Nuclear Power Plant Unit Olkiluoto 3

Contents

TVO – a pioneer in its own field 3

Olkiluoto 3 4

One unit, many buildings 9 n PRIMARY CIRCUIT 13

Reactor pressure vessel and internal structures 15

Reactor core and fuel 17

Reactor operation and control 23

Primary coolant circuit 25 n SECONDARY CIRCUIT 31

Turbines and generator 33

Condenser 37 n SEA WATER COOLING SYSTEMS 39 n NUCLEAR SAFETY 41 n WATER CHEMISTRY AND VOLUME CONTROL SYSTEMS 47 n INSTRUMENTATION AND CONTROL SYSTEMS 49 n ELECTRICAL POWER SYSTEMS 51 n WASTE PROCESSING SYSTEMS 53 n TRAINING SIMULATOR 57

Technical data 58

The reactor pressure vessel was lifted into the reactor pit in June 2010.

Olkiluoto 3 1 2 Olkiluoto 3 TVO – a pioneer in its own field

Teollisuuden Voima Oyj (TVO) is a non-listed public High in international ranking company founded in 1969 to produce electricity for its TVO’s nuclear expertise is clearly evident by the high ca- stakeholders at cost price. TVO is the developer, owner pacity factors of the Olkiluoto plant units. The capacity and operator of the Olkiluoto nuclear power plant. factors of OL1 and OL2 have varied between 93% and The production of the nuclear power plant units in 98% since the early 1990s, ranking among the very top by Olkiluoto (OL1 and OL2) covers about one sixth of the international comparison. total electricity consumption in Finland. Half of this elec- The high capacity factors indicate reliability of opera- tricity goes to the industry, the other half is consumed by tion, among other things. private households, service sector and agriculture. The results achieved are based on meticulous and Because of the need for increase in both self-sufficien- proactive planning of annual outages and modifications. cy and additional capacity of electricity production, TVO The radiation exposure doses of the personnel, which is currently building a third power plant unit, Olkiluoto 3 have been consistently low at the Olkiluoto power (OL3). With the electrical output of approximately 1,600 plant, have also yielded good results in international MWe, OL3 will almost double the production capacity of comparison. the Olkiluoto power plant. In summer 2010 the Finnish Parliament granted TVO permission to build a fourth TVO’s operating philosophy unit; Olkiluoto 4 (OL4). As a nuclear power company, TVO is committed to a high level safety culture, which creates the comprehen- Solid nuclear expertise sive basis for all activities. According to the principles of TVO employs a staff of about 800, many of them with the safety culture, issues are prioritised according to their solid experience in the operation and maintenance of a safety significance and a high degree of operability and nuclear power plant gained over several decades. This ex- reliability of production are the key objectives of opera- pertise is also utilised and further developed in the con- tion. Safety and factors affecting safety always take pri- struction of the OL3 and OL4 units. ority over financial considerations. The future vision of Throughout its existence, TVO has provided further TVO is to be an acknowledged Finnish nuclear power training to the employees and improved the competence company and a pioneer in its field. To achieve this goal, of the staff in nuclear technology. The company’s nuclear TVO acts responsibly, proactively and transparently, fol- expertise is being sustained by participating in interna- lowing the principles of continuous improvement in close tional development programmes. Also the upgrading cooperation with various interest groups. and modernisation projects as well as development and construction projects carried out at the existing Olkiluoto units develop the staff’s expertise. The modernisation projects implemented over the years have improved the safety as well as the production capacity and economy of the Olkiluoto power plant.

Olkiluoto 3 3 Olkiluoto 3

Olkiluoto 3 (OL3) was decided to build for many reasons. components are Civaux 1 and 2 in France, which went The added capacity brought by OL3 not only meets the on stream in 1997 and 1999, respectively. AREVA NP increasing demand but also compensates for the decreas- also delivered the principal components to units which ing output of ageing power plants. Together with the use went on stream in Brazil (Angra 2) and China (Ling Ao 1 of renewable energy, the unit helps Finland to reach its and 2) in 2002. carbon dioxide emission targets, contributes to the sta- Siemens is one of the leading power plant suppliers in bility and predictability of electricity prices and reduces the world. The combined output of the power plants de- Finland’s dependence on imported electricity. livered by Siemens exceeds 600 GWe. It was on this basis that TVO submitted an applica- tion to the Government in November 2000 concerning a Technology based on solid practical experience Decision in Principle for the building of a new nuclear OL3 is an evolutionary unit compared with the current power plant unit. The Government adopted a Decision power plant units, meaning that its basic design is based in Principle, and Parliament ratified the Decision in on the proven technology of existing power plants. Its de- Principle on 24 May 2002. The Decision in Principle velopment was based on plants commissioned in France states that building the new nuclear power plant unit is in (N4) and Germany (Konvoi). the interest of society as a whole. Safety features in particular have been developed fur- After a call for tenders, in December 2003 TVO took ther. The unit was originally designed to allow for the the decision to invest in the construction of a power plant management of a severe reactor accident (cooling of core unit with a Pressurized Water Reactor (PWR) with an melt) and a large aircraft crash (double shell of the reac- output of approximately 1,600 MWe at Olkiluoto. The tor containment building). type of the unit is known as a European Pressurized Water Reactor (EPR). The unit is being built on a turn- key basis by a consortium formed by AREVA NP and Siemens. AREVA NP is delivering the reactor plant, and Germany (Konvoi) Siemens is delivering the turbine plant. Neckarwestheim 2 1,269 MWe 1989 Experienced power plant suppliers Isar 2 1,400 MWe 1988 Emsland 1,290 MWe 1988 Both of the principal suppliers are leaders in their respective fields. AREVA NP has delivered the principal France (N4) components for a total of 100 light-water reactor units Chooz 1 1,450 MWe 1996 – 94 pressurized water reactors (PWR) and 6 boiling Chooz 2 1,450 MWe 1997 water reactors (BWR). The most recently commissioned Civaux 1 1,450 MWe 1997 PWR units for which AREVA NP supplied the principal Civaux 2 1,450 MWe 1999

4 Olkiluoto 3 Operating principle of a pressurized water reactor (PWR) A PWR plant has two circuits for heat transfer. Water is kept under high pressure by the pressurizer (1) and circulated by the reactor coolant pumps (2) in the primary circuit (3), which transfers the heat from the reactor (4) to the secondary circuit (5) in the steam generator (7). Reac- tor power is controlled by control rods (6). The pressure in the secondary circuit is much lower than in the primary circuit, which makes the water in the steam generator boil. The steam from the steam generator makes the turbine (8) rotate. The turbine rotates the coaxially mounted generator (9), generating electricity for the national grid. The steam from the turbine is cooled back to water in the condenser (10) with sea water (11). Condensate water is fed back to the steam generator with feedwater pumps (12), and the warm sea water is pumped back into the sea.

60 years service life Compared with similar units recently commis- In addition to safety, the design of OL3 emphasizes econ- sioned in Europe, OL3 will have a reactor output about omy in particular. The efficiency rate of the new unit, for 1% greater and an electricity output about 10% greater. instance, is 37% – some four percentage points higher OL3 is being delivered as a turn-key project. TVO has than the original efficiency of OL1 and OL2. been responsible for site preparation and for the expan- The design is based on an expected service life of sion of the infrastructure at Olkiluoto. Site preparation 60 years for the largest structures and components and has involved earthmoving, excavation, road building, 30 years for the more easily replaceable structures and electrical power supply for the construction site and the components. Allowing in advance for such replacements building of the tunnels for the cooling water. The actual enables the unit to have an economic service life of at construction work that is the responsibility of the AREVA least 60 years. NP – Siemens consortium began in 2005.

Multi-stage quality control and inspection are carried out by representatives of TVO, plant supplier, subcontractors, and authorities.

