nvironmental protection eport 2004 › en › documents › enviromental_protection_rep… · 2...

1

Paks Nuclear Power Plant Inc.

ENVIRONMENTAL PROTECTION REPORT

2004

Paks 2005

Paks Nuclear Power Plant Environmental Report on

year 2004

2

Edited by

Sallai Orsolya

environmental protection engineer

Collated by

Volent Gábor Pécsi Zsolt

Head of Industrial Safety Department Environmental Protection Team Leader

Bujtás Tibor Demeter Károly

Head of Radiation Protection Section Head of Operational Department

Dr. Schunk János Radnóti István

Head of Chemistry Department Safety Manager

Signed by

Kovács József

Chief Executive

3

Co-Editors:

Sallai Orsolya

Pécsi Zsolt

Fink Gábor

dr. Schunk János

Köves László

Feil Ferenc

Ranga Tibor

Nagy Zoltán

Demeter Károly

4

Contents

1 Introduction ...................................................................................................................................... 5

2 Company Profile .............................................................................................................................. 5

3 Nuclear Enviromental Protection ..................................................................................................... 8

3.1 Radioactive Emission ............................................................................................................... 9

3.2 Enviroment Control ................................................................................................................ 12

4 Annual Evaluation Report on the Enviromental Protection Activities of Paks Nuclear Power Plant

in 2004................................................................................................................................................ 15

4.1 Water Quality Protection ........................................................................................................ 15

4.1.1 Surface Water Protection ................................................................................................ 15

4.1.2 Subsurface Water Protection ........................................................................................... 21

4.2 Atmospheric Purity Protection ............................................................................................... 22

4.3 Waste Management – Inactive Waste .................................................................................... 22

4.3.1 Hazardous Waste ........................................................................................................... 22

4.3.2 Industrial and production Waste ..................................................................................... 24

5 Abolishing the Consequences of the Serious Incident that Happened in Unit 2 of PNPP in April

2003 .................................................................................................................................................... 25

5.1 Ensuring the Autonomous Operation of the No. 1 Pit ........................................................... 26

5.2 The Licensing of the Restoration ........................................................................................... 26

5.3 The Fulfilment of the Removal Contract .............................................................................. 27

5.4 Other Activities Related to the Removal ............................................................................... 28

6 Radioactive Waste Management .................................................................................................... 28

6.1 Developments in connection with the Management and Interim Storage of Radioactive

Waste at PNPP .............................................................................................................................. 28

6.2 Low and Intermediate Level Solid Waste .............................................................................. 30

6.3 High Activity Solid Radioactive Waste .................................................................................. 33

6.4 Liquid Radioactive Waste....................................................................................................... 35

6.4.1 Evaporation Residues ..................................................................................................... 35

6.4.2 Evaporator acidifying solution ....................................................................................... 35

6.4.3 Spent primary loop ion-exchange resins ........................................................................ 36

6.4.4 Active solvent mixtures .................................................................................................. 36

6.4.5 Contaminated technological boric acid solutions ........................................................... 36

7 Enviromental Protection Management System .............................................................................. 38

7.1 Enviromental Politics of Paks Nuclear Power Plant .............................................................. 38

7.2 Enviromental Centered Goals and Programs ......................................................................... 40

8 Transport of Hazardous Products and the Safety Advisory System............................................... 44

9 Abbreviations and concepts ........................................................................................................... 46

1 Introduction

Paks Nuclear Power Plant (PNPP) is Hungary’s major electric power company.

Under the aegis of environmentally sound power production, the PNPP established the Environment

Centered Control System in 2001. In 2002 the Hungarian Standards Institution standardized the

Environment Centered Control System by the MSZ EN ISO 14001:1997 standard.

The second annual audit (and inspection) of the Environment centered Control System was carried

out by the Hungarian Standards Institution in November 2004. On the audit the operation of the

PNPP environmental protection management system was proved to be adequate. The continuous

5

improvement in environmental protection projects was averred, so the MSZ EN ISO 14001:1997

standard deed of assignment was confirmed again by the Hungarian Standards Institution.

2 Company Profile

The PNPP’s basic activity is electric power output. Last year the PNPP produced 36 % of the home

electric power production, i.e. 11 915 GWh (1 GWh = 1,000,000 kWh).

Since 1988 (one year after starting Unit 4) the amount of electric power output produced by the four

blocks of PNPP has fluctuated between 13,400 and 14,180 Gwh; except for the years 2003 and

2004 when, due to the incident in 2003, Unit 2 did not work most of the year in 2003 and in 2004 as

well, so the nuclear power plant functioned in a 3-unit mode because the consequences of the

incident had to be abolished. In 2004, the utilization rates of the units were the following:

Unit 1: 87,5 %

Unit 2: 29,3 %

Unit 3: 88,5 %

Unit 4: 85,7 %

The electric power output of PNPP from the start till nowadays is presented in Figure 1.

1. figure translation:

év = year

Figure 1. Electric power output of the PNPP.

Hungary’s total energy consumption is added up by home production and import. The proportion of

6

home production to import is illustrated in Figure 2, where “other home energy production”

includes coal-, oil-, gas-fired power plants and reviving energy sources.


atomerőműi termelés = electric power production of the power plant

egyéb hazai termelés = electric power production of other home sources

import = import

Figure 2. Hungary’s electric energy consumption

The four units of the PNPP started between 1982 and 1987. Their operating data are summarized in

Table 1 below.

(Table 1)

7

1. table translation:

típus = type

nyomottvizes, vízhűtésű, víz moderátorú VVER-440 V-213 energetikai reaktor = pressurized water,

water-cooled, water moderated VVER-440 V-213 energetic reactor

a primerköri hurkok száma = number of primary loops

hőteljesítmény = heat output

turbinák száma = number of turbines

blokkok névleges villamos teljesítménye = nominal electric capacity of the Units

az aktív zóna töltete = reactor core loading

42 tonna urándioxid = 42 tons of uranium dioxide

Table 1. Basic operational data of the PNPP.

3 Nuclear Enviromental Protection

In the evaluation of the operation of the PNPP besides nuclear safety and energy production

efficiency indexes, environmental effects also play an important role. The basic requirements

include to have detailed information on the nuclear environmental effects of the power plant. It is

also very important that the measure of the effects mentioned above don’t exceed the levels allowed

by the authority regulations. The main task of radiation protection activity was to prove that the

PNPP complies the derived emission limits and the primary dose restriction applied to the operation

of the power plant in 2004, too. For the documentation radiation indexes of the environment and

direct survey data were used.

In order to reach the goals mentioned above, the Radiation Protection Section accomplished a

comprehensive inspectorial program and took necessary actions. In 2004, similarly to past years,

8

the nuclear environmental protection was characterized by two-levelled control including

measurement taken by remote-controlled metering system and sampling based laboratory

measurement.

