REPORT DEVELOPMENT OF THE MATERIALS FOR ASSESSMENT … · assessment, NP 306.2.099-2004 (approved...

14
UDK 550.4:574.3 State № 0115U002736 NATIONAL ACADEMY OF SCIENCE OF UKRAINE «STATE INSTITUTION «INSTITUTE OF ENVIRONMENTAL GEOCHEMISTRY» (RC "IHNS NAS OF UKRAINE») 03142, Kyiv, Palladina avenyu, 34а; tel (+38044) 424 00 60, fax 423 81 37 APPROVED Deputy of head RC "IHNS NAS OF UKRAINE» __________Y.O.Olkhovyk REPORT DEVELOPMENT OF THE MATERIALS FOR ASSESSMENT OF ENVIRONMENTAL IMPACT IN THE COURSE OF SOUTH-UKRAINE NPP OPERATION 2015

Transcript of REPORT DEVELOPMENT OF THE MATERIALS FOR ASSESSMENT … · assessment, NP 306.2.099-2004 (approved...

Page 1: REPORT DEVELOPMENT OF THE MATERIALS FOR ASSESSMENT … · assessment, NP 306.2.099-2004 (approved with the SNRIU Order No. 181 dated 26.11.2004). The justification of the environmental

UDK 550.4:574.3

State № 0115U002736

NATIONAL ACADEMY OF SCIENCE OF UKRAINE

«STATE INSTITUTION «INSTITUTE OF ENVIRONMENTAL GEOCHEMISTRY» (RC "IHNS NAS OF UKRAINE»)

03142, Kyiv, Palladina avenyu, 34а;

tel (+38044) 424 00 60, fax 423 81 37

APPROVED

Deputy of head RC "IHNS NAS OF UKRAINE»

__________Y.O.Olkhovyk

REPORT

DEVELOPMENT OF THE MATERIALS

FOR ASSESSMENT OF ENVIRONMENTAL IMPACT

IN THE COURSE OF SOUTH-UKRAINE NPP

OPERATION

2015

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CONTENT

Introduction

1 The bases for EIA

1.1 Information about the documents that are the basis for the development of EIA

1.2 Description of impacts sources and types of nuclear power plants on the

environment

1.3 The list of environmental, sanitary-epidemiological, fire and urban limits

1.4 The data on public attitudes and other stakeholders

1.5 The main results of previously prepared material content of the environmental

safety of SUNPP

1.6 List of used regulatory guidance documents and information sources

2 Physical and geographical features of the area of the SUNPP and the whole

South-Ukraine energy complex

2.1 Physical and geographic characteristics

2.2 Geological structure

2.3 Relief

2.4 Climate

2.5 Surface waters

2.6 Groundwater

2.7 Soils

2.8 Flora

2.9 Fauna

2.10 The objects of natural reserve fund

2.11 Historic landscapes. Archaeological sites

2.12 Recreational terms

2.13 Characteristics of the main negative environmental factors

3 General characteristics and design of the object for proposed activity

3.1 Comparison of planned and alternative ("zero") options and positive aspects of the

planned activity

3.2 Brief description of production activity

3.3 Data on areas occupied land, raw materials, water, labor and other resources used

3.4 Waste Management

3.5 Evaluation of possible emergencies

3.6 The list of major sources of exposure and the zone of influence

4 Environment impacts assessment of SUNPP activities

4.1 The climate impact

4.2 The air impact

4.3 Physical radiation effects

4.4 The geological environment and relief impact

4.5 Groundwater impact

4.6 Surface water impact

4.7 Soils impact

4.8 The flora and fauna impact

5 Impact Assessment of industrial activity on the SUNPP objects of natural

reserve fund

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6 Impact Assessment of industrial activity on the SUNPP objects for social area

