Software of Safety Important I&C Systems - Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - page 177

Lawrence, S., Hatton, L., & Howell, C. (2002).
Solid Software . Prentice Hall.

Pullum, L. (2001). Software fault tolerance tech-
niques and implementation . ARTECH HOUSE.

Lyu, M. R. (1996). Handbook of software reli-
ability engineering . McGraw-Hill Company.

Sterpone, L. (2008). Electronics System Design
Techniques for Safety Critical Applications.
Lecture notes in electrical engineering. Springer
Science + Business Media B.V., 2008.

NS-G-1. 1 (2000). Software for computer based
systems important to safety in nuclear power
plants. Vienna, Austria: IAEA.

Pressman, R. S. (1997). Software Engineering: A
Practioner's Approach . McGraw-Hill Company.

KEY TERMS AND DEFINITIONS

Common-Cause Failure (CCF): Failure of
two or more structures, systems or components
due to a single specific event or cause.
Common-Mode Failure (CMF): Failure of
two or more structures, systems and components
in the same manner or mode due to a single event
or cause.
Diversity: Presence of two or more redundant
systems or components to perform an identified
function, where the different systems or compo-
nents have different attributes so as to reduce the
possibility of common cause failure, including
common mode failure.
Fault Tolerance: Is the ability of software to
retain a certain functioning level during the onset
of software malfunctions.
Fault Tree Analysis (FTA): Deductive tech-
nique that starts by hypothesizing and defining
failure events and systematically deduces the
events or combinations of events that caused the
failure events to occur.
Failure Mode, Effects and Criticality Analy-
sis (FMECA): Is a reliability evaluation/design
technique which examines the potential failure
modes within a system and its equipment, in order
to determine the effects on equipment and system
performance.
Off-the-Shelf (OTS) Software Component:
Pre-developed software components, usually de-
veloped by other organization and designed for
specific solutions.

Vilkomir, S., & Kharchenko, V. (2000). An
“asymmetric” approach to the assessment of
safety-critical software during certification and
licensing. Paper presented at ESCOM-SCOPE
2000 Conference, Munich, Germany.

Vilkomir, S. A., & Kharchenko, V. S. (1999).
Methodology of the review of software for safety
important systems. In G. I. Schueller, P. Kafka
(Eds). Safety and Reliability. Proceedings of
ESREL'99 - The Tenth European Conference on
Safety and Reliability (pp. 593-596). Munich-
Garching, Germany.

ADDITIONAL READING

IAEA. (1999, b). Verification and validation of
software related to nuclear power plant instru-
mentation and control. Technical reports series
Nº384. IAEA, Vienna.

IAEA - TECDOC-1328. (2002). Solutions for
cost effective assessment of software based instru-
mentation and control systems in nuclear power
plants . Vienna: IAEA.

IEC 62340 (2008). Instrumentation and Control
Systems Important to Safety - Requirements to
Cope with Common Cause Failure.

NUREG (2008) Diversity Strategies for Nuclear
Power Plant Instrumentation and Control Systems.
NUREG/CR-7007. Office of Nuclear Regulatory
Research, NRC, 2008.