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3914Containment5140 heat removal39 system 50 48 49 252149 22 33 234151391341 3839 3739 1 Inner and outer containment system heat exchangers53 50 2216 Main control23 room 5234 51 30heat37 exchanger 68 24 50 23 2467 22 44 39 38 building 14 Core melt spreading area25 26202423 Computer24 room24 25 27 F41 3440Fuel building 2238 26 51 21 29 155241 40 21 2 Reactor building main crane51 15 Emergency49 cooling water50 storage 26225024 Emergency feedwater23 tank34 244252401435 42 Fuel building crane3940 3840 54 51 17 24 23 5335 523138 69 (polar crane) 25 (In-containment51 refueling water 24D Safeguard2568 building division45 3 36 Refuelling machine40 39 26 2725 2525 26 28 4235 2339 22 3 Containment heat removal system: 27 storage tank, IRWST) 52 2125 Emergency22 feedwater pump 30 5337 43 4116Fuel5342 pools 3941 52 50 51 272351 24 35 25434115 40 sprinklers 26 16 Intake screens for the cooling55 52 2618 Medium head25 safety24 injection46 pump5436 5338 32 Fuel39 transfer tube41 41 70 52 25 2669 43 41 40 4 Equipment hatch (large system for reactor emergency27 2826E Safeguard26 building26 27division29 4 39 36 17Fuel pool cooling system2440 heat 23 28 53 22 23 541644425443 4042 components) 53 cooling and51 containment52 heat 28245227 Switchgear room 25 36 31 2644 exchanger 27 56 53 19 26 25 47 5537 54423340 4142 42 5 Refuelling machine removal system53 2628 Instrumentation2770 & control room G44 Reactor plant42 auxiliary building 28 2927 2727 28 30 3718 2541 24 6 Steam generator 1729 Hydraulic accumulator of the54 2329 Battery rooms24 1740 43Coolant5544 supply and storage4143 system 54 52 29 26 37 32 27455545 41 28 5357 54 255320 27 5638 554334 4243 43 7 Main steam lines reactor emergency54 cooling system 2730 Emergency28 feedwater26 tank48 4145 Coolant41 supply and storage system 29 3028 2828 29 3819 43 2642 25 8 Main feedwater lines 1830 Primary circuit pressurizer 55 2431 Component25 cooling system31 heat 1842 44Offgas5645 delayer 4244 55 53 30 27 38 33 28465646 42 9 Reactor control rod drives29 19 Main steam valves 5458 55 2654 21exchanger 28 5739 564443 35 Ventilation stack4344 44 55 28 29 27 49 46 42 27 10 Reactor pressure vessel 20 Feedwater valves 30 2932 Low head29 safety29 injection30 pump H 3920Radioactive44 waste processing43 26 31 3125 26 32 19455746 4345 11 Primary circuit reactor coolant56 21 Main steam54 system safety valve56 33 Containment heat removal28 39system34 294757 47building 43 30 5559 56 31275522 29 5840 574536 4445 45 pump and relief valve56 exhaust silencer 29 heat30 exchanger 28(sea water50 circuit) 4447 Liquid43 waste collecting28 tank 31 30 3030 40 45 44 27 12 Primary circuit main coolant lines B32 Safeguard building division 1 3226 27 31 33 2045 4621Monitoring58 tanks 4446 57 55 57 29 40 35 305848 47 5660 57 32285623 485846 4546 4446 31 57 30 29 51 5941 483744 29 32 30 31 46 45 28 33 283131 34 2259 4547 58 58 332731 3230 36 315921414947 48 56 57 58 295724 41 495947 4647 4547 32 58 61 33 31 30 52 6042 493845 30 33 32 47 46 29 34 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44 48 55 52 19 54 53 53 52 5 5454 62 48 15 8 59 62 50 55 58 66 36 2045 49 56 53 55 54 54 53 6 16 9 5555 63 63 49 56 60 50 51 59 67 37 2146 56 57 55 54 54 7 55 5656 64 50 17 10 64 52 57 61 60 68 38 2247 51 57 58 56 55 55 8 56 5757 65 1 18 11 65 51 53 58 62 69 39 2348 52 58 59 57 56 61 9 57 58 66 56 2 19 12 58 66 52 54 59 63 70 40 2449 53 60 58 57 62 59 10 58 57 3 20 13 5959 67 67 53 55 60 64 2550 54 58 63 41 60 6159 59 58 4 11 21 14 6060 68 68 1 54 56 61 65 26 55 59 64 42 51 61 6260 60 59 5 12 22 15 6161 69 69 2 55 57 62 66 27 56 60 65 43 52 62 63 61 60 6 13 2361 16 6262 70 70 3 56 58 67 28 57 63 66 44 53 63 64 62 61 61 7 14 2462 17 6363 4 57 29 59 64 68 45 54 58 62 67 648 15 65 63 62 2563 18 6464 5 58 30 60 65 69 55 59 68 46 659 16 66 64 63 63 2664 19 6565 6 59 70 31 60 61 66 69 47 56 6610 17 67 65 64 64 2765 20 66 7 60 66 32 62 67 70 48 57 61 68 65 6711 18 2866 66 8 65 21 6767 61 33 63 68 49 58 62 69 66 6812 19 2967 67 9 66 22 6868 62 34 64 69 50 59 63 20 70 67 6913 3068 68 10 67 23 6969 63 35 65 70 60 64 51 7014 21 69 68 3169 24 70 11 68 70 64 36 66 1 52 61 65 69 1 15 22 3270 7025 1 69 2 1 12 2 65 37 2 67 3 2 66 70 3 53 62 16 23 33 26 3 70 4 3 13 4 66 38 4 68 5 4 67 5 54 63 17 24 34 27 5 6 1 5 14 6 67 39 Olkiluoto 3 building complexes6 69 7 2 6 68 1 7 55 64 18 25 35 28 1 7 AREVA NP 8(nuclear3 island)7 15 2 8 68 40 1 2 8 70 9 4 8 69 19 26 3 9 56 65 36 29 Siemens PG (turbine2 island)3 9 16 10 5 9 4 10 69 41 3 4 10 TVO (the office building)6 10 70 11 57 20 27 37 30 5 11 6646 Concentrate tanks 58 Turbine building main crane 1 4 5 11 7 17 121 11 47 Drum storage area 59 Low-pressure feedwater preheater 6 12 70 2 5 6 12 42 8 I Emergency power generating28 60 Feedwater pumps 132 12 58 38 7 13 67 21 31 1 3 6 7 13 building 61 Low-pressure feedwater preheater 9 18 1 143 13 1 8 14 43 48 Emergency diesel generators M Switchgear building 2 4 7 8 14 1 10 29 1 2 154 14 59 68 22 39 2 9 5 15 J Access building 3262 Transformer boxes 3 1 8 9 15 19 2 11 2 3 1651 15 K Office building N Circulating water pump building 3 1 10 6 16 44 4 2 9 10 16 30 3 12 L Turbine building 40 O Essential service water pump 3 4 1762 16 60 69 23 4 2 11 7 17 33 5 3 10 11 17 20 49 Moisture separator/reheater building 4 13 4 5 1873 17 45 65 31 12 8 18 50 High-pressure feedwater P Anti-icing pumps 4 11 12 18 5 14 65 24 31 5 6 1984 18 70 41 34 76 42 13 9 19 61 preheaters Q Auxiliary boiler building 5 12 13 19 6 15 21 6 7 2095 19 46 51 High-pressure turbine 63 Demineralized water storage tanks 87 53 14 10 20 6 13 14 20 66 7 106 16 20 52 Low-pressure turbine25 32 64 Auxiliary stand-by transformer 8 47 8 21 42 35 9 6 15 21 62 117 14 15 21 22 53 Condensers 65 Unit transformers 8 7 17 64 9 58 9 1122 21 47 10 7 16 22 54 Cross over lines 66 Auxiliary normal transformers 128 15 16 22 9 8 18 26 33 43 36 10 69 10 1223 22 8 17 23 63 55 Generator 67 Switchyard 11 139 16 17 23 23 10 9 19 48 107 11 1324 23 56 Exciter 68 High-voltage lines 11 9 18 24 12 1410 17 18 24 27 34 11 10 20 57 Feedwater tank 44 37Computer graphics: Images & Process 10118 12 1425 24 64 12 19 15 25 24 13 11 18 19 25 12 21 49 129 13 151126 25 13 11 20 16 26 14 12 19 20 26 28 35 38 13 22 45 131014 161227 26 65 14 12 21 17 27 25 15 13 20 21 27 50 14 23 1415 131728 27 1615 1311 22 18 28 14 21 22 28 29 36 46 39 15 24 1516 141829 28 66 1716 1412 23 19 29 26 15 22 23 29 51 16 25 Olkiluoto 3 1617 151930 29 7 1817 1513 24 20 30 30 37 16 23 24 30 47 40 17 2016 26 30 18 141718 31 2767 19 16 25 31 2117 24 25 31 52 18 17 27 19 151819 2132 31 20 17 26 32 38 2218 25 26 32 31 48 19 18 28 41 20 161920 2233 32 2868 18 27 33 21 2319 26 27 33 53 20 19 29 201721 2334 33 21 19 28 34 39 49 22 2024 27 28 34 32 42 21 20 30 20211822 2435 34 2969 22 29 25 35 54 23 21 28 29 35 22 31 221923 252136 35 40 23 21 30 26 36 33 50 24 22 29 30 36 43 23 32 30 232024 262237 36 70 24 22 31 27 37 55 25 23 30 31 37 24 33 2425 272338 37 2625 2321 32 28 38 34 41 51 24 31 32 38 44 25 34 2526 282439 38 31 2726 2422 33 29 39 56 25 32 33 39 26 35 2627 292540 39 2827 2523 34 30 40 35 42 52 45 26 33 34 40 27 3026 36 40 28 242728 41 32 57 29 26 35 41 2731 34 35 41 28 27 37 29 252829 3142 41 36 43 53 30 27 36 42 46 2832 35 36 42 29 28 38 33 30 262930 3243 42 58 28 37 43 31 2933 36 37 43 30 29 39 273031 3344 43 37 44 54 31 29 38 44 47 32 3034 37 38 44 31 30 40 34 30312832 3445 44 59 32 39 35 45 33 31 38 39 45 32 41 55 322933 353146 45 38 45 48 33 31 40 36 46 34 32 39 40 46 33 42 35 60 333034 363247 46 34 32 41 37 47 35 33 40 41 47 34 43 39 46 56 3435 373348 47 49 3635 3331 42 38 48 34 41 42 48 36 35 44 3536 383449 48 61 3736 3432 43 39 49 35 42 43 49 36 45 40 47 57 3637 393550 49 50 3837 3533 44 40 50 36 43 44 50 37 37 46 62 3738 403651 50 3938 3634 45 51 3741 44 45 51 58 38 47 48 3839 413752 51 41 51 4039 3735 46 52 3842 45 46 52 38 39 48 63 3940 423853 52 40 3836 47 53 41 3943 46 47 53 49 59 40 49 52 40 433954 53 42 41 39374148 54 39 42 4044 47 48 54 64 41 4055 50 54 40413842 44 42 49 45 55 50 60 43 41 48 49 55 42 56 51 55 43 53 423943 4541 43 41 50 46 56 40 44 42 49 50 56 65 43 57 52 56 434044 4642 44 42 51 47 57 51 45 43 50 51 57 61 54 44 58 53 57 44 4445 4743 45 4341 52 48 58 46 44 51 52 58 41 66 45 59 54 58 4546 4844 46 4442 53 49 59 52 47 45 52 53 59 45 62 55 46 60 55 59 4647 4945 47 4543 54 50 60 48 46 53 54 60 42 67 56 47 48 504661 60 48 464447 55 61 53 49 4751 54 55 61 46 63 56 57 48 49 514762 61 49 474548 56 62 50 4852 55 56 62 43 68 58 49 50 524863 62 50 484649 57 63 54 64 51 4953 56 57 63 47 57 50 59 51 534964 63 51 494750 58 64 44 52 5054 57 58 64 69 60 51 50 64 5152 5465 52 5048 59 55 65 48 55 65 58 53 51 58 59 65 52 61 65 5253 555166 53 5149 60 56 66 45 70 54 52 59 60 66 53 62 66 5354 565267 56 54 5250 61 57 67 49 66 59 55 53 60 61 67 54 63 67 5455 575368 55 5351 62 58 68 46 56 54 61 62 68 55 64 68 5556 585469 57 56 5452 63 59 69 50 67 60 57 55 62 63 69 56 65 69 5657 595570 47 57 5553 64 60 70 58 56 63 64 70 66 57 58 6056 70 58 68 58 565457 65 51 61 59 5761 64 65 58 67 59 6157 48 59 575558 66 60 5862 65 66 59 68 60 6258 59 69 60 585659 67 52 62 61 5963 66 67 60 69 60 6359 49 61 59576168 62 6064 67 68 61 60 70 60 70 615862 64 62 60 69 65 53 63 63 61 68 69 62 50 625963 6561 63 61 70 66 64 62 69 70 63 636064 6662 54 61 64 62 67 64 65 63 70 64 51 6465 6763 65 6361 68 66 64 65 62 6566 6864 55 65 66 6462 69 67 65 66 52 6667 6965 67 6563 70 68 66 63 67 68 7066 56 66 68 666467 69 67 53 68 69 67 69 676568 70 68 64 69 70 68 57 67 70 686669 69 54 70 69 696770 70 58 65 70 68 7068 55 69 59 66 69 70 56 60 67 70 57 61 68 58 62 69 59 63 70 60 64 61 65 62 66 63 67 64 68 65 69 66 70 67

70 The reactor building is surrounded Safeguard by the fuel building and four inde- building pendent safeguard building divisions. division 1

Safeguard building Fuel building division 2

Safeguard building Reaktorirakennus division 3

Polttoaine- rakennus

Safeguard building division 4

Reaktorilaitoksen poikkileikkaus

CONTAINMENT BUILDING (REACTOR BUILDING)

FUEL BUILDING SAFEGUARD BUILDING DIVISIONS 2 AND 3

STORAGE AREA FOR RPV – CLOSURE H. SPENT FUEL MAST BRIDGE

INCORE INSTRUMENT

STORAGE POOL

L SPRAY

O VALVES

S SPRAY

R U LINES

SG –BLOW DOWN SYSTEM PIPE CVCS DUCT

CVCS PIPE VALVE VALVE DUCT EBS–TANK ROOM ROOM

IRWST PIPE SPREADING AREA CVCS PUMP DUCT

EBS PUMP SUMP

8 Olkiluoto 3 One unit, many buildings

The new OL3 power plant unit is being built to the west of temperature and pressure loads that may be caused by the existing ones. The buildings in the new complex can pipe breaks. The massive outer containment is a cylinder be roughly divided into three parts: the nuclear island, in reinforced concrete that shares the same base slab as the turbine island, and auxiliary and support buildings. the inner containment and protects it against external hazards. This massive double-shell structure is a new Nuclear island safety feature which the earlier power plants do not have. The principal components of the nuclear island are the Preventing release of radioactive material in case of an reactor containment, the fuel building and safeguard accident sets extreme requirements on the leak-tightness building divisions surrounding it. The reactor primary of the containment building, which has an inner liner circuit is housed in a gas-tight and pressure-resistant of steel for this reason. The tightness of the building is double-shelled containment building, also known as the closely monitored. Any leaks which occur are arrested reactor building. between the inner and outer shells of the containment The fuel building, which houses pools for fresh and building, then filtered and delayed in the annulus ven- spent fuel, is on the south side of the reactor building and tilation system before being conveyed to the ventilation is about 50 m long, about 20 m wide and more than 40 m stack. high. In addition to fuel storage, it is connected to work- Personnel access to the containment building is man- shop areas. Flanking the fuel building are the reactor aged through a special airlock during normal operation. plant auxiliary building and waste management building; The airlock has double-sealed doors at both ends; it is the latter is used for handling plant waste. impossible to open both ends of the airlock at the same The reactor building, fuel building and safeguard time. Personnel access is at ground level. There is also building divisions are designed to be able to withstand an emergency airlock on the service floor at about 19 m various types of external hazards such as earthquakes and level through which personnel access to and from the pressure waves caused by explosions. All these buildings containment building can be managed. are built on the same base slab. The big equipment hatch on the maintenance plat- The reactor building, the fuel building and two of the form is used during construction and annual outages for safeguard building divisions are designed to withstand a bringing large components and devices into the contain- crash by a large aircraft. ment building. The main crane of the reactor building, located above the containment building service floor has Reactor containment building a lifting capacity of 320 tonnes. The OL3 reactor unit has a double-shelled containment The reactor building has an external diameter of about building in reinforced concrete. 57 m, a volume of about 80,000 m3 and a total height in- The shape of the building was chosen for strength cluding underground levels of about 70 m. The ventila- and on the basis of construction technology. The inner tion stack is about 100 m high. containment is a prestressed cylinder in reinforced concrete with an elliptical cover. It is designed to withstand

Olkiluoto 3 9 The inner containment building is clad with steel to ensure the gas-tightness of the building. The containment’s design pressure is 5.3 bar.

Lifting of the steel liner dome part in November 2009.

10 Olkiluoto 3 Safeguard buildings above four. The emergency and station blackout diesel The OL3 plant unit has parallel redundant safety systems generators ensure that the safety systems have power sup- which are physically separated from each other to ensure ply even under abnormal circumstances. safe operation under all circumstances. The safety systems are divided into four independent subsystems, each Turbine island of which is housed in a separate safeguard building di- The turbine building is almost 100 m long, 60 m wide vision. All four buildings have their own low head and and 60 m high, including underground levels. Its volume medium head safety injection systems, a residual heat re- is about 250,000 m3. Adjacent to it are the circulating moval system, an intermediate cooling system, a sea wa- water pump building and switchgear building. The main ter cooling system, and an emergency feedwater system. transformers and plant transformers are located to the The electrical and instrumentation and control systems north of the turbine building. are located on the upper levels of the safeguard building divisions. The control room is located in one of the safe- Auxiliary and support buildings guard building divisions. Beside safeguard building divisions 2 and 3, there is an Buildings 2 and 3 are between the reactor building and access building, which contains locker rooms and wash- the turbine island, and buildings 1 and 4 are on opposite rooms, and a monitored accessway to the radiation-con- flanks of the reactor building. Each of the buildings is trolled area. There is a bridge from the access building about 30 m long, 20 m wide and 30 m high. to the office building, where radiation-controlled office The power plant unit has four emergency diesel gen- space is available during annual outages. The power plant erators suppling power to the safety systems in case of area also contains separate buildings for housing diesel loss of offsite power. There are also two additional diesel generators, the sea water system buildings (mainly un- generators, station blackout diesels, independent of the derground), and a number of minor support buildings.