6.1 Characteristics of the main social and living conditions of the local population

6.2 Positive and negative impacts of proposed activities on the social conditions of

life

6.3 Assessment of the forecast impact of the designed object to public health

6.4 Measures to prevent the deterioration of living conditions of the local population

and Countervailing Measures

7 Impacts Assessment of proposed activities on man-made environment

7.1 The effects of the proposed activity on the environment of technogenic objects

7.2 The effects of man-made objects to the planned environmental activities

8 Comprehensive measures to ensure standard state of the environment and its

security and comprehensive impact assessment

8.1 Resource-saving measures

8.2 Protective measures

8.3 Remedial measures

8.4 Compensatory measures

8.5 Security measures

8.6 Radioactive waste management

8.7 The system of environmental management

8.8 Residual effects

9 Environment Impact Assessment of the South-Ukraine energy complex

consisting SUNPP, Alexander GES and GAES

10 Transboundary impacts of SUNPP in standard operation and in emergency

situations within the requirements of the Espoo Convention

10.1 Procedural aspects

10.2 Technical aspects

EIA conclusions

Attachments

А The scheme of SUNPP

Б Statement of intent

В Environmental Impact Statement

Г Characteristics of rare species, populations are located in the zone of influence

SUNPP

Д Characteristics of the fauna in the area of influence SUNPP

Е The report on the collection and systematization of information necessary to

assess fire safety in the SUNPP

Ж Impact Assessment of radioactive releases into the atmosphere of the SUNPP on

the environment and people

З Assessment of the impact of cross-border emissions of radioactive substances in

the air of the SUNPP

І Development of EIA report in terms of impact assessment of SUNPP. Part 1. Air

environment. Dry air pollution

К Development of EIA report in terms of impact assessment of SUNPP. Part 2

Radiation effect on air

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10 TRANSBOUNDARY IMPACTS OF SUNPP IN STANDARD OPERATION

AND IN EMERGENCY SITUATIONS WITHIN THE REQUIREMENTS

OF THE ESPOO CONVENTION

10.1 Procedural Aspects

Brief contents of Espoo Convention stipulations regarding nuclear facilities

The Espoo Convention sets out the obligations of the countries, which have ratified

this Convention or have joint it, to assess the environmental impact of the planned activities,

if such activities can impact the environment of another country. Nuclear power production

is considered to be a kind of activities, which can lead to significant harmful transboundary

impact as a consequence of radiation factor effect.

Actually the Convention sets out the obligations to make a final decision with regard

to the beginning of the planned potentially dangerous, in the transboundary sense, activities

only after promulgation and public discussion of all consequences of such activities at the

international level. In other words, the Espoo Convention is a tool of public control, to which

the citizens of another countries are involved. In this sense it is important to underline that

ascertainment of the ecological acceptability of the planned activities inside the country of

origin of these activities in accordance with the internationally adopted levels of

environmental safety unconditionally means the absence of impacts on the other countries

(absence of transboundary impacts), which can be considered to be unacceptable.

The Espoo convention describes the procedure, which includes:

Preparation for assessment of the environmental impact;

Notification of the parties;

Consultations of the parties.

As nuclear power production is subject to increased attention of the public ecological

movements and, in a number of countries, of the general public, especially after the

accidents at ChNPP and Fukushima NPP, the issue of extension of the nuclear power plants

operation in Ukraine attracts meticulous attention of the certain circles inside and outside

the country. However, coverage of the activities, which provide no provision for either new

construction, or change of technology, by the Convention procedures, Energoatom have

made a decision to ensure transparency of assessment of impacts in the transboundary

aspects in full. Legal Basis for Environmental Impact Assessment (EIA) of Nuclear Power Units

Operation

At present application of stipulations of the Convention in the transboundary context

for the activities related to operation extension of the power units in operation at the NPPs

of Ukraine within the beyond-design period is subject to discussions between Energoatom

and a number of public organizations.

The draft updated Energy Strategy of Ukraine until 2030 stipulates extension of

operation of all NPP power units in operation within the beyond-design period. Energoatom

have already received a legal approval of operation extension of Rovno NPP Units 1 and 2

and South-Ukrainian NPP Unit 1.

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Activities of Energoatom in this area are governed with the individual legislative and

legal acts. Thus, in accordance with the Law of Ukraine No. 2861-IV dated 08.09.2005

‘Order of making decisions about location, design, construction of nuclear installations and

facilities designed for radwaste handling possessing national importance’, a decision about

extension of the power units operation is made by State Nuclear and Radiation Safety

Regulation Authority based on the positive conclusion of the State Expertise of the

deliverables by revising the nuclear installation operation license.

