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Regulatory oversight of nuclear safety in Finland. Annual ... - STUK

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4.1 Loviisa NPP<br />

One event occurred <strong>in</strong> 2011 <strong>in</strong> <strong>in</strong>termediateand<br />

low-level waste management. It was detected<br />

at the Loviisa power plant <strong>in</strong> early 2011 that<br />

the seepage water collection system <strong>of</strong> the low-level<br />

waste repository conta<strong>in</strong>ed small amounts <strong>of</strong> radioactive<br />

tritium. Radioactivity had escaped <strong>in</strong>to<br />

the system when the dra<strong>in</strong> pipe for water dropp<strong>in</strong>g<br />

from the ceil<strong>in</strong>g had become blocked and water<br />

had run on some waste barrels. The event had no<br />

impact on the <strong>safety</strong> <strong>of</strong> personnel or the environment.<br />

Follow<strong>in</strong>g the event, Fortum replaced the<br />

dra<strong>in</strong> pipes <strong>of</strong> the seepage water collection funnels<br />

on the ceil<strong>in</strong>g <strong>of</strong> the repository. The activity <strong>of</strong> seepage<br />

water and condensation water <strong>in</strong> the ventilation<br />

system is closely monitored.<br />

The project implementation schedule has now<br />

been further specified so that the <strong>in</strong>stallations <strong>of</strong><br />

phase 2 will be made <strong>in</strong> 2014 for Loviisa 1. In deviation<br />

from the earlier schedule, the whole I&C<br />

upgrade <strong>of</strong> Loviisa 1 will be completed <strong>in</strong> 2015<br />

before the <strong>in</strong>stallations at Loviisa 2 beg<strong>in</strong> <strong>in</strong> 2016<br />

and 2017.<br />

Modernisation <strong>of</strong> refuell<strong>in</strong>g mach<strong>in</strong>es<br />

Fortum is <strong>in</strong> the process <strong>of</strong> modernis<strong>in</strong>g the refuell<strong>in</strong>g<br />

mach<strong>in</strong>es at the Loviisa power plant. The<br />

modernisation project will <strong>in</strong>clude a basic upgrade<br />

<strong>of</strong> the electrical and I&C systems <strong>of</strong> the refuell<strong>in</strong>g<br />

mach<strong>in</strong>e, now based on 1970s technology, as well<br />

as a possible <strong>in</strong>crease <strong>in</strong> the height <strong>of</strong> the mach<strong>in</strong>e.<br />

The latter can be implemented either by modernis<strong>in</strong>g<br />

the exist<strong>in</strong>g mach<strong>in</strong>e or by replac<strong>in</strong>g it. The<br />

ma<strong>in</strong> reason for <strong>in</strong>creas<strong>in</strong>g the height <strong>of</strong> the bridge<br />

is that it would allow <strong>in</strong>stall<strong>in</strong>g permanent <strong>safety</strong><br />

rails at the fuel pools. Provisions also exist for extend<strong>in</strong>g<br />

the rails <strong>of</strong> the refuell<strong>in</strong>g mach<strong>in</strong>e. This<br />

would allow re-rout<strong>in</strong>g the heavy load lifts <strong>in</strong> the<br />

reactor hall, thus reduc<strong>in</strong>g the risk <strong>of</strong> core damage<br />

caused by fall<strong>in</strong>g loads. Fortum submitted a conceptual<br />

modernisation plan for the refuell<strong>in</strong>g mach<strong>in</strong>e<br />

to <strong>STUK</strong> <strong>in</strong> June 2010. <strong>STUK</strong> reviewed the<br />

conceptual design plan and required additions to<br />

be made to it with respect to, among other th<strong>in</strong>gs,<br />

quality management, systems classification and<br />

the I&C qualification plan. <strong>STUK</strong> approved the<br />

conceptual design plan with remarks <strong>in</strong> November<br />

2011. Fortum submitted an updated I&C qualification<br />

plan to <strong>STUK</strong> at the end <strong>of</strong> the year.<br />

<strong>STUK</strong>-B 147<br />

Quantities <strong>of</strong> spent fuel and lowand<br />

<strong>in</strong>termediate-level waste<br />

The volume <strong>of</strong> spent <strong>nuclear</strong> fuel stored on-site<br />

at the Loviisa power plant at the end <strong>of</strong> 2011<br />

was 4,339 assemblies* (522 tU), an <strong>in</strong>crease <strong>of</strong><br />

192 assemblies (23 tU). The volume <strong>of</strong> low- and<br />

<strong>in</strong>termediate-level waste f<strong>in</strong>ally disposed <strong>of</strong> was<br />

1,774 m³. The total <strong>in</strong>crease <strong>of</strong> volume from 2010<br />

is 93 m³. Approximately 50% <strong>of</strong> the waste has been<br />

f<strong>in</strong>ally disposed <strong>of</strong>.<br />

* The assembly figures do not <strong>in</strong>clude the assemblies<br />

<strong>in</strong> the reactors. The average weight <strong>of</strong><br />

spent fuel assemblies at the Loviisa power plant<br />

is 120.3 kgU.<br />

4.1.6 Spent <strong>nuclear</strong> fuel storage and low-<br />

and <strong>in</strong>termediate-level waste<br />

<strong>STUK</strong> reviewed, <strong>in</strong> accordance with the <strong>in</strong>spection<br />

programme, the low- and <strong>in</strong>termediate-level waste<br />

management and f<strong>in</strong>al disposal <strong>of</strong> waste materials<br />

at the Loviisa power plant. The <strong>in</strong>spection <strong>of</strong><br />

low- and <strong>in</strong>termediate-level waste management focused<br />

on the situation <strong>of</strong> the project for develop<strong>in</strong>g<br />

the handl<strong>in</strong>g <strong>of</strong> low- and <strong>in</strong>termediate-level waste,<br />

the arrangements at the liquid waste solidification<br />

facility, waste account<strong>in</strong>g, organisation and<br />

<strong>in</strong>structions. Follow<strong>in</strong>g the <strong>in</strong>spection observations,<br />

<strong>STUK</strong> required the Loviisa power plant to assess<br />

the rust<strong>in</strong>g and corrosion mechanism <strong>of</strong> low-level<br />

waste barrels placed <strong>in</strong> the VLJ repository, as well<br />

as the impacts that the deteriorat<strong>in</strong>g condition <strong>of</strong><br />

the barrels will have on <strong>nuclear</strong> waste management<br />

and its <strong>safety</strong>.<br />

In October, <strong>STUK</strong> carried out an <strong>in</strong>spection <strong>of</strong> f<strong>in</strong>al<br />

disposal facilities for waste at the Loviisa power<br />

plant. It covered the ma<strong>in</strong>tenance procedures at<br />

the plant site, the repairs and modifications carried<br />

out and the results <strong>of</strong> <strong>in</strong>spections performed<br />

by the power company. The latter also <strong>in</strong>cluded the<br />

results <strong>of</strong> groundwater chemistry measurements<br />

taken from the bedrock <strong>of</strong> the disposal facility,<br />

as well as the hydrological and rock-mechanical<br />

monitor<strong>in</strong>g measurements. No requirements were<br />

imposed follow<strong>in</strong>g the <strong>in</strong>spections.<br />

The process<strong>in</strong>g, storage and f<strong>in</strong>al disposal <strong>of</strong><br />

low- and <strong>in</strong>termediate-level waste (so-called operat<strong>in</strong>g<br />

waste) at the Loviisa power plant were<br />

carried out as planned. The volume and activity<br />

37

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