Environmental Engineering Reference
In-Depth Information
safety standards “Design of Instrumentation and
Control Systems for Nuclear Power Plants,” which
will supersedes IAEA standards NS-G-1.1 and
NS-G-1.3.
Besides international standards, all countries
used national ones. The harmonization of national
and international standards is an urgent task.
Note that some of the standards in force in
the United States(developed by the American
Institute of Electrical and Electronics Engineers
- IEEE, and the American Society of Mechani-
cal Engineers -- ASME and others) de facto have
become international standards and have been
widely adopted not only in the United States but
in other countries, successfully supplementing
the IEC standards. This, for example, pertains to
standards on qualification of equipment, to post-
accident monitoring, etc. The main distinction,
however, is the fact that the IEEE standards focus
on safety systems, and the IEC standards focus on
systems that are important for safety.
Many documents of the U.S. Nuclear Regu-
latory Commission (U.S.NRC) have received
international use. An example of a U.S.NRC
document which has been widely disseminated
is NUREG-0800, which contains standard plans
for safety analysis of different structures, compo-
nents, equipment and systems. Section 7.0 of this
document is devoted to I&C systems.
Cox, M., & Shumov, S. (2011). About activities of
IEC/TC45 nuclear instrumentation. Nuclear Mea-
surement and Information Technologies, 3 (35).
Hashemian, H. (2006). Maintenance of process
instrumentation in nuclear power plants . Berlin:
Springer.
Hashemian, H. M. (2005). Sensor performance
and reliability . Research Triangle Park, NC: The
Instrumentation, Systems and Automation Society.
Hashemian, H. M. et  al. (1998). Advanced in-
strumentation and maintenance technologies for
nuclear power plants (NUREG/CR-5501) . Wash-
ington, DC: U.S. Nuclear Regulatory Commission.
Hughes, P. J., & Johnson, G. L. (2000). Instru-
mentation and control systems important to
safety: A new IAEA safety guide. International
Topical Meeting on Nuclear Plant Instrumenta-
tion, Controls, and Human-Machine Interface
Technologies (NPIC&HMIT 2000). Washington,
DC: NPIC & HMIT.
IAEA. (1980). 50-SG-D3. Protection systems and
related features in nuclear power plants . Vienna,
Austria: IAEA.
IAEA. (1984). 50-SG-D8. Safety related instru-
mentation and control systems for nuclear power
plants . Vienna, Austria: IAEA.
IAEA. (1988). 50-C-D. Code on the safety on
nuclear power plants: Design . Vienna, Austria:
IAEA.
REFERENCES
Biscoglio, I., & Fusani, M. (2010). Analyzing
quality aspects in safety-related standards. In
Proceedings of Seventh American Nuclear Society
International Topical Meeting on Nuclear Plant
Instrumentation, Control and Human-Machine
Interface Technologies NPIC&HMIT 2010 . Las
Vegas, NV: American Nuclear Society.
IAEA. (1998). TECDOC-1016. Modernization
of instrumentation and control in nuclear power
plants . Vienna, Austria: IAEA.
IAEA. (1999a). INSAG-12. Basic safety principles
for nuclear power plants . Vienna, Austria: IAEA.
IAEA. (1999b). Modern instrumentation and
control for nuclear power plants: A guidebook .
Vienna, Austria: IAEA.
Bouard, J.-P. (2002). International standardization
in nuclear I&C engineering. In Proceedings of
CNRA/CSNI Workshop on Licensing and Operat-
ing Experience of Computer-Based I&C Systems .
AEN/NEA.
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