A corresponding decision is made based on the results of the periodical safety re-

assessment reflected in the Periodical Safety Re-Assessment Report (PSRAR) and on the

positive conclusion of the State Nuclear and Radiation Safety Expertise. The structure and

contents of the PSRAR are stated in the General Requirements for extension of NPP units

operation within beyond-design period based on the results of periodical safety re-

assessment, NP 306.2.099-2004 (approved with the SNRIU Order No. 181 dated

26.11.2004). The justification of the environmental safety is included into the separate

PSRAR section (‘environmental impact’ safety factor).

However, based on the results of extension of Rovno NPP Units 1 and 2 operation,

upon complaint of «Ecoclub» Union (Rovno City) in 2011 to the Espoo Convention

Observance Committee, during its 27th session it was decided to launch an initiative of the

Committee and to clarify, if the extension of the NPP units operation within the beyond-

design period is subject to the definition of the Espoo Convention, and if it is necessary to

apply relevant procedures with the involved parties.

In the period of 2012-2014 Energoatom, from their side, insisted on their position in

view of nonproliferation of the Espoo Convention stipulations to the activities related to the

operation extension of the NPP units in operation within the beyond-design period,

emphasizing that they implemented and are implementing their activities in this direction

exclusively in compliance with the requirements of the national legislation. The mentioned

approach for the procedure of extension of the power units operation within the beyond-

design period is compliant with the international experience and considers recommendations

of the international organizations (IAEA, WANO, etc.) and approaches of the other

operators, i.e. EDF (Operator of the NPPs in France and Great Britain), which is confirmed

with the results of numerous international missions in the course of implementation of the

projects in Ukraine together with IAEA and EC, as well as compliance of the national

regulatory policy with the requirements of the international standards.

Also, it was noted that, as no essential changes are made to the design basis of a power

unit in the course of extension of the power unit operation and making a correspondent

decision by SNRIU, the mentioned activity of Energoatom cannot be treated as «planned

activity» in understanding of the Espoo Convention. Along with this the decision of SNRIU

cannot be considered as a final one, which is required to be made in case of the «planned

activities». On the other hand, a final decision in understanding of the Espoo Convention

can be considered a decision about impossibility of the further extension of the power unit

operation (with the further termination of the «Operation» life cycle of the nuclear

installation) and about the necessity to obtain a license for implementation of activities at a

separate stage, «Decommissioning».

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Also, the activities related to extension of the power units operation within the

beyond-design period are implemented in the frames of a separate life cycle «Operation of

nuclear facility», for which a corresponding license is issued by the authorized body

(SNRIU). The license validity is limited with the issuance of a new license for

implementation of activities at the next separate stage of the life cycle «Decommissioning

of nuclear installation». In case of Rovno NPP, a license was issued with new identification

by revising of the previous license.

The mentioned position of Energoatom was supported by Ministry of Ecology and

Natural Resources of Ukraine, being a specially authorized body in Ukraine for control of

the Espoo Convention observance. The Committee was informed by the Ministry with the

letters No. 8679/13/10-13 dated 30.05.2013, No. 14925/13/10-13 dated 15.10.2013 and No.

5/1-13/2147-14 dated 13.02.2014.

At the 6th meeting of the Espoo Convention parties in June 2014 the decision

ECE/MP.EIA/20/Add.1−ECE/MP.EIA/SEA/4/Add.1 was adopted, stating the following:

sec. 68 of the decision VI/2: «endorses the conclusions of the Implementation

Committee that NPP life-time extension, being a subject for consideration, after

expiration of the original license should be considered as a proposed activity in

accordance with the paragraph v) of Article 1 of the Convention and therefore it

is covered by the provisions of the Convention»;

sec. 71 of the decision VI/2: «proposes the Implementation Committee in the

process of further activities related to analysis of this case to consider, when

assessing compliance with the Convention by Ukraine, the particular

circumstances of this case and the fact that Ukraine has acted in good faith in

relation to the design, based on the information to be submitted by Ukraine, which

will be analysed by the Implementation Committee».

