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16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

16.2 - Severe Accident Analysis (RRC-B) - EDF Hinkley Point

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SUB-CHAPTER : <strong>16.2</strong>PRE-CONSTRUCTION SAFETY REPORTCHAPTER 16: RISK REDUCTION AND SEVEREACCIDENT ANALYSESPAGE : 243 / 295Document ID.No.UKEPR-0002-162 Issue 04Two types of countermeasures were distinguished outside the area enclosed by the plantfence where specific protective measures are coordinated by the operator:• Countermeasures to be performed before the accident is fully under control(evacuation):oIn this initial stage, intervention will generally be performed over a circulararea with radius r centred on the plant because it is difficult to predictchanges in wind direction with sufficient confidence. In order to evaluatethis kind of countermeasure, maximum dose values were calculated whichwill not be exceeded with a probability of 95% at any location beyond thedistance r from the plant. The evaluation is performed for different values ofr. Dose values are then plotted as a function of r.• Countermeasures to be performed after termination of release of radioactivematerials into the environment:oThis second type of intervention (e.g. relocation and banning the sale offoodstuffs) will only be performed in those areas in which measurementsshow that an intervention level D is exceeded. D may be a dose, a doserate or a contamination level for particular foodstuffs (measured in Bq/kg).For this type of intervention, the areas over which they may have to beapplied are considered more important than the distance from the plant.The evaluation is therefore done for different types of area.The potential radiological consequences depend on:• Release height.• Nuclide - specific activity of releases as a function of time.• Meteorological conditions during a defined, representative time period.The results of these calculations are given in the Section <strong>16.2</strong>.3 - Figures 5 to 15.Information about the potential dose originating from the passing radioactive cloud is given inSection <strong>16.2</strong>.3 - Figure 5, which gives the effective dose to adults and to infants due toinhalation and direct radiation from the cloud as a function of distance, and Section <strong>16.2</strong>.3 -Figure 6, which gives the thyroid dose for adults and for infants due to inhalation only as afunction of distance. The portions of the dose values relating to inhalation account forradiation exposure due to inhaled radionuclides over a time period of 50 years for adults and70 years for infants, respectively (committed dose).For the area-related countermeasures, a corresponding calculation was performed. In thiscase, the main interest is related to the size of areas in which certain dose or contaminationlevels are exceeded. Twenty dose and contamination levels were evaluated simultaneouslyon the basis of the activity release pattern of the EPR Reference Source Term and aparticular weather condition.This calculation was performed for all weather conditions for the given representative timeperiod. For each of the 20 dose and contamination levels, cumulative distribution functions ofarea sizes were calculated. It was then possible to select those area sizes for which thegiven dose and contamination levels are not exceeded in 95% of all evaluated cases.Section <strong>16.2</strong>.3 - Figures 7 to 15 show the size of these areas:

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