3.1 Radioactive Emission

The new emission limitation system appointed by the 15/2001 (VI.8.) decree took effect in 2004.

This limitation compares the proportion of airborne and liquid emission to that of isotope specific

emission limits. The aggregate emission data and their ultimate value criterion are presented in

Table 2. In summary it can be stated that the PNPP utilized 0.27% (0.15% liquid, 0.12% airborne)

of the emission ultimate value (emission criterion: 2.67 × 10-3

).

The emission ultimate value criterion of the PNPP in 2004: 2.67 × 10-3

, i.e. 0.27%.

The emission ultimate value criterion applied to a certain isotope and a emission type is the quotient

of the emission ultimate value and the amount of isotope emitted.

Calculation of the ultimate value criterion:

Elij = emission ultimate value applied to i radionuclide and j emission type (Bq/year)

Rij = yearly emission applied to i radionuclide and j emission type (Bq/year)

9


Izotóp-csoportok = Isotope groups

Összes kibocsátás = Total emission

Kibocsátási határérték kritérium = Emission ultimate value criterion

Légnemű kibocsátások = Airborne emissions

Korróziós és hasadási termékek = Corrosion and fission product

Radioaktív nemesgázok = Radioactive noble gases

Radiojódok = Radioiodines

Trícium = Tritium

Radiokarbon = Radiocarbon

Összes légnemű kibocsátás = Total airborne emission

Folyékony kibocsátások = Liquid emissions

Alfa-sugárzók = alpha-emitters

Összes folyékony kibocsátás = Total liquid emission

Table 2. Summarized emission data.

Emission values of the PNPP are compared to international data in Table 3, which shows emission

indexes normalized for energy production of PWR (pressurized water reactor) nuclear power plant

units similar to the PNPP’s. International data are available from only the 1995-1997 period, so the

UNSCEAR1 used these data (except for emission indexes of radiocarbon, which are available from

only the 1990-1994 period) in its report in 2000.

It appears from the comparison that the amount of corrosion and fission products has seemingly

increased. According to the new regulations, emission data are calculated from isotope selective

measuring. Unmeasured isotopes are counted in with their detection ultimate value. In past years

these values were determined by measuring total-beta radiation.

In case of Paks liquid emission the amount of corrosion and fission products as well as that of

tritium is under the international average.

1 UNSCEAR stands for the United Nations Scientific Committee on the Effects of Atomic Radiation.

10


Radionuklid = Radionuclide

Év = year

Légnemű kibocsátások = Airborne emissions

Összes aeroszol = Total aerosol 131

I egyenérték = 131

I equivalent

Összes nemesgáz = Total noble gas

Összes trícium = Total tritium

Total radiocarbon = Total radiocarbon

Folyékony kibocsátások = Liquid emissions

Korróziós és hasadási termékek = Corrosion and fission product

Trícium = Tritium

Table 3. Amount of the PNPP radioactive emission in consideration of UNSCEAR data mirror.

Note: The international data are applied to pressurized water reactor units working the same way as

those of the PNPP (UNSCEAR Report 2000)

* : average of the 1985-2003 period

** : average of the 1988-2003 period

*** : average of the 1995-1997 period

3.2 Enviroment Control

The PNPP runs the Industrial Environmental Radiation Protection Control System (Üzemi

Környezeti Sugárvédelmi Ellenőrző Rendszer, ÜKSER). The radiation protection control of the

PNPP’s environment is carried out by telemetric systems, sampling inspections and lab-

examinations. The locations of the sampler and telemetre stations in an area of 30-km semi-

diameter is shown in Figure 3. The lab-examinations cover the environmental sphere and factors of

11

the food-chain that means data processing and measurement of approximately 4000 samples yearly.

The operation of the PNPP did not have directly measurable effects on the radiation rates of the

environment in 2004. The measurements of dose rate metering sondes at “A” and “G” type

measuring stations and TL detectors at other stations showed dosage rate and dose of the natural

gamma-radiation.

3. ábra szószedete

távmérő és mintavevő állomás (A típusú) = telemetre and sampler station (A type)

mintavevő állomás (B típus) = sampler station (B and C type)

vízmérő és mintavevő állomás = flood-measuring post and sampler station

meteorológiai mérőtorony = meteorological instrument tower

az ÜKSER központja (KAR) = the ÜKSER Centre

Környezetellenőrző Laboratórium = Environment Control Laboratory

Figure 3. Locations of sampler and telemetre stations near the PNPP.

Considering the correction derived from the change of the physical variables, the average dose rates

values measured by ALNOR TL dose-meter (Figure 4) correspond to the data of earlier years’

reference level period. It can be stated that it is not possible to conduct the adjunct of the nuclear

power plant from the data of the 2004 environmental dosage measurement. This phenomena is in

12

accord with the picture derived from the atmospheric emission of radioactive materials. According

to this picture the adjunct arising from the power plant is much less than the value of the natural

background radiation and its fluctuation, so it is undetectable by direct dosage measurement

methods.


dózisteljesítmény = dose rate

mintavevő állomások = sampler stations

Figure 4. Monthly average environmental dose equivalent rate of the environmental gamma

radiation measured by ALNOR TLD at telemetre and sampler stations in 2004.

Approximately 2.4-3.7 Bq/kg of radionuclide (60

Co) emitted from the power plant was found in

some of the Danubian mud samples taken from the discharge culvert and some further places.

Emitted radioactive isotope was not detected in the soil, grass, fishpond and mud samples taken

near the measuring stations. In the case of tritium the yearly average accrue of radioactive materials

emitted into the Danube was less than 1 Bq/dm3, while examining all other radionuclides it was less

than 0.1 mBq/dm3. The measurements were taken after total blending. Emitted radioactive isotopes

were not found in milk and fish samples.

The direct environmental presence of radioactive isotopes was undetectable or occasionally showed

low concentration in spite of the accurate examination methods. Concerning the surface air samples,

among the radioaerosols emitted form the power plant only the 54

Mn and 60

Co was detectable in

activity-concentration of 10 µBq/m3

at the outmost at “A” type measuring stations. The

radiocarbon was detected in concentration of 0.1-1 µBq/m3. The activity concentration of tritium

was estimated at 10 mBq/m3

while that of radioactive noble gases was approx. 100 mBq/m3

in the

same place. In the fall-out samples there were no detectable radioactive isotopes emitted by the

PNPP. The samples were taken from the area 1-2 kilometers far from the power plant.

13

In summary, according to the results of the 2004 environmental measurements, it can be stated that

the environmental effects of Interim Storage of Spent Fuel Cartridges of the PNPP were negligible.

