Emergency and Preventive Reactor Protection Systems - Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - page 319

KEY TERMS AND DEFINTIONS

NP. (2000). NP 306.5.02/3.035. Nuclear and
radiation safety requirements to instrumentation
and control systems important to safety to nuclear
power plants . Kiev, Ukraine: State Committee for
Nuclear Regulation.

Channel: An arrangement of interconnected
components within a system that initiates a single
output. A channel loses its identity where single
output signals are combined with signals from
other channels, e.g., from a monitoring channel,
or a safety actuation channel.
Diversity: A property related to a group of
two or larger number of I&C systems and SHC,
which simultaneously and independently from
each other perform functions identical for achieved
safety purposes, and differ from each other by an
operating principle, structure, applied component
parts, software and / or other attributes or achieve
a target goal in different ways.
Emergency Protection: I&C function, in-
tended for a rapid transfer and a long support of
a reactor core in a subcritical state, that is char-
acterized of a value of an effective multiplication
factor, less than one, and a lack of a local criticality.
Preventive Protection: I&C function, intend-
ed for limitation or decrease of a reactor power to
a safety level in case of normal operation violation.
Redundancy: Application of additional
means and / or possibilities, redundant in regard
to those, which are minimum required for func-
tion performance.
Safety Function: A specific purpose that have
to be fulfilled for safety assurance.
Standard: A set of mandatory requirements
with which compliance is not a legal requirement,
but with which failure to comply without valid
reason would be negligent.

NP. (2008a). NP 306.2.141. General provisions on
the safety of nuclear power plants . Kiev, Ukraine:
State Committee for Nuclear Regulation.

NP. (2008b). NP 306.2.145. Nuclear safety regu-
lations the reactors nuclear power plants with
pressurized water reactors . Kiev, Ukraine: State
Committee for Nuclear Regulation.

NUREG. (2002). NUREG-0800. US nuclear regu-
latory commission: Standard review plan: Section
7.0: Instrumentation and control - Overview of
review process .

ADDITIONAL READING

ANSI/IEEE (1987). ANSI/IEEE 352. Guide for
general principles of reliability analysis of nuclear
power generating station protection systems .

Bakhmach, E., Siora, A., Bezsalyi, V., & Yas-
trebenetsky, M. (2008). Digital systems for re-
actor control: Design, Experience of operation.
Proceedings of the 16th International Conference
on Nuclear Engineering ICONE16 , Orlando,
Florida, USA.