CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 1
Analysis of Worldwide Events Related to The Construction
and Commissioning of Nuclear Power Plants:
Lessons Learned and Recommendations
Marc Noël
EC-DG Joint Research Center
http://clearinghouse-oef.jrc.ec.europa.eu/
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 2
• Background
• Methodology
• Trends • Trends
• Lessons learned
• Recommendations
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 3
European Clearinghouse - NPP OEF
OEF Clearinghouse
Centralized Office (JRC)
Coordination and Communication
Review of draft IRS reports
Event Data management
Dissemination and Training
Services at request
EU Safety Authorities
International
Community
IAEA
OECD-NEA
MembersFinland Hungary Lithuania
The Netherlands Romania Slovenia
Switzerland
Observers Services at request
EU Technical
Support Organizations
OECD-NEA
Others (bilateral)
ObserversCzech Republic
FranceGermany
Spain
Main deliverables
for EU Safety Authorities:
- Improved draft IRS
- Topical reports
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 4
On-going programme of Topical Studies
Topic
Reactivity management - 1999 Shika NPP criticaliy event
2006 Forsmark NPP event
Maintenance events
Fuel damaging events
Construction & commissioning events
External events (natural and man-induced origin)
2009
2010
2008
Event related to supply of NPP components
Events related to plant modifications
Events related to ageing of NPPs
Loss of safety-classified electrical equipment due to generator
high voltage peak
Events related to decommissioning of NPPs
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 5
Background
The challenge:
• Roughly more than 50 NPP construction projects are currently launched or under consideration worldwide.
• Much of the earlier experience and resources have progressively been lost from the nuclear industry.
• No recent comprehensive study published yet on lessons learned from events related to pre-operational phases.
• No dedicated repository of worldwide construction experience yet.
⇒ EU Clearinghouse members launched an up-to-date in-depth analysis of both past and current construction experience
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 6
Methodology
• 3 main sources of information:– IRS database– US NRC Licensee Event Reports (LERs)– WGRNR Inspection findings
• Selection criterion:– All events initiated during NPP pre-operational stages (construction,
US
LERWGRNR
IRSDB
Data sources
US
LERWGRNR
IRSDB
Data sources
– All events initiated during NPP pre-operational stages (construction, commissioning and component supply).
– Events occurring both before start of commercial operation or long after.
• Screening from the beginning of these DB until end 2009 : 1090 IRS reports, 857 LERs and 100 WGRNR findings have been screened.
⇒ After final screening, total of 582 events applicable
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 7
Methodology
• Distribution of events in categories (construction, manufacturing, commissioning)
and sub-categories (civil works, electrical components, welding, valves…)
• Final aim = to raise concrete lessons learnt and recommendations
Construction Manufacturing
Commissioning
Cab
les
Break
ers
Electrical Civil Works ….
….
….
….
….
….
….
….
Lesson
s learnt
Lesso
ns learn
t
Lesson
s learnt
…
Lesso
ns le
arnt
Lesso
ns learn
t
….
Electrical Civil Works Electrical Civil Works ….
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 8
Trends
• I&C, electrical components, and welds are the items leading to the highest number of reported events
Civil Work
8%
Diesel
5%Other
2%
Weld
14% commissioning
13%
Electrical
19%
Fire protection
5%
I&C
17%Ventilation
1%
Pipes
9%
Pumps
5%
Valves
10%
2%
SG
5%
construction
48%
manufacturing
39%
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 9
Trends
• Average detection time of the issues is ~8 years after the start of commercial operation.
– Up to 40 years for some events!
– Shorter detection for active components - diesels (2.6 y), pumps (4.5 y)
– Longer detection time for passive components - civil structures (8.9 years), pipes (11.7 y) or welds (12.7 y).
50
60
40
50
• High average rate of Common Cause Failures (CCF): 34%. More than 50% for civil work and fire protection, 45% for electrical components.
0
10
20
30
40
Civil Work Diesel Electrical Fire
protection
I&C Pipes Pumps SG Valves Weld
% o
f C
CF
-10
0
10
20
30
Op
era
tio
n Y
ears
% of CCF AVERAGE DETECTION TIME Maximum detection time Minimum detection time
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 10
Trends
• More than 75% of the events are found out fortuitously (following failure, spurious actuation, fire, flooding or “by chance” through unrelated tests or inspections)
70
80
90
100
0
10
20
30
40
50
60
70
Civ
il W
ork
Die
sel
Ele
ctric
alFire
pro
tect
ion
I&C
Pip
es
Pum
ps SG
Val
ves
Ven
tilat
ion
Weld
s
% of fortuitous detection Average
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 11
Trends
• Some families accumulates a long detection time, a high rate
of common cause failure and a high rate of fortuitous
detection, mainly:
– Building structures
– Anchors & supports
– Electrical components
⇒⇒⇒⇒ Potential latent failures
• High rate of I&C issues in commissioning events
Diesel
9%
Electrical
12%
Fire protection
12%
I&C
43%
Pipes
6%
Pumps
9%
Valves
9%
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 12
Lessons learned
• Approx. 60 concrete lessons learned identified for 21 separate sub-families
• Among lessons learned:
Welds .Welds .