September 2010

Olkiluoto 3 11 Primary circuit main components

1 Reactor pressure vessel 2 Main coolant line, hot leg 3 Steam generator 4 Main coolant line, cross-over leg 5 Reactor coolant pump 3 6 Main coolant line, cold leg 7 Pressurizer 8 Pressurizer surgeline

8 4 2 5

12 Olkiluoto 3 PRIMARY CIRCUIT

Primary circuit

The OL3 primary circuit system consists of four individual loops. It is designed for a service life of 60 years and constructed to withstand the loads caused by every conceivable situation of operation or accident.

Primary circuit main functions The safety systems are designed so that in abnormal In each of the four loops comprising the primary circuit, events they are able to perform a rapid shut-down of the coolant leaving the reactor pressure vessel at a tem- the reactor, known as a reactor scram. This ensures that perature of 328°C goes through the main coolant line hot the reactor releases as little energy as possible while also legs to the steam generators, where heat is transferred to helping reduce pressure with maximum efficiency and the secondary circuit. The coolant, its temperature now keeping the actuation of the safety valves to a minimum. approximately 296°C, is returned by the reactor coolant pump to the reactor through the inlet nozzles. Inside the reactor pressure vessel, the coolant first flows down out- side the reactor core. From the bottom of the pressure vessel, the flow is reversed up through the core, where the coolant temperature increases as it passes through the fuel rods and the assemblies formed by them. The pressurizer connected to the primary circuit keeps the pressure in the reactor high enough to prevent the coolant from boiling. Under normal conditions, the circuit is full of water which effectively transfer heat from the reactor core. Connected to one of the four individual Aligning of a cross-over leg. loops, the pressurizer is larger in volume compared with the existing power plants so that it can better respond to any pressure transients during operation. This helps smooth pressure spikes and extends the useful life of the main components of the primary circuit.

Reactor cooling system properties

Reactor thermal power 4,300 MWth Primary circuit flow 23,135 kg/s Primary coolant flow per loop 28,330 m3/h Coolant temperature in the cold leg 296°C Coolant temperature in the hot leg 328°C Primary circuit design pressure 176 bar Primary circuit operating pressure 155 bar Secondary circuit design pressure 100 bar Main steam pressure under normal conditions 78 bar Main steam pressure during hot shut-down 90 bar

Olkiluoto 3 13 Properties of the reactor pressure vessel and itsPW innerR structures Cross-section of reactor pressure vessel and internal structures Control Rod Drive Reactor pressure vessel Mechanis Design pressure 176 barm(CRDM) Design temperature 351°C Control rod drive mechanism Reactor level measurement probe Life time (capacity factor 90%) 60 years Inside diameter (under cladding) 4,885 mm Wall thickness (under cladding) 250 mm Bottom wall thickness 145 mm Height with closure head 12,708 mm Reactor pressure vessel head Base material 16 MND 5 Cladding material stainless steel (less than 0.06% cobalt) Mass with closure head 526 t Control End of life fluence level (E > 1 MeV) rod guide - design value 2.65 x 1019 n/cm2 assembly - expected value ca. 1 x 1019 n/cm2 Core Base material final RTNDT barrel (final ductile-brittle transition temperature) ca. 30°C Coolant Coolant Closure head inlet outlet nozzle nozzle Wall thickness 230 mm Number of penetrations: - control rod mechanisms 89 pcs - dome temperature measurement 1 pcs Pressure - instrumentation 16 pcs vessel - coolant level measurement 4 pcs shell Base material 16 MND 5* Cladding material stainless steel (less than 0.06% cobalt) Control Upper inner structures assembly Upper support plate thickness 350 mm Upper core plate thickness 60 mm Main material Z3 CN 18-10 / Z2 CN 19-10** Lower inner structures Lower support plate thickness 415 mm Lower inner structure material Z3 CN 18-10 / Z2 CN 19-10** Core support grid Fuel assembly Neutron reflector Material Z2 CN 19-10** Weight 90 t * low-alloy ferrite steel Flow distribution plate ** austenitic stainless steel

14 Olkiluoto 3 Reactor pressure vessel and

internal structures Primary circuit

Pressure vessel structures include the control rod guide The reactor pressure vessel contains the thimbles, whose fastenings and beams are reactor core. Both the pressure vessel and fixed to the control rod support plate and the vessel head are made of forged ferrite the upper core support plate. steel. They are also clad with stainless steel on the inside to prevent corrosion. Core barrel The pressure vessel is supported by The flange of the core barrel rests on the beams which rest on the support ring in machined flange of the pressure vessel, the top part of the reactor cavity, under and is kept in place by a large spring. The the eight primary circuit pipes. The vessel fuel assemblies rest on a perforated core head is fastened with bolts and a sealing Source: AREVA support plate, made of forged stainless gasket. Reactor pressure vessel upper inner steel and welded to the core barrel. Each To manufacture the reactor with as few structures (Chooz 1, France). fuel assembly is positioned by two pins welding seams as possible, the flange and 180° apart. nozzle area of the pressure vessel is forged from a single piece of metal. There are no welding seams Neutron reflector (heavy reflector) between the flange and the nozzles. Combined with the There is a steel neutron reflector, heavy reflector, around structure of the nozzles, this ensures that there is a con- the polygonal core, between the core and the cylindrical siderable distance and a large volume of water between core barrel. The reflector reduces the number of neutrons the nozzles and the top of the core. This minimizes the escaping from the core and flattens the power distribu- exposure of the structures to neutron radiation. tion. It also reduces the exposure of the pressure vessel to the neutron radiation that reduces ductility in its mate- Internal structures rial, and also dampens any pressure spikes which the in- The internal structures of the reactor pressure vessel sup- ternal structures and fuel in the reactor might be exposed port the fuel assemblies in the core, enabling the reactiv- to in case of pipe break. ity of the core to be controlled by the control rods and The heavy reflector consists of pieces of stainless steel the fuel to be cooled with water under all circumstances. piled up and linked together. The tie rods bolted to the The inner structures are partly removed during refuelling core support plate keep the pieces in place axially. The and can be completely removed for an inspection of the heat generated in the steel by gamma radiation is ab- inner wall of the pressure vessel. sorbed by the primary coolant flowing through cooling The pressure vessel also contains upper internal struc- ducts in the reflector. tures, whose function is to support the top of the fuel assemblies and to keep them correctly aligned axially. These

Olkiluoto 3 15 16 Average linearheatrate Number offuelrods Number offuelassemblies Active coreheight Equivalent diameter Primary coolanttemperatureintheoutlet Primary coolanttemperatureintheinlet Operating pressure Reactor thermalpower Reactor core properties Olkiluoto 3 High enrichedassemblywithgadolinium Medium enrichedassemblywithgadolinium Low enrichedassemblywithoutgadolinium Initial core loading 156.1 W/cm 63,865 pcs 241 pcs 4,200 mm 3,767 mm 329°C 296°C 155 bar 4,300 MWth TC

temperature measurement core externalneutronfluxmeasurements 4 waterlevelprobes 89 controlassemblies 3-4 aeroballprobes 6 in-coreneutronfluxdetectors 3 coreoutlettemperaturesensors 12 lanceyokes,eachcomprising: In-core instrumentation

Aeroball system (neutron flux measurement calibration system)

Core instrumentation TC Primary circuit 17 - Olkiluoto 3 Olkiluoto 3 The core power distribution is is also distribution power core The The main core properties and opera - and properties core main The

measured at regular intervals using the the intervals using regular at measured tional conditions have been selected have to conditions tional low a high and achieve thermal power is also core reactor OL3 The costs. fuel ternal and external instrumentation. The The external instrumentation. ternal and comprises instrumentation in-core fixed - measure temperature and flux neutron the of the distribution monitoring ments - tempera and the in core the flux neutron the part of in the upper distribution ture used is for instrumentation Ex-core core. monitor also for and measurement power All outages. during sub-criticality core ing instru- core for required thepenetrations head. vessel in the pressure are mentation achieved thus results The system. aeroball neu- in-core fixed calibrating used for are devices. measurement flux tron output are controlled using the control the control using controlled are output assemblies. - refuel various to designed be to adaptable situations. operating intervals and ling instrumentation Core in- with both measured is power core The Active core height core Active gas Aeroball system tube Carrier flux in the reactor core. Shroud Ball stop Balls made of a vanadium alloy results are used to calibrate the The activation of the balls in one Ball guide are fed into 40 narrow tubes from Steel balls tube is measured at 36 points. The guide tubes in the fuel assemblies. above the reactor and pneumatically devices used to measure the neutron propelled to the reactor core through - Reactor core and fuel and core Reactor - gadolin U also contain 235 - its com to due primary The coolant, The refuelling interval of the reactor reactor of intervalrefuelling the The The number and properties of the fuel properties and number The position, is a significant neutron mod - neutron a significant is position, conveys The coolant reflector. and erator - ap of a pressure at the core from heat temperature a and bar 155 proximately control changes in reactivity that are fairly fairly are that reactivity in changes control fuel burn-up. of the impact as such slow, in power and in reactivity changes Rapid of 312°C on average. The primary The coolant average. 312°C on of the of some which absorbs boron, contains helps level the boron Adjusting neutrons. core can be 24 months. can 12 to core ticularly the load pattern and the length of the of length and ticularly the load pattern interval. the refuelling tens the power distribution. the power tens depend on annually replaced assemblies par chosen, plan the fuel management thus reduces the reactivity of the initial the initial of the reactivity reduces thus - flat and operation the reactor’s of phase The OL3 reactor core consists of 241 fuel consists core reactor OL3 The the For in structure. identical assemblies di- are loading, the assemblies initial core their to according groups three vided into with the groups two The level. enrichment of levels highest ium, which acts as a neutron absorber and and absorber which acts a neutron as ium, 17 x 17 fuel assembly

Top nozzle

Spacer grid

Fuel rod

Fuel properties

Fuel uranium dioxide UO2 Fuel assembly type 17 x 17 HTP Number of fuel rods per assembly 265 pcs Number of guide thimbles per assembly 24 pcs Bottom nozzle Number of spacer grids per assembly 10 pcs Length of fuel assembly 4.8 m Weight of fuel assembly 735 kg Width of fuel assembly 213.5 mm Cladding material M5TM 3 UO2 pellet density 10.45 g/cm Fuel discharge burnup 45 MWd/kgU