10.2 Technical aspects

Potential transboundary radiological impact of SUNPP

Preliminary analysis based on the results of the long-term integrated environmental

monitoring, reflected in the numerous technical reports and several scientific studies, shows

that the impact of all non-radiation factors almost does not extend beyond the SPZ and under

no conditions (even with potentially possible accidents) does not extend outside the

surveillance area. The parameters of these impacts do not exceed acceptable national and

international levels, in fact, such cases were not recorded for the observation period. Thus

non-radiative effects are excluded from consideration in a transboundary context

The background radiation and concentrations of radionuclides 90Sr, 137Cs, 134C, 60Co, 54Mn in air and atmospheric fallouts, according to observation data, are on the level of the

values, which were measured before commissioning of SUNPP. Thus, the SUNPP impact

on atmospheric environment during the period of its operation was not significant even for

the surveillance area. As in a distance from the release source the radionuclides

contamination density of the territory decreases rapidly, under normal operating conditions

and even for neighbouring countries – the Republic of Moldova (the distance from SUNPP

to the border ~ 130 km) and Romania (~ 250 km), so the significant transboundary impact

associated with the SUNPP is not expected.

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Transboundary impact under normal operation

Below there are the results of the radionuclides activity calculations on the surface air

layer depending on distance and density of fallouts on the ground. To simulate spread of the

radioactive substances in the atmosphere and formation of doses from releases of

radionuclides from the South-Ukraine NPP under normal operation the software complex

PC CREAM was used, that was developed by the National Radiological Protection Board

(England).

Fig. 6.1. − Expected volumetric activities IRG, tritium, carbon and iodine isotopes in the

surface air layer vs. distance

Fig. 6.4. − Expected LLA fallouts on ground surface vs. distance

1,00E-06

1,00E-05

1,00E-04

1,00E-03

1,00E-02

1,00E-01

0 20 40 60 80 100 120 140 160

Відстань, км

Об

'єм

на

акти

вн

ість

в

атм

осф

ерн

ом

у п

овіт

рі,

Бк/м

3

H-3 C-14 KR-87 XE-133 XE-135

1,00E-11

1,00E-10

1,00E-09

1,00E-08

1,00E-07

1,00E-06

0 20 40 60 80 100 120 140 160

Відстань, км

Об

'єм

на

акти

вн

ість

в

атм

осф

ерн

ом

у п

овіт

рі,

Бк/м

3

I-131 I-133 I-135

1,00E-12

1,00E-11

1,00E-10

1,00E-09

1,00E-08

1,00E-07

0 20 40 60 80 100 120 140 160

Відстань, км

Об

'єм

на

акти

вн

ість

в

атм

осф

ерн

ом

у п

овіт

рі,

Бк/м

3

CR-51 MN-54 FE-59 CO-58 CO-60

1,00E-12

1,00E-11

1,00E-10

1,00E-09

1,00E-08

1,00E-07

0 20 40 60 80 100 120 140 160

Відстань, км

Об

'єм

на

акти

вн

ість

в

атм

осф

ерн

ом

у п

овіт

рі,

Бк/м

3

SR-90 ZR-95 NB-95 AG-110m

1,00E-06

1,00E-05

1,00E-04

1,00E-03

1,00E-02

0 20 40 60 80 100 120 140 160

Відстань, км

Оп

ади

на

по

вер

хн

ю г

ру

нту

,

Бк/(

м2*

рік

)

CS-134 CS-137

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As can be seen from the figures, the maximum values of volumetric activity in

atmospheric air on the sanitary protection zone (SPZ) boundary (2 500m) are expected to

be – 0,03 Bq/m3 and tritium - 0.024 Bq/m3. On the border with the nearest country –

Moldova, distance 130km, the values of volumetric activity of radionuclides, released by

SUNPP in atmospheric air, will not exceed 0,00057 Bq/m3.

The maximum value of fallouts on the ground at the border of SPZ (2 500m) is

expected to be for tritium – 781 kBq/(m2*year) and carbon - 7.2 kBq/(m2*year). On the

border with Moldova the values of radionuclide releases, made by SUNPP on the ground,

will not exceed 15 kBq/(m2*year).

In Fig. 6.5. there are results of calculations of maximum committed doses for

population dependant on a distance. The results are given for three age groups: children

under 1 year old, children under 10 years old and adults.

