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

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Regulation <strong>of</strong> operat<strong>in</strong>g plants <strong>in</strong>cludes<br />

cont<strong>in</strong>uous <strong>safety</strong> assessment.<br />

<strong>STUK</strong>’s regulation <strong>of</strong> operat<strong>in</strong>g <strong>nuclear</strong> facilities<br />

ensures that the condition <strong>of</strong> the facilities is and<br />

will be <strong>in</strong> compliance with the requirements, the<br />

facilities function as planned and are operated <strong>in</strong><br />

compliance with the regulations. The regulatory<br />

activities cover the operation <strong>of</strong> the facility, its systems,<br />

components and structures, as well as the<br />

operations <strong>of</strong> the organisation. In this work, <strong>STUK</strong><br />

employs regular and topical reports submitted by<br />

the licensees, on the basis <strong>of</strong> which it assesses the<br />

operation <strong>of</strong> the facility and the plant operator’s<br />

activities. In addition, <strong>STUK</strong> assesses the <strong>safety</strong> <strong>of</strong><br />

<strong>nuclear</strong> power plants by carry<strong>in</strong>g out <strong>in</strong>spections<br />

on plant sites and at component manufacturers’<br />

premises, and based on operational experience<br />

feedback and <strong>safety</strong> research. On the basis <strong>of</strong> the<br />

<strong>safety</strong> assessment dur<strong>in</strong>g operation, both the licensee<br />

and <strong>STUK</strong> evaluate the need and potential for<br />

<strong>safety</strong> improvements.<br />

Safety analyses provide tools for assess<strong>in</strong>g<br />

the <strong>safety</strong> <strong>of</strong> <strong>nuclear</strong> facilities<br />

Safety analyses ensure that the <strong>nuclear</strong> facility<br />

is designed to be safe and that it can be operated<br />

safely. Determ<strong>in</strong>istic and probabilistic approaches<br />

complement each other.<br />

Determ<strong>in</strong>istic <strong>safety</strong> analyses<br />

For the purpose <strong>of</strong> <strong>STUK</strong>’s regulatory YVL Guides,<br />

determ<strong>in</strong>istic <strong>safety</strong> analyses are analyses <strong>of</strong><br />

transients and accidents required for justify<strong>in</strong>g<br />

the technical solutions employed by <strong>nuclear</strong> power<br />

plants. The licensees update these analyses <strong>in</strong><br />

connection with the renewal <strong>of</strong> operat<strong>in</strong>g licences,<br />

periodic <strong>safety</strong> reviews and any significant modifications<br />

carried out at the plant.<br />

Probabilistic risk analyses<br />

Probabilistic risk analysis (PRA) refers to quantitative<br />

estimates <strong>of</strong> the threats affect<strong>in</strong>g the <strong>safety</strong><br />

<strong>of</strong> a <strong>nuclear</strong> power plant and the probabilities <strong>of</strong><br />

cha<strong>in</strong>s <strong>of</strong> events and any detrimental effects. PRA<br />

makes it possible to identify the plant’s key risk<br />

factors, and can contribute to the design <strong>of</strong> <strong>nuclear</strong><br />

power plants and the development <strong>of</strong> plant operation<br />

and technical solutions. The licensees employ<br />

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

PRA for the ma<strong>in</strong>tenance and cont<strong>in</strong>uous improvement<br />

<strong>of</strong> the technical <strong>safety</strong> <strong>of</strong> <strong>nuclear</strong> facilities.<br />

<strong>STUK</strong> reviews the determ<strong>in</strong>istic <strong>safety</strong> analyses<br />

and probabilistic risk analyses related to construction<br />

and operat<strong>in</strong>g licences and the operation <strong>of</strong> a<br />

<strong>nuclear</strong> power plant. When required, <strong>STUK</strong> has<br />

its own <strong>in</strong>dependent comparison analyses made <strong>in</strong><br />

order to verify the reliability <strong>of</strong> results.<br />

<strong>STUK</strong> oversees modifications from<br />

plann<strong>in</strong>g to implementation<br />

Various modifications are carried out at <strong>nuclear</strong><br />

facilities to improve <strong>safety</strong>, replace aged systems<br />

or components, facilitate plant operation or ma<strong>in</strong>tenance,<br />

or improve the efficiency <strong>of</strong> energy generation.<br />

<strong>STUK</strong> <strong>in</strong>spects the plans for extensive or<br />

<strong>safety</strong>-significant plant modifications and oversees<br />

the modification work by review<strong>in</strong>g the documents<br />

submitted by the licensee and carry<strong>in</strong>g out <strong>in</strong>spections<br />

on site or at manufacturers’ premises.<br />

As a consequence <strong>of</strong> modifications implemented<br />

at the plant, several documents that describe<br />

the plant’s operation and structure – such as the<br />

Operat<strong>in</strong>g Limits and Conditions, the F<strong>in</strong>al Safety<br />

Analysis Report and the operat<strong>in</strong>g and ma<strong>in</strong>tenance<br />

procedures – have changed. <strong>STUK</strong> oversees<br />

the document revisions and generally follows the<br />

updat<strong>in</strong>g <strong>of</strong> plant documentation after the modifications.<br />

Operability <strong>of</strong> the plant is overseen dur<strong>in</strong>g<br />

operation and annual ma<strong>in</strong>tenance<br />

The technical operability <strong>of</strong> <strong>nuclear</strong> facilities is<br />

overseen by assess<strong>in</strong>g the operation <strong>of</strong> the facility<br />

<strong>in</strong> compliance with the requirements laid down <strong>in</strong><br />

the operational limits and conditions, and oversee<strong>in</strong>g<br />

annual ma<strong>in</strong>tenance outages, plant ma<strong>in</strong>tenance<br />

and age<strong>in</strong>g management, fire <strong>safety</strong>, radiation<br />

<strong>safety</strong>, physical protection and emergency<br />

preparedness.<br />

Operational limits and conditions<br />

The operational limits and conditions (OLC)<br />

<strong>of</strong> <strong>nuclear</strong> facilities lay down the detailed technical<br />

and adm<strong>in</strong>istrative requirements and restrictions<br />

concern<strong>in</strong>g the plant and its various<br />

systems, equipment and structures. The licensee<br />

is responsible for keep<strong>in</strong>g the operational limits<br />

17

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