The PNPP radiation protection organization using emission and meteorological data as well as

direction models calculated the public extra exposure dose. According to the calculation the public

extra exposure dose derived from liquid emission, applied to a critical public group is 57 nSv that

corresponds with the levels of extra exposure dose before 2003.

4 Annual Evaluation Report on the Enviromental Protection Activities of

Paks Nuclear Power Plant in 2004

4.1 Water Quality Protection

4.1.1 Surface Water Protection

The PNPP is the largest user of raw water, so it takes great care of water quality protection. The

amount of coolant and technological water taken from surface waters was 2.17 billion m3 in 2004. It

is similar to year 2003 and less than in the years before 2003 (Figure 5.). The reason for this

phenomenon was that Unit 2 did not produce electric power in most of the year of 2003 and 2004.

The social featured drinking-water utilization provided from confined-water wells was 238 583 m3.

Although the emitted cooling water did not lead to the thermal pollution of the Danube, it caused

heat-loading of the river. The degree of the warming up does not disturb the ecological balance. The

PNPP kept the heat-scale and the water temperature maximum licence in 2004, too.

Because of its good quality, it is possible to utilize the condenser water. It also provides fresh water

supply for the nearby fish ponds. In 2004 7.3 million m3 water was sent to supply the Fadd dead

channel in summer time.

14


felhasznált hűtővíz mennyisége [1000 m3/év] = amount of used cooling water [1000 m

3/year]

év = year

Figure 5. Cooling water utilization of the PNPP between 1996 and 2004.

Waste water of the social water use is emitted through the sewage clarification system of the power

plant. The technical control and the Low Danube Environmental Advisory Board (Alsó-Duna-

völgyi Környezetvédelmi Felügyelőség) regularly check the efficiency of the sewage clarification.

The efficiency of the sewage clarification and the quality of emitted water always met the

requirements. 258 000 m3 municipal waste water was issued in 2004.

The results of the 2004 municipal waste water tests are summarized in the table below.


komponens = component

mért max. érték* = maximum value measured

hatósági korlát = official ultimate value

NH3 – NH4+ N-ben kifejezve = NH3 – NH4

+ given in N

olajtartalom = oil content

Table 4. Parameters of municipal waste water in 2004.

Most of the inactive waste water consists of acid and alkaline contamination waters generated

during desalted water production. The amount of waste water of the softening plant was 132 000 m3

in 2004. The neutralization of waste water takes place in a 10 000-m3

sludge tank. The water quality

and emission of the tanks is under regular technical control. The quality of waste water emitted after

neutralization and emission was satisfactory. The concentration of contaminating substances did not

each the limit values in the discharge culvert.

Emission data of the discharge culvert in 2004 are showed in the Table 5.

15


komponens = component

mért max. érték = maximum value measured

hatósági korlát1 = official ultimate value


összes oldott anyag = total solute

összes lebegőanyag = total suspended-matter

NH3 – NH4+ N-ben kifejezve = NH3 – NH4

+ given in N

Table 5. Water quality parameters of the values measured in the discharge culvert in 2004

14. oldal lábjegyzet: 2Maximum value measured by the Environmental Protection Authority.

3Official ultimate value according to the 3/1984. (II.7.) decree.

The waste water of the softening plant and discharge culvert is regularly checked once a week.

Quality parameters of the discharge culvert are presented in the figures (6 a-b-c) below.

16

6.a. figure translation:

hatósági korlát százaléka* = percentage of the official ultimate value

2004. január = January 2004

2004. február = February 2004

2004. március = March 2004

2004. április = April 2004

2004. május = May 2004

2004. június = June 2004

2004. július = July 2004

2004. augusztus = August 2004

2004. szeptember = September 2004

2004. november = November 2004

2004. december = December 2004

dátum = date

összes oldott anyag = total solute


ammónia – ammónium = ammonia – ammonium

17

6.b. figure translation:

hatósági korlát százaléka* = percentage of the official ultimate value





2004. május = May 2004







dátum = date

összes lebegőanyag tartalom = total suspended-matter content

18

6.c. figure translation:





2004. május = May 2004







dátum = date

pH alsó korlát = pH lower bound

pH felső korlát = pH upper bound

Figure 6.a-b-c. Water quality parameters of the discharge culvert.

The figures and tables show that the ultimate values were not exceeded.

19

4.1.2 Subsurface Water Protection

The effects of the PNPP’s emissions are monitored by an expanded ground-water controlling well

system. Different parameters are examined – independently on the tested technology – in

approximately 50 ground-water controlling wells. The examinations are carried out accordingly to

water rights licence authorized by the partially determined environmental protection inspection of

the year 2000. In order to follow the proceeding of possible ground-water pollution, water-level of

80 wells are recorded regularly.

In order to prevent ground-water pollution the PNPP started to work out a program for the check of

the conduit-pipe systems, which endanger the open space environment and are neither under cyclic

control nor ranged among safety classes. The program successfully finished in December 2004. The

inspection of the oil extracting station and oil dump system was not doable in 2005, so it was

postponed to 2005. As a result of the condition tests a program for ensuring good condition of the

systems mentioned above was worked out.

In recent years the on-site damage prevention near the two transformers was efficient. The oil

contamination of the soil stopped. The results of the ground-water tests showed that the

contamination concentration was under the official ultimate unit. The Environmental Protection

Authority prescribed quarterly accredited sampling from the observation wells in the area of the two

transformers and TPH and Σ PAH content measurement. The results of the follow-up tests are

presented in the table below.


Mintavétel időpontja = Date of sampling

kút = well

határérték = ultimate value

Table 6. The results of the follow-up tests ( TPH and Σ PAH content)

6. table footnote: 4

The ultimate values are equal to “B” type contamination ultimate values determined in the

10/2000. (VI.2.) KöM-EüM-FVM-KHVM decree.

20

4.2 Atmospheric Purity Protection

Due to the technology applied at nuclear power plants, the airborne emission is low.

Three traditional, inactive atmospheric load technologies are applied in the Paks in-plant area.

safe diesel generators working as emergency power supply (12 point emitters);

diesel-driven fire water pump (2 point emitters);

painting technology: paint room, paint-spraying booth (2 point emitters).

The PNPP has environmental authority license for all of the technologies mentioned above.

The gr. pollution emitted during the short test runs (200 hours altogether) is relatively small and

hardly has effects on the emission itself.

The concentration of air contaminant materials emitted by the point emitters was measured by

accredited measuring organization. The measuring was carried out by standard emission measuring.

In 2004 the official ultimate value was not exceeded and all operations of the PNPP met the

requirements of air purity protection applied to diesel generators and emergency power supply.

4.3 Waste Management – Inactive Waste

4.3.1 Hazardous Waste

In 2004, 361 455 kilograms of hazardous waste (principally dead oil, waste contaminated with oil,

electric waste, rejected technological chemicals and paint packs) were generated.