Fig. 6.5. – Population committed doses vs. distance

As we can see from the figure, the dose limit quota 40 µsv/year according to NRBU-

97 for releases from NPPs, is not exceeded (independently on location of the critical group

of the population). The maximum dose on the border of the sanitary protection zone will not

exceed 8,6 nZv/year. On the border with the nearest country – the Republic of Moldova, the

distance is 140 km, the radiation dose from radioactive substances, which were released

from SUNPP, will not exceed 0.17 nZv/year

Transboundary impact in the event of an accident

Below there are results of calculation on radioactive releases to the environment of

different types of accidents. The software complex PC COSYMA was used for the

calculations, it was developed by the National Radiological Protection Board (national

Committee on radiation protection, England) for emergency situations. All calculations

were performed for conservative conditions of spreading contamination and formation of

exposure doses (maximum doses).

1,00E-04

1,00E-03

1,00E-02

1,00E-01

0 20 40 60 80 100 120 140 160

Відстань, км

По

туж

ніс

ть д

ози

оп

ро

мін

енн

я,

мкЗ

в/р

ік

Діти до 1 року Діти до 10 років Дорослі

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Table 6.1. − Release of radioactive substances at maximum design accident

Radionuclide Environmental release, Bq

Kr-88 2,00E+13

Sr-90 3,10E+11

Ru-103 4,50E+12

Ru-106 6,60E+11

I-131 4,98E+12

I-132 2,70E+12

I-133 4,00E+12

I-135 2,30E+12

Cs-134 7,80E+11

Cs-137 5,00E+11

La-140 8,40E+12

Ce-141 1,40E+13

Ce-144 8,60E+12

Total activity 7,17E+13

Table 6.2. − Release of radioactive substances in the accident, «Steam generator header

break– emergency spike»

Radionuclide Environmental release, Bq

Kr-87 6,50E+13

Kr-88 2,00E+14

I-131 2,53E+13

I-132 9,20E+13

I-133 8,44E+13

I-134 1,00E+14

I-135 7,90E+13

Cs-134 2,10E+11

Cs-137 5,30E+11

La-140 2,60E+12

Xe-133 2,00E+15

Xe-135 1,70E+15

Total activity 4,35E+15

Table 6.3. − Release of radioactive substances in the accident «Steam generator header

break – pre-accident spike»

Radionuclide Environmental release, Bq

Kr-88 2,00E+13

I-131 4,50E+12

I-132 1,60E+13

I-133 1,54E+13

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Radionuclide Environmental release, Bq

I-134 1,70E+13

I-135 1,30E+13

Cs-134 2,10E+11

Cs-137 5,30E+11

La-140 2,60E+12

Xe-135 1,70E+14

Total activity 2,59E+14

Table 6.4. − Release of radioactive substances in the accident «Drop of hydrolock in

cooling pool»

Radionuclide Environmental release, Bq

Sr-90 4,70E+11

Ru-103 3,60E+12

Ru-106 4,10E+11

I-131 1,65E+13

I-133 1,50E+12

Cs-134 9,30E+11

Cs-137 5,80E+11

La-140 1,90E+12

Ce-141 6,60E+12

Ce-144 1,40E+12

Xe-133 5,00E+14

Total activity 5,34E+14

Table 6.5. − Release of radioactive substances in the accident «Drop of spent fuel

assembly in reactor core and at top nozzles of fuel assemblies in cooling pool»

Radionuclide Environmental release, Bq

Kr-87 1,10E+13

Kr-88 1,70E+13

Sr-90 3,90E+10

Ru-103 4,50E+11

Ru-106 6,90E+10

I-131 3,80E+11

I-133 2,60E+11

Cs-134 8,30E+10

Cs-137 6,50E+10

La-140 8,40E+11

Ce-144 9,70E+11

Xe-133 7,40E+13

Total activity 1,05E+14

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Table 6.6. – Release of radioactive substances in the accident, «Drop of container with

spent fuel from height of over 9 meters»

Radionuclide Environmental release, Bq

Sr-90 4,40E+11

Ru-106 1,00E+11

Cs-134 3,50E+11

Cs-137 7,30E+11

Ce-144 8,30E+11

Total activity 2,45E+12

Table 6.7. – Release of radioactive substances in the accident «Drop of fuel assembly

into reactor core»

Radionuclide Environmental release, Bq

Sr-90 1,20E+12

Ru-103 2,30E+12

Ru-106 4,30E+11

I-131 4,63E+12

Cs-134 1,60E+12

Cs-137 8,20E+11

Ce-144 4,10E+10

Xe-133 1,10E+14

Total activity 1,21E+14

Table 6.8. − Release of radioactive substances in the accident «Rupture of pulse tube

outside containment»

