Nuclear Design Practices and the Case of Loviisa 3



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Transcription:

Nuclear Design Practices and the Case of Loviisa 3 Harri Tuomisto Fortum Power, Finland Third Nuclear Power School, 20-22 October 2010, Gdańsk, Poland 22 October 2010 Harri Tuomisto 1

Objectives The objective of this presentation is to introduce current situation of nuclear power utilization in Finland discuss design principles and practices of a nuclear power plant, with a special emphasis on the safety, demonstrate the use of design practices with a practical case of combined heat and power CHP option for Loviisa Unit 3, 22 October 2010 Harri Tuomisto 2

Design and construction practices CONTENTS Finnish licensing process of new builds Nuclear power facilities in Finland Licensing situatiion with new builds Nuclear design principles and requirements Design practices Loviisa 3 CHP option as a practical design case Summary 22 October 2010 Harri Tuomisto 3

Licensing process of New Builds in Finland OPERATING LICENSE ENVIRONMENTAL IMPACT ASSESSMENT DECISION IN PRINCIPLE Government Parliament CONSTRUCTION PERMIT Government Government Ministry of Labour and Economy 22 October 2010 Harri Tuomisto 4

Nuclear power facilities in Finland Hannu Huovila/TVO Loviisa (Fortum) Units 1, 2 - VVER 2x500 MW, start of operation in 1977 and 1980 Unit 3: DiP not granted Posiva (TVO 60%, Fortum 40%) disposal of the spent fuel at Olkiluoto site start operation in 2020 Olkiluoto (TVO) Units 1, 2 - ABB BWR 2x850 MW, start of operation in 1978 and 1980 Unit 3: EPR under construction Unit 4: DiP granted in 2010 * Fennovoima DiP granted for 1 new unit on two new candidate sites * * Decisions-in-Principle granted by the Finnish Government in May 2010, ratified by the Finnish Parliament in July 2010 22 October 2010 Harri Tuomisto 5

Performance of the current fleet Net power Commercial Licensed Cumulative Cumulative MWe operation until production load factor TWh % Loviisa 1 488 1977 2027 120 86 Loviisa 2 488 1981 2030 110 89 Olkiluoto 1 860 1979 2039 191 92 Olkiluoto 2 860 1982 2040 175 93 Loviisa reactors are of VVER-440 type, initial power 440 MWe Olkiluoto reactors are of BWR type, initial power 660 MWe 22 October 2010 Harri Tuomisto 6

Nuclear Waste Management in Finland - the full responsibility of the licensee - Interim storage of spent fuel Loviisa 1983, Olkiluoto 1987 Final repository for low and intermediate level waste Loviisa 1997, Olkiluoto 1992 Deep repositories in crystal bed rock, 100 m below ground level Final repository of spent fuel Posiva selected Olkiluoto site in 1999 Deep repository, crystal bed rock, 500 m below ground level Government Decision in Principle ratified by the Parliament in 2001 New DiP granted for the capacity extension 22 October 2010 Harri Tuomisto 7

Licensing Stages - Schedule of Olkiluoto 3 Operating License 2013? Construction Construction License February 2005 technical stage Bidding & site preparation political stage Decision in Principle May 2002 Feasibility studies Siting including EIA May 1998 - EIA started 22 October 2010 Harri Tuomisto 8

Features of the nuclear power companies in Finland TVO (Olkiluoto Units 1 and 2 operating, Unit 3 under construction, DiP granted for Unit 4) TVO is owned by the Finnish industry, municipal companies and Fortum (25%) TVO produces electricity to its owners (non-profit company) Fortum (Loviisa Units 1 and 2 operating, owns minority assets in TVO and in Sweden) Fortum is a Nordic energy company listed in the Helsinki exchange, owned 51% by the Finnish state Fortum sells the electricity through Nord Pool (the Nordic power exchange) Fennovoima Fennovoima is owned by E.ON (33%), Finnish industrial, trade and municipal companies Fennovoima plans to produce electricity to its owners (non-profit company) 22 October 2010 Harri Tuomisto 9