The PNPP provided the elimination of 343 629 kilograms of hazardous waste by passing it to

licensed contractors.

The hazardous waste generated on 2004 is showed in Figure 7.

21

7. figure translation::

olajos föld = oil-contaminated soil

egyéb = other

fénycső = luminous tubes

selejt tecnológiai vegyszer = rejected technological chemical

ioncserélő gyanták = ion-exchange resins

nyomdafesték hulladék = book-ink waste

bontott tetőszigetelés = demolished roof structure

ólom akkumulátor = lead accumulator

olajos iszap = oil-contaminated sludge

kommunális szennyvíziszap = communal sewage sludge

veszélyes anyagot tart. göngyöleg = hazardous paint pack

olajos fold = oil-contaminated soil

elektronikai hulladék = electronic waste

fáradt olaj = dead oil

Figure 7. Hazardous wastes occurred in large amount in 2004.

The category, “other” refers to hazardous waste including medical waste, chemicals, office

technology waste, waste containing asbestos, off-warranty period paint, dry batteries, spray bottles,

glue containing hazardous materials, drilling fluid. The weight of each waste type mentioned above

did not reach the 5000 kilograms.

22

Figure 8. The amount of hazardous waste between 1996 and 2004.

Figure 8 illustrates well that the total amount of hazardous waste was smaller than between 1996

and 1997. It is due to that the caustic mud was pronounced to be non-hazardous waste, the decrease

of the amount of waste derived from rejection and the end of changing accumulators. The amount

of nascent hazardous waste significantly increased in comparison with the year 2003, because the

replacing the temporary foundation of the transformers generated crushed stone.

Collection and storage of hazardous waste is provided according to the regulations in the licensed

Hazardous Waste Industrial Collector.

29,5 tons of hazardous waste were stored in the Hazardous Waste Industrial Collector on 31

December 2004. Most of the hazardous waste in the area of the PNPP is 150 tons of communal

sewage sludge, which is treated in the slime-thickener bed.

4.3.2 Industrial and production Waste

Industrial waste is collected separately from communal waste and stored in an appointed place for

selective waste collecting or in a store room.

In the area of the PNPP, the amount of non-hazardous industrial waste was 55,7 tons at the of 2003.

In 2004, 921 tons of non-hazardous industrial waste were generated during the operation of the

PNPP. In 2004 the PNPP sold 795 tons of non-hazardous industrial waste for further utilization and

placed 83.8 tons of inapplicable waste into industrial waste stores. The total amount of non-

hazardous waste remained from the year of 2003 and generated in 2004 was 976.7 tons.

The industrial waste traffic in 2004 is presented in the figure below.

23


lerakóban elhelyezett = placed in waste stores

telephelyen tárolt = stored in waste depots

hasznosított = utilized

Figure 9. Industrial waste traffic in 2004.

5 Abolishing the Consequences of the Serious Incident that Happened in

Unit 2 of PNPP in April 2003

The preliminary steps in the removal of the damaged fuel elements from the No. 1 pit in Unit 2

were taken under the direction and organization of the Restoration Project (RP) in 2004.

At the same time, at the beginning of the year the management of the power plant established a

preparatory team for the restoration of Unit 2, which worked parallel with the RP, coordinating their

tasks.

This chapter evaluates how the consequences of the incident are being abolished.

5.1 Ensuring the Autonomous Operation of the No. 1 Pit

In the first half of 2004, the autonomous coolant loop and the emergency boration system was

established, the reconstruction ensuring the jodine-filtered ventilation of the reactor hall was

prepared and the reconstruction was finished in December. In the course of the establishment of

these autonomous systems, there were some difficulties caused by the preparatory tasks – the

determination of the fund, the preparation of safety analysis – that enhanced the time-demand of the

process. After their installation the autonomous systems were working in order and on the basis of

operation experiences they were qualified as fit for the fulfilment of their functions.

The neutron-flux control system of the damaged fuel elements was too sensitive for electric

24

interferences as a result of temporary extension and so some boric acid was dissolved in the

cleaning tank, several times and practically without any real reason. After due consideration, the

obligatory dissolving of boric acid was excluded from the process of intervention so the new

regulations reduced the number of unwarranted interventions significantly. Besides, we were

examining the application of 3/2 logic in the case of the neutron-flux increase but the application of

this logic needs further analysis and a more realistic dilution model.

5.2 The Licensing of the Restoration

The licensing of the restoration was harmonized with the authorities which means that it has to be

carried out according to the relevant regulations of the Nuclear Safety Regulation (NSR). The

Nuclear Safety Management of the Hungarian Atomic Energy Authority (HAEA NSM) had

published its requirements in January 2004 on the basis of which the form and content of the

theoretical licensing documentation was worked out. Then the general designer of the nuclear

power plant, Erőterv started to draw up the documentation. The documentation was based on the

technological safety reports and technological plans drawn up by the Russian company TVEL.

However, to a significant extent, it became necessary to to work out the documents requiring home

resources. Because of the overall official requirements, the theoretical licensing documentation was

finished much later than it was planned. The theoretical licensing documentation was handed over

to the technical authorities for licensing and to independent experts so that they could report on it.

According to the plans the documentation would have been handed in to the HAEA NSM in

December but this did not happen because there were some difficulties in connection with the

design of the capsules that would serve for the storage of the damaged fuel elements. The nuclear

power plant requested from the Russian partner the the design of a new capsule-top that would

serve to close the the capsule as a result of which the capsules would become fit for longer storage

in the cooling pond. However, the original, hermetically closed construction was not abandoned

because it might be nedded for the transportation or the final disposal of the capsules.

Parallel to the working-out of the theoretical licensing documentation, the import /

production licensing of the facilities required for the removal (of the damaged fuel elements) had

started to be prepared on the basis of the export plans drawn up by the company TVEL. The

documentation was worked out by the company Transelektro and after the revision it will probably

be handed in to the authorities for licensing in the first quarter of 2005. Besides the working-out of

the licensing documentation of the facilities, the production / import licensing documentations of

the capsules and the tools and instruments needed for the removal also started to be worked out and

prepared for licensing. These documentations will probably be handed in to the authorities for

licensing in the second quarter of 2005.

5.3 The Fulfilment of the Removal Contract

On the basis of the contract about the removal, the Russian company TVEL had handed over the

technological safety founding reports in February 2004 and the technological plans at the end of

March. Although the handing over of the documents met the deadline, they had not been accepted

until the supplements and corrections necessitated by the deficiencies were finished. The

technological / execution plans were handed over two months later than the contractual deadline

and a significant correction was necessary in this case, too. The corrections can be attributed to the

uniqueness of the task and to the continuous improvement of the solutions. Besides, several

difficulties were caused by the misunderstandings arising from the translations and by the

25

differencies between the two planning cultures. Meeting the new official requirements in the

documents also needed considerable extra effort from both the Hungarian and the Russian partner.

