory phase Construction Technical part Politica l part

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 3 PVM/NN TSO Support at Olkiluoto 3 Review Stakeholders involved in the licensing

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 4 PVM/NN TSO Support at Olkiluoto 3 Review Criteria for TSO’s; –Competent organisation to carry out EPR analysis –Independent from the licensee –Codes independent from the licensee’s codes –Adequately validated safety codes for EPR Main TSO which were used in OL3 licensing was –Technical Research Centre of Finland (VTT) Other TSOs –Lappeenranta Technical University –Institute for Safety and Reliability (ISar) –Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) Codes used by TSO’s –TRAB3D/SMABRE (VTT) –APROS (VTT) –ATHLET (ISar)

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 5 PVM/NN TSO Support at Olkiluoto 3 Review VTT: Anticipated operational transients and accident analyses (DBC 2, 3, 4) with the TRAB3D/SMABRE code »Main steam line break »Loss of offsite power »Main coolant pump seizure »ATWS Accident analyses (DBC 3 and 4) with the APROS and TRAB3D/SMabre codes –Independent comparative analyses of primary circuit behaviour during accident situations. »Small break LOCA »Steam Generator Tube Rupture »Large break LOCA »Feedwater line break –Independent comparative analyses of containment behaviour during accident situations »EPR/OL3 - APROS simulation of containment behaviour during main steam line break and large break LOCAs

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 6 PVM/NN TSO Support at Olkiluoto 3 Review Severe Accident analyses with the MELCOR and GEMINI2 codes –EPR/FIN5 - Station blackout analyses with MELCOR –EPR/FIN5 - Large break LOCA analyses with MELCOR –Severe accident analyses of EPR/FIN5 –Erosion of sacrificial concrete in the dry cavity of EPR/FIN5 Fire safety –Experiments (cables) and review

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 7 PVM/NN TSO Support at Olkiluoto 3 Review Primary circuit design: strength analysis, review of manufacturing technology –Evaluation of the welding preheat and work temperatures and associated heat treatments for a few reactor pressure vessel and steam generator forgings. –Comments on the Expediency of the Welding Procedure Qualification Test Specification for Safe End Welding –Comments on the Expediency of the Document 'Dissimilar Metal Narrow Gap TIG Welds with Nickel-Base Alloy 52 - Manufacturing and Material Properties (NFPMT DC 1080, Rev.C)' –Evaluation of OL 3 quality requirement procedures of following specifications: ASME-QR-NDT-2102, ASME-QR-NDT-2108, ASME-QR- NDT-2110, ASME-QR-NDT-2114, ASME-QR-NDT-2200, ASME-QR- NDT-2201 and ASME-QR-NDT-2231 –Evaluation of OL 3 quality requirement procedures of specifications listed in section 1 –Final Comments on the Expediency of the Document 'Dissimilar Metal Narrow Gap TIG Welds with Nickel-Base Alloy 52 - Manufacturing and Material Properties (NFPMT DC 1080, Rev. C) –OL3 Inspection guidelines for forgings –Statement on analysis data for a few forgings.

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 8 PVM/NN TSO Support at Olkiluoto 3 Review –Review of design phase PSA Risk-informed review of safety classes of OL3, design phase Review of HRA for OL3-PSA –Analysis of airplane crashes Operation of emergency diesel generators after an aircraft crash. Short-term combustion of jet fuel after an aircraft crash. Olkiluoto 3 NPP Aircraft Crashes –OL3 - Primary circuit water chemistry Literature survey of primary side water chemistry aspects for OL3 nuclear power plant

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 9 PVM/NN TSO Support at Olkiluoto 3 Review Finnish organisations Lappeenranta University : –Experiments on core melt coolability

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 10 PVM/NN TSO Support at Olkiluoto 3 Review European organisations Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) –Break Preclusion Concept –Airplane crashes Institute for Safety and Reliability (ISar) –Transient and Design Basis Accident analyses with the ATHLET code Preparation and Qualification of Basic ATHLET Input Deck for the Finnish EPR (Olkiluoto-3). SB LOCA Boron Dilution Analysis for the Finnish EPR (Olkiluoto-3) ATWS Analyses for the Finnish EPR Olkiluoto-3. Evaluation of the Effectiveness of the Emergency Core Cooling System (ECCS) of EPR and Comparison of the Effectiveness of ECCS between EPR and the Convoy Plants

SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY 11 PVM/NN TSO Support at Olkiluoto 3 Review European organisations 2A LOCA Analyses for the Finnish EPR Olkiluoto-3. Calculation of the SGTR at full Power (2 U-tubes with Coincident LOOP) for the Finnish EPR (Olkiluoto-3) Calculation of the SGTR at Hot Zero Power (2 U-tubes break at 2% Reactor Power) for the Finnish EPR (Olkiluoto-3) DGSNR and IRSN France Exchange of information on the Finnish and French EPR design topics