NPP Personnel Training Center

Transcription

1 NPP Personnel Training Center Juraj Marec, Ivana Maixnerova TM on Developing Systematic Education and Training Approach Using PC Based Simulators for Nuclear Power Programmes, IAEA, Vienna, May 2017

2 Power sources and work locations of VUJE in Slovakia BANSKÁ BYSTRICA KOŠICE EBO EMO TRNAVA BRATISLAVA Vienna Work locations of VUJE: Trnava; Bratislava; Križovany; Mochovce; Košice; Jaslovské Bohunice NPP in operation NPP under construction NPP under decomissioning Power lines 400 kv Main distribution plant Hydroelectric PP Thermal PP 2

3 Overview from PRIS

4 Activities of VUJE in the nuclear power industry

5 Company structure 0100 Department of General Director 0200 Division for Nuclear Safety 0300 Division for Diagnostic of Nuclear Power Components 0400 Division for Preparation of NPP Operation 0500 Division for Support of NPP Operation 0600 Division for NPP Personnel Training Centre 0700 Division for Radiation Safety, NPP Decommissioning and Radwaste Management 0800 Division for Information Technologies 0900 Division for Commerce, Engineering Activities and Services 1000 Division for Economy 1200 Division for Support of Electric Grid Control and Operation 1300 Division for Project Coordination of Research and Development 1700 Division for Preparation and Construction of New Nuclear Power Installations

6 NPP Training center VUJE Training Center performs both theoretical preparation and training of personnel on simulators. The basis of the training is the educational system for the areas of nuclear industry, conventional power plants, electric grid, and for other users. The Training Center develops and designs hardware and software for education and training including simulator development. It carries out examinations for granting licensees for the execution of functions in nuclear power plants and organizes specialized and international courses. Personnel training is carried out in the following areas: Theoretical training Simulator training International courses (EU framework projects) Other training (for NRA, suppliers, internal staff) 6

7 NPP Bohunice V-2, Mochovce 1-2 The Bohunice Nuclear Power Plant (NPP) (Slovak: Atómové elektrárne Bohunice, abbr. EBO) is a complex of nuclear reactors situated in Trnava District in western Slovakia. Bohunice NPP comprises two plants: V1 (shutdown in 2004, now under deccomissioning) and V2. Both plants contain two reactor units. The plant was connected to the national power network in stages in the period between 1978 and The Mochovce Nuclear Power Plant (NPP) (Slovak: Atómové elektrárne Mochovce, abbr. EMO) is a complex of nuclear reactors situated in the Levice District in western Slovakia. Mochovce NPP comprises two units: EMO 1,2 (connected to grid 1999, and second unit 2000). Second plant two units EMO 3,4 are now under construction. All four power reactors are pressurized water reactors (PWR) of the Russian WWER-440, V213 design. 7

8 Section of theoretical training develops programs and elaborates teaching materials and teaching aids for theoretical education, realises teaching of operational and maintenance personnel of the nuclear facilities and training of supplier s organizations for the nuclear facilities. All courses are conducted in accordance with approved training programs for different categories (I.-VI.), professional groups of NPP personnel and different types of training. Nuclear facilities in Slovakia Status Company A-1 Under decommissioning JAVYS V-1 Under decommissioning JAVYS V-2 In operation ENEL RAW Treatment Centre Interim Spent Fuel Storage Facility JAVYS JAVYS EMO-1,2 In operation ENEL EMO-3,4 Under construction ENEL Liquid RAW Treatment Facility JAVYS Basic theoretical training Preparation for the job rotation Periodical training National RAW Repository JAVYS Foreman training Severe accident management training

9 Section of simulator training BANSKÁ BYSTRICA KOŠICE EBO EMO TRNAVA BRATISLAVA FSS Mochovce 1,2 FSS Mochovce 3,4 (operated by S.E.) FSS Bohunice V2 (operated by VUJE) 9

