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atw - International Journal for Nuclear Power | 2.2024

Internationale Entwicklungen und Trends

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Environment and Safety<br />

45<br />

⁃ To provide medical assistance and manage the<br />

treatment of radiation injuries<br />

⁃ To protect property and the environment from<br />

contamination and damage<br />

⁃ To prepare <strong>for</strong> the resumption of normal social and<br />

economic activity<br />

It is important to note that Emergency Planning cannot<br />

be discussed without considering nuclear accidents<br />

and the relative risks associated with these accidents.<br />

In 1975, Professor N. Rasmussen produced a report<br />

<strong>for</strong> the <strong>Nuclear</strong> Regulatory Commission namely,<br />

WASH-1400, ‘The Reactor Safety Study’. WASH 1400 put<br />

into consideration the course of events that may arise<br />

during a serious accident at conventional modern Light<br />

Water Reactors. The report established the radiological<br />

consequences of these events and the probabilities at<br />

which they occur using the Fault Tree and Event Tree<br />

techniques which is known today as part of Probabilistic<br />

Risk (or Safety) Assessment (PRA/PSA). It was<br />

concluded that risks to individuals posed by nuclear<br />

power stations were acceptably smaller than other<br />

tolerable risks, in fact a conclusion was also drawn<br />

that the probability of a complete core meltdown is<br />

approximately 1 in 20,000 per reactor year [13], [14], [15] .<br />

Despite the significance and relevance of this new<br />

method introduced in the WASH-1400 report, a storm<br />

of criticism and several questions were raised years<br />

after its release. As soon as the report was published,<br />

several reports that either peer reviewed the methodology<br />

or judged the probabilities and consequences<br />

of various nuclear accidents at commercial reactors<br />

were developed [16], [17], [18] . To this date, several PRA<br />

related studies have been per<strong>for</strong>med to assess the risks<br />

associated with nuclear power plants. In more recent<br />

years (at NuScale <strong>Power</strong>), C. Williams et al, in her study<br />

to integrate defense-in-depth metrics into new reactor<br />

designs explains an approach <strong>for</strong> augmenting the<br />

traditional defense-in-depth philosophy with quantitative<br />

risk data from plant specific PRA in such a way<br />

that is well structured, can be used consistently and<br />

allows <strong>for</strong> a clear acceptance criterion [19] .<br />

2. Emergency Planning Zone<br />

Emergency Planning zones define the areas beyond the<br />

boundary of a reactor facility, in which implementation<br />

of operational and protective actions are or might be<br />

required during a nuclear emergency, to protect public<br />

health, safety, and the environment [20]. In 2015, the<br />

<strong>Nuclear</strong> Energy Institute published a white paper that<br />

provides a proposed approach <strong>for</strong> re-evaluating the<br />

size of the plume exposure pathway EPZ and the ingestion<br />

exposure pathway EPZ <strong>for</strong> SMRs. The paper argued<br />

that SMR designs have a significantly reduced potential<br />

<strong>for</strong> accident-related offsite releases, and there<strong>for</strong>e, the<br />

consequences from an accident involving an SMR facility<br />

are expected to have a limited impact on public<br />

health and safety. A suggestion was made that the EPZ<br />

size <strong>for</strong> an SMR facility should be determined using a<br />

dose/distance approach based on appropriate protective<br />

action guidelines established by Federal agencies,<br />

and that considers the consequences from a spectrum<br />

of accidents. Moreover, the paper also identified proposed<br />

changes to existing regulations and guidance<br />

documents to support the implementation of scalable<br />

EP requirements <strong>for</strong> SMR facilities. The proposed approach<br />

in this paper maintains consistency with the<br />

safety philosophy applied to large light water reactors,<br />

i.e., a framework that is technology-neutral, dose-based,<br />

and consequence-oriented [21].<br />

2.1 Regulatory History and Policy Considerations<br />

governing EPZ <strong>for</strong> SMR<br />

The USNRC has a compilation of a few documents that<br />

provide the regulatory history associated with NRC‘s<br />

consideration of establishing a scalable, dose-based,<br />

and consequence-oriented plume exposure pathway<br />

(PEP) emergency planning zone (EPZ) <strong>for</strong> small<br />

modular reactors (SMRs) [22] .<br />

It also summarizes the staff’s evaluation of potential<br />

policy issues associated with use of mechanistic source<br />

terms in DBA dose analyses and siting.<br />

Each nuclear power plant‘s EPZ size and shape is<br />

determined individually, considering specific site<br />

conditions, distinctive geographical features of the<br />

area, and demographic in<strong>for</strong>mation. EPZ-specific<br />

strategies offer a solid foundation to introduce further<br />

measures outside the planning zone in case highly<br />

improbable events occur [35]<br />

2.2 Radiological Safety<br />

People‘s perception of nuclear power plants‘ safety has<br />

been impacted by the historical nuclear accidents<br />

(Three Mile Island plant, Chernobyl, Fukushima Daiichi),<br />

which raised questions about the safety of nucler<br />

reactors. The lesson learned from the Fukushima accident<br />

is that it is necessary to emphasize the safety of<br />

nuclear power plants to enhance public acceptance of<br />

nuclear power and reduce the public’s fear of radiation<br />

(effects); some called “radiophobia”. Several researchers<br />

have conducted experiments that highlight the<br />

importance of thoroughly validating the anticipated<br />

safety features of SMRs. Consequently, it can be inferred<br />

that Small Modular Reactors (SMRs) have the capacity<br />

to provide improved radiological safety and robustness<br />

in the face of unplanned, service disruptions. The<br />

quantity and kind of radioactive materials that could<br />

be released into the environment after a nuclear accident<br />

are referred to as the „source term.“ A study done<br />

by Lulik [36] and his team used an empirical approximation<br />

to determine the source term based on the expression<br />

given as,<br />

Vol. 69 (2024)

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