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<strong>atw</strong> Vol. 62 (<strong>2017</strong>) | Issue 8/9 ı August/September<br />

ENERGY POLICY, ECONOMY AND LAW 524<br />

well as to the “conventional” constructions<br />

of light-water small modular<br />

­reactors (SMRs).<br />

6 Design of a nuclear<br />

installation<br />

For the construction of a HTR generating<br />

process heat for industrial<br />

applications the authors postulate<br />

changes in the concept of defense in<br />

depth as described in art. 36c Atomic<br />

Law and developed in § 3 regulation<br />

on design [31]. This direction does<br />

not seem right.<br />

Keeping the requirement to include<br />

safety level sequences in a<br />

­design of a nuclear installation is<br />

­crucial for safety and the criteria set<br />

out in the abovementioned legal acts<br />

are so flexible (the authors themselves<br />

indirectly point out the different ways<br />

they are implemented depending on<br />

the design of the nuclear installation)<br />

that they do not appear to have the<br />

­potential negative impact on the HTR<br />

construction. It must be emphasized<br />

that the formal obligation to apply the<br />

concept of defense in depth results<br />

both from international treaty law<br />

(art. 18 pt. 1 CNS) and from Euratom<br />

directives (art. 8b sec. 1 nuclear safety<br />

directive as amended [32]).<br />

It is also not possible to opt out for<br />

the prohibition to use in the design<br />

and construction of a nuclear installation<br />

solutions and technologies that<br />

have not been tested in practice in<br />

­nuclear installations or by means of<br />

tests, studies and analyzes as contained<br />

in art. 36b Atomic Law. The<br />

authors raise as a shortcoming of this<br />

solution a broad field for the interpretation<br />

of the facts by the regulator<br />

potentially leading even to stopping of<br />

the HTR construction [33]. However,<br />

it seems that the disposition of art.<br />

36b Atomic law is clear and precise. It<br />

also does not diverge from the international<br />

standards in this regard<br />

­implementing the art. 18 pt. 2 CNS.<br />

The authors seem to have missed the<br />

fact that it is not necessary to conduct<br />

a practical examination of all planned<br />

solutions and technologies in nuclear<br />

installation. Although in fact even<br />

prototype reactors are largely based<br />

on solution already proven in practice<br />

art. 36b Atomic Law explicitly permits<br />

other, including theoretical, easier<br />

and cheaper verification methods, i. e.<br />

tests, studies and analyzes. Besides it<br />

is hard to imagine for an investor to<br />

submit an application for the construction<br />

of a HTR (or other nuclear<br />

installation) without at least a theoretical<br />

confirmation of the safety of its<br />

particular elements. The answer to<br />

the question of whether the solutions<br />

proposed in a design fulfill the<br />

­requirement of being previously<br />

“­tested” within the meaning of art.<br />

36b Atomic law belongs to the regulator.<br />

The position of the party in the<br />

proceedings against the regulator<br />

­balance the general procedural guarantees<br />

contained in the Code of<br />

­Administrative Proceedings [34] and<br />

above mentioned prelicensing elements,<br />

as well as regulatory guidelines<br />

based on art. 110 pt. 3 Atomic<br />

Law.<br />

The application of the regulation<br />

on design provisions to HTRs does not<br />

require a change of definitions, as the<br />

authors claim [35]. Within the ­current<br />

legal status cogeneration reactors will<br />

be treated as NPPs with the additional<br />

requirements from § 46 regulation on<br />

design, whereby the reactor connections<br />

to district heating networks or<br />

industrial plants should be designed<br />

to prevent releases of radioactive<br />

­substances from a reactor to these<br />

­systems both during normal operation<br />

and under accident conditions. Heat-­<br />

generating reactors will be covered by<br />

milder provisions applying to research<br />

reactors. As an example requirements<br />

regarding a second containment or<br />

failure-free operation system without<br />