18 Olkiluoto 3 Primary circuit 19

2 - ). 2 Olkiluoto 3 Olkiluoto 3 U. The enrichment level of of level enrichment The U. 235 - re reduce to helping , the latter 3 O 2 The rods are welded hermeticallywelded leak-are rods The The helium. using pressurized and tight - the fis from comes the reactor of power in the pellets, mainly the uranium of sion theisotope the pellets varies, being just under 5% at 5% at under the pellets being just varies, the the fuel rods, of some In highest. its UO of alloy an of made fuel pellets are Fuel rods Fuel compressed containing a tube is A fuel rod (UO dioxide uranium pellets of ceramic and Gd - distribu the power flatten to and activity fuel rods. in fresh tion Source: AREVA The cladding tubes of the fuel rods are made of a zir made are rods of the tubesfuel cladding The conium alloy. The cladding is the first barrier to the re- barrier tothe is first the cladding The alloy. conium the fuel and separates it as radioactivelease emissions of is There primary the coolant. products from theirfissile reduces rod, gases which within the fuel fission space for the gases from released by caused increase the pressure are The pellets reaction. pellets in the nuclear uranium the fuel rod. of the top inside a spring by in place held The fuel supplier for the OL3 reactor is AREVA NP. OL3 reactor is AREVA The eight middle spacer grids in the fuel assembly are are middlespacer grids eight in assembly The the fuel The fuel rods form a 17 x 17 matrix. matrix. a 17 x 17 form rods The fuel - dis to shaped is nozzle The bottom and lowermost spacer grids are made of nickel-based al nickel-based - of made spacer grids are lowermost and requirements. their higher strength because of loy made of zirconium alloy. They have flow guides to en- guides flow Theyhave alloy. zirconium of made uppermost The the fuel rods. from transfer heat hance which the fuel assemblies are kept stationary against the against stationary kept are which the fuel assemblies flow. primary coolant any foreign objects that may end up in the up end may objects that foreign any - ob the fuel assembly; such entering from primary circuit has nozzle top The it. damage jects mechanically could with the force achieve side to each set on spring a leaf tied together by end pieces at either end. either at pieces end by tied together isalso There evently. flow coolant tribute prevent to end at lower the filter a debris Each fuel assembly contains 265 fuel rods, fuel 265 rods, contains Each fuel assembly grids,spacer 10 and thimbles guide 24 guide thimbles, spacer grids and the end the end spacer grids and guide thimbles, of structure the supporting form pieces the assembly. Fuel assembly Fuel spac- fuel rods, of consists A fuel assembly The nozzles. bottom and top er grids and The final repository for spent fuel is being built at built is fuel being for spent repository final The After sufficient cooling, the spent fuel is transported to transported isfuel thecooling, spent sufficient After fuel spent the repository, in the final placement Before Olkiluoto by Posiva Oy, a company which is jointly jointly which is company a Oy, Posiva by Olkiluoto time, the radioactivity and heat output of the fuel de- of output heat the radioactivitytime, and making their original values, 1/1000 of than less to crease simpler. the fuel much the of further handling who will Oy, Heat and Power Fortum and TVO by owned fuel spent from The operation. its for also be responsible will in Loviisa units also be de- plant power the nuclear will begin Final placement in 2020. Olkiluoto. at posited for a few years to cool them off. At the same time, the the At time, the same cool them off. to years a few for fuel decreases substantially. the spent radioactivity of a using site plant the power at facility storage interim an fuel pool the spent below docked which is fuel cask spent facility. a transfer using several decades. for During this storage in interim kept is Spent fuel assembly handling assem - fuel spent reactor, the from removed being After fuel pools in the fuel in the building spent kept are blies Spent fuel assemblies that have been in the reactor are are been in the reactor have that fuel assemblies Spent Core unloading takes about 40 hours in all, and core core in all, and 40 hours unloading takes about Core Fuel assemblies are moved between the reactor and and between the reactor moved are assemblies Fuel Olkiluoto 3 radiation protection, at Olkiluoto the fuel assemblies are are the fuel assemblies Olkiluoto at protection, radiation water. 3 m of least at under kept always safeguard measures of reactor fuel. reactor of measures safeguard radiation and cooling all times for at water under kept be sufficient would water 1 m of Although protection. The Finnish Radiation and Nuclear Safety Authority Authority Safety Nuclear and Finnish The Radiation in each all participate the IAEA and Euratom (STUK), and handling appropriate the to ensure final inspection in the refuelling machine takes about 45 hours. The final The 45 hours. takes about machine in the refuelling of placement the correct ensure to intended inspectionis plan. the refuelling following in the core, fuel assemblies reloading plus a final core inspection using the camera camera the using inspection a final core plus reloading the fuel building through the fuel transfer tube. There is a There tube. the fuel transfer through the fuel building in the and building in the reactor machine fuel handling fuel building. being operated at 12-month cycles, one quarter of fuel is fuel is of quarter cycles, one 12-month at being operated are assemblies of fuel kinds Different annually. replaced the restrictions with in compliance placed in the reactor fuel use. and core the reactor on - out During a refuelling also stored. are assemblies spent are in the reactor fuel assemblies the spent of some age, is if the reactor example, For ones. fresh with replaced Fuel handling Fuel fuel in the fresh either stored are fuel assemblies Fresh in the fuel pools racks where in storage or dry storage

Primary circuit 20 Primary circuit 21 Olkiluoto 3 Olkiluoto 3 Refuelling machine in the reactor building Installing new fuel assemblies in the core is performed using the same Installing new fuel assemblies fuel building. The container is again turned to a vertical position, and the and position, vertical a to turned again is container The building. fuel the fuel assembly out and transfers it to the spent fuel mast bridge lifts the spent fuel pool. spent fuel storage rack in process in reverse. Fuel assembly transfer mechanism Fuel transfer tube Fuel transfer systems in the reactor building and fuel building in the reactor systems transfer Fuel Spent fuel mast bridge in the fuel building Transferring fuel out of and into the core fuel out of and into Transferring a fuel assembly out of the reactor core and The refuelling machine lifts which is in a vertical position. The container, transfers it to the transfer the transfer container to a horizontal position transfer mechanism turns transfer tube to the and moves it from the reactor building through the Cross-section of control rod drive mechanism

Plug connector

Upper limit position indicator coil Drive Control rod system properties rod upper final Rod cluster control assemblies position Number 89 pcs Weight 61.7 kg Control rods per assembly 24 Position indicator coil Sheet steel Absorber casing B4C part (upper part) 10 Lower limit position - natural boron 19.9% B atoms indicator coil 3 Drive rod lower - specific weight 1.79 g/cm final position - external diameter 8.47 mm - length 1,340 mm Lifting pole AIC part (lower part) Lifting coil - weight composition: silver, indium, cadmium (%) 80,15, 5 Lift armature - specific weight 10.17 g/cm3 - external diameter 8.65 mm Gripping coil - length 2,900 mm Gripping armature Cladding Gripping latch Material stainless steel Gripping latch carrier Surface treatment (external surface) ion nitrification External diameter 9.68 mm Holding pole Holding coil Internal diameter 8.74 mm Holding latch carrier Filling gas helium Holding armature Control rod drive mechanisms Holding latch Number of drive mechanisms 89 pcs Flange connection Weight 403 kg Sealing area Lifting power >3,000 N Travel range 4,100 mm Stepping speed 375 mm/min or Control rod drive 750 mm/min mechanism nozzle Maximum scram time allowed 3.5 sec Materials austenitic and martensitic stainless steel

22 Olkiluoto 3 Primary circuit 23

- Olkiluoto 3 Olkiluoto 3 The control assemblies in the control control in the assemblies control The The control bank in operation is regu- is operation in bank control The insertion sequence and control assembly assembly control insertion and sequence - timeregard any at bebankscan changed power. reactor the current of less primary circuit and flatten vertical power flatten and primary circuit core. in the reactor distribution quadruplets, further divided into bank are sequences drive used in various which are the on depending insertion sequences and The current interval in progress. refuelling 36 elements control the temperature of the of the temperature control 36 elements larly changed at intervals of about 30 days 30 days about intervals of at changed larly - dis fuel avoids This operation. power of - effec the affecting from burnup charge equalizes the and the control of tiveness burnup. Source: AREVA The control rod drive mechanisms are installed into installed into are mechanisms rod drive control The A control rod drive mechanism consists of the pressure the pressure of consists mechanism drive rod A control drive the unit, latch the connection, flange with housing of control the role The their housings. and the coils rod, to is the reactor in controlling mechanisms drive rod of the length throughout assemblies the 89 control move Their required. location any them at keep to and the core the into assemblies the control drop to secondary is role shutting and reaction the chain stopping thus reactor, particularly seconds, in of in a number down the reactor assem the control and grooves, the rod from retracted gravity. of force by the core into drop blies Each head. vessel pressure the reactor to welded adapters be can installed that entity a separate is mechanism drive the others. of independently removed and a scram situation. When the reactor scram signal scram acti is - the reactor When situation. a scram are the latches de-energized, are coils all operating vated, Control rod drive mechanisms mechanisms drive rod Control neutron sources. The individual control rods of the reactor control assemblies move in blies. These guide thimbles are also the guide thimbles in the fuel assem- used for placing instrumentation and - Reactor operation and control and operation Reactor - con separate divided into are assemblies control The The control rod system is governed by the reactor reactor by the governed is rod system control The shut-down bank, which executes a rapid shut-down of of shut-down rapid a bank,whichexecutes shut-down remaining The necessary. if scram, reactor or thereactor, trol groups. The majority of them, 53 elements, are in the are elements, of 53 them, majority The groups. trol The rods contain materials that absorb neutrons (silver, (silver, neutrons absorb that materials rods contain The the rods When carbide). boron and cadmium indium, they totally almost the core, inserted into completely are the fuel assemblies. of length the active cover There are 89 identical control assemblies. Each consists consists Each assemblies. control identical 89 are There mount. single a to attached rods absorber identical 24 of Control assemblies Control control, surveillance and limitation system and manually manually and system surveillance limitation and control, is trig - reactor scram The operators. room the control by - back its or system the protection by automatically gered may operator An system. back-up a hardwired system, up also manually. scram trigger the reactor reactor scram. The control rods enter the rods enter control The scram. reactor in the fuel guide thimbles through core assemblies. nism operating system. The system is usedis system The system. operating nism a for and power the reactor controlling for actor power control system. It consists of of consists It system. control power actor con with formed assemblies the control - mecha drive rod the control rods, trol - mecha drive rod the control and nisms Control rod system system rod Control re- of is a the rodpart system control The vertical power distribution in the reactor reactor the in distribution vertical power the bo - term, decreasing the long In core. the loss for compensate helps content ron fuel burnup. to due reactivity of The control assemblies are one system to to system one are assemblies control The to addition In power. the reactor control they also flatten control, power short-term Cross-section of steam generator

Steam outlet nozzle

Steam dryer Secondary manway

Steam separator Steam generator properties

Number of steam generators 4 pcs Emergency Heat transfer surface per Emergency feedwater ring feedwater nozzle steam generator 7,960 m2 Feedwater ring Primary circuit design pressure 176 bar Primary circuit design temperature 351°C Feedwater nozzle Secondary circuit design pressure 100 bar Secondary circuit design temperature 311°C Upper lateral Bundle double wrapper Heat transfer tube external diameter / support brackets wall thickness 19.05 mm / 1.09 mm Number of tubes 5,980 pcs Triangular pitch 27.43 mm Total height 23 m Materials Bundle wrapper Tube support plates Tubes Inconel 690 alloy, heat treated Shell 18 MND 5* Cladding tube sheet Ni-Cr-Fe alloy Tube support plates 13% Cr-treated Tube sheet Partition plate stainless steel Tube bundle Other Total weight 520 t Feedwater temperature 230°C Main steam moisture content 0.25% Main steam flow 2,443 kg/s Partition plate Main steam temperature 293°C (primary circuit) Main steam saturated pressure 78 bar Pressure during hot shut-down 90 bar Coolant inlet nozzle Coolant outlet nozzle *low-alloy ferrite steel

24 Olkiluoto 3 Primary circuit 25 - Olkiluoto 3 Olkiluoto 3 - particular at generators, steam the OL3 the design of In also a higher has generator the steam hand, On the other The design concept, with the cold feedwater mixedbeing feedwater cold with the designThe concept, the asymmetrical conveying of feedwater into a discrete a discrete into feedwater of the asymmetrical conveying generator. the steam the walls of from separated channel in the sec- cross-flows of the prevention to paid was tention by thermal effects caused the adverse of and ondary circuit space steam The exchange. heat the efficient to due layering volume. the steam increasing beenhas enlarged, which the upon units plant thein power than volume water in- and margin the safety design based. is improves This all where feedwater thecreases grace period in a situation for available is water cooling no malfunction and systems generator. thesteam into feeding Inconel 690, which has a cobalt content of less than 0.015%. than less of content cobalt a 690, which has Inconel steel. of 18 MND 5 made is generator steam of the shell The a ensures water, recirculated the warmer 10% of only with efficient more a hence and differential temperature larger the OL3 of pressure steam the main a result, As transfer. heat ar exchange heat higher of per 3 bar is unit generator steam which the design based is units plant power of ea that than through achieved is generator steam efficiency of the The on. Primary coolant circuit coolant Primary The axial feedwater preheater enables not only a larger a only larger not enables preheater feedwater axialThe The primary coolant passes through U-shaped tubes in U-shaped primarypasses through The coolant the power plant unit. The tubes in the steam generator are are generator tubessteam in the The unit. plant the power called alloy corrosion-resistant and wear-resistant of made the turbine. bar, 78 of pressure also saturation a but area exchange heat in highthe efficiency factor of (37%) a significant which is along the outer shell of the steam generator. The feedwater feedwater The generator. the steam of shell the outer along gen- refill the steam of secondary the side continously pipes into fed steam of the mass to equivalent water with erator er at the top of the secondary circuit portion separate the separate the portion secondary of circuit the top at er down returns water The separated the water. from steam power plant unit is of the vertical of is type. unit plant power of the secondary circuit, feedwater The generator. the steam the shell inside circulates steam, be into to turned whichis drysteam and - separators steam The generator. the steam of ary circuit. As in a typical heat exchanger, the contents of of the contents exchanger, heat in a typical ary As circuit. direct into come the secondary primary never and circuits an EPR in generator steam The another. one with contact Steam generators generators Steam heat which transfers exchanger a heat is generator A steam - the in second thewater to circuit the primary coolant from Cross-section of reactor coolant pump

1. Flywheel 2. Radial bearings 3. Thrust bearing 4. Air cooler 5. Oil cooler 6. Motor (stator) 7. Motor (rotor) 8. Motor shaft 9. Spool piece 10. Pump shaft 11. Shaft seal housings Pump casing 12. Main flange 13. Seal water injection 14. Thermal barrier Reactor coolant pump and pipe properties 15. Diffuser 16. Impeller Pump 17. Pump casing Number of pumps 4 pcs 18. Outlet nozzle Design pressure 176 bar 19. Inlet nozzle Design temperature 351°C Primary coolant flow 28,330 m3/h Design head 100.2 m ± 5% Seal water injection 1.8 m3/h Seal water return 0.680 m3/h Speed 1,465 rpm Total height 9.3 m Total weight without water and oil 112 t Motor Rated power 9,000 kW Frequency 50 Hz Main circulation pipes Internal diameter 780 mm Wall thickness 76 mm Material Z2 CN 19-10* Pressurizer connection pipe Internal diameter 325.5 mm Thickness 40.5 mm Material Z2 CN 19-10* *low carbon stainless austenitic steel

