Overall Instrumentation and Control Systems - Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - page 281

Figure 4. Main control room at Rovno NPP

indicators, numerical indicators, visual and audio
alarms, mnemonic diagrams, manual control ele-
ments (see Figure 3).
NPP control room obtains from I&C systems of
all NPP power units information on their state and
operation, required for a shift engineer to control
and coordinate operation of common systems.
The central part of overall I&C systems is
formed by relatively isolated individual I&C sys-
tems, interacting during execution of informational
and control functions.
Unit computer information system (CIS )
performs: • Monitors actions of normal operation con-

trol systems and safety systems.

• If required, inputs guidelines for control

I&C systems dedicated to elimination of
detected deviations.

• Collection and generation of signals from
sensors of heat engineering, electric and
other parameters, from other informational
and control power unit systems and also
from Radiation safety monitoring (RSM)
system.
• Informational support of operational per-
sonnel during making decisions for control
of technological processes and equipment
of the power unit (control of deviations and
technological parameters from speciied
values, deviation alarm, calculation and
analysis of technical and economic indica-
tors, etc.)
• Archiving (memorization and storage) of
parameter values, events, states, actuation
of protection and interlocking, actions of
operational personnel.
• Display on video monitors and registra-
tion of current information and archival
data during by personnel guidelines dur-
ing normal operation, in emergencies and
accidents (for control of accidents and
further analysis and assessment of occur-
rence causes, ways of behavior and acci-
dent efects).

• Issues commands of remote control and

monitors their performance by technologi-
cal equipment.

Emergency control room (ECR) is a specifically
equipped room, territorially separated and com-
pletely independent from MCR, having nuclear
electric communications and own facilities of
habitability and operability (continuous presence
of personnel is not provided). Systems and equip-
ment of ECR provide personnel with a possibility
to control significant process parameters, assess
power unit state and issue commands to tech-
nological systems and equipment, required for
transfer of the reactor to sub-critical state, keep it
in this state for a sufficiently long time and control
residual heat removal in situations when the pos-
sibility to perform these functions from MCR is
lost, including failures of control I&C systems,
initiating safety shutdown and cooling of reactor.
Information on the neutron flux density required
for control is displayed in video monitors placed
in ECR, included into the structure of software-
hardware complex of neutron flux monitoring sys-
tem (third set). Peripheral equipment of adjacent
I&C systems is also placed at ECR: quasi-analog

Safety parameters display system (SPDS)
provides informational support to the operator in
quickly determining deviations in unit operation.