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INES
international nuclear event scale

The International Nuclear Event Scale (INES) was introduced by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) in 1990 as a tool to communicate the safety significance of reported events at nuclear installations
or involving nuclear materials to the international community.
Use of the INES by IAEA and OECD Member States (a number of whom have their own nuclear event classification scales) serves to promote a common understanding of the significance of reported
events among governments, the nuclear community, the media and the public.
La The INES consists of a 7-level event classification system.
Events of greater safety significance (levels 4-7) are termed "accidents,"
events of lesser safety significance (levels 1-3) are termed "incidents,"
and events of no safety significance (level 0 or below scale) are termed "out-of-scale deviations."


INES scale

ACCIDENT
7
MAJOR ACCIDENT
ACCIDENT
6
SERIOUS ACCIDENT
ACCIDENT
5
ACCIDENT WITH OFF-SITE RISK
ACCIDENT
4
ACCIDENT WITHOUT SIGNIFICANT OFF-SITE RISK
     
INCIDENT
3
SERIOUS INCIDENT
INCIDENT
2
INCIDENT
INCIDENT
1
ANOMALY
DEVIATION
0
NO SAFETY SIGNIFICANCE


The becquerel (Bq) 1 Bq = 2.7x10E-11 Ci.
The sievert (Sv) 1 Sv = 1 J/kg.


LEVEL
DESCRIPTOR
NATURE OF THE EVENTS
EXAMPLES
ACCIDENTS
7
MAJOR
ACCIDENT
• External release of a large fraction of the radioactive material in a large facility (e.g. the
core of a power reactor). This would typically involve a mixture of short and long-lived
radioactive fission products (in quantities radiologically equivalent to more than tens of
thousands of terabecquerels of iodine-131). Such a release would result in the possibility of
acute health effects; delayed health effects over a wide area, possibly involving more than
one country; long-term environmental consequences.
Chernobyl NPP, USSR
(now in Ukraine), 1986
6
SERIOUS
ACCIDENT
• External release of radioactive material (in quantities radiologically equivalent to the order
of thousands to tens of thousands of terabecquerels of iodine-131). Such a release would
be likely to result in full implementation of countermeasures covered by local emergency
plans to limit serious health effects.
Kyshtym Reprocessing
Plant, USSR
(now in Russia), 1957
5
ACCIDENT WITH
OFF-SITE RISK
• External release of radioactive material (in quantities radiologically equivalent to the order
of hundreds to thousands of terabecquerels of iodine-131). Such a release would be likely
to result in partial implementation of countermeasures covered by emergency plans to
lessen the likelihood of health effects.
• Severe damage to the installation. This may involve severe damage to a large fraction of
the core of a power reactor, a major criticality accident or a major fire or explosion releasing
large quantities of radioactivity within the installation.
Windscale Pile, UK, 1957

Three Mile Island, NPP,
USA, 1979
4
ACCIDENT
WITHOUT
SIGNIFICANT
OFF-SITE RISK
• External release of radioactivity resulting in a dose to the critical group of the order of a
few millisieverts.* With such a release the need for off-site protective actions would be
generally unlikely except possibly for local food control.
• Significant damage to the installation. Such an accident might include damage leading to
major on-site recovery problems such as partial core melt in a power reactor and comparable
events at non-reactor installations.
• Irradiation of one or more workers resulting in an overexposure where a high probability of
early death occurs.
Windscale Reprocessing
Plant, UK, 1973

Saint-Laurent NPP, France, 1980

Buenos Aires Critical
Assembly, Argentina, 1983
INCIDENTS
3
SERIOUS
INCIDENT
• External release of radioactivity resulting in a dose to the critical group of the order of
tenths of millisievert.* With such a release, off-site protective measures may not be needed.
• On-site events resulting in doses to workers sufficient to cause acute health effects
and/or an event resulting in a severe spread of contamination for example a few thousand
terabecquerels of activity released in a secondary containment where the material can be
returned to a satisfactory storage area.
• Incidents in which a further failure of safety systems could lead to accident conditions, or
a situation in which safety systems would be unable to prevent an accident if certain initiators
were to occur.
Vandellos NPP, Spain,
1989
2
INCIDENT
• Incidents with significant failure in safety provisions but with sufficient defence
remaining to cope with additional failures. These include events where the actual
would be rated at level 1 but which reveal significant additional organisational inadequacies
or safety culture deficiencies.
• An event resulting in a dose to a worker exceeding a statutory annual dose limit
an event which leads to the presence of significant quantities of radioactivity in the installation
in areas not expected by design and which require corrective action.
1
ANOMALY
• Anomaly beyond the authorised regime but with significant defence in depth remaining.
This may be due to equipment failure, human error or procedural inadequacies and may
occur in any area covered by the scale, e.g. plant operation, transport of radioactive material,
fuel handling, waste storage. Examples include: breaches of technical specifications or
transport regulations, incidents without direct safety consequences that reveal inadequacies
in the organisational system or safety culture, minor defects in pipework beyond the expectations
of the surveillance programme.
DEVIATIONS
0
BELOW SCALE
• Deviations where operational limits and conditions are not exceeded and which are
properly managed in accordance with adequate procedures. Examples include: a single
random failure in a redundant system discovered during periodic inspections or tests, a
planned reactor trip proceeding normally, spurious initiation of protection systems without
significant consequences, leakages within the operational limits, minor spreads of contamination
within controlled areas without wider implications for safety culture.
NO
SAFETY SIGNIFICANCE

Examples of Rated Nuclear Events

The 1986 accident at the Chernobyl nuclear power plant in the Soviet Union (now in Ukraine) had widespread environmental and human health effects. It is thus classified as Level 7.

The 1957 accident at the Kyshtym reprocessing plant in the Soviet Union (now in Russia) led to a large
off site release. Emergency measures including evacuation of the population were taken to limit serious health
effects. Based on the off-site impact of this event it is classified as Level 6.

The 1957 accident at the air-cooled graphite reactor pile at Windscale (now Sellafield) facility in the United Kingdom involved an external release of radioactive fission products. Based on the off-site impact, it is
classified as Level 5.

The 1979 accident at Three Mile Island in the United States resulted in a severely damaged reactor core. The off-site release of radioactivity was very limited. The event is classified as Level 5, based on the on-site impact.

The 1973 accident at the Windscale (now Sellafield) reprocessing plant in the United Kingdom involved a release of radioactive material into a plant operating area as a result of an exothermic reaction in a process
vessel. It is classified as Level 4, based on the on-site impact.

The 1980 accident at the Saint-Laurent nuclear power plant in France resulted in partial damage to the reactor core, but there was no external release of radioactivity. It is classified as Level 4, based on the on-site impact.

The 1983 accident at the RA-2 critical assembly in Buenos Aires, Argentina, an accidental power excursion due to non-observance of safety rules during a core modification sequence, resulted in the death of the operator, who was probably 3 or 4 metres away. Assessments of the doses absorbed indicate 21 Gy for the gamma dose together with 22 Gy for the neutron dose. The event is classified as Level 4, based on the on-site impact.

The 1989 incident at the Vandellos nuclear power plant in Spain did not result in an external release of radioactivity, nor was there damage to the reactor core or contamination on site. However, the damage to the plant’s safety systems due to fire degraded the defence in depth significantly. The event is classified
as Level 3, based on the defence in depth criterion.


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