Radionuclide Environmental release, Bq

Kr-88 7,10E+11

I-131 6,70E+12

I-132 1,70E+13

I-133 1,30E+13

I-134 9,60E+12

I-135 1,10E+13

Cs-137 7,40E+09

Xe-133 6,40E+13

Xe-135 9,80E+12

Total activity 1,32E+14

Table 6.9. − Release of radioactive substances in the accident «Rupture of planned

cooldown line»

Radionuclide Environmental release, Bq

I-131 6,42E+07

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Radionuclide Environmental release, Bq

Cs-134 2,50E+07

Cs-137 3,70E+07

Xe-133 6,80E+12

Total activity 6,80E+12

Table 6.10. – Release of radioactive substances in the accident «Rupture of the inlet

pipe of technological blowing-in for cleaning in the system of technological blowing-in of

reactor island»

Radionuclide Environmental release, Bq

Ar-41 4,00E+11

Kr-85m 7,20E+11

Kr-88 2,20E+11

Xe-133 2,90E+13

Xe-135 4,00E+12

Xe-138 7,90E+10

Total activity 3,44E+13

The analysis of the given results shows that amount of potential accidental releases

does not exceed the levels which meet the maximum permissible values of radiation criteria

for equivalent and absorbed doses on the border and outside the sanitary protection zone,

specified in the documents SP АS-88 and NRBU-97. Thus, the maximum dose rates of all

types of design and beyond design-basis accidents will be lower the levels of unconditional

justification. The transboundary spread of radiation releases in case of accidents,

considering the distance of SUNPP from the borders with the other countries, will be slightly

different from the indicators for normal operation of the power units.

The analysis results for the beyond design-basis accidents confirm the surveillance area

(30 km), specified by the plant design, which defines area of unconditional justification for

urgent countermeasures.

Probable environmental contamination due to transboundary atmospheric transfer

of releases from SUNPP power units.

Spread of releases depends on scope and intensity of the atmospheric transfer –

velocity and direction of wind. Below there are probable consequences of SUNPP impacts

to the adjacent territory, based on the average wind-rose in the Yuzhnoukrainsk town in

2014 for tritium radionuclides which releases are most significant, and exposure dose limit.

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Fig. 6.6. – Probable activity of radionuclides of tritium in the surface layer of air due to

atmospheric transfer of releases from SUNPP

The area of contamination, Bq/m3:

1 - ≥ 0,01; 2 - ≤ 0,01, ≥ 0,005; 3 - ≤ 0,005, ≥ 0,001; 4 - ≤ 0,001, ≥ 0,0005; 5 - ≤ 0,0005, ≥

0,0001

The global indicators of tritium activity in atmospheric air amount to 0,12 Bq/m3.

As wee can see from Fig. 6.6., content of tritium in air of the neighbouring countries

due to releases from SUNPP in 2014 caused the probable increase in activity which does

not exceed 0.4% of the average global value.

Fig. 6.7. – Probable activity of tritium radionuclides in fallouts on the ground surface due

to atmospheric transfer of releases at SUNPP

The areas of contamination, kBq/(m2/year)

1 - ≥ 100; 2 - ≤ 100, ≥ 50; 3 - ≤ 50, ≥ 10; 4 - ≤ 10, ≥ 5.

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Fig. 6.8. – Probable additional exposure dose due to atmospheric transfer of releases at

SUNPP

The areas of contamination, mSv/year:

1 - ≥ 0,001; 2 - ≤ 0,001, ≥ 0,0005; 3 - ≤ 0,0005, ≥ 0,0001.

The average global value for exposure dose limit is 2.4 mSv/year.

As we can see from the figure, the impact of releases from the SUNPP power units to

the neighbouring countries is almost not noticeable (it is 2 E-5% of global average value).

Considering the nature of the proposed activity, it can be stated that the analysed

impacts of radioactive releases from the SUNPP will remain at the current level.

The analysis allows to make a conclusion about practical absence of harmful

transboundary impacts associated with life-time extension of the SUNPP power units in

normal operation or in case of design or beyond design-basis accidents.