Safety Analysis for NPP
Deterministic Safety Analysis
Design Basis Accident (DBA) Analysis
• Performing of the DBA analysis for RNPP Unit 3 in the framework of Periodic Safety Reassessment Report development
• Preparation of substantiating materials for development of the Safety Factor №5 (SF) “Deterministic safety analysis” as a part of DBA analysis for Periodic Safety Reassessment Report for ZNPP Units 1,2
• Updating of DBA analysis for RNPP Unit 1. Analysis of initiating events (IE) during reactor cooldown and shutdown mode
• Development of the DBA analysis for RNPP Unit 2. Performing of the additional substantiating materials for implementation of the fuel of new generation
Beyond Design Basis Accident (BDBA) Analysis
• Performing of the BDBA analysis for RNPP Unit 3 in the framework of PSRR development
• Preparation of substantiating materials for development of the SF-5 “Deterministic safety analysis” as a part of BDBA analysis for Periodic Safety Reassessment Report for ZNPP Units 1,2
• Analysis of selected BDBA scenarios for “pilot” SUNPP Unit 1 with VVER-1000/V-302 reactor
• Development of the substantiation for BDBA analysis for additional IE during operation of control algorithm “Primary to Secondary LOCA” for SUNPP Units 1,2 with VVER-1000/V-302,338 reactor
• Participation in BDBA analysis for KhNPP Unit 1
• Development of draft set of basic technical documentation for BDBA analysis of SUNPP Unit1
• Development of recommendations for the management of BDBA and preparation of Safety Analysis Report Chapter “Beyond design basic accident analysis” for RNPP Unit1
• Calculation analyses for selected BDBA scenarios for full-power reactor operation in the framework of Chapter 19 of Safety Analysis Report “Probabilistic safety analysis” for KhNPP Unit 2
Severe Accident Analysis
• Vulnerability analysis for RNPP Unit 1 under severe accidents at shutdown reactor and spent fuel pool
• Participation in vulnerability analysis for RNPP Unit 1 under severe accidents
• Analysis of the containment failure under accidents with severe core damage for
VVER-1000/V-320 reactor
• Adaptation of the Severe Accident Management Guidance for spent fuel pool for “non-pilot” units of Ukrainian NPPs
Strength Analysis
• Thermohydraulic supporting calculations for strength analysis of the reactor vessel, steam generators, main circulating pumps, pressurizer, bubbler tank, piping systems of pressurizer and emergency core cooling system, main circulation pipeline
• Mechanical and strength analysis of accident during fuel handling and refuelling
• Performing of thermal-hydraulic analysis to justify the acceptable number of loading cycles for equipment and pipelines of NSSS during RNPP Unit 1,2 overdesigned operation
Pressurized Thermal Shock Analysis
• Integrity assessment of RNPP Units 1,2 reactor vessels
• Integrity assessment of RNPP Units 3 reactor vessel
Supporting Deterministic Studies for Probabilistic Safety Analysis
• Analysis of primary success criteria
• Analysis of secondary success criteria
Probabilistic Safety Assessments (PSA)
PSA Level 1
• Development of the seismic PSA level 1 for reactor and spent fuel pool for ZNPP Unit 1,2
• Participation in PSA level 1 for RNPP Unit 4
• Using PSA methods for evaluation of SUNPP safety under accidents
• Adaptation of PSA level 1 for internal initiators for ZNPP Units 1,2,3,4,6
• Adaptation of reactor Low power and shutdown PSA, including spent fuel pool for ZNPP Units 1-4, 6; SUNPP Units 2,3
PSA Level 2
• Development of the seismic PSA level 2 for reactor and spent fuel pool for ZNPP Units 1,2
• Development of supporting materials for low power and shutdown PSA level 2 for NPPs with VVER-1000/V-320 reactors
Justifications of NPP Modifications and Modernizations
• Safety substantiations for implementation of HPIS control valves at SUNPP Unit 1
• Safety substantiations for implementation of LPIS control valves at SUNPP Unit 1
• Safety substantiations for implementation of LPIS control valves at RNPP Unit 3
• Safety substantiations for pressurizer safety valve replacement for RNPP Unit 3
• Safety substantiations for pressurizer safety valve replacement for SUNPP Unit 1
• Safety substantiations for steam generator safety valve replacement RNPP Unit 3
• Safety substantiations for implementation of automated control algorithm of primary to secondary leak accidents for SUNPP Unit 1
• Substantiation for modifications of algorithm and setpoints
• Substantiation for implementation of TVSA fuel at SUNPP Unit 1
• Substantiation of design change for differential pressure measurement in reactor for ZNPP Unit 1
Development of the “Stress-Tests”
• Participation in stress-tests studies for ZNPP Units (in part of assessing of extreme meteorological impact, loss of electricity and hydrogen hazards during severe accidents)
• Participation in stress-tests studies for SUNPP Units (in part of assessing of extreme meteorological impact, loss of electricity and hydrogen hazards during severe accidents)
Radiation Protection. Radioactive Waste Management
• Consulting Services during Preparation of the Licensing Plan for the Central Spent-Fuel Storage Facility (CSFSF) at Chernobyl site
• Independent engineering review of structural, thermal and accident analyses documents developed for CSFSF equipment substantiations for compliance with nuclear and radiation safety regulatory requirements
• Justification of nuclear and radiation safety of transport containers TC-6 and TC-11 during transport and technological operations with fuel for VVER-440
• Participation in development of Preliminary Safety Analysis Report for nuclear facility – Nuclear Fuel Fabrication Plant
• Radiation protection, environmental impact assessment of nuclear installations on the environment and population
• Scientific and technical support for decommissioning and radioactive waste management