26 Olkiluoto 3 Primary circuit 27 Olkiluoto 3 Olkiluoto 3 The shaft seal system consists of three of three consists sealsystem shaft The When the pump is in operation, the the in operation, is the pump When dynamic seals assembled into a cartridge into seals assembled dynamic seal. a standstill a first seal The is and seal, leakage controlled hydrostatically The standstill seal ensures that no prima- no that standstill sealThe ensures which takes the full primary pressure. The The which takes the full primary pressure. seal which sealsecond a hydrodynamic is can but pressure the remaining receives - primary pres the entire also withstand seal The third is also if necessary. sure leak seal. a backup is and hydrodynamic ry coolant is lost in the event of a loss of of a loss of in the ry event lost is coolant malfunction of the simultaneous or power stopped. is allsealspump shaft when the with lubricated and cooled are sealsshaft Source: AREVA The motor is a drip-proof squirrel-cage asyncronous asyncronous squirrel-cage drip-proof a is motor The seal injection water which is injected below the seals at a the seals below injected which is at seal water injection the primary of coolant. that higher than slightly pressure two, first tothe is ashaft seal, backup which The third the demineralized water from water cooling its receives system. distribution the and placed A spool between piece the pump motor. enable structure housing shaft seal and the shafts motor the seal on be without pack to carried out maintenance the motor. removing (N4, 1,500 MWe). Reactor coolant pump at the Jeumont plant in France The pump hydraulic cell consists of the impeller, the of impeller, the cell consists hydraulic pump The - hydro have pumps coolant reactor The parts: main three of consists pump coolant A reactor one hydrostatic bearing at the impeller. There is a double- is There theimpeller. bearingat hydrostatic one under shaft, the motor of the top action thrust bearing at forces. axial to compensate the flywheel, diffuser and the suction adapter. The pump shaft is in two in is shaft pump The adapter. suction diffuserand the bewhich a spool can removed piece parts by connected on three supported is shaft The seal maintenance. for and bearings in the motor oil-lubricated bearings: two the pump itself, the shaft motor. and sealsthe the shaft itself, the pump have three separate shaft seals and an ad- and seals shaft separate three have seal standstill operated which is ditional pressure. gas by erator outlet and the reactor inlet. the reactor and outlet erator - vibra a low bearings, which ensure static pumps coolant reactor OL3 The level. tion secondary circuit. In each of the four loops loops the four each of secondary In circuit. coolant the reactor the primaryof circuit, - gen between located the is steam pump Reactor coolant pump Reactor forced provide pumps coolant reactor The the reactor through water of circulation removes circulation This system. coolant the steam to core the reactor from heat the to transferred is it where generators, Cross-section of pressurizer

Access hatch Venting nozzle Safety valve nozzle

Level and temperature Convex end measurement nozzle

Spray inlet Source: AREVA Spray nozzle

Cylinder shells

Pressurizer properties

Design pressure 176 bar Support plate Design temperature 362°C Support Total volume 75 m3 Total length 14.4 m Base material 18 MND 5* Cylindrical shell thickness 140 mm Number of heaters 108 Convex end Total weight, empty 150 t Level and Total weight, filled with water 225 t temperature measurement Number of safety valves and capacity nozzle Flow distributor under design pressure 3 x 300 t/h Relief valve capacity under design pressure (doubled for valves) 1 x 900 t/h Heaters Surge line * low-alloy ferrite steel

28 Olkiluoto 3

Primary circuit

Pressurizer All components of the pressurizer shell, except for the The pressurizer contains primary coolant in its lower part heater penetrations, are made of forged ferrite steel with two and steam in its upper part. The pressurizer is part of the layers of cladding. The material is the same as in the reactor primary circuit and is connected through a surge line to the pressure vessel. The heater penetrations are made of stain- hot leg of one primary loop. The purpose of the pressurizer less steel and are welded using a corrosion-resistant alloy. is to keep the pressure in the primary circuit within speci- The pressurizer supports are welded to its frame. fied limits. Compared with plants which the design of OL3 is based The pressure in the primary circuit is controlled by regu- on, the volume of the pressurizer has been increased in or- lating the steam pressure. For this purpose, the pressurizer der to smooth the response to operational transients. has heaters in its lower part to produce steam and a spray system in its upper part to condense steam into water. Main coolant lines The pressure-relief and safety valves at the top of the The main coolant lines of the four loops that form the pri- pressurizer protect the primary circuit against excessive mary circuit and the pressurizer surge line are part of the pressure. There are two parallel pressure-relief lines with reactor coolant system in the reactor building. The main valves which the operators can use, in the case of a severe coolant lines convey the primary coolant from the reactor accident, to relieve pressure quickly in the primary circuit: pressure vessel to the steam generators and onward to the the primary coolant released from the primary circuit is dis- reactor coolant pumps, which return the coolant to the charged to the pressurizer relief tank, where a rupture disk pressure vessel. One of the four loops is connected to the breaks and releases the coolant into the containment build- pressurizer. ing. There the steam condenses into water, which is collect- Each of the four loops has three parts: the hot leg from ed in the emergency cooling water storage tank at the reactor pressure vessel to the steam generator, the the bottom of the containment building and cross-over leg from the steam generator to the re- pumped back into the reactor. actor coolant pump, and the cold leg from the The maintenance platform running reactor coolant pump to the reactor pressure around the pressurizer facilitates heater vessel. replacement and reduces radiation dos- The main circulation pipes are made of es during valve maintenance. forged austenitic stainless steel, which is resistant to thermal fatigue and can be inspected using ultrasound.

The pressurizer was installed in November 2010.

Olkiluoto 3 29 1 Moisture separator reheater (MSR) 2 High-pressure turbine 3 Low-pressure turbine 4 Condenser 5 Generator

30 Olkiluoto 3 Secondary circuit 31 Olkiluoto 3 Olkiluoto 3 The feedwater is preheated in three feedwater heating heating feedwater in three preheated is feedwater The The main condensate is preheated in four low-pressure low-pressure four in preheated is condensate main The contains a mechanical condensate purification system for for system purification condensate mechanical a contains impurities. removing system Feedwater feedwater pumping three pumps, feedwater four are There the high pressure tank through storage thefeedwater from The generators. the steam to system preheating feedwater pump. acts a stand-by as pump fourth - high-pres two of consisting train each trains, two in stages - con 2 stage the reheating and preheaters feedwater sure - high-pres the is extracted into steam The coolers. densate extractions theturbine HP from preheaters feedwater sure is the feedwater system, the preheating A6. From A7 and in the safeguard valves the feedwater through conveyed generators. the steam into divisions building There are three condensate extraction pumps (CEP), two (CEP), pumps extraction condensate three are There - con the condenser from condensate the main pumping tank storage the feedwater to wells) (hot chambers densate system. preheating feedwater the low-pressure through pump. stand-by actsas a pump The third the efficiency ofthe improve to stages heating feedwater also system condensate main The process. steam-water Main condenser and condensate system Main condenser and condensate SECONDARY CIRCUIT SECONDARY The purpose of the turbine bypass steam system is tois system steam bypass purposeturbine The of the From the MSRs, the reheater steam goes through the LP goes through steam the reheater the MSRs, From is condensed turbines LP the steam from exhaust The - re is driedand turbine HP the steam from exhaust The control the main steam pressure depending on the power the power on depending pressure steam the main control mode. operation plant in three separate sea water condenser units. In addition to addition In units. condenser sea water separate three in the turbine the LP turbines, from the steam condensing units. in these also is condenser condensed steam bypass heated in the moisture separator reheaters (MSR). The re- The (MSR). reheaters separator thein moisture heated extracted using steam stages, performed in two is heating steam the main from extraction and A7 theturbine HP from valves. control and stop extracted between the HP turbine the LP turbines. three to valves control and stop turbine eration. The steam is conveyed through the relief system system relief the through conveyed is steam The eration. the atmosphere. into straight valves the safety and through the four main steam lines. The main steam is fedis steam main The lines. steam main the four through - the high pres through turbine (HP) the high-pressure to each main in located valves control and stop turbine sure safety train, a relief has line steam Every main line. steam - op abnormal of in the event valve isolation an and valves Main steam system Main steam be- generators steam in the generated steam main The plant the turbine to fed is the primary to circuit longing The purpose of the steam-water secondary circuit in the turbine plant is in the turbine plant circuit secondary of the steam-water The purpose the nuclear steam entering from of the main thermal energy to convert the as efficiently and generator the turbine through energy island into electrical to the steam feedwater to return the secondary-circuit as possible and in the secondary plant. There is no radioactivity in the reactor generators are secondary circuits of the primary and water because the circuit each other. from separated The HP turbine is a double- flow turbine consisting of inner and outer casing structures split horizontally.

Turbine plant main figures Lifting of the HP turbine rotor in September 2008. General Gross electrical output 1,720 MWe Net electrical output 1,600 MWe Main steam pressure (HP turbine) 75.5 bar Main steam temperature 290°C Steam flow 2,443 kg/s Rated speed 1,500 r.p.m. HP turbine 1 LP turbine 3 Last expansion stage - exhaust area 30 m2 - last stage blade (LSB) airfoil length 1,830 mm - overall diameter 6,720 mm Length of turbine-generator rotor train 68 m Condenser Cooling surface 110,000 m2 Cooling medium sea water Cooling water flow 53 m3/s Vacuum at full load 24.7 mbar abs. Sea water temperature rise 12°C Feedwater Preheating stages 7 Final feedwater temperature 230°C Inner casing of the HP turbine.

32 Olkiluoto 3 Secondary circuit 33 - - - , produced by by , produced Olkiluoto 3 Olkiluoto 3 2 inner inner casings casings outer 9 stages, expansion stationary blade (6 stages stages running blade and as 3 stages and blades shrouded with blades) free-standing and (forged rotor machined spindle shaft shrunk-on where fitted forged and machined blade wheel discs)

• • • • LP turbines ap- produce turbines OL3 LP The three out power gross the of 60% proximately (approximately unit plant the power of put double- are each). LP turbines 320 MWe fol of consisting turbines reaction flow components: main lowing - spin of a through-bored consists rotor turbine LP The of blade sealstrips stationary and blades The running The inner and outer casings of the LP turbines consist of consist turbines of LP the casings outer and inner The the 1,830 mm profile length of the last running stage blades stage of last the running length the 1,830 mm profile the LP turbine are attached to grooves machined in themachined grooves to attached are the LP turbine (LSB). The stationary blades in the last stage are hollow hollow are stage blades in last the stationary The (LSB). is steam the expanding of moisture part of type, and vane stage. the LSB before vane the hollow via on cuts separated inner and outer casing constructions split horizontally. horizontally. split constructions casing outer and inner tur to the attached is turbine LP an of casing inner The welded is casing the outer and structure, foundation bine is which construction, condenser the to permanently - station The structures. the base foundation by supported to attached ary seal running blade are and strips blades of the The thermal expansion structures. casing theinner casing the inner from separated is structures casing outer the LP turbines. of construction rotor and flow) each for blade discs wheel (four eight with dleshaft turbine of the LP flanges coupling The fitted. shrunk-on a with shaft also partly secured the rotor are to rotors fit. shrink-on are so blade stages six wheelblade discs. running first The three the last and bands, blade called have and drum stages so exhaust The called blades. are free-standing stages blade 30 m is stage running blade the last of area

shrunk on to the turbine shaft. attached to blade wheel discs The OL3 LP turbines are double- flow turbines with running blades

Turbines and generator and Turbines inner inner casing (cast, machined) outer casing (cast, outer machined) rotor (6.26 m rotor and 100 t, and machined) forged 12 expansion 12 stages, expansion stationary blade and running blade stages stages blade

The HP turbine rotor is machined from the forging. forging. the machined is from rotor turbine HP The The rated speed of the turbine-generator turbine-generator speed of the rated The The single-shaft turbine-generator set set turbine-generator single-shaft The • • • • consists of one HP turbine and three LP LP three and turbine HP one of consists seal grooves. strip The running blades of the rotor and the stationary blade stationary and the rotor of the blades The running and blade machined the rotor to attached seal are strips and the running blade seal strips are attached to the HP to attached the seal running blade and are strips at- are constructions shaft seal The casing. inner turbine casing. outer the HP turbine tached to - construc casing outer and inner split horizontally with casing outer to the attached is casing inner The tions. turbine of HP the blades stationary The construction. The OL3 HP turbine produces about 40% of the gross of the gross 40% about produces turbine OL3 HP The a is It (650 MWe). unit plant the power of output power - fol of consisting turbine reaction double-flow admission components: main lowing HP turbine The planned - planned replace service The of the life 30 years, is the turbine of components able service the planned the turbine and of life 60 years. is a whole as plant i.e. there are double bearings between double are there i.e. module. each turbine is 68 m. length shaft its and 1,500 r.p.m., is turbines, a generator and an exciter. Each exciter. an and a generator turbines, bearings, two on mounted is rotor turbine the generator. The high 1,600 MWe power power high The MWe 1,600 the generator. the high to ef- partly is due OL3 of output set. turbine-generator ficiencyof the The thermal energy generated in the re- in the The thermal energygenerated energy mechanical to converted is actor electricity thento by and the turbines by The inner and outer casings of the HP turbine are formed formed are turbine of HP the casings outer and inner The