� Events related to welds show the very high importance of appropriate weld QA, QC & inspection programme.
� All welds should be inspectable during the construction stage.
� The welding environment (on construction site) should allows the compliance with the construction code.
� The original welding documents and inspection results should be carefully kept as they are needed for the further in service inspection.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 13
Lessons learned - examples
• Electrical cables .
� A comprehensive cable condition monitoring programme should be implemented already at the construction stage. Cable sheathing of the safety-significant systems should be checked where it is accessible, in particular at the bends and at the electrical connection. During the construction, inspection should be performed in the cable trays before there are closed.there are closed.
� For installation of multiples cables in a single penetration, a specific procedure should be written in order to avoid damage during installation. Installation of designed separations in the penetrations should be checked.
� During cable manufacturing, special attention should be paid to:
• In PVC sheathing, homogenous blending of additives
• the eccentric arrangement of the conductor towards the protective sheath
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 14
Lessons learned - examples
• Penetrations and building seals .
� To ensure adequate follow-up during further plant operation, every single penetration and building seal should be properly documented (location, role, characteristics, design bases, etc).
� The initial design of inter-building seals should take into consideration the need to be able to conduct checks on the quality of installation at the construction stage and subsequently. To do so, the seals should be construction stage and subsequently. To do so, the seals should be accessible over their entire length.
� When a penetration seal functions as both fire and flood barrier, it is important to consider both functions in the design, installation, inspection, and maintenance. This includes accounting for static head pressure to ensure watertight seals do not dislodge.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 15
Lessons learned - examples
• Building structures .
� The minimum thickness of lubricant on the external wire layers following manufacture of containment pre-stressing system cables should be precisely specified.
� The humidity and the lubrication inside the channelling device of the pre-stressing cables should be monitored during construction.
� The concrete pouring should be validated by mock-up for locations where the access for concrete consolidation may be difficult (high density of steel reinforcement, etc)
(see also transversal recommendations – QC, SC, …)
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 16
Lessons learned - examples
• Pipes .
� A rigorous management of temporary devices should be implemented to avoid remaining temporary blind flanges, orifices, etc. inside the pipes after commissioning of the plant.
� Pipe clogging: measure will be taken to avoid pipe clogging by construction debris and other foreign materials. A FME + cleanliness / housekeeping policy will be implemented from the very beginning of the housekeeping policy will be implemented from the very beginning of the project.
� The pipes should be exhaustively inspected during construction.
� Special attention should be paid to proper installation of pipe support and restraints intended to mitigate consequences of earthquakes and HELB.
� The installed pipes insulation weight should be verified to comply with the seismic qualification of pipes supports.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 17
Lessons learned - examples
• I&C .
� The probes installation should be closely monitored during construction and appropriate commissioning tests should be made up and carried out in order to detect a defect of each single component of a measuring channel (including namely impulse lines).
� The minimal distance allowing functional redundancy should be ensured between redundant impulse lines.between redundant impulse lines.
• Others .
� Cranes should be included in the commissioning programme and test should be performed before 1st load lifting.
+ ~40 other lessons learned identified
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 18
Transversal recommendations
• Based on the analysis of each individual event, more than 30 concrete transversal recommendations have been identified.
• A lot of them are at the level of the management of the construction project and at QM level.
• Among them:
Communication .
� Special attention should be paid to the communication between the different companies and/or entities involved in a plant construction. This communication should be done through pre-defined and documented procedures, and submitted to a Quality Control Programme. Moreover, this communication should enable the information transfer about the safety significance of components or equipment from the design stage until the contractor and its sub-contractors in charge of the installation of the components or equipment
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 19
Recommendations - examples
• Management of non-conformances .
� The requirements for handling the non-conformances should be clearly identified. These requirements should specify the definition of the non-conformances, the roles and responsibilities of the licensee, the vendor and the subcontractor for reporting and correcting the non-conformances, as well as the regulatory approval process. The compliance with those requirements should be checked by the licensee and the regulatorrequirements should be checked by the licensee and the regulator
• Tasks interfaces .
� The interfaces between different tasks should be clearly identified and managed in such a way that the departments or companies in charge of these tasks are aware of the precise scope of their work, and that interface works are not omitted.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 20
Recommendations - examples
• Change management .
� Any changes from the design, the installation or the manufacturer procedures should be properly documented and assessed.
• Quality assurance and quality control scope .
� Handling, packaging, transportation and storage conditions of safety significant components should be covered by and monitored through a
� Handling, packaging, transportation and storage conditions of safety significant components should be covered by and monitored through a Quality Assurance Programme.
• Specific nuclear requirements .
