Regulatory Issues on Decommissioning of Nuclear Power Plant in Lithuania

Regulatory Issues on
Decommissioning of Nuclear Power
Plant in Lithuania
Vidas Paulikas
State Nuclear Power Safety Inspectorate (VATESI)
28th Annual Regulatory Information Conference,
North Bethesda, Maryland, 8-10 March 2016
Nuclear safety regulator - VATESI
VATESI STRUCTURE
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VATESI was established in 1991
Head of VATESI appointed by President
Reporting directly to the President and Government VATESI staff – 75 positions
Head
Mandate
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State regulation and supervision of nuclear and radiation safety in Nuclear Facilities
State control of Euratom and IAEA safeguards implementation
State regulation and supervision of physical security of NFs and NMs
Has Emergency centre with officers 24 h on duty
Performs international cooperation in all of the competence areas (bilateral, IAEA, WENRA, ENSREG, ENSRA and other)
2016: planned IRRS mission (full scope)
Assistant
Internal Audit
Division
Public
Communication
Division
Finance and
Accounting Division
Project Management
Division
Administration
Department
Deputy Head for
Nuclear Safety
Deputy Head for
Radiation Safety
Legal Affairs and
Personnel Division
Safety Analysis
Division
Radioactive Waste
Management
Division
Information
Technologies
Division
Systems and
Components
Division
Decommissioning
Division
Asset Management
and Public
Procurement
Division
Operational
Experience Analysis
Division
Transportation and
Radiation Safety
Division
Nuclear Materials
Control and Physical
Security Division
Surveillance
Division
2
Nuclear program
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Ignalina NPP (under decommissioning):
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Spent fuel:
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Unit 1 (RBMK‐1500) operation 1983‐2004
Unit 2 (RBMK‐1500) operation 1987‐2009
Existing spent nuclear fuel storage facility (~1/4 of INPP inventory) Construction of new spent nuclear fuel storage facility (project B1 ‐ construction license, “cold trial” stage; ~3/4 of INPP inventory including damaged spent fuel)
Ignalina NPP (under decommissioning)
Planned Visaginas NPP
Radioactive waste:
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Existing storage facilities for operational waste
Treatment of liquid waste (bituminization and cementation) Construction of new treatment facility (projects B2, B3 4 ‐
construction license, “cold trial" stage)
Design of disposal facilities (project B19‐2 ‐ combined license issued, tendering for construction works; project B25 ‐ review of TDD and PSAR by VATESI)
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Decommissioning of Ignalina NPP
The Final Decommissioning plan shall consists of following descriptions:
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facility, its site and region, the operation history of the nuclear facility;
radiological characterisation;
decommissioning strategy;
major decommissioning phases and (or) projects;
need for new infrastructure;
dismantling, decontamination technologies;
decommissioning waste management;
need for the staff competent;
general radiological surveys programme …
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Decommissioning of Ignalina NPP
Transition period:
Means process of termination of the operation of a nuclear facility when the licensee implements the measures which help to get ready for conducting decommissioning of a nuclear facility and (or) to reduce the time of performing it. District heating equipment (before and after dismantling)
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License for operation of nuclear power plant still valid;
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Main activities of licensee are removal of spent nuclear fuel, isolation, decontamination of systems and components, management of radioactive waste;
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Dismantling of not anymore needed systems, components and structures is subject of justification;
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Implementation of new infrastructure necessary for decommissioning.
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Decommissioning of Ignalina NPP
New infrastructure for radioactive waste and spent nuclear fuel management:
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Storage of spent nuclear fuel (construction license, review of “cold trial" programme)
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Treatment facilities for solid radioactive waste (construction license, review of “cold trial" programme)
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14 200 FA will be stored;
capacity of the facility will be 15 m3 per day, 28 000 m3 of operational waste and 100 000 m3 of decommissioning waste will be treated;
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Retrieval of radioactive waste (construction license, review of “cold trial" programme)
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Free release facility (in operation)
Very low level radioactive waste disposal facility (combined license issued)
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about 25000 m3 solid radioactive waste;
capacity of the facility is about 60000 m3 ;
Low and intermediate level radioactive waste disposal facility (TDD and PSAR review stage)
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capacity of the facility is about 100 000 m3 .
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Licensing of new nuclear facilities
Authorisation process for construction and operation
CONSTRUCTION LICENSE
OPERATING LICENCE
Site evaluation
Analysis of division to protection
zones
Construction
List of vital and important areas; Security Plans
Operation
Commissioning
Approval of Commissioning Program (incl. security); updated List of VIA
Operating licence
Programme of effectiveness evolution and the report; Updated security plan
Construction
Permits to resume operation after shut down (NPP)
Permit for commercial operation
Permit for the first shipment of the NM into the site
Operation
Commissioning COMBINED (CONSTRUCTION AND OPERATING) LICENSE
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Schedule of decommissioning and infrastructure authorizations
B25
05
10
15
25
20
38
30
B1, B2, B34,
B19
U1 RPS
U1 Defueled
U1 operation license
Site decommissioning
license
U2 Defueled
U2 RPS
U2 operation license
Dismantling and decontamination projects
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Dismantling & Decontamination
District heating
Bldg.
119
D0
Fire Protection
System
ECCS
Tanks
Turbine Hall G1
Turbine Hall G2
Control, Electrics & Deaerators D1
7,132 t
Control,
Electrics & Deaerators D2
V1
117/1
ECCS
Gas circuit
& Venting
Reactor /
Fuel
Building
A1
V2
B1
117/2
Water
Treatment
Gas circuit
& Venting
Unit 1
Completed
x 1000 tons
Reactor /
Fuel
Building
A2
B2
Water
Treatment
Unit 2
In progress
2010-2014
(in all)
Design stage
2015
(7 months)
Planning
2015
(plan)
2010-2038
(in all)
Equipment dismantled
26.5
4.9
7.0
131.0
Waste free-released
23.8
4.0
5.6
110.0
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Waste Inventory
0
3000 MW (RBMK)
Solid Waste
Bituminized Waste
Cemented
Waste C
Buildings
Dismantled Waste
2010 to July 2014
Intermediate Level Waste (>2 mSv/h)
27,000 m3
D
E
Low Level Waste (<10 mSv/h)
Intermediate Level Waste (>10 mSv/h)
4,000 m3
15,555 vnt.
Dismantled Steel (equipment)
A CDE
Graphite DE 3,800 t.
Fillers
A C
Concrete
0 A B
Steel
0 A
Steel
Reactor
Very Low Level Waste (<0,5 mSv/h)
Low Level Waste (0,5-2 mSv/h)
Long-lived Low Level and Intermediate Level Waste:
A B C
B 14,000 m3
Fuel Assemblies
Decommissioning Waste
A
B
C
6,016 vnt.
FA
Stored Operational Waste
Free Release Waste
Short-lived Low Level and Intermediate Level Waste:
Ignalina NPP
Steel and Structures
A B C
130,000 t.
12,170 t.
11,940 t.
1000,000 m3
200,000 t.
0 A
16,403 t.
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Thank you for your attention!
www.vatesi.lt
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