1. Water tank 2. Four hydrogen / water heat exchangers 3. Fan 4. Shaft seals

Generator properties

Rated speed 1,500 r.p.m. Frequency 50 Hz Effective power 1,793 MWel Nominal rating 1,992 MVA Power factor 0.9 Voltage 27 kV ± 5% Efficiency ca. 99% Magnetization current 9,471 A Cooling water temperature 45°C Hydrogen cooling medium temperature 40°C

34 Olkiluoto 3 Secondary circuit 35 - Olkiluoto 3 Olkiluoto 3 The rotor windings are cooled using hy- cooled using are windings rotor The axially through conveyed which is drogen, The 5 bar. of a pressure at the windings cooled is the hydrogen/water in hydrogen in circuit hydrogen The exchangers. heat a multi- by powered is side the generator the rotor. on mounted fan stage national grid. and is almost 17 m long. transformer and onward to the The generator output terminals through the bus duct to the main transfer the electricity generated rotates at 1,500 r.p.m., weighs 250 t rotates at 1,500 r.p.m., The hydrogen-cooled generator rotor - citation system. The stator winding and and winding stator The system. citation water-cooled. are terminals the winding Generator hydro four-pole, a is generator OL3 The ex- a brushless with generator gen-cooled Condenser unit from the inside. pumps are in use, one is a standby pump. Two of the three turbine island condensor of the three turbine Two Construction of cooling water tubes for condenser unit. Construction of cooling water tubes for condenser Olkiluoto 3

Secondary circuit 36 Secondary circuit 37 Olkiluoto 3 Olkiluoto 3 - clean feeding by soft cleaned are tubes condenser The in low vacuum sufficient a have must condenser The order to increase the power plant effeciency. The vacuum The vacuum effeciency. plant the power increase to order con- inthe vacuum a sufficient maintains system pump gases. uncondensed extracting and air denser by used as coolant is fed into the tubes through the water the water through the tubes into fed is used coolant as in water of cooling the rise temperature The chambers. 12°C. about is the condenser - col and flow water the cooling into balls ing (Taprogge) - the passed condens through theylectinghave them once er tubes. Condenser section weighs about 250 t. There are One sea water chamber for a condenser . The tube material used is titanium, which which used is tube material titanium, . The six of them in total, two for each LP turbine. 2 In addition to condensing the exhaust steam from the from steam the exhaust condensing to addition In about of surface cooling total a has condenser The 110,000 m is highly resistant to sea water corrosion. The sea water The sea water corrosion. sea to water highlyis resistant LP turbines, the condenser receives condensate and gas gas and condensate receives the condenser LP turbines, systems. process various extracted flows from chamber to be removed and inspected without turbine turbine inspected without and be to removed chamber shut-down. The exhaust steam from the LP turbines is condensed is condensed turbines LP the steam from exhaust The unit is a condenser There in the condenser. water into sea wa- separate two divided into each LP turbine, under structural one sea The water design allows chambers. ter A = Cooling water systems B = Service water system C = Anti-icing system D = Essential service water piping system E = Essential service water system pumping station F = Anti-icing pumps G = Circulating water

38 Olkiluoto 3 SEA WATER COOLING SYSTEMS

Sea water cooling systems

Sea water is conveyed along its own un- The pumping station contains four derground cooling water tunnel at a rate sea water pumps, which are vertically of 57 m3/s into the OL3 pump station. mounted in a concrete casing. Each pump Before entering the tunnel, major impuri- conveys about 13 m3/s of sea water to the ties are filtered out of the sea water with condensers. To cool the power plant sys- coarse screens. In the pumping station, tems, 4 m3/s of the total sea water flow is the water is conveyed through four fil- used. From the condenser, the water goes tering lines to the sea water pumps. The to a seal pit and then through the outfall filtering lines contain a fine screen and a tunnel to the sea. The outfall channel is chain basket filter to remove minor impu- shared with OL1 and OL2. rities from the sea water. The cooling water intake tunnel has a cross-section of about 60 m2.

The cooling water pumped by the sea water pumps is conveyed into a sea water condenser through the manifold shown below.

Olkiluoto 3 39 The safety system consists of four parallel trains, each capable of performing the required safeguard function on its own. The four parallel trains are located in separate buildings on different sides of the reactor building to eliminate the possibility of simultaneous failure.

40 Olkiluoto 3 Nuclear safety 41 - Olkiluoto 3 Olkiluoto 3 Double concrete walls of the gas-tight containment The design of the safety systems is based on quadruple quadruple is on based systems of the designsafety The contains divisions building safeguard thefour Eachof Any one of these barriers is tight enough to ensure ensure to these enough tight barriers of is one Any that no radioactive materials can be released into the the be can into released radioactive materials no that environment. of OL3 features Safety technology on developed evolutionary represents OL3 and plants German Konvoi recent the most the of basis these experience from operating The plants. N4 French the for considered and been studied has carefully plants - fo the main process, the development In OL3. design of se - of the prevention and systems beensafety cushas on the damage minimizing as well as accidents, reactor vere accident. an by caused consist the systems that means It systems. of redundancy - the re performing of each capable paralleltrains, four of - physi are trains four The own. its on task safety quired reac- of the parts in different located and cally separated divisions. in independent building tor system cooling emergency medium-pressure and a low service essential the closed circuits with and cooling water feedwater emergency generator them, the steam cooling instrumenta and electrical the equipment and system, these systems. for required systems control and tion Third barrier by leak-the enclosed completely is primary The circuit - walls. dou The concrete massive with containment tight on built are containment the OL3 walls of concrete ble covered is containment the inner and thick basea slab, a leak-tightwith metal liner. primary circuit Reactor pressure vessel and NUCLEAR SAFETY NUCLEAR in a metal fuel rod cladding Ceramic uranium fuel enclosed Control of the chain reaction and of the power the power of and reaction the chain of Control it. by generated reaction has chain the fuelCooling alsothe of after heat. residual of removal i.e. stopped, Isolation of radioactive products from the environment. from radioactive products of Isolation Three functions are a prerequisite to ensure reactor reactor to ensure prerequisite a are functions Three uranium fuel encased this within in metal is fuel rods uranium core. in the reactor vessel formed is enclosed is in a metal cladding. fuel rod formed barrier Second steel. of thick made closedprimary a is circuit The circuit The of circuit. this part forms vessel pressure reactor The First barrier are products in radioactive fuel which uranium The - pre The barriers the environment. and products active in all circumstances. radioactive products of releases vent Three protective barriers protective Three to a series refers barriers protective of three concept The barriers between radio- leak-tight physical and strong of Reactor safety is based on three protective barriers to barriers to based protective is three safety Reactor on the defence-in-depth on and radioactive releases prevent principle. 2. 3. all under circumstances: safety 1. In case of abnormal operation, OL3 has safety systems systems safety has OL3 operation, abnormal case of In of each capable subsystems, redundant four of consisting own. its function on safety the required performing The general objective is to ensure the safety of the nuclear power plant of the nuclear power is to ensure the safety objective The general or the health of employees risks to causes no radiation so that its use damage to the environment nor any other in the vicinity, of people living substances must principle is that no radioactive The general or property. environment. ever be released into the Containment heat removal system Core melt spreading area Safety systems: four-fold redundancy Safety systems: four-fold Examples of principal safety features of Olkiluoto 3 of Olkiluoto features safety Examples of principal Double containment (ventilation, filtering) Emergency cooling water storage tank (in-containment refuelling water storage tank) Olkiluoto 3

Nuclear safety 42 Nuclear safety 43 - Olkiluoto 3 Olkiluoto 3 During normal use or in case of an accident, the excess the excess accident, an in case use of During or normal be the fuel can by produced heat residual energy and - the second to generators the steam through transferred water with provided are generators steam ary The circuit. the use and normal during system the feedwater through accident. an in case of system feedwater emergency ator safety valves so that in case of a leak in case between so of - that thevalves pri safety ator and of low consists system cooling core emergency The nitrogen-pressurized pumps, injection medium-pressure refuelling the in-containment and accumulators pressure func - the system use, normal tank. Under storage water when the plant system removal heat a residual as tions The shut-down. a cold to down being powered is unit which each of divisions, separate four of consists system the primary circuit into water pump independently can pumps. injection medium-pressure and low the using building safeguard own in its housed is Each subsystem of loops four of the one a different into feeds and division sufficient ensures arrangement This the primary circuit. coolant. of loss in case of capacity cooling injection boron Emergency of a failed event rare the counteracts designThis concept when drop to fail assemblies the control If scram. reactor the reactor actuated, are conditions scram the automatic injection boron the emergency and stop pumps coolant starts up. pumps, three and lines two which has system, injection boron emergency usedfor pumps piston The 260 to up pressures at water boron-containing pump can bar. Residual heat removal steam generators are minimized by lowering pressure pressure lowering minimized by are generators steam automatic and valves relief bypass the turbine through activation The generator. steam the damaged of isolation are systems cooling emergency the OL3 of levels pressure gener the open steam that levels the pressure than lower safety generator marysecondary the steam and circuits, be will actuated. valves not cooling and residual core Emergency system heat removal The large steam volume of the steam generator means means generator steam of the volume steam large The The volumes of the largest reactor components, i.e. i.e. components, reactor of largest the volumes The The OL3 safety design is based on the concept that in that designis on concept basedOL3 the safety The The probability of a serious reactor accident has has been accident reactor of a serious probability The The emergency cooling systems take their water from from water take their systems cooling emergency The denser is not available, environmental releases from any any from releases environmental available, not denser is leak between secondary the in the primary and circuits steam is conveyed from the damaged steam generator generator steam the damaged from conveyed is steam bypass the turbine through the condenser to primarily - the con When atmosphere. into straight not and valves that it takes a long time to fill with water from the pri - the from fill time to water with takes a long it that The tube. transfer heat ruptured a in casemary of circuit shut-down. - the pressu and generators the steam vessel, thepressure to designs plant previous been over increased have rizer, transients the reactor of the time progression down slow corrective initiate time to more the operators give to and actions. - the pres lowering by the secondary and through circuit re- or cooling emergency The in the primary circuit. sure cold then used attain to are systems removal heat sidual the emergency feedwater system, the main steam relief relief steam the main system, feedwater the emergency injection boron emergency the primary and circuit train sys- removal heat residual at which the level The system. cooling by attained 180°C) is and (30 bar operate can tem - will automati the plant operation, abnormal of the event a hot as known state a controlled to cally betransferred a stable to control, manual by further, and shut-down using by is achieved state controlled The shut-down. cold lows for a planning period of 30 minutes for corrective corrective for period 30 minutes a planning of for lows room. control the plant by actions Safety design Safety required functions safety and protection All thereactor - situa operating abnormal in an activated beto instantly This al- systems. based automatic on are accident or tion also been- further the conse drastically limit to developed accident. a severe of quences further reduced compared with earlier power plants by by plants power earlier with further compared reduced have OL3 systems The systems. preventive enhancing the in-containment emergency cooling water storage storage water cooling emergency thein-containment tank. ) ensures cooling of of cooling ) ensures 2 The efficiency of the cooling system is sufficient to sufficient is system efficiency of theThe cooling The integrity of the reactor containment building in in building containment reactor of the integrity The the cooling area, the spreading enters melt the core As Situations that would result in a release of any signifi- any of in a release result would that Situations - col is melt the core fails, vessel pressure the reactor If reactor containment, flowing down by gravity into the the into by gravity down flowing containment, reactor melt. the core onto and catcher the core under channels the which after days, a few within melt solidify the core begin. can management long-term post-accident ment have been virtually eliminated. have ment that structures with ensured is meltdown a core case of core a passive and melt core of the progression retard the containment, of the bottom At system. cooling melt a metal of consisting area spreading melt a core is there of a 10 cm layer with covered catcher) (core structure to is cool purposecatcher The ofthe sacrificial concrete. the reactor the base of slab protect to and melt the core lead leaks. to Water might that damage against building - spread melt the core under channels in cooling circulates The melt. will the also core rise water above and area, ing (170 m catcher the core of area large of The transfer pit. the reactor of the bottom lected at is area the spreading into pit the reactor from melt core forcing melt core the hot with event, passive a as initiated catcher. the core into plug the aluminium through way its alumini- overthe of sacrificialconcrete 50 cm layer The of the failure delaying melt, the core into melts um plug - in the re accumulated has melt all theuntil core theplug vessel. the pressure under pit actor over The sacrificialconcrete activated. passively is system - Cooling contin melt. thecore into melts catcher thecore the a tank inside from water with process a passive ues as In the design of OL3, a severe reactor accident is ad- is accident reactor a severe OL3, the design of In independ- and redundant even if the multiple dressed: the event of the impact allfail, to were systems safety ent of in terms beminor would site plant the power beyond range. both time and - the environ into radioactive products of amounts cant the core melt. the core Preparedness for severe reactor accidents reactor severe for Preparedness - In addition to the four main chains, the essential the essential chains, main the four to addition In Residual heat can be removed either through the steam the steam through either be can removed heat Residual The emergency feedwater system consists of four sepafour - of consists system feedwater emergency The Olkiluoto 3 service water system has two dedicated pumping chains chains pumping dedicated two servicehas system water chain transfer heat the independent part of which form used accident. is a severe in case of that cooling water system, which cools the safety systems, to to systems, which the cools safety system, water cooling the sea. The essential service water system is a safety system system is a essential The safety service system water chains pumping separated physically four of consisting sys- The divisions. building safeguard thein four housed the closed of exchangers the heat from heat transfers tem Essential service water system Essential service water chain formed by the reactor cooling system, the closed system, cooling the reactor by formed chain service system essential and water system water cooling of the safety pipes suction sink. The heat the ultimate to to valve isolation the first to up pipe a guard have systems break. pipe a suction in case loss of water prevent mediate cooling circuit powered by an emergency diesel emergency an by powered circuit cooling mediate heat containment the independent using or generator, the cooling through transferred is Heat system. removal the primary circuit using the low and medium-pressure medium-pressure and the low using the primary circuit in-containment the2,000-tonne and pumps, injection inter an cooled tank is using storage water refuelling generators. Each injection pump has its own emergency emergency own its has pump Each injection generators. in housed sep- are systems and tank. The tanks feedwater divisions. building in the safeguard compartments arate the then through the secondary and to circuit generators - the out into steam of release the sea by to or condensers a case of In trains. relief steam the main through side air in thepressure in secondary loss circuit, coolant complete in- discharge steam by be can lowered the primary circuit or lines relief the pressurizer through the containment to into injected is water cases, make-up such In valves. safety rate parallel subsystems that are independent of each each of independent are that parallel subsystems rate the steam of one into water which feeds each of other,

