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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