Nuclear design principles and practices General design principles Safety functions Safety classification Defense in Depth Design practices 22 October 2010 Harri Tuomisto 10

General design basis General Design Basis is to cope with the range of operational states and DBAs within defined radiological consequences To be achieved with conservative design measures and sound engineering practices In addition to the design basis the performance of the plant beyond the design basis including severe accidents and large airplane crash has to be accounted for, but it can be done on the best-estimate basis. It is now customary to call them Design Extension Conditions or DEC (as launched in the EUR documentation). 22 October 2010 Harri Tuomisto 11

Design principles: Safety functions SAFETY FUNCTIONS Fundamental safety functions have to be performed in operational states and DBA conditions and in the BDBA to the extent practicable. Three fundamental safety functions are: 1. Reactivity control 2. Core heat removal 3. Confinement of radioactive material Altogether 19 detailed safety functions have been derived from the three fundamental safety functions. A given SSC can perform one or more safety functions: this provides a basis for safety gradation or classification of the SSC. 22 October 2010 Harri Tuomisto 12

Design principles: Safety classification Principle: All SSC of safety importance including I&C have to be classified. The classification is to be based on deterministic methods and complemented with probabilistic methods and engineering judgment that can account for 1. the safety functions to be performed by a SSC 2. the consequences of failure to perform its function 3. the probability of calling upon performing the safety function 4. the time or the period of its operation SSC: system, structure and component 22 October 2010 Harri Tuomisto 13

Design principles: Defence in depth Defence in depth consists in the hierarchy of different levels of equipment and procedures to maintain the effectiveness of physical barriers placed between radioactive materials and workers, the public and the environment. Defence in depth is implemented through design and operation to provide a graded protection against a wide variety of transients, incidents and accidents. Defence in depth is applied at three various levels and contexts 1. Functional level 2. Physical barriers 3. Failure tolerance 22 October 2010 Harri Tuomisto 14

Defence in depth: Functional levels Level 1 Prevention of abnormal operation and failures Level 2 Control of abnormal operation and detection of failures Level 3 Control of accidents within the design basis Level 4 Management of severe accidents Level 5 Mitigation of radiological consequences 22 October 2010 Harri Tuomisto 15

Defence in depth: Physical barriers Fuel structure Ceramic material that retains radioactivities Fuel cladding Reactor cooling circuit Containment Pressure resistant and leaktight building 22 October 2010 Harri Tuomisto 16

Defence in depth: tolerance to failures Three different principles are applied in the design of SSC important to safety to improve the tolerance to failures Redundancy several similar and parallel subsystems (or components) against single failures vulnerable to common cause failures Diversity parallel components and subsystems that function on mutually different principles against common cause failures failures maintenance requires more effort Independence (separation) parallel subsystems are physically separated from each other against external (fire, flood etc) common cause failures and consequential failures (pipe whips, jets etc) 22 October 2010 Harri Tuomisto 17

Design in the licensing process in Finland Approval of the design of the plant to be Principal designs constructed. Not design specific of candidate plants Approval of the detailed design separately along the plant construction. ENVIRONMENTAL IMPACT ASSESSMENT Ministry of Labour and Economy DECISION IN PRINCIPLE Government Parliament CONSTRUCTION PERMIT Government OPERATING LICENSE Government 22 October 2010 Harri Tuomisto 18

Design practices Importance of the 3D-modelling 3D CAD models should be availble as soon as possible in the design phase detailed and advanced models will be an essential support for the justification of design and for planning the construction and erection works 3D models can be utilized for generation of models into safety analysis codes and for the structural calculations coupled analysis methods will benefit of the compatible 3D models 22 October 2010 Harri Tuomisto 19

3D Models Loviisa VVER-440 Overall containment model 22 October 2010 Harri Tuomisto 20

3D Models Loviisa VVER-440 Overall reactor circuit model 22 October 2010 Harri Tuomisto 21