Nuclear safety 44

Nuclear safety

Emergency cooling water storage tank Core melt spreading area

Source: AREVA

Core melt cooling system

In the highly unlikely event of a core meltdown at OL3, the core melt is transferred to the core melt spreading area, where it is cooled and solidified.

Spray nozzles

Passive flooding device

Containment emergency heat removal system Emergency cooling (2 x 100%) Core melt spreading area water storage tank

Melt flooding Water level in case of water injection via cooling device into spreading area Flow limiter

Olkiluoto 3 45 Coolant handling system

Heat exchanger Letdown Auxiliary spray Low pressure reducing station

Pressurizer CCWS High-pressure heat exchanger Sampling

PRT water system M Loop 2 M system Component cooling Reactor Loop 1 pressure vessel

Charging line Coolant purification

Loop 4 Loop 3 Coolant degassing Reactor coolant pump seal injection and leak-off system Coolant storage

Boron-containing make-up water

Make-up water

Gaseous waste processing system

Volume control tank Emergency Emergency cooling water cooling water storage tank storage tank (IRWST) (IRWST)

Gas treatment

N2 H2

46 Olkiluoto 3 Water chemistry and volume control systems 47 Olkiluoto 3 Olkiluoto 3

B, ca. 30–32% by weight). Its purpose Its weight). ca. 30–32% by B, 10 Boron and make-up water system water and make-up Boron is enriched with in coolant the The boron All the solutions required for the plant the plant for required All thesolutions - solu this storage from made are systems for water ion-exchanged pure using tion, regard to one of its two natural isotopes isotopes natural two its of one to regard ( in reactivity residual for compensate to is acid The boric solution core. thereactor 4%, which of a concentration at stored is boron. of 7,000 ppm about to corresponds diluting. reactivity core Controlling the be - at highest its at is reactivity Core interval because the refuelling of ginning loaded fuel is fresh When fuel. the fresh of assemblies rod all control the core, into Slow changes in power output over the long term term the long over output power in changes Slow are inserted, and the primary circuit, the reactor pool and pool and the reactor the primary inserted, and circuit, are whose solution filled pool a with boron are the transfer injection The boron 1,550 ppm. about is concentration down powered is used when the reactor always is system the state sub-critical ensure so to as shut-down, cold a to - the re When temperature. its of regardless the reactor of first are assemblies rod the control up, powered is actor primaryrod in the level which the boron after retracted, the critical is until level diluting decreased is by circuit use during is always maintained level The boron reached. 1,200 ppm. than less to discharge due fuel flux in the neutron the decline and level the boron lowering by for compensated are burnup be- just ppm 5 about of level a reaches it until gradually refuelling. fore - safety function. that control the automatic action measurement devices The boron content of the make-up monitored with double continuous- water added to the primary circuit is WATER CHEMISTRY AND AND CHEMISTRY WATER VOLUME CONTROL SYSTEMS CONTROL VOLUME Boron is used in OL3 in the form of boric- acid dis of used in the form is in OL3 Boron The chemical and volume control system man also system control volume and chemical The The most important of the coolant of coolant the important most The treatment systems is the chemical and and the chemical is systems treatment directly is which system, control volume solved in water. The boron content of the primary of the circuit content The boron water. in solved bo- or water pure either adding by regulated is coolant - re as the circuit, into fed the coolant to ric acid solution extractedand to added of coolant the volume The quired. the run with - be consistent must the primary circuit from situation. ning ages the reactor coolant pump seal injection and leak-off. leak-off. seal and injection pump coolant the reactor ages of is inlet also line system the source control volume The which system, auxiliary spray the pressurizer for coolant the in pressurizer. pressure lower helps - the chemi of the regulation to connected in the primary the coolant of properties physical cal and volume. and content boron its e.g. circuit, the availability of make-up water needed water make-up of theavailability prima- of the refilling and in the draining ry circuit. preparing, storing and injecting the boron the boron injecting and storing preparing, in the systems various needed for solution ensure the systems During outages, plant. - con and injection coolant, the circulating gases in the dissolved chemicals, of trol and handling degassing, the and coolant; in various extracted coolant of storage alsoused for are systems The situations. The coolant treatment systems manage manage systems treatment coolant The thein primary circuit content theboron of purification chemistry, water coolant, OL3 has a total of about 120 process systems for handling liquid, steam systems 120 process of about OL3 has a total system of the reactor control volume The chemical and and gas flows. between the high-pressure acting as an interface one, plant is an essential systems. and the low-pressure primary circuit Instrumentation & control systems architecture

I&C service Technical Control room centre support centre

Terminal bus

Plant bus

SA I&C

Field instrumentation Switchgear Control Release Field instrumentation Switchgear Field instrumentation Switchgear

Functional I & C Control rods Safety instrumentation Severe accident management

SICS Safety information and control system PS Protection system TGI Turbine-generator instrumentation SA I&C Severe accident management system PICS Process information and control system SAS Safety automation system TXS TeleprmXS protection automation system RCSL Reactor control, surveillance and PAS Process automation system TXP TeleprmXP automation system limitation system PAC Priority and actuator control HBS Hardwired backup systems

48 Olkiluoto 3 Instrumentation and control systems 49

- - Olkiluoto 3 Olkiluoto 3

- automati which system, protection reactor The is which system, automation safety hardwired The be can and I&C systems the other of independent is which system, management accident The severe The process I&C systems, which maintain the the maintain which I&C systems, process The operating normal within unit the plant of state action which take corrective systems, Limitation operating if normal operation normal restore to parameters are exceeded. are parameters (reactor functions safety the required cally initiates if required), action situation-specific any and scram the of exceed any parameters process or the plant values. limit system protection lost. are used if the digital I&C systems used for and systems I&C the other of independent management. accident the severe parameters. Level 0 (process instrumentation or process inter - shut the remote room, control in the main panels Level centre. the technical support and station down which link user the I&C systems, 2 also comprises I&C. system-level to interfaces face) consists of e.g. sensors and switches. and sensors e.g. of face) consists sur control, reactor protection, in reactor involved process and safety functions, limitation and veillance automation. Level 2 (process monitoring and control) consists of the control the workstations, i.e. the user interfaces, Level 1 (I&C system level) consists of control loops •

3. 3. 4. 5. • • 1. 1. 2. I&C system functions I&C system All the subsystems of the I&C system (measurements, (measurements, the I&C system of All the subsystems divided into are user interface) instrumentation, controls, by functions: levels different The I&C architecture is designed to follow defence- the follow is designedto architecture I&C The have levels functional following The principle. in-depth safety:beento ensure defined Architecture

CONTROL SYSTEMS CONTROL INSTRUMENTATION AND AND INSTRUMENTATION - the protec the plant, the design to of basis According remote shutdown station, if necessary. if necessary. station, shutdown remote of the plant. A conventional hardwired panel is provided provided is panel hardwired A conventional the plant. of user the workstation-based in case of use backup as for a to brought can be unit The available. not is interface a also from manner controlled a in state shutdown safe information on the basis of which the operators carry which the operators the of basis on information monitoring and the control for required the actions out transient and emergency procedures. The monitoring monitoring The procedures. emergency and transient - the work using implemented is the plant of control and room. control in the main user interface station-based - con main in the area work specifica has Eachoperator the which present screens, several with display room, trol accidents for the first thirty minutes without operator operator without thirty the first minutes for accidents to establish time operators the This gives intervention. the required investigate to and thetransient of thecause - sub independent and redundant four of each consisting - con independent and redundant four also have systems, subsystems. system trol and transients to responding of I&C shall betion capable diversity and redundancy. For example, the emergency the emergency example, For redundancy. and diversity system, feedwater the emergency and system cooling plement the I&C systems fulfil the quality requirements requirements fulfil quality the I&C systems the plement OL3 The classification. safety based the respective on equipment and functions the associated and I&C systems - nu of principles the general with comply designed to are functional separation, and physical including safety, clear Design bases just of I&C systems, the and equipment The functions to their according classified are all systems, like other to im- used equipment The significance. safety nuclear technology. Safety and availability have been emphasised in the in the been emphasised have availability and Safety design of I&C systems for OL3. The I&C systems of of systems I&C The OL3. for I&C systems design of digital proven using fully automated are unit the plant hardwired conventional by up backed technology, Instrumentation and control (I&C) systems consist of field instrumentation, consist of field instrumentation, (I&C) systems and control Instrumentation and used for the monitoring as well as I&C user interfaces systems control of the plant. control 50 Generator G Olkiluoto 3 400 kV

Nuclear island Turbine island Unit transformer 10kV 10kV 690V 400V 400V 690V EDG G M M Simplified schematic ofthe Olkiluoto 3power plantunit M RCP 10kV 10kV 690V 400V 690V 400V EDG G transformer Auxiliary normal M M M RCP 10kV 10kV 690V 400V 690V 400V EDG G transformer Auxiliary normal M M M RCP 10kV 10kV 690V 400V 690V 400V EDG G M RCP M 110 kV M transformer Auxiliary stand-by ELECTRICAL POWER SYSTEMS

Electrical power systems

The electrical power systems have two purposes: to transfer the electricity generated into the external grid and to supply and distribute the electricity needed by the power plant itself. The former function involves the generator busbar, the main transformer and the 400 kV switchyard and power line. The latter function involves the auxiliary unit transformers, medium-voltage switchgear, diesel generators and low-voltage distribution network.

The generator busbars between the gen- supplied by the Olkiluoto gas turbine erator and the main transformer are in- plant. dependent, single-phase busbars with The systems are designed to ensure suf- earthed metal cladding. The main trans- ficient capacity for maintaining nuclear former consists of three single-phase units. safety even if one division fails and anoth- The transformer is cooled with oil run- er is simultaneously out of operation due ning through the coils, which is cooled by to maintenance. a separate, external water-cooling circuit. Safety-critical systems are connected to The electricity needed by the power backed-up electrical power systems. These plant itself is taken from the 400 kV grid are systems that ensure safe reactor shut- through two auxiliary unit transform- down and residual heat removal and pre- ers, which are backed up by an auxiliary 400 kV power line isolator chain. vent the spreading of radioactivity. stand-by transformer connected to the In case of the loss of all exter- 110 kV grid. These two power supplies are nal power supplies, the malfunc- independent of one another. tion of all four diesel generators at once, i.e. the The reactor plant electrical power system is divided complete loss of all AC power, the plant unit has into four parallel and physically separated sub-divisions. two smaller diesel generators with an output of The power supply to equipment critical for the safety of approximately 3 MVA each. These ensure power supply to each division is backed up with a 7.8 MVA diesel gen- safety-critical systems even in such a highly exceptional erator. The busbars of the diesel generators can also be situation.