The official requirements in connection with the content of the theoretical licensing documentation

and the specified technological requirements made it necessary to modify the technological content

of the contract and the timing of its fulfilment. These modifications were atteched to the contract as

a supplement.

As to the fulfilment of the contract, the designing of the capsules for the storage of the damaged

fuel elements caused some technological difficulties and in the case of certain solutions (catalyst,

wadding, emptying valves) the contractual guarantees are not fulfilled at the present. These

problems have to be settled before the import / production licensing because if these guarantees

failed to be realized, they would endanger the obtaining of the official license. In connection with

the capsules, the handling activities in the cooling pond after the encapsulation also began to be

worked out because they are not included in the removal contract.

The Russian partner began to work out the procedures and orders related to the direct execution

activities of the removal which were discussed at the end of this year. According to this discussion,

each partner began to work out the procedures and orders that should be prepared by them. These

procedures will be discussed in the beginning of the next year.

5.4 Other Activities Related to the Removal

Significant complementary activities are needed in connection with the process of removal which

are primarily necessary for the on-the-spot operation of the removal. The preparatory works of the

ventilation system (planned to be used during the removal), of the system for the keeping of the

water level and for the washing of the tools planned to be used for the removal, and of the safe-

guard measuring system were all started. Also, a contract was made with the company VUJE about

the decontamination of the No. 1 Pit before and after the removal, and about the decontamination of

the of the cleaning tank. As to the operating systems, the first versions of the technological plans

had been accomplished, they had been evaluated and revised on the basis of which the contractors

began to work out the technological plans of the final solutions and the licensing documentations.

Summary

The task set in connection with the removal of the damaged fuel elements in Unit 2 is carried out

slower than it was originally planned. The reason for this is the complexity and uniqueness of the

task. At the original programme the knowledge was not available on the basis of which it would

have been possible to define aims realistically – except for the main aim. Consequently, in many

instances the aims were modified or the activities were corrected which influenced the whole

procedure of the work. The encapsulation of the damaged fuel elements as soon as possible should

still be considered as the main goal because the present state means a certain risk factor for the

nuclear power plant and its surroundings. However, the encapsulation can only be accomplished

within the framework of an absolutely safe solution even if it takes more time than it was originally

planned.

26

6 Radioactive Waste Management

6.1 Developments in connection with the Management and Interim Storage of

Radioactive Waste at PNPP

'Radioactive Waste Management' is a term in the international practice which means the collection,

temporary storage, volume reduction, conditioning (i. e. the development of waste packages the

form of which is suitable for final disposal), characterization and on-site interim storage of the

radioactive waste produced in a nuclear power plant before the waste is transported to the final

repository facility. (It has to be noted that the spent fuels are not considered as radioactive waste.)

Because the regulatory control is getting tighter and tighter, and also because of the serious

incident of Unit 2 in April 2003, developments related to waste management form an important task

in Paks NPP.

The 'Atomic Energy Act' accepted at the end of 1996 together with the decrees and orders based on

it established the Public Agency for Radioactive Waste Management (PURAM) which has to take

charge of the final disposal of radioactive waste. In order to finance the tasks in connection with the

final disposal of radioactive waste, the interim storage and final disposal of spent fuel and the

decommissioning of the power plant, Paks NPP pays an amount annually to the Central Nuclear

Fund (CNF) based on the amount of waste produced.

The task of the NPP is the management and on-site interim storage of radioactive waste. This task

should be accomplished in the following way:

the radioactive waste should not disturb the operation of the power plant

the unavoidable investments should be minimal and cost-efficient (if necessary, the interim

storage facilities could be enlarged in a modular way; superfluous storage capacities should

not be built),

the present technologies of waste management should be utilized optimally even if new

technologies will have to be applied

waste packages should be developed so that the form of the waste intended for final disposal

together with the engineered barriers of the container and with the geological features can

ensure safe storage

the standards of waste management and interim storage should be in level with the

international reputation of the power plant

the necessary changes should not have a detrimental effect on the public approval of

radioactive waste management.

We were able to reach these aims with the help of technologies that were quite different from the

methods of low and intermediate level waste management specified in the original Russian

technical specifications.

The following improvements were accomplished in the last few years:

A significant amount of solid waste is compacted to the one-fifth of its original volume with

a 50-tonne press and put into 200 l metal vessels. (We have been using this technology for

the volume reduction of solid waste since 1988.)

For the storage of low and intermediate level waste we formed – through rebuilding – a

container which stores waste-packages in a modern, retrievable way.

The two container fleets in the auxiliary buildings, which store liquid radioactive waste,

27

have been connected with a tunnel bridge with the use of which storing capacity can be used

more optimally.

We have introduced a gamma-spectometric measuring system with the help of which the

isotope-content and -composition of low and intermediate level solid waste in the vessels

can be determined.

We have introduced a semi-automatic equipment selecting solid waste with the help of

which we have managed to reduce the amount of low and intermediate level solid waste by

about 10%.

We have developed a method of filtering through a kind of silica with the help of which the

amount of radioactive oils and solvents that require management have decreased

significantly.

With the help of underwater treatment with plasma, we have managed to reduce

significantly the amount of liquid waste produced during the chemical clean-up of the

equipments.

The production of liquid radioactive waste can be prevented by the installation of industrial

ultra-filtering equipments that can clean boric acid solutions used in the power plant. We

have installed such high-performance equipments in both of the auxiliary buildings, one in

each.

The following improvements are being implemented :

It will be possible to reduce the amount of liquid radioactive waste – which has

been produced and which is stored in containers in the auxiliary buildings – with

the use of a Finnish technology which is being installed at present.

Those mud-like radioactive waste the amount of which cannot be reduced further

will be solidified with a cementing equipment developed in Germany.

The serious incident in No. 1 sink of Unit 2 in 2003, the uncertainites about the accomplishment of

the planned final repository of low and intermediate level waste in Bátaapáti, and the exhaustion of

the on-site interim storage capacities resulted in the reconsideration of the waste management

strategy applied in the nuclear power plant. As part of this reconsideration, the realization or

planning of the following improvements have started out:

It is necessary to expand the capacity of the storing container fleet for liquid radioactive waste,

through the building of further containers. (This work is in progress and the system will be

ready for use in the beginning of 2005.) With this expansion the interim storing capacity of

liquid waste will expand by 3800m3.

The modular expansion of the capacity available for the interim storage of low and intermediate

level solid waste.

