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ADDITIONAL INFORMATION ON ARTICLE 15 RADIATION PROTECTION
History of NPP Krsko operation
INDIVIDUAL DOSES
Average annual dose: 1.2 mSv (1997)
Maximum dose: 11.66 mSv (1997)
Notes:
1. In the year 1983 extensive modification was performed on D4 Steam generators
2. In the year 1991 there was no refueling outage due to longer fuel cycle
3. In the years 1992 to 1998 ? extensive SG inspection and
COLECTIVE DOSES
Collective dose: 0.99 manSv (1997)
Collective dose per TWh: 0.21 manSv (1977)
RELEASE OF RADIONUCLIDES
Gaseous effluents (1997): noble gases 2.5 TBq or 2.3% annual limit value, iodine-131 1.45 GBq or 7.8 % of annual
limit dose, aerosols 3.6 MBq or less tan 0.1%, H-3: 1.0 TBq (no limitations), C-14: 0.14 TBq (no limitations)
Liquid effluents (1997): Activity of fission and activation products (without H-3) 1.2 GBq or 0.6% annual limit value, tritium releases 7.8 TBq or 39%, Co-60 0.15 GBq, Cs-137 0.02 GBq, J-131 2 MBq.
(NOTE: radiological impact of H-3 releases at limit value is in the order of magnitude of 1 mSv/y)
Trends: gaseous releases were stable or slightly decreasing, except noble gases releases which showed a rapid decrease in the last two years
Note: In the years 1993 to 1995 fuel leakage was causing increased iodine concentration in the effluents. Ater 1996 corrective measures (fuel examination by sipping and ultasound, foreign material exclusion programme, introduction of Debry Filtered Bottom Nozzles and Zirlo cladding) eliminated the problem.
RADIOLOGICAL IMPACT TO THE PUBLIC
News assessments of the effective dose to a critical group (members of the public around the nuclear power plant) show the dose below 50 mSv for each calendar year. Very conservative assessments are reported yearly that the commitment to the dose burden of any member of the critical group is below 10 to 20 mSv. The conservative calculations based on total liquid and gaseous activity released give result of about 8 mSv per year for a hipotetical person living at the plant fence.
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