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in the world. These standards concentrate the
best international experience of development and
operation of NPP I&C. It is especially important
for the countries that have less experience of using
NPP and, in particular, NPP I&C. Our chapter is
devoted to the description these standard bases,
especially classification of I&C systems and their
safety components.
Thirdly, there are particular aims of standards
for nuclear I&C - to increase the confidence of
the public with more stringent requirements than
those typically applied to conventional industry
standards, to verify and demonstrate the quality
and reliability of the safety systems before NPP
operation, to create international consensus among
participating countries, operators, and vendors.
Note that besides international standards each
country has a standard base concerning nuclear
power engineering, including NPP I&C, e.g.
American National Standards Institute (ANSI) in
USA, Deutsches Institut fur Normung (DIN) in
Germany, British Standards Institute (BSI) in UK).
In addition, USA standards of professional orga-
nizations are widespread - American Society of
Mechanical Engineering (ASME) and, especially
concerning NPP I&C, - Institute of Electrical and
Electronic Engineers (IEEE).
However, the main attention in this chapter is
further given not to national, but to international
standards, since harmonization of national stan-
dards with ones is currently a vital task.
reactor instrumentation” was issued in 1967. IEC
understood importance of computer technique
for NPP automatics: publication “Application of
digital computer to nuclear reactor instrumenta-
tion and control “dates back to 1979.Computers
only began to make first steps for their using at
NPP at that time.
During more than 50 years IEC developed a
lot of standards applicable to different types of
I&C, to different aspects of NPP I&C design and
operation. Special attention is paid to application
of computer systems and the latest achievement
in information technology.
The International Atomic Energy Agency
(IAEA) elaborated Codes on safety of NPPs,
which related to all NPP systems, including I&C
(e.g., “50-C-D. Code on Safety on Nuclear Power
Plants. Design” -1979). Special safety guides
related exclusively to NPP I&C (“50-SG-D3. Pro-
tection Systems and Related Features in Nuclear
Power Plants”- 1980). IEC and IAEA have close
connections in the development of standard base
for NPP I&C.
Many countries where NPPs are operated
developed their national standard base related to
I&C. One of the first American National Standards
(based on IEEE Standard 323-1974) was ANSI/
IEEE Std.323-1983 “IEEE Standard for Qualifying
Class1 Equipment for Nuclear Power Generating
Stations” which did not lose its importance for long
time. The first USSR Regulation PBYa- 04-74
“Rules of NPP Nuclear Safety” which contained
requirements on reactor control and protection
systems, was issued in 1974.
Ukraine after gaining independence (1991)
used to 1999 USSR regulations and standards
related to NPP I&C. Ukrainian regulation “NP
306.5.02/3.035-2000. Requirements for nuclear
and radiation safety information and control sys-
tems important to safety of nuclear power plants”
was issued in 2000.
BACKGROUND
Elaboration of international standards related to
NPP I&C began immediately after commissioning
of the first NPP. The International Electrotechni-
cal Commission (IEC) created a separate techni-
cal committee devoted to NPP I&C, with name
“Nuclear Instrumentation” in 1960. One of the first
IEC publications-”General principles of nuclear
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