First of all, the possibilities of the reprocessing and volume reduction of the various types of

radioactive waste should be reviewed in a study plan; after that, it will be possible to decide on

the specific improvements. (Cutting up large pieces of solid waste, the treatment of high dry

matter content mud, the further volume reduction of the waste (pre-compressed by the 50-tonne

press) using a supercompactor; the treatment of waste containing long-lived isotopes, etc.)

Certain analyzing and preparatory tasks are in progress which aim at the installation of

technologies for the processing and conditioning of solid and liquid radioactive waste that was

produced in connection with the damaged fuel cells in No. 1 sink of Unit 2, and still being

produced in connection with their removal.

The Public Agency for Radioactive Waste Management is preparing the requirements of the

final disposal of low and intermediate level waste. Some of the temporary requirements

necessitate the installation of new technologies of waste management (eg. waste dryer

28

equipment). The related analyzing and preparatory tasks are in progress.

The problems that need to be solved in the future are difficult, but with the improvements that are

planned and that are already in progress we will be able to manage the situation.

6.2 Low and Intermediate Level Solid Waste

In 2004, 759 vessels containing low and intermediate level solid waste were produced which is 31%

(334 vessels) less than the amount produced in the previous year. During the major repairs and the

operation of the units, the amount of radioactive waste produced was in level with the previous

years (except 2003).

The Storage / Disposal of Solid Radioactive Waste

In 1996, the final repository at Püspökszilágy received the last transport of solid radioactive waste.

Since then, the vessels of solid radioactive waste are stored in interim storage premises and

temporary collecting facilities within the controlled area of the power plant until the commissioning

of the final repository.

The aim of the interim storage of radioactive waste is the temporary, controlled storage preliminary

to its final disposal. All of the amount of waste produced and managed during this year was placed

in an appropriate room (VK302/I).

The following table shows the amount of low and intermediate level solid waste stored in the power

plant at the end of 2004, broken down into storing rooms.

(table 7)

Table translate:

7. táblázat Átmeneti tárolók és ideiglenes gyűjtőhelyek töltöttsége = Table 7 The utilization of

interim storage and temporary collecting facilities.

Helyiség = Room

Összesen = Total

Kapacitás (db hordó) = Capacity (vessels)

2004-ban betárolt mennyiség (db hordó) = Amount placed in 2004 (vessels)

Tárolt mennyiség (db hordó) = Amount stored (vessels)

Szabad kapacitás (db hordó) = Free capacity (vessels)

29

The next figure (Figure 10) shows the amounts of low and intermediate level solid waste produced

in the period between 1998-2004 and after processing.

Figure translate:

10. ábra Az 1998-2004 között keletkezett és a feldolgozás utáni kis- és közepes aktivitású

szilárd hulladékok mennyisége = Figure 10 The amounts of low and intermediate level solid waste

produced in the period between 1998-2004 and after processing.

keletkezett hulladék = waste produced

feldolgozás utáni hulladék = waste after processing

(év) = (year)

6.3 High Activity Solid Radioactive Waste

Until 31th

December 2004, 91.2 m3 of high activity radioactive waste was produced during the

operation of Paks NPP. Out of this amount 2.386 m3 were produced in 2004, which required 4.645

m3 storing capacity.

Out of the whole storing capacity, 53.8 m3 are free on Extension I2, and 76.8 m3 are free on

Extension II.

2 Extension I = twin Units 1 and 2 of the nuclear power plant that have shared technological

systems

Extension II = twin Units 3 and 4 of the nuclear power plant that have shared technological

systems

30

This means that on Extension I. 48,21% of the whole storing capacity is available, and 72,59 % on

Extension II.

Table translate:

8. táblázat A 2004-ben képződött nagy aktivitású szilárd radioaktív hulladékok típusai

blokkonként = Table 8 The types of high activity radioactive waste produced in 2004, for each unit

Blokk = Unit

Hulladék típusa = Type of waste

Térfogat (m3) = Volume (m3)

Százalékos arány [%] = Rate [%]

szűrőbetétek = filters

blokk összesen = unit total

közbenső rúd = intermediate rod

I. kiépítés összesen = Extension I. Total

vegyes = mixed

összesen = total

The following features can be seen in the above table on the basis of the amount of high activity

radioactive waste and the place of its production:

In 2004, 0,659 m3 less solid radioactive waste was produced than in 2003, and almost solely in

Extension I.

The amount of waste produced can mainly be attributed to the planned replacement of 28

intermediate rods of Unit 2 in December.

The high activity solid radioactive waste was placed in storing wells developed in the controlled

area of the power plant (rooms A501/I, A501/II, A101/1-4) and in lead containers in room A216/3

and A216/6.

31

6.4 Liquid Radioactive Waste

The main types of liquid radioactive waste are:

evaporation residues (concentrates)

evaporator acidifying solutions

spent primary loop ion-exchange resins

active muds

active solvent mixtures

contaminated technological boric acid solutions.

6.4.1 Evaporation Residues

In the controlled area of the nuclear power plant chemical waste waters containing radioactive

isotopes are produced from various sources. In these low dry matter content (3-5g/l) water solutions

all those solved chemicals are present which are used for the primary coolant loop, for the

regeneration of deionizers, for the fine control of reactor performance and for decontamination.

After treatment with chemicals (with “metaborate”), the collected waste waters are evaporated to

200 g/l “boric acid concentrate.” There ins't an option for collecting waste waters selectively. Until

31th

December 2004, 4645 m3 evaporation residue was produced, out of which 2625 m3 were

stored in No. 1 auxiliary building and 2020 m3 in No. 2.

In 2004, 190 m3 evaporation residue was produced, 145 m3 on Extension I (out of which 125 m3

are containing alpha-emitters because they are from Unit 2) while 45 m3 on Extension II.

6.4.2 Evaporator acidifying solution

The evaporator acidifying solution is used for the cleaning of the evaporators of No. 3. water filterig

equipment and it is stored in No. 2 auxiliary building. In 2004, 20 m3 evaporator acidifying solution

was produced, so the container which was determined for its storage last year contained 250 m3

evaporator acidifying solution.

6.4.3 Spent primary loop ion-exchange resins

The number of regenerations and resin replacements carried out on the primary coolant loop

deionizers is much less than it was estimated. It was estimated that 89 m3/year/two Units ion-

exchange resins will be produced (41 m3/year high level and 48 m3/year low level) and will have to

be stored separately. With the modification of the liquid waste storing system, we have completed

the united storage of ion-exchange resins. Until 31th

December 2004, 114.1 m3 spent resins were

produced during the operation in both auxiliary buildings, out of which 21.1 m3 were produced in

2004.

There isn't an emergency concerning the processing of ion-exchange resins. If we consider the

reconstruction of the storing containers of spent resins, the available storing capacity – 870 m3 –

will be sufficient for the interim storage of the amount produced through the whole lifetime of the

32

power plant.