Olkiluoto 3 51 Discharge of clean water

Radioactive waste water collection and storage 3. Evaporation Return plant

2. Monitoring tank Centrifuge plant 1. Controlled water Ion-exchange outlet Solid waste* resin dosing tank Ion-exchange resins from the Tank sludge feedwater purification system

Concentrate tank Buffer tank Mixing circuit

Condensate

Concentrate and resin drying in drums by vacuum heating (drying station) 1. Radioactive water from primary circuit and fuel pools, and decontamination water 2. Low-level radioactive water, e.g. from laundry * Waste separated in centrifugal apparatus is and washrooms also dried by vacuum heating (drying station) 3. Possibly radioactive water from the steam and the waste drying drum is then filled with generator dump valves concentrated waste to be further solidified

Gaseous waste handling schematic Degasification system and vent stack Pressure relief station Decay filters

Compressor Pressure relief station

Gas Recombiner Cooler Pre-dryer Gas filter dryer Coolant degassing system

Gel dryer Flushing the tanks in the reactor building Reduction stations

Flushing the tanks in the auxiliary building and fuel building

52 Olkiluoto 3 Waste processing systems 53 - Olkiluoto 3 Olkiluoto 3 The ion exchange resins, evaporator resins, evaporator exchange ion The concentrates and other sludges are after after are sludges other and concentrates drying dried barrel the in storage tank - process in the waste provided facility is started. The filter element willthen be- element The filter started. is enclosed in the drying The come material. be to dried 200-litre a placedin is waste a in heating dried through and barrel dry. is the waste of 90% until vacuum, of a temperature at continued is Heating evaporated. has all water ca. until 130°C to the returned is water condensed The Waste of this type is first stored in tanks in tanks stored this type of first is Waste drying in a then mixed and process. can element A filter OL3. of building ing the drying before be placed in the barrel The initial activity level of the waste and filter ele- and filter of waste the initial level activity The Final disposal placed is in OL3 at produced waste operating The solid final disposal to the for transferred and boxes concrete The in Olkiluoto. located repository waste operating operating final also disposalof is repository used for are records Accurate OL2. and OL1 at generated waste liquid waste processing system. system. processing waste liquid be can intermediate-level equal to dried in barrels ments OL3 insidethe stored first are groups These waste waste. storage interim TVO’s to transferred they are before unit, until kept is the waste where waste, intermediate-level for theCo-60, making the which primary is (>90%) nuclide After half-lives. 5–10 undergone has radioactive, waste final disposal in the for be can emplaced the waste that waste. low-level other like repository waste operating waste of solidified mixed Processing oils waste e.g. different includes Solidified waste mixed oil of waste the activity The activity. with contaminated for barrels 200-litre placedin is the oil and measured is gener waste used for already in system the solidification OL2. and OL1 at ated - from the circuit. into the ion-exchange resins by a Impurities in the coolant are bound chemical reaction and thus removed WASTE PROCESSING SYSTEMS PROCESSING WASTE Low-level waste comprises materials materials comprises waste Low-level concentrates, tank bottom sludge, ion exchange resin and and resin exchange ion sludge, tank bottom concentrates, water. process of used purification in the elements filter Processing of filter elements and waste dried in of filter elements and Processing barrels evaporator of consists primarily dried barrels in Waste final disposal. Mixed maintenance waste is veryis waste low-level maintenance finalMixed disposal. a rule. as waste packed either in steel boxes or directly in concrete boxes, boxes, in concrete directly or boxes in steel either packed before boxes also placed concrete in are the barrels and for repository waste in the operating emplaced they are in barrels is compacted to a smaller volume in the bar a smaller to volume compacted is in barrels half to also compressed are the barrels of some and rels are the items original size in vertical Large of direction. to plastic bags or directly into 200-litre steel barrels and and barrels steel 200-litre into directly bags or plastic to to sorting according the for sorting facility to transported bags collected into type. Waste and their content activity packed waste compactable The barrels. in packed later is So-called small items representing low-level waste are are waste low-level So-called representing small items in- either produced they where are the point collected at liquids. liquids. and scrap of mixed maintenance waste Processing metal ing, and low-active components, such as as such components, low-active and ing, Low- the systems. from seals, removed the following divided into is waste active scrap waste, maintenance mixed groups; ele- filter dried in a barrel, metal, waste mixed and insertssolidified filter ments, and substances contaminated with radio- with contaminated substances and - fire-resist includes material Such activity. - cloth protective covers, plastic fabrics, ant No solid waste classified as intermediate- classified solid waste No - pro final disposalis requiring waste level unit. the OL3 at in substance, duced, Solid operating waste Solid operating low- divided into is waste Solid operating waste. intermediate-level and waste level Radioactive waste is classified on the basis of its radioactivity and physical radioactivity and physical of its is classified on the basis Radioactive waste appropriately. is processed Each type of waste properties. and chemical radioactive low-level from separate is kept waste High-level radioactive lines for different processing and there are separate at all times, waste gaseous waste. types of solid, liquid and - level before the gases are released. From From released. the gases are before level for released the gases are unit delay the sys- a ventilation into further processing Plant filters. separate with equipped tem actions process shut-down, and start-up of flushing nitrogen as such events and tanks, to reduce the hydrogen concentra hydrogen the reduce to tanks, - convert these gases by catalytically of tion flush to and water, into gas hydrogen ing storage various gas inertwith nitrogen accumulate. gases may waste tanks where ofthe filters active carbon pressurised The radioac - retain designed to are unit delay so to Krypton) as gases (Xenon, noble tive acceptable an their radioactivity to reduce the reactor pressure vessel head can cause cause head can vessel pressure the reactor The overflow is in this case conveyed through the ac- through conveyed is incase this overflow The gases of waste processing in the involved systems The activity has been reduced to an acceptable level. The ac- The level. acceptable an to been has activity reduced - moni finally is the all plant gases of from released tivity measurements activity operating continuously with tored stack. in the vent a substantial gas flow to the gaseous waste processing processing waste to gaseous the flow gas a substantial system. pressurised in the unit of delay the units filter carbon tive further the mechanical and through the system part of The stack. activity vent to the filters micro and coarse system analysedventilation in is the flow the gas of level flow the detected, gas is level activity excessive if an and an io- further to mechanical filters the after diverted is The mechanical system. filter carbon active dine-treated aerosols active any retain system ventilation of the filters in the waste contained small particles other possibly and same ofthe filters carbon active iodine-treated The air. introduced radioactive iodine possibly any bind system fuel damage. severe e.g. of a result as gas the waste into the ra- delay or retain completely designed either to are their until flow in the gas contained dioactive materials - - - high ventilation stack. conveyed from the plant into the atmosphere through a 100-metre- Offgases are delayed, filtered and In order to minimize gas emissions, a gaseous waste waste gaseous a emissions, minimize gas to order In Olkiluoto 3 processing system based on a semi-enclosed circuit has has based a semi-enclosed system circuit on processing unit parts: two the flushing of consists been selected. It re- is designed to unit flushing The unit. the delay and storage coolant and the the degasifier from gas ceive sure vessel. A residual concentration of Argon can also can Argon of concentration A residual vessel. sure be dissolved in the primary coolant. Argon-41 is a short- a is Argon-41 thein primary becoolant. dissolved hours. two than less of a half-life with isotope lived space that surrounds the structures of the reactor pres reactor the of structures the surrounds that space - complete be can removed in the coolant gases dissolved propor is gases inthe coolant fission of amount The ly. also reactors water Light the fuel. of the integrity to tional activates radiation when neutron waste, gaseous produce in the air present and in air contained Argon the natural coolant, and other dissolved gases are controlled in the the in controlled gases are dissolved other and coolant, volume and chemical in the included is which degasifier, the necessary, If the primary of circuit. system control to create the chemical conditions required by the reactor the reactor by required the conditions chemical create to - dis and fuel nuclear releasedthe gases from fission of the of in the airspace and in the primarysolved coolant Thesefission auxiliary the associated systems. tanks of The Xenon. and gases Krypton noble e.g. gases include added hydrogen gases, the the fission of concentrations Gaseous waste consists mostly radioactive waste Gaseous acceptable inspection result is obtained, obtained, is result inspection acceptable discharge to issued is permission separate the unit. from the water lected from the liquid waste collection and collection and waste the liquid lected from tanks inspection into systems processing - meas activity taken for are samples where an When analyses. chemical and urements Liquid waste - col is the unit from removed All water maintained of all solid waste emplaced in emplaced all solid waste of maintained location and data (activity the repository in the repository).

Waste processing systems 54 Waste processing systems 55 Olkiluoto 3 Olkiluoto 3 to the Olkiluoto disposal repository. A special vehicle takes the waste packages Some of the solid plant waste is packed into 200-litre drums. Some of the solid plant waste is packed into 200-litre 56 Olkiluoto 3 TRAINING SIMULATOR

Training simulator

Part of the OL3 power plant supply to The purpose of the training simula- TVO will include a full-scope training tor is for personnel to practise all pos- simulator, which will be completed and sible events that may occur at the power ready for use one year before the first fuel plant unit, including transients and ac- loading of the power plant unit. The simu- cidents, and to validate operation, abnor- lator can replicate exactly the functions of mal operation and emergency operation the new unit, and the simulator control procedures. room is a full-scale replica of the real one. The plant supplier is responsible for The simulator will mainly be used for op- designing and building the simulator to- erator training before the power plant unit gether with several well-known suppliers is started up, and subsequently for annual in the field. The simulator and its auxiliary Simulator control room being tested supplementary training. facilities will be housed in a new annexe in the manufacturer’s facilities. to be built at the existing TVO training centre.

3D process models are utilized in training the nuclear power plant operators.

Olkiluoto 3 57 Technical data

General Fuel

Reactor thermal power 4,300 MWth Fuel uranium dioxide UO2 Electrical power, gross 1,720 MWe Assembly type 17x17 HTP Electrical power, net 1,600 MWe Fuel rods per assembly 265 Efficiency ca. 37% Guide thimbles per assembly 24 Primary coolant flow 23,135 kg/s Spacer grids per assembly 10

Reactor operating pressure 155 barabs Length of fuel assembly 4.8 m Coolant temperature in the reactor Weight of fuel assembly 735 kg pressure vessel, average 312°C Width of fuel assembly 213.5 mm Coolant temperature in the hot leg 328°C Cladding material M5TM 3 Coolant temperature in the cold leg 296°C UO2 pellet density 10.45 g/cm Electricity output per year ca. 13 TWh Fuel discharge burnup 45 MWd/kgU Sea water flow 57 m3/s Service life ca. 60 years Control assemblies Building volume 1,000,000 m3 Number of control assemblies 89 Containment volume 80,000 m3 Absorber length: Containment design pressure 5.3 bar lower part 2,900 mm upper part 1,340 mm Reactor core total length 4,717.5 mm Number of fuel assemblies 241 Absorber material Active core height 4.2 m lower part silver, indium, Core diameter 3.77 m cadmium Total fuel weight ca. 128 tU upper part boron carbide Fuel enrichment level, initial core loading 1.9%—3.3% 235U Fuel enrichment level, reloading 1.9%—4.9% 235U Pressure vessel Fuel consumption per year ca. 32 tU Inner diameter 4.9 m Fuel consumption per year ca. 60 assemblies Inner height 12.3 m Wall thickness 250 mm Bottom thickness 145 mm Thickness of stainless steel cladding 7.5 mm Design pressure 176 bar Design temperature 351°C Weight with cover 526 t

58 Olkiluoto 3 Turbine plant Generator Turbine generator unit 1 Nominal rating 1,992 MVA Gross electrical output ca. 1,720 MW Power factor, nominal 0.9 Main steam pressure 75.5 bar Rated voltage 27 kV ± 5% Steam temperature 290°C Frequency 50 Hz Steam flow 2,443 kg/s Rated speed 1,500 r.p.m. Rated speed 1,500 r.p.m. Cooling, stator coils water HP turbine 1 Cooling, rotor hydrogen LP turbine 3 Magnetization current 9,471 A HP turbine stop and control valves 4/4 Cooling water temperature 45°C LP turbine stop and control valves 6/6 Hydrogen cooling medium temperature 40°C Last stage – exit annulus area 30 m2 Power supply – blade length 1,830 mm Main transformer 3 x 1-phase – overall diameter 6,720 mm Nominal rating 3 x 701 MVA Turbine-generator shaft length 68 m Rated voltage 410/27 kV Auxiliary unit transformers 2 Condenser Nominal rating 90/45/45 MVA Cooling surface 110,000 m2 Rated voltage 400/10.5 kV Cooling medium sea water Auxiliary standby transformer 1 Sea water flow 53 m3/s Nominal rating 100/50/50 MVA Vacuum at full load 24.7 mbar Rated voltage 110/10.5 kV Temperature rise 12°C Emergency power supply 4 x EDG and 2 x SBO Nominal ratings 4 x 7.8 MVA and Feedwater 2 x 3.0 MVA Preheating stages 7 Turbine plant diesel engine 1 Final feedwater temperature 230°C Nominal rating 1.6 MVA

Olkiluoto 3 59 1

10 9/2010

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70 1 1. Installation of steel structures on top of the inner containment dome 4. Acidifying of a battery at the turbine island. preceded the construction of the outer dome. 5. Lifting2 of the reactor pressure vessel. 2. Installation of the steam generator tubes. 6. Closure head of the reactor pressure vessel inside the reactor 3. Delivering1 the steam generators to the site. building.3

2 7. The4 low-pressure turbine rotors.

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70 Teollisuuden Voima Oyj Olkiluoto FI-27160 EURAJOKI, FINLAND Tel. +358 2 83 811 Fax +358 2 8381 2109 www.tvo.fi

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