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Preliminary Plan for Decommissioning and Post
Shutdown Activities of Brazilian NPPs
Bruno Estanqueira Pinho Fuel Assembly and Safety Analysis Advisory Technical
Directorate
+55 21 2588-7938 May 2018
1. CNAAA – Alvaro Alberto Admiral Nuclear Center - Description
2. Chronology of Brazilian Licencing - Decommissioning
3. Decommissioning in Brazil
4. PDP – Preliminary Decommissioning Plan of CNAAA
I. Table Of Contents Of PDP
II. Summary Schedule
III. Decommissioning Cost Estimate (DCE)
IV. Radioactive Waste Summary Foreseen:
a) Operacional
b) Decommissioning
5. Transition Period Preliminar Planning
I. Table Of Contents Of TPPP of Angra 1
II. Spent Fuel Management at CNAAA
III. Post Shutdown Activities for Angra 1- Summary
IV. TPA1 Cost Estimate – order of magnitude
2
TABLE OF CONTENTS
1. Almirante Álvaro Alberto Nuclear Center
CNAAA
For sites with more than one facility, a site
strategy for decommissioning
shall be developed to ensure that
interdependences between the facilities
are
taken into account in the planning for
individual facilities that will lead to final
decommissioning plans for each facility
An important consideration when selecting
the decommissioning strategy
is the desired end state5 of the facility
following completion of the
decommissioning.
The preferred end state would be to
achieve a situation whereby the
site is released for unrestricted use (with or
without buildings) or a situation
whereby it may be released for restricted
use. Other end states could involve
partial release of a site or release of a site
under restricted conditions to control
its future use. The foreseen end states for
the three different strategies are
shown in Fig. 1.
The end state is defined as a
predetermined criterion defining the point
at which
a specific task or process (i.e.
decommissioning) will be considered
complete
GSR part 6 , Decommissioning of Facilities, IAEA, 2014)
INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning of Facilities Using Radioactive
Material, IAEA Safety Standards Series No. WS-R- 5, IAEA, Vienna (2006).
Decommissioning Strategies for Facilities Using Radioactive Material, SRS no 50. IAEA, 2007.
São Paulo
220km
Belo
Horizonte
350km
Rio de Janeiro
130km CNAAA
ANGRA 1 PWR
Power: 640 MW
Technology: Westinghouse
Operation start: Jan. 1985
ANGRA 2 PWR
Power: 1,350 MW
Technology: KWU/ Siemens
Operation start: Jan. 2001
ANGRA 3 PWR
Power: 1,405 MW
Technology: KWU/ Siemens - Framatome Civil works reached ~67 %.
(illustrative view) ANGRA 1
ANGