KRB-A (Grundremmingen, Germany) KRB-A General Description • Type:Boiling Water Reactor • Power: 250 MW(e) • Started in 1966, shut down in 1977 • First commercial power.
Download ReportTranscript KRB-A (Grundremmingen, Germany) KRB-A General Description • Type:Boiling Water Reactor • Power: 250 MW(e) • Started in 1966, shut down in 1977 • First commercial power.
Slide 1
KRB-A
(Grundremmingen, Germany)
1
Slide 2
KRB-A
General Description
• Type:Boiling Water Reactor
• Power: 250 MW(e)
• Started in 1966, shut down in 1977
• First commercial power reactor in the Federal
Republic of Germany
2
Slide 3
KRB-A Layout
3
Slide 4
KRB-A
Project Summary
• 1977: reactor shut down
• 1980: decommissioning planning
• 1983: phase I: removal of components and
systems in the turbine house
• 1990: phase II: decommissioning of primary
circuit
• 1992-date: phase III: dismantling of RPV,
internals and biological shield
• 2005: complete reactor removal
4
Slide 5
KRB-A
Operational lessons learned
• The use of chemical decontamination to minimise
waste for disposal
• Ice sawing technique successfully used to stabilise
and cut through tube bundles
• Thermal cutting is flexible and reliable
• Mechanical tools are simple to handle
5
Slide 6
KRB-A
General learning points
• No single dismantling tool
• Avoidance of complicated techniques
• Clearly defined waste management process
6
Slide 7
KGR (Greifswald,Germany)
7
Slide 8
KGR
General Description
• Type:8 Pressurised Water Reactors
• Power: 440MW(e) each
• Four reactors operational between 1973 and
1990
• Reactor units based on Russian WWER
design, three reactors never commissioned,
one test operation
8
Slide 9
KGR
Project Summary
• 1989-90: units 1-5 shut down and construction of
units 6-8 halted
• 1995-2009: dismantling of equipment, units 1-5
• 1998: start of Interim Storage North (ISN)
operations
• 1999-2002: demonstration remote dismantling,
unit 5
• 2004-2007: dismantling of reactor and internals,
units 1-4
• 2012: completion of reactor buildings demolition
9
Slide 10
KGR
Site re-use
Harbour construction works at
the former cooling water outlet
channel
10
Slide 11
KGR
Progress
Percent dismantling
complete (by mass) as at
May 2004
Unit 1
71%
Unit 2
73%
Unit 3
16%
Unit 4
66%
Unit 5
80%
Turbine hall
51%
Removal of large components to the
ISN for decay storage
RPV (214Mg)
Steam
generator
(166Mg)
11
Slide 12
KGR
Waste management
Total mass site decommissioning waste
1,800,000 Mg
Radiologically unrestricted material
1,233,600 Mg
Remaining building
structures
471,200 Mg
Other radioactive residuals
566,400 Mg
Concrete for radioactive waste
or decay storage
26,000 Mg
Dismantling plant
parts
69,200 Mg
Sorting, packaging and
buffer storage
Unrestricted
release
511,100 Mg
Restricted
re-use
2,500 Mg
Conventional
waste
3,750 Mg
12
Decay
storage
28,400 Mg
Controlled re-use
in nuclear facilities
4,150 Mg
Radioactive
waste
16,500 Mg
Slide 13
KGR
Operational lessons learned
• No specific problems
• Development of a comprehensive inventory
• Use of simple, sturdy equipment
• Complete planning - shut down to disposal
• ALARA principle
13
Slide 14
KGR
General learning points
• Challenge to project management and logistics
• Social aspects - strategy for site re-use
• Clear and realistic requirements from the
licensing authority
• Open dialogue with the public
14
Slide 15
NPP-A1 (Jaslovske Bohunice,
Slovakia)
Refuelling machine
in reactor hall
Long term spent
fuel store
Steam generators
Turbines
Reactor
15
Primary circ.
Turbocompressors
Slide 16
NPP-A1
General Description
• Type:Heavy Water Gas Cooled Reactor
• Power: 143 MW(e)
• Started in 1972, shut down in 1977
• Experimental and power prototype reactor for
the development of gas cooled, heavy water
moderated reactors using natural uranium.
16
Slide 17
NPP-A1
Project Summary
• 1977: reactor shut down
• 1980-94: transition period
• 1999: all spent fuel transported to Russia
• 1999-2007: first decommissioning phase
• 2008-2033: final decommissioning
17
Slide 18
NPP-A1
Operational lessons learned
• Decommissioning greatly influenced by reactor
history (accidents) and fuels and liquid waste
storage issues
• Successful co-operation with European companies
• Use of operational staff knowledge
• Clear definition of waste management routes and
process requirements
• Carrying out activities in small steps with small
teams
18
Slide 19
NPP-A1
General learning points
• Maintaining fuel cladding integrity during
operation
• Co-operation between project managers,
technicians, health physicists and regulators
19
Slide 20
Summary of lessons learned(1)
Initial characterisation
Impacts cost, schedule, decontamination
strategy, waste managaement
20
Slide 21
Summary of lessons learned(2)
Tools and equipment
• Simple, appropriate, tested, commercially
available where possible
• manual > remote
• develop contingency solutions and tooling
• consider effect of aging
21
Slide 22
Summary of lessons learned(3)
Operational management
• remove debris promptly and in a controlled
way
• consider effect of temporary systems on
existing systems
• establish a fit for purpose working
environment
22
Slide 23
Summary of lessons learned(4)
Risk management
• prioritise
• take a total risk approach avoid creating new
hazards
• consider non radiological and radiological
hazards equally
• risk assessment/management must be an
ongoing process
23
Slide 24
Summary of lessons learned(5)
Waste management
• plan all operations
• minimise production of wastes e.g. segregate
wastes at source
• do not generate a waste stream until a
disposal strategy has been defined
• adequately consider effect of decontamination
techniques on secondary waste generation,
cost, worker health and safety
24
Slide 25
Summary of lessons learned(6)
Staff experience
• make use of available expertise
• maintain team continuity where possible
• small experienced teams are generally more
effective
25
Slide 26
Summary of lessons learned(7)
International collaboration
• benchmarking
• exchange agreements - sharing technologies
and experiences
26
Slide 27
Summary of lessons learned(8)
Stakeholder involvement
• openness and transparency
• develop mechanisms for consulting and
dissemination of information
27
Slide 28
Questions?
28
KRB-A
(Grundremmingen, Germany)
1
Slide 2
KRB-A
General Description
• Type:Boiling Water Reactor
• Power: 250 MW(e)
• Started in 1966, shut down in 1977
• First commercial power reactor in the Federal
Republic of Germany
2
Slide 3
KRB-A Layout
3
Slide 4
KRB-A
Project Summary
• 1977: reactor shut down
• 1980: decommissioning planning
• 1983: phase I: removal of components and
systems in the turbine house
• 1990: phase II: decommissioning of primary
circuit
• 1992-date: phase III: dismantling of RPV,
internals and biological shield
• 2005: complete reactor removal
4
Slide 5
KRB-A
Operational lessons learned
• The use of chemical decontamination to minimise
waste for disposal
• Ice sawing technique successfully used to stabilise
and cut through tube bundles
• Thermal cutting is flexible and reliable
• Mechanical tools are simple to handle
5
Slide 6
KRB-A
General learning points
• No single dismantling tool
• Avoidance of complicated techniques
• Clearly defined waste management process
6
Slide 7
KGR (Greifswald,Germany)
7
Slide 8
KGR
General Description
• Type:8 Pressurised Water Reactors
• Power: 440MW(e) each
• Four reactors operational between 1973 and
1990
• Reactor units based on Russian WWER
design, three reactors never commissioned,
one test operation
8
Slide 9
KGR
Project Summary
• 1989-90: units 1-5 shut down and construction of
units 6-8 halted
• 1995-2009: dismantling of equipment, units 1-5
• 1998: start of Interim Storage North (ISN)
operations
• 1999-2002: demonstration remote dismantling,
unit 5
• 2004-2007: dismantling of reactor and internals,
units 1-4
• 2012: completion of reactor buildings demolition
9
Slide 10
KGR
Site re-use
Harbour construction works at
