National Report of the Slovak Republic - Radiation and Nuclear Safety , September 1998

2.5.2 ISFS Safety Reviews


Internal safety reviews (within Slovakia) were performed during the construction and commissioning of the facility, by assessing safety-related documentation on the part of the regulatory authorities and organizations from the SR (safety reports, quality assurance programs, limits and conditions). Reports on ISFS operation including UJD-performed operation reviews are prepared on an annual basis. No international safety review of the facility has so far been conducted.

ÚJD inspectors perform regular inspections during the ISFS operation directed towards the assessment of the condition of selected nuclear equipment, ISFS operation safety; and also, towards the storage and recording of nuclear materials together with IAEA inspectors. Any deficiencies identified by the inspections are recorded in protocols and considered mandatory tasks to be fulfilled by the operators without any undue delay within set periods of time.

After 9 years of ISFS operation, a safety assessment report was prepared serving the purpose of decision-making with respect to extension of storage capacity.

A brief assessment of the facility condition is as follows: Shipping containers and cars have shown a high operation reliability. The frequent breaks of the lifting equipment (cranes) could be eliminated by general overhaul and reconstruction.

The tasks concerning surface protection of containers were resolved by introducing a new type of surface protection.

So far, production of liquid and solid RAW has been substantially below the design levels which is mainly connected with the low activity of the storage pond waters.

The dose intensity at the storage and container hall of 120 m Sv/hr during times when containers are not handled, is due to the stored fuel assemblies shielded by water layers in the storage ponds. No marked increase in dose equivalent intensity is produced upon handling of spent fuel at the storage and container hall as all handlings are performed under shielding water layers. The work at the ISFS premises is organized so as to prevent unnecessary irradiation of the staff (ALARA principle).

None of the staff members working in ISFS premises has received, throughout the ISFS operation, IDE exceeding the maximal acceptable value of 20 mSv/year (act No.290/96 Coll.ll.). The highest IDE values for regular ISFS operating staff members reach 5 mSv/year. There have been no radiation accidents.

Environmental monitoring of the ISFS surroundings is a part of the radiation situation monitoring of the vicinity of nuclear power plants V-1 and V-2 at the Bohunice site. With respect to the assessment of environmental impact, ISFS is considered a separate premise with respect to atmospheric emissions only. The balancing of radionuclides emitted into the air is done using monitoring of airborne particles, strontium and tritium in the ventilation stack.

Emissions from ventilation stack represent a negligible part of the limits set for the entire site of Jaslovské Bohunice. It could be stated that the ISFS operations have no significant impact on the radiation situation of the NPP surronndings.


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