35 Years of Safe and Reliable Operation of Loviisa NPP
35 Years of Safe and Reliable Operation of Loviisa NPP
35 Years of Safe and Reliable Operation of Loviisa NPP
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1<br />
<strong>35</strong> YEARS OF SUCCESSFUL<br />
OPERATION – LOVIISA <strong>NPP</strong>
2<br />
Overview <strong>of</strong> Fortum’s nuclear fleet<br />
<strong>Loviisa</strong><br />
Two units<br />
2 × 498 MW = 996 MW<br />
Olkiluoto<br />
Two units, one under construction<br />
880 + 860 MW = 1740 MW<br />
Under construction 1600 MW<br />
Fortum’s share: 27 % (463 MW)<br />
Oskarshamn<br />
Three units<br />
473 + 638 + 1400 = 2511 MW<br />
Fortum’s share: 43 % (1089 MW)<br />
Forsmark<br />
Oskarshamn<br />
Forsmark<br />
Olkiluoto<br />
<strong>Loviisa</strong><br />
Three units<br />
978 + 990 + 1170 = 3138 MW<br />
Fortum’s share: 22 % (696 MW)
<strong>Loviisa</strong> 1 <strong>and</strong> <strong>Loviisa</strong> 2
Fortum Power Division – <strong>Loviisa</strong> Nuclear Power Plant<br />
<strong>Loviisa</strong> <strong>NPP</strong> includes two PWR units<br />
VVER-440, 2 x 496 MWe (net)<br />
<strong>Loviisa</strong> 1 started operation in 1977<br />
<strong>and</strong> <strong>Loviisa</strong> 2 in 1980<br />
Strategic plant lifetime target 50 years<br />
• Gross load factors 2011: LO1 94,7 %<br />
Annual production 8,06 TWh (net)<br />
LO2 94,8 %<br />
Own personnel 504 <strong>and</strong> 80 permanent contractors
Production – Annually 1977 - 2011<br />
TWh<br />
9,00<br />
8,00<br />
7,00<br />
6,00<br />
5,00<br />
4,00<br />
3,00<br />
2,00<br />
1,00<br />
0,00<br />
LO1+LO2 Electricity production (TWh, net) <strong>and</strong> capacity factor (%, gross)<br />
1977-2011<br />
1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011<br />
TWh 2,51 2,98 2,90 1,73 5,82 6,24 6,82 6,91 7,15 6,70 7,17 6,95 7,13 6,52 6,80 6,58 6,99 6,62 6,45 6,82 7,60 7,54 7,86 7,50 7,70 7,29 7,68 7,72 8,14 7,73 8,12 7,67 8,15 7,74 8,06<br />
% 36,8 39 37,9 45,7 75,6 81 88,2 89,6 92,4 86,5 92,9 89,9 92,1 84,7 88,2 85,2 90,4 85,6 83,5 87,9 94,5 89,1 92,1 87,9 90,6 85,8 90,2 90,5 95,5 91,0 95,4 89,9 95,7 91,1 94,7<br />
%<br />
100<br />
90<br />
80<br />
70<br />
60<br />
50<br />
40<br />
30<br />
20<br />
10<br />
0
Production - Efficiency<br />
<strong>35</strong>,0<br />
34,8<br />
34,6<br />
34,4<br />
34,2<br />
34,0<br />
33,8<br />
33,6<br />
33,4<br />
33,2<br />
33,0<br />
2011<br />
2010<br />
2009<br />
2008<br />
2007<br />
2006<br />
2005<br />
2004<br />
2003<br />
2002<br />
2001<br />
2000<br />
1999<br />
1998<br />
1997<br />
1996<br />
1995<br />
1994<br />
1993<br />
1992<br />
1991<br />
1990<br />
1989<br />
1988<br />
1987<br />
1986<br />
1985<br />
1984<br />
1983<br />
1982<br />
1981<br />
1980<br />
1979<br />
1978<br />
1977<br />
Lo1 gross efficiency<br />
Lo2 gross efficiency<br />
<strong>Loviisa</strong> 1 <strong>and</strong> 2 gross efficiency 1977 - 2011
Selected actions to support the current operating<br />
license <strong>and</strong> optimized decommissioning<br />
Current license<br />
OSART<br />
2014<br />
EOP’s upgraded<br />
2014<br />
Security imp.<br />
Legis.<br />
2014<br />
<strong>Safe</strong>ty Review<br />
2012-2015<br />
Fuelling<br />
machine 2014<br />
LARA U1S1<br />
2008<br />
<strong>Safe</strong>ty imp.<br />
Stress test etc.<br />
2012 - 2017<br />
Current license<br />
Current license<br />
Polar Crane<br />
2012-2014<br />
PSR 2015 Spent fuel<br />
h<strong>and</strong>ling<br />
2016-2020<br />
Wano PR<br />
2018-20<br />
PSR 2023<br />
LARA U2S1<br />
2009<br />
Current license<br />
Wano PR<br />
Followup<br />
2012<br />
Turb.hall crane<br />
2009-2011<br />
End <strong>of</strong><br />
LO1 12/2027<br />
LO2 RPV license<br />
renewal 2010<br />
LO1 RPV license<br />
renewal 2012<br />
YP<br />
2012-2014<br />
End <strong>of</strong><br />
LO2 12/2030<br />
EPDiesel<br />
2011<br />
LARA<br />
2012-2018<br />
Decomm.