� Each call for tender about safety-related components should include and emphasize the specific nuclear requirements and local nuclear regulations concerning namely quality management and safety culture. The compliance with those requirements should be properly checked at the stage of contracts awarding and until the work is fully implemented.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 21
Recommendations - examples
• Third party quality control .
� The oversight and the quality control of on-going works should be performed by an organization which is competent and experienced in the works, clearly identified as responsible of the quality control, and independent from the organization in charge of the works.
• Temporary devices .• Temporary devices .
� Temporary devices used at manufacturing, construction and commissioning stages should be properly documented so that to allow removing all the temporary devices after their use, in order to ensure that the remaining devices are not temporary devices and to track a potential constraint that the temporary devices may have caused on the component.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 22
Recommendations - examples
• Safety culture .
� The adherence to nuclear safety principles should be the top priority already during construction and manufacturing.
� The safety culture and safety awareness of the personnel involved in the pre-operational stages should be ensured through an adequate training, highlighting the role and the safety significance of the components concerned. Each person attending the project needs to understand the safety significance of his / her work, to promote personal responsibility. safety significance of his / her work, to promote personal responsibility.
� This is necessary for all the staff involved in the process, including the manufacturer’s staff, the vendor’s staff, contractors and sub-contractors, the staff in charge of the surveillance of the activities, and the staff in charge of the acceptance of the components.
� This safety awareness should be ensured not only for “complicated” works like welding but even for “more simple” tasks like anchoring, especially since some sub-contractors may not have any experience of working for the nuclear industry.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 23
Recommendations - examples
• Construction .
� Impact on nearby NPP units in operation: The potential consequences of construction works on the safety of operating units should be assessed (Risk Analysis). In particular, the consequences of the potential pollution from a construction site on the operating units should be assessed and if needed, the pollution should be monitored. All other potential risks should be assessed (digging, excavation, spurious fall of cranes, use of explosives, etc.).
� Labelling - The labelling of the components should be in place as soon as the components are installed.
� Torque - The applied torque should be submitted to independent verification during the related sequence of assembly operations.
� Welding - Special attention should be paid to the Quality control of the welding and the control sampling rate should be adapted to the safety-significance of the welds and to the welding technique. Moreover, the welding should be carried out by appropriate trained and experienced welders.
� Wiring - Wiring checks should follow any cabling installations – it should be a part of the installation procedure or program and should be verified by the regulator.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 24
Recommendations - examples
• Component manufacturing .
� Special attention should be paid to the purchasing of commercial grade components for safety-related equipment by the equipment manufacturer, which should be properly documented.
� The mastership of technologies should be proven and � The mastership of technologies should be proven and verified by the licensee, not only through final acceptance tests but also by checking that proven state-of-the-art technology is used. Augmented regulatory approach and inspections should verify that new manufacturing techniques and new type of equipment meet the specifications set by the designer.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 25
Recommendations - examples
• Commissioning .
� Time of tests performance - In case of a standby component, which is normally not in operation, its functionality must be regularly tested, as a long period of inactivity and the construction of other equipment during this period could question the test results.
� Scope of the tests:
• Tests conditions - The safety systems should be tested in conditions simulating the real accidental conditions and if not possible, provisions should be taken for the concerned systems in terms of acceptance tests, QA, etc.
• Tests comprehensiveness - The scope of the tests should include all the components and devices that are used during normal operation or under accidental conditions, including the passive components like pipes, as they may be during normal operation or under accidental conditions, including the passive components like pipes, as they may be clogged, and including the manufactured components, as the QC at the manufacturing plant may be deficient.
• Fragmented tests - Safety systems should be submitted to overall functional tests as far as possible to ensure not only the performance of each single component but the performance of the whole system, including the interactions between different components.
• Non-actuation tests - The tests should allow to detect an unexpected (spurious) actuation of a safety system.
• Simultaneous tests - The commissioning tests should be made up considering the fact that simultaneous tests may have an influence on each other’s results.
� The test acceptance criteria should allow verifying not only the functionality of a system or component but as well its level of performance.
� The proper reconfiguration of the systems after the commissioning tests should be checked.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 26
Conclusions
• 582 events reports from various sources were analyzed.
• Lessons learnt and recommendations about pre-operational stages can be raised from operational experience
• OE shows that anomalies during pre-operational stages can lead to serious breaches of nuclear safety during the operation of the plant.
• More than 50 concrete lessons learned for individual components or activities have been raised.
•• More than 30 transversal generic recommendation have been raised (→management of the construction project and QM!)
• The IRS database is not specific to the construction experience:
⇒ Non-conformances corrected before operation are generally not included
because no consequences on safety
⇒ The reports focus more on corrective actions for the operating plants and the
lessons learnt for other construction projects are often not fully considered.
⇒ Need for improvement of experience capture from anomalies related to preoperational stages, at international level.
CNRA International Workshop on New Reactor Siting, Licensing and Construction Experience, 15-17/09/2010, Prague 27