the former cooling water outlet
channel
10
Slide 11
KGR
Progress
Percent dismantling
complete (by mass) as at
May 2004
Unit 1
71%
Unit 2
73%
Unit 3
16%
Unit 4
66%
Unit 5
80%
Turbine hall
51%
Removal of large components to the
ISN for decay storage
RPV (214Mg)
Steam
generator
(166Mg)
11
Slide 12
KGR
Waste management
Total mass site decommissioning waste
1,800,000 Mg
Radiologically unrestricted material
1,233,600 Mg
Remaining building
structures
471,200 Mg
Other radioactive residuals
566,400 Mg
Concrete for radioactive waste
or decay storage
26,000 Mg
Dismantling plant
parts
69,200 Mg
Sorting, packaging and
buffer storage
Unrestricted
release
511,100 Mg
Restricted
re-use
2,500 Mg
Conventional
waste
3,750 Mg
12
Decay
storage
28,400 Mg
Controlled re-use
in nuclear facilities
4,150 Mg
Radioactive
waste
16,500 Mg
Slide 13
KGR
Operational lessons learned
• No specific problems
• Development of a comprehensive inventory
• Use of simple, sturdy equipment
• Complete planning - shut down to disposal
• ALARA principle
13
Slide 14
KGR
General learning points
• Challenge to project management and logistics
• Social aspects - strategy for site re-use
• Clear and realistic requirements from the
licensing authority
• Open dialogue with the public
14
Slide 15
NPP-A1 (Jaslovske Bohunice,
Slovakia)
Refuelling machine
in reactor hall
Long term spent
fuel store
Steam generators
Turbines
Reactor
15
Primary circ.
Turbocompressors
Slide 16
NPP-A1
General Description
• Type:Heavy Water Gas Cooled Reactor
• Power: 143 MW(e)
• Started in 1972, shut down in 1977
• Experimental and power prototype reactor for
the development of gas cooled, heavy water
moderated reactors using natural uranium.
16
Slide 17
NPP-A1
Project Summary
• 1977: reactor shut down
• 1980-94: transition period
• 1999: all spent fuel transported to Russia
• 1999-2007: first decommissioning phase
• 2008-2033: final decommissioning
17
Slide 18
NPP-A1
Operational lessons learned
• Decommissioning greatly influenced by reactor
history (accidents) and fuels and liquid waste
storage issues
• Successful co-operation with European companies
• Use of operational staff knowledge
• Clear definition of waste management routes and
process requirements
• Carrying out activities in small steps with small
teams
18
Slide 19
NPP-A1
General learning points
• Maintaining fuel cladding integrity during
operation
• Co-operation between project managers,
technicians, health physicists and regulators
19
Slide 20
Summary of lessons learned(1)
Initial characterisation
Impacts cost, schedule, decontamination
strategy, waste managaement
20
Slide 21
Summary of lessons learned(2)
Tools and equipment
• Simple, appropriate, tested, commercially
available where possible
• manual > remote
• develop contingency solutions and tooling
• consider effect of aging
21
Slide 22
Summary of lessons learned(3)
Operational management
• remove debris promptly and in a controlled
way
• consider effect of temporary systems on
existing systems
• establish a fit for purpose working
environment
22
Slide 23
Summary of lessons learned(4)
Risk management
• prioritise
• take a total risk approach avoid creating new
hazards
• consider non radiological and radiological
hazards equally
• risk assessment/management must be an
ongoing process
23
Slide 24
Summary of lessons learned(5)
Waste management
• plan all operations
• minimise production of wastes e.g. segregate
wastes at source
• do not generate a waste stream until a
disposal strategy has been defined
• adequately consider effect of decontamination
techniques on secondary waste generation,
cost, worker health and safety
24
Slide 25
Summary of lessons learned(6)
Staff experience
• make use of available expertise
• maintain team continuity where possible
• small experienced teams are generally more
effective
25
Slide 26
Summary of lessons learned(7)
International collaboration
• benchmarking
• exchange agreements - sharing technologies
and experiences
26
Slide 27
Summary of lessons learned(8)
Stakeholder involvement
• openness and transparency
• develop mechanisms for consulting and
dissemination of information
27
Slide 28
Questions?
28