12<br />
10<br />
<strong>Safe</strong>ty, EHS & HR- <strong>Operation</strong>al Incidents<br />
8<br />
6<br />
4<br />
2<br />
0<br />
2002 2003 2004 2005 2006 2007 2008 2009 2010 2011<br />
ER HK INES INES 1<br />
2010<br />
– 2 INES > 0<br />
– 0 INES = 0<br />
– 1 Special reports (ER)<br />
– 3 <strong>Operation</strong>al disturbance report<br />
(HK)<br />
2011 (7.11.2011)<br />
– 0 INES > 0<br />
– 2 INES = 0<br />
– 2 Special reports (ER)<br />
– 5 <strong>Operation</strong>al disturbance report<br />
(HK)
Most important safety systems at <strong>Loviisa</strong> <strong>NPP</strong><br />
1. Steel containment<br />
2. Containment’s external spray system<br />
3. Air filters<br />
4. Reserve emergency feed water pumping station<br />
5. Reactor pressure vessel<br />
6. Low-pressure safety injection pumps<br />
7. High-pressure safety injection pumps<br />
8. Emergency feed water pumps<br />
9. Electric connection from hydro power plant<br />
+ gas turbine<br />
10. Emergency power diesel generators<br />
11. Containment spray<br />
12. Hydrogen recombiners <strong>and</strong> igniters<br />
13. Ice condensers<br />
14. Hydro accumulators<br />
9
10<br />
Severe Accident Management (SAM)<br />
If all cooling systems <strong>and</strong> power supply are<br />
lost, the fuel starts to melt in the reactor<br />
core. The reactor pressure vessel can be<br />
cooled from outside with water melting<br />
from ice condensers, thus retaining molten<br />
core inside the vessel.<br />
Heat is removed from the containment by<br />
outside spray cooling (autonomous<br />
system).<br />
With these arrangements the reactor<br />
pressure vessel <strong>and</strong> containment are kept<br />
intact.<br />
Dedicated, radiation protected SAM<br />
control room has been constructed.<br />
To prevent hydrogen explosions, the<br />
containment is equipped with passive<br />
recombiners <strong>and</strong> igniters.<br />
Containment external spray system<br />
Liitäntä paloautolle<br />
Connection for external<br />
water supply<br />
SAM diesels to secure power to<br />
containment external spray system<br />
<strong>and</strong> important reactor protection<br />
<strong>and</strong> automation systems
CDF (1/a)<br />
Improvement in plant safety<br />
4,50E-04<br />
4,00E-04<br />
3,50E-04<br />
3,00E-04<br />
2,50E-04<br />
2,00E-04<br />
1,50E-04<br />
1,00E-04<br />
5,00E-05<br />
0,00E+00<br />
1996<br />
1998<br />
<strong>Loviisa</strong> 1 Risk distribution<br />
2000<br />
2002<br />
2004<br />
2006<br />
2008<br />
2010<br />
WEATHER<br />
(at shutdown)<br />
WEATHER<br />
(at power)<br />
FIRE<br />
(at shutdown)<br />
FIRE<br />
(at power)<br />
SEISMIC<br />
FLOOD<br />
(at shutdown)<br />
FLOOD<br />
(at power)<br />
INTERNAL<br />
(at shutdown)<br />
INTERNAL<br />
(at power)<br />
<strong>Loviisa</strong> 1<br />
Risk distribution after year 2011 outage<br />
Core damage frequency 4,3E-5/a<br />
PSA11M3<br />
Shutdown<br />
flood<br />
0,3 %<br />
Shutdown<br />
fire<br />
2,0 %<br />
Shutdown<br />
weather<br />
11,7 %<br />
Shutdown<br />
internal<br />
46,4 %<br />
Shutdown<br />
seismic<br />
0,1 % Fire at<br />
power<br />
17,9 %<br />
Seismic at<br />
power<br />
0,2 %<br />
Internal at<br />
power<br />
8,3 %<br />
Weather at<br />
power<br />
6,7 %<br />
Flood at<br />
power<br />
6,4 %
The results <strong>of</strong> the stress tests <strong>and</strong> future actions<br />
• Design Criteria's are right<br />
• Finnish requirements <strong>and</strong> guidelines are more stringent than in other<br />
countries or in relevant IAEA st<strong>and</strong>ards<br />
• Continuous improvement <strong>of</strong> safety has been done in a systematic way on the<br />
Finnish plants<br />
• Planned actions are right<br />
• No need for immediate actions<br />
• STUK has required plans for planned actions, <strong>and</strong> will present specific<br />
requirements to the Finnish plants during summer 2012<br />
• <strong>Safe</strong>ty improvements can be made in the frame <strong>of</strong> annual investment programs,<br />
<strong>and</strong> do not affect availability
<strong>Safe</strong>ty improvements to be further evaluated in<br />
<strong>Loviisa</strong> based on “stress tests”<br />
– Containment heat removal without sea water systems<br />
– Study <strong>of</strong> need to increase fuel for emergency power at site<br />
– Decay heat removal from SFP to UHS in extreme events<br />
– Alternative means <strong>of</strong> decay heat removal from in-containment fuel pools<br />
– Measures to increase margins in case <strong>of</strong> flooding will be evaluated<br />
– Battery capacity<br />
– Multi units severe accidents; emergency preparedness
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