6.4.4 Active solvent mixtures

Although their amount is not significant (4 m3 were produced in 2004), they are inflammable so it

was necessary to form a properly installed place which accomplishes the proper interim storage of

both the uncleaned and cleaned liquids.

Contaminated oils and organic solvents are filtered by a kind of silica. This method of filtering

achieves favorable results with quite simple instruments.

6.4.5 Contaminated technological boric acid solutions

There are thousands of m3 boric acid solutions of different concentration which have specific

technological use in the primary coolant system. During the operation, micron-sized or submicron-

sized active contaminations accumulate in these boric acid solutions which cannot be removed

effectively by the traditional method of built-in ion-exchangers. However, there are several reasons

why it is very important to remove them and not to let them increase without restraint. Firstly, their

replacement would become necessary because of the requirements of cleanness, which would result

in a significant increase in liquid waste. These contaminations have a detrimental effect on

transparency and on control. Besides, sediments might be deposited which would spoil heat-

exchange and would generate further processes of corrosion.

In 2004, we carried out the following filtering programs:

We cleaned the primary coolant of both units with the industrial ultra-filtering equipment of

Extension I (on Unit 1 as part of the stoppage and restart, and on Unit 2 as part of the fine

decontamination operation during the stoppage).

We cleaned the coolant of both units with the industrial ultra-filtering equipment installed on

Extension II, as well, during the stoppage and restart. In addition, we accomplished the

cleaning of the cooling pond of Unit 3, and the filtering of the technological boric acid

solution stored in the “contaminated” condensate container (02TC01B002), and the ultra-

filtering of containers 40TH10B001 and 40TR15B001.

We cleaned technological boric acid solutions containing alpha-emitters several times with

the low-performance ultra-filtering equipment installed in No. 1 auxiliary building.

In summary, the measurements (of transparency and the gamma-spectometric analysis) showthat we

completed all the filtering programs with excellent results.

The next chart shows the utilization of liquid waste containing vessels on 31th

December 2004.

(Figure 11)

33

Figure translate:

11. ábra Folyékony hulladéktároló tartályok töltöttsége (2004.12.31-i állapot) = Figure 11 The

utilization of liquid waste containing vessels (31th

December 2004.)

térfogat [m3] = volume [m3]

ioncserélő gyanta és transzportvíz = ion-exchange resin and transport water

technológiai bórsavoldat = technological boric acid solution

evaporátor savazó oldat = evaporator acidifying solution

sűrítmény = concentrate

szabad térfogat = free volume

7 Enviromental Protection Management System

7.1 Enviromental Politics of Paks Nuclear Power Plant

The PNPP’s most important aim is to produce energy in a safe and antipollution way as well as to

provide competitive prices. In order realize its future plans, the PNPP provides the environmental

conditions of the life-time extension and the increase of output of the power plant.

34

One of the PNPP’s duty is to maintain the environmental safety of the power plant, which develops

continually. It proves that the PNPP tries to meet the requirements of the neighbouring population

and the measures.

The PNPP determinates and evaluates the environmental risk factors meaning hazard point to the

environment during the PNPP’s operation. The PNPP decreases the effects of those factors as

efficiently as it can.

To improve environmental protection activity the PNPP is steadily developing the Environment

Centered Controlling System according to the MSZ EN ISO 14001 License. The PNPP’s contracted

partners are required to comply the environmental regulations. The PNPP has made certain of that

their partners’ activity is adequate to the environmental politics and the Environmental Centered

Controlling System of the power plant.

The PNPP applies the measures, regulations concerning and principles of environment protection as

well as:

the principle of precaution, prevention and reconstruction

the principle of responsible utilization of the environment

the principle of co-operation with society, the surrounding country, concerned

organizations and authorities

the principle of direct information,

and realize them consistently.

The PNPP regards the improvement of environmental efficiency and prevention of environment

pollution as its own responsibility. It carefully attends to economic use of natural resources and

utilization of waste generated at the power plant.

The PNPP provides regular courses on environment conscious thinking for its employees.

The environmental politics of the PNPP is under regular control and modified when it is found

necessary.

19 August, 2003 Paks

Dr. Kocsis István

Chief executive

7.2 Enviromental Centered Goals and Programs

One of the main characteristics of the Environment Centered Controlling System is the

improvement of the environmental protection activity, whose most important task is to determine

environmental goals and achieve them.

35

The environmental protection activity does not appear in every field of the corporation profile. The

aims of environmental protection are changing dynamically. While new goals are determined

annually, others get achieved.

The realization of programs for achieving the PNPP’s goals is continually evaluated by managerial

inspections.

Detailed programs belong to all of the PNPP’s goals.

New goals are determined every year. Some of the goals are short-term ones, so a few goals

determined earlier have already achieved (such as making the Environmental Reports 2001 and

2002); while others are long-term ones, whose realization is in progress according to the programs.

New goals are to be determined in 2004, too.

Present environmental goals of the PNPP and their evaluations are summarized below.

36

Enviromental Centered Goal

Enviromental Centered Goal Evaluation

We are accomplishing the full-scope

reconstruction of radiation protection and

environment control systems of the power plant.

The reconstruction of the radiation protection

and environment control systems is carried out

within the frames of an investment. The most

important task of the year 2004 was to finish the

establishment of the radiation protection and

environment control systems, and according to

this to guarantee the operation of the new, higher

technological quality monitoring system. Putting

the new system into operation was carried out

gradually, in parallel with the operation of the

old system. The execution of this work was

carried out continuously according to the action

program and it is expected to be finished in the

first half of the year 2005.

We are executing a complex program of

environmental protection in order to check the

direct and indirect environmental effects of the

nuclear power plant.

On the basis of the schedule discussed with the

authorities the so-called company site

characterization program, consisting of 13 sub-

programs, the goal of which is to carry out the

preparations for the environmental protection

licensing of the extension of the operating time

has been in progress since the year 2001. The

program was going on in 2004 as well, using the

basic concept, the technological content of

which is checked every year. The tasks were

carried out according to the schedule during the

year. The program is going to be finished on 31

December 2005.

Rebuilding subsurface oil tanks using cutting-

edge technologies.

According to the 33/2000. (III.17.) decree, in its

decision the Environmental Authority obligated

the PNPP to inspect the oil tanks partially. The

PNPP performed the obligation and in its report

it advanced the plans for the reconstruction of

the tanks on the basis of the measures given.

In order to rebuild the underground oil

containers, a development plan was accepted on

7 September 2004; according to the accepted

schedule the rebuilding of the containers

(making them double-walled) is going to be

carried out between 2005 and 2007. To do the

task, the selection of the entrepreneur has

started – within the frames of a public

procurement process.