human factor in case of an accident do<br />

not apply to this kind of a nuclear<br />

installation [36]. Regardless of the<br />

above both categories of facilities will<br />

have to meet the general requirements<br />

foreseen for all nuclear installations.<br />

The authors also point out incorrectly<br />

the inadequacy of the provision<br />

of § 52 sec. 3 pt. 2 regulation on ­design<br />

to pebble-bed reactors, calling it<br />

“­humorous”. This provision states that<br />

“During credible accidents, the fuel<br />

elements remain in the same place<br />

and do not undergo deformations<br />

which would make it impossible to<br />

provide effective post-accident reactor<br />

core cooling.” The authors’ criticism is<br />

probably based on the assumption<br />

that the fuel elements in the core<br />

are inherently movable and that the<br />

probability of their deformation<br />

­during an accident is low due to their<br />

safety characteristics. “Remaining in<br />

the same place” does not mean, however,<br />

that a particular element cannot<br />

move. As long as it follows from the<br />

design, as the element moves in<br />

­accordance with the design assumptions,<br />

it must be assumed that it<br />

­remains “in place”. On the other hand,<br />

undesirable are such displacements<br />

of the fuel elements that go beyond<br />

the design assumptions for normal<br />

­operation and the applicant will need<br />

to demonstrate that such situation<br />

will not occur. The deformation of<br />

fuel elements of the reactor also<br />

­cannot be completely excluded. This<br />

can ­happen, for example, as a result<br />

of a very unlikely, but not entirely<br />

­impossible, ignition of graphite in the<br />

fuel elements.<br />

The authors' proposal to change<br />

the content of § 1 pt. 36 of the design<br />

regulation, related to the alleged need<br />

to change the definition of “core<br />

­damage” [37] is completely wrong.<br />

This provision contains a (correct)<br />

definition of a completely different<br />

concept, i.e. “common cause failure”.<br />

7 Decommissioning fund<br />

According to the authors, the Atomic<br />

Law does not specify how the money<br />

for the decommissioning fund for<br />

heating plants and nuclear CHPs will<br />

be collected [38]. This assertion is<br />

wrong. Article 38d Atomic Law<br />

on principles of establishment and<br />

­operation of the decommissioning<br />

fund is precise. Only entities authorized<br />

to operate a NPP have the obligation<br />

to establish it (art. 38d sec. 1). A<br />

contrario operators of nuclear heating<br />

plants (formally research reactors)<br />

are not obliged to do so. Please note<br />

that according to art. 38d sec. 2<br />

­Atomic Law contributions to the fund<br />

are made from each MWh generated<br />

electricity rather than heat.<br />

From an economic point of view,<br />

the fund is an important financial<br />

­ailment for the operator. First and<br />

foremost, he must regularly contribute<br />

to the fund, which increases<br />

the costs. In addition, there are only<br />

very limited possibilities to make use<br />

of money accumulated in the fund.<br />

The only operations that can be<br />

­carried out, except for the main<br />

­purpose of the fund (decommissioning<br />

and radioactive waste<br />

­management), are to place them on<br />

a long-term bank deposit or to<br />

buy ­long-term treasury bonds. In<br />

­addition, in case of payment delay<br />

by 18 months, the operator may be<br />

­ordered to suspend the operation of<br />

the NPP.<br />

The provisions in force are therefore<br />

favorable for HTR operators. In<br />

the case of nuclear CHPs the contribution<br />

to the fund will probably be<br />

significantly smaller than for a NPP,<br />

given that electricity production will<br />

only be part of the operation. In the<br />

case of nuclear heating plants built<br />

and operated as research reactors, the<br />

situation is even more favorable<br />

­because their operators do not need to<br />

set up a fund at all.<br />

Energy Policy, Economy and Law<br />

On Legal Requirements for Construction of High Temperature Reactors (HTR) in Poland ı Tomasz R. Nowacki

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