10 Last activities on simulator for NPP Bohunice V-2 WHY FURTHER MODERNIZATION? Two main reasons: Simulator was running on SUN system under Solaris There still were discrepancies between the simulator and reference unit (NPP 3) which needed to be corrected. Slovak NRA (UJD SR) raised a direct demand to S.E. to modernize the simulator software to ensure its long-term and reliable operation and achievement of required accuracy of simulation of EBO V2 Unit. S.E. decided to upgrade simulators in EMO and EBO site in one project due to their similar design and technology used. CORYS TESS used the same scope and tools on these two simulators. 10

11 Project scope and organization :Overall Project Management CORYS - VUJE s competencies for the renovation of Mochovce and Bohunice simulators Mochovce Bohunice Deep knowledge of VVER 440 nuclear plant technology and operation Long experience of CORYS technologies thanks to previous cooperation Extensive know-how on Bohunice simulator CORYS/VUJE/CER 15 years of effective cooperation Data Collection Sim. Executive I&C Containment I/O replacement 3D Core model IS HMI & param. Elec. models Integration & Acceptance Data Collection Sim. Executive I&C 3D Core model IS HMI & param. BNI/BOP model rehosting Integration & Acceptance Containment - development tools (ALICES, T-REX ) and training as necessary were provided to the subcontractor s team - multi-site configuration management tools were implemented to facilitate co-development and support (3 teams in 2 continents) 11

12 Phase 1 - Rehost Rehost stage consisted of five main tasks: 1) All documents were ported from SUN to PC environment and encapsulated in ALICES executive software. All existing snapshots have been converted in ALICES environment. 2) The exchange communication between systems (I&C) was adapted to work in the new PC environment using ALICES software. 3) The code which manages the connection to hard panels was adapted. A graphic visualizer is available. 4) Two new T-Rex instructor stations were provided (119 new graphics P&IDs). 5) New computers were delivered and installed on site. MODELIX ALICES 12

13 Configuration of Bohunice Simulator V2 for full NPP scope Bohunice simulator V-2after upgrade 13

14 Phase 2 Upgrade of hydraulic circuits DRAC THOR HYDRAULIX 14

15 Phase 2 - Upgrade Thermo hydraulic code - THOR two-phase, non-equilibrium, fluid dynamics model for flow networks, model simulates the flow of water, steam, multiple non-condensable gases, and any mixture of those fluids, THOR is used primarily in the areas of the plant that are; high energy subject two phase change important for accurate radio-isotope transport As a result of an extensive installed base for FSS (> 50), THOR is the most thoroughly bench-marked advanced thermal-hydraulic model in the commercial nuclear power industry First NSSS at Watts Bar/USA (1997) First BOP at Surry/USA (2002) First Containment/HVAC at Perry/USA (2006) First ECCS at Farley/USA (2007) First THOR/MELCOR at Monticello (2012) 15

16 Upgrade NEUTRONIC CODE - KIKO KIKO3D - developed in the KFKI Atomic Energy Research Institute - is a three-dimensional reactor dynamics program for coupled neutron kinetics and thermo-hydraulics calculation of VVER type pressurized water reactor cores. - KIKO3D has also its own thermal hydraulic modeling of the reactor core - the thermo-hydraulics is calculated in separate axial hydraulic channels, each of which relates to one fuel assembly - calculation of the middle-fast asymmetric accidents and transients like control rod ejection, start-up of inoperable loop, inadvertent control rod - the equations of the xenon and samarium evolutions are solved and can be accelerated - VVER-440 correlations are used in the thermo-hydraulic module. 16

17 Upgrade T-Rex INSTRUCTOR STATION 17

18 Upgrade T-Rex INSTRUCTOR STATION 18

19 Upgrade EXTERNAL SYSTEMS TPS (Technological information system ) an identical system is used as in the Bohunice NPP SCORPIO (Reactor core surveillance system) - a new SCORPIO system was connected to the TPS Data are sent from simulator to TPS which provides necessary data for SCORPIO modules Center of emergency response - CER - CER computers are now available in Bohunice NPP - it allows to run emergency scenarios on simulator and at the same time in Bohunice NPP 19

20 Upgrade VUJE responsibilities in upgrade cooperation with CORYS TESS in portion of MX modules into ALICES software during integration phase models connection discrepancies cleaning up development of HMI for IS (Mochovce, Bohunice) development of electric model for Mochovce simulator providing of actual plant data and safety analysis support during tuning of THOR and I&C FAT and SAT performance 20

21 Exercise Loss of one MCP Course of event: - MCP nr.6 tripped - reactor power reduced by acting of RLS (reactor limitation system AO3) from 100% reactor power to less then 75% of nominal reactor power - turbine load reduced due to drop of pressure in main steam line (acting of p correctors) - drop of the water level in steam generator and its regulation back to nominal value - unit stabilized by 75% reactor power with 5 MCPs running 21

22 SG 6 narrow level (mm) SG level recovering Level ramping to 0 mm in 10 minutes SG Boiling stop Narrow level -100mm 22

23 reactor neutron power (%) RLS (AO3) Nre < 75% 23

24 Exercise SG pipes leakage Course of event: - leak from primary to secondary water - primary pipes are leaking into steam generator secondary water, increase of level and pressure - SG L tot 2,52m fast acting valve on steam pipe of SG closed - > 5 MPa steam dump valves open to decrease the pressure - new detailed THOR nodalisation ensures the correct response of pressure (i.e. steam trap added to steam lines) 24

25 Leak 25

26 Reactor scram SG4 pressure (MPa), Reactor neutron power (%) Leak started FAV closing > 2.52m in SG 26

27 SG4 total level (m), SG4 pressure (MPa) MSL Full SG4 Full SG4 steam valve closing 27

28 STEAM DUMP STEAM TRAP 28

29 SG4 steam line flow rates (kg/s) STEAM DUMP opening STEAM TRAP flow 29

30 After FSS upgrade after SAT performed in May 2014, Bohunice V-2 simulator is now fully used in training under license given by UJD SR (Slovak nuclear regulatory body) in August 2014 scope of simulation has been extended new scenarios to train (open reactor, SG drainage, over heated steam.) more realistic behavior (tested and compared with NPP data and complied with ANSI norm) better training user friendly environment (PC, Windows OS) more features within instructor station (events, schedules, control from P&IDs) THOR model is ready to be connected to code supporting melting core (i.e. MELCORE) and used in SAM (Severe Accident Management) scenarios 30

31 New initiatives in our division bring more operational staff to the training to cooperate with the shift visualize better implement new tools for better understanding be more realistic create new scenarios for the Severe Accident Management training

32 New initiatives in our division SAM console developed by VUJE installed on Bohunice and Mochovce NPP control room copy of the console also on simulator 2 PCs 4 screens connected via OPC server control of the plant in case of sever accident used during SAM training scenarios for usage of SAM diesel generator in case of blackout

33 CONTAINMENT SPRAY SYSTEM REACTOR HALL SPENT FUEL POOL REACTOR AXIS PASSIVE HYDROGEN RECOMBINERS VENTCENTRUM 33

34 New initiatives in our division new graphic visualisation during refueling Trainees and instructors is able to see in what state they are to better understand the process

35 New initiatives in our division new graphicly visualized and animated technological P&IDs in use for field operator but also for instructors

36 New initiatives in our division electrical scheme based on ThunderElectric better and more realistic behaviour more mesurements and scenarios available

37 Bug tracking system list Filter Excel report 37

38 Bug tracking system bug overview 38

39 elearning sample

40 Conclusion Relation to specific plant FSS E&RS BPS generic BPS specific Simplified animations Plant specific Plant specific Not plant specific Plant specific Licensed Training and usage Based on plant data Personnel with direct impact on NS => MCR staff, field operators, physicists, regulatory body staff Based on design data, later on plant data Engineers, validation of I&C, validation of design, safety analysis Based on code used (thermo hydraulic, neutron) University students, decision makers, regulatory body staff, suppliers, public Based on plant data Personnel with impact on NS => same as generic + MCR staff, field operators, physicists, regulatory body staff Elementary fundamentals for supporting personnel and public 40

41 Questions and answers 41