Overall Instrumentation and Control Systems - Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - page 296

• About commands of protective actions ini-
tiated by the safety systems and actions of
the personnel directed to safety assurance.
• About state of structures, systems and com-
ponents important for safety, about values
of technological parameters and radiation
conditions at the beginning or during the
mitigation of incidents, passing of the ac-
cident and post-accident period.

automatic protection of systems, equipment and
unit as whole, monitoring of non-exceeding of
margins of operation and safe operation limits.
Reactor control and protection system (RC&PS)
is singled out. The overall I&C system includes
a set of closely interconnected individual I&C
systems, which fulfill control of processes in
nuclear reactor. The distribution of functions
between I&C systems, included in RC&PS, and
interconnections these systems and connections
with the other parts of overall I&C system accepted
on Ukrainian NPPs is described.
Information which was described in this chapter
is recommended for use in safety analysis of NPPs
and in elaboration of conceptual technical deci-
sions in implementation of overall I&C systems
for new NPP units with WWER-1000 reactors.

Ukrainian organizations fulfilled the first steps
in elaboration of post-accident monitoring system.
The operator (National Nuclear Energy Generating
Company) prepared terms of reference and started
development of pilot designs of the post-accident
monitoring system to be implemented at each NPP.

CONCLUSION

REFERENCES

After 2001 Ukraine passed from a country that
imported I&C systems for its own NPPs and be-
came a country that not only satisfies own needs,
but exports these systems. Some features peculiar
to the strategy for NPP I&C modernization in
Ukraine may be of interest to specialists from
other countries:

Adamov, E. O. et al. (2005). Nuclear engineering:
Encyclopedia . Moscow: Mashinostroenie.

Bachmatch, E., Marshevsky, M., Rozen, Y., et al.
(2008). Assurance and safety assessment of fire-
alarm systems and automatic fire extinguishing in
the accommodations NPP. Nuclear and Radiation
Safety, 1 .

• Use of an aggregate of hardware, software
and service apparatus called «hardware-
software complex» (HSC) as the central
part of systems.
• HSC are delivered to NPPs in full assembly,
after checkout and testing, with high level
of factory availability, what can decrease
time to replacement for modernization.
• Use of ield programmable gate array
(FPGA) for performance of safety func-
tions, including reactor protection systems.

Bessalov, G. et al. (2004). Middle power WWER
reactors . Moscow: Akademkniga.

Brenman, O., Denning, R., et al. (2006). Licens-
ing review of foreign I&C systems for Ukrai-
nian nuclear power plants. In Proceedings of
International Topical Meeting on Nuclear Plant
Instrumentation, Controls, and Human-Machine
Interface Technologies-5 . Albuquerque, NM:
Academic Press.

GND 306.7.02/2.041. (2000) Methodic of as-
sessment of compliance of I & C systems to
safety requirements . Kiev, Ukraine: State Nuclear
Regulatory Committee.

Overall I&C system is considered as a set of
interacting individual I&C systems, which imple-
ment automatic control of NPP unit technological
processes and equipment in all operating modes,