Complete reconstruction of catchment basin

system of extra water.

The development proposal considering the

reconstruction of the supplementary water

preparing wastewater system was accepted in

37

the year 2004. On the basis of the prepared plans

the reconstruction was supported by the

environmental authority. The deadline for

finishing the reconstruction is 2006.

Getting the environmental influence test and

operation license for over the planned lifetime of

the power plant

The Paks Nuclear Power Plant handed in the

preliminary environmental study (PES) of the

extension of the operating time to the

environmental authority in April 2004, and the

supplement of the missing things prescribed by

the authorities in September 2004.

The environmental authority informed the

neighboring local governments about the request

of the Paks Nuclear Power Plant on 31

December 2004.

Windup of the oil-contaminated wastewater tank The development proposal connected to the

liquidation of the pool for oil-containing sewage

was accepted in September 2004. The plans

connected to the liquidation were accepted by

the authorities.

According to the accepted schedule the pool for

oil-containing sewage is going to be replaced by

an oil-separating construction works in 2005,

and it will have been liquidated by December

2006.


Recultivation of the building-rubble dump The Environmental Authority obligated the

PNPP to close down the building-rubble dump.

One of the tasks was to carry out the placing

2300 m3 of concrete units and rubble in an

ordinate way and mulching in accordance with

the local circumstances (recultivation).

On the basis of the plans accepted by the

environmental authority the restoration of the

tip for building rubble was finished. The

required closing documentation was prepared

and handed in before the deadline, and it was

accepted by the environmental authority in its

resolution.

In the resolution the five-year aftercare of the

territory and the regular checking of the

groundwater were prescribed.

Extension of the selective collection of office

and wrapping paper produced by the PNPP

The collection of paper waste was recorded in

the internal regulation. From the beginning of

this year the waste store receives packaging and

“crushed” paper waste without documentation,

in case the organizational units transport them

there.

38

The type of the collecting container used for

selective collection was chosen; the places

where the containers should be put were

determined, and after their procurement the

containers were transported to the given places.

Our goal is to enhance the amount of the re-

collected office- and wrapping paper waste.


The execution of the program concerning the

examination of the conditions of the systems

belonging to the class ABOS 4, steel and other

pipelines that can be found in the territory of the

Paks Nuclear Power Plant and that endanger the

environment in case of being damaged and do

not belong to the group of cyclic revision.

The condition-examining program had been

prepared by 31 December 2003, and most of its

tasks were carried out in 2004.

It was not possible to carry out the examination

of the station for drawing off oil and the

emergency oil-removing system in 2004 because

of operational problems; these parts of the

program are going to be re-scheduled to the

main reparations of the year 2005.

Paks Nuclear Power Plant carries out an open

and efficient policy of giving information, in

order to enhance the social acceptance of

nuclear energetics and the awareness of

environmental protection.

The events determined in the program connected

to this goal were carried out (Open Day, Angling

Family Day); the Paks Nuclear Power Plant took

part in the exhibition of ÖKOTECH, and

according to the signed contracts the Paks

Nuclear Power Plant appeared in the regional

media.

8 Transport of Hazardous Products and the Safety Advisory System

The safe transport of hazardous products including tasks such as sending, delivery, storage,

packaging and forwarding has a very important role in the life of the PNPP and its neighbourhoods.

The consolidation and operation of the hazardous product transport advisory system of the PNPP

started with the appointment of advisors in December 2002.

The hazardous product safety transport advisors’ tasks are determined by the measures.

Their main tasks are: - consultative assistance

- controlling

- giving reports.

39

The power plant has carried out many tasks in order to fulfill the regulations connected to the

hazardous products since the system was introduced in 2003. The most important events of the year

2004 are going to be discussed below:

In the year 2003 the system of regulations connected to the transport of hazardous products was

established in the power station, the revision of which is going to be carried out in 2004 – on the

basis of the experiences of its one-year operation.

The exaction of fulfilling the regulations connected to the transport of hazardous products from

the haulers has been started.

In 2004 the complex ADR training of the new employees and property guards of the Atomix

Security Service was going on. Some of our staff members also did the course “Administrator of

hazardous products”. The training and the examinations were recorded in the educational

database.

The ADR equipment of the motor vehicles used for transporting hazardous products were

purchased in 2004. The drivers involved in the transport of hazardous products gained ADR

educational certificates, as well as certificates of the aptitude test “PÁV II”.

The hazardous products were recorded in the information system.

Paks Nuclear Power Plant has got a license of transport concerning Tolna County, the whole

country, as well as international license of transport in connection with radioactive and nuclear

materials belonging to the seven classes of the ADR, with the exception of the nuclear fuel

elements of the seven classes. In order to carry out the transport the nuclear power station

operates two motor vehicles that have got official certificates. The equipment required by the

Traffic Regulations and the ADR are available in the cases of both motor vehicles.

We have met our engagements towards the Hungarian Central Statistical Office, as far as the

supplying of statistical data connected to the transport of hazardous products is concerned, at the

end of each quarter.

The transport of the spent fuel elements between the Paks Nuclear Power Plant and the

PURAM3 is considered on-site transport so the ADR/RID regulations do not pertain to it.

The spent fuel elements were not transported outside the company seat in 2004; in connection

with the nuclear fuel most of the advisory tasks connected to the transport of nuclear fuel

elements of the seven classes as hazardous products were determined by keeping tabs on the

transport of the new fuel elements.

Paks Nuclear Power Plant becomes responsible for the shipment of new fuel elements regarded

as hazardous products after the reception of Csap.

The regulations connected to the transport of hazardous products are going to be extended with

a chapter entitled “Prescriptions of Public Security” from 1 January 2005. The reason for the

extension is the demand for taking the recent terrorist threats into consideration on the level of

the legislative regulations, and the position of the UN and the EU that the protection against

3

PURAM = Public Agency for Radioactive Waste Management

40

terrorism plays the primary, most important role in the field of transport/traffic as well. After the

ADR of 2005 comes into force the Paks Nuclear Power Plant has to look at the tasks connected

to this.

41

9 Abbreviations and concepts

TPH = Total Paraffin Hydrocarbons, oil content

PAH = Polycyclic Aromatic Hydrocarbons

SZOE = szerves oldószer extrakt (olaj-zsír) = organic solvent extract (oil, fat)

KOICr = dichromate oxygen consumption

NH3 - NH4+ = total amount of ammonia and ammonium ions per 10-3

kg/m3 of nitrogen

PCB = Polychlorine Biphenils

UNSCEAR = United Nations Scientific Committee on Effects of Atomic Radiation

nvironmental protection eport 2004 › en › documents › enviromental_protection_rep… · 2...

Documents