3D Models Loviisa liquid waste solidification plant Constructed in 2003-2006 by Fortum Extensive utilization of 3D modelling 22 October 2010 Harri Tuomisto 22

Loviisa 3 CHP Next slides introduce some findings from the studies carried out by Fortum Option of combined heat and power production (CHP) from the Loviisa Unit 3 Heat would be transported to the Helsinki metropolitan area: - distance from Loviisa NPP is about 80 km - heat capacity up to 1000 MW 22 October 2010 Harri Tuomisto 23

Loviisa 3 CHP Basis of the Loviisa 3 CHP option Replacement of heat generated with fossil fuels thermal energy consumption (district heat) 11-12 TWh per year Large reduction of carbon dioxide emissions up to 4 million tons annually (6 % of the entire CO 2 emissions in Finland) Higher plant efficiency reduction of heat discharge to the Gulf of Finland net electrical power loss approx. 1/6 of the thermal power generated Steam extraction from the turbine Before low-pressure turbines or several extractions from lp turbine optimisation, and redesign vs. design of new turbine 22 October 2010 Harri Tuomisto 24

Power (MW) Loviisa 3 CHP Cumulative probability distribution of heat generation power in Helsinki metropolitan area for 12 TWh annual generation 3500 3000 2500 2000 1500 12 TWh 1000 500 0 0 0,1 0,2 0,3 0,4 0,5 0,6 0,7 0,8 0,9 1 p 22 October 2010 Harri Tuomisto 25

PWR connection Heat extraction from a Pressurized Water Reactor 22 October 2010 Harri Tuomisto 26

BWR connection Heat extraction from a Boiling Water Reactor 22 October 2010 Harri Tuomisto 27

Loviisa 3 CHP technical data District heat transport system Distance over 75 km (Loviisa eastern Helsinki) 2 x Ø 1200 mm pipes, PN25 bar, Q = 4-5 m 3 /s 4-7 pumping stations total pumping power needed tens of MWs compensates for heat losses Control scheme district heat water temperature or flow rate Heat accumulator needed, heat distribution to the local district heat network via heat exchangers 22 October 2010 Harri Tuomisto 28

Loviisa 3 CHP heat transport on a long distance Heat transport in pipes Mounting in a rock tunnel, cross section 30 m 2 stable conditions positive maintenance aspects Near surface installation lower costs environmentally more challenging Further options: Heat transport by sea with boats or pusher barges requires a lot of new infrastructure 22 October 2010 Harri Tuomisto 29

Application of nuclear design principles for CHP (1) General design requirement The cogeneration plant shall be designed to prevent transport of any radioactive material from the nuclear plant to district heating units under any condition of normal operation, anticipated operational occurrences, design basis accidents and selected severe accidents. Additional safety requirements The heat generation design solutions have to be such that they will not increase safety risks of the NPP The heat transport system should not pose unacceptable safety hazards to the population and environment 22 October 2010 Harri Tuomisto 30

Application of nuclear design principles for CHP (2) Design of a NPP for the combined heat and power production: Coping with the design requirements: General design requirement The heat ectraction takes place via heat exchangers and intermediate circuits The PWR case: heat exchangers at the NPP site and at the connection to city district heating network The BWR case: additionally an on-site intermediate circuit is foreseen Additional safety requirements Application of advanced accident analysis method (APROS, integrated model of the whole plant and the heat transport system) to show that there are no consequences from the heat transport system transients to the plant safety Implementation of the heat transport piping in the tunnel. Analysis of the consequences of the heat transport pipe leakages (with the APROS) 22 October 2010 Harri Tuomisto 31

Summary Finland has a good experience of deploying nuclear power for more than 30 years Commitment to using fission nuclear power with light water reactor continues at least for the next 60-70 years Nuclear waste facilities exist for low and intermediate level waste, spent fuel disposal planned to start in 2020 One new NPP unit is under construction (Olkiluoto 3 EPR) Two granted Decisions in Principle for two more units Loviisa 3 application made provisions to deploy nuclear also for district heat production 22 October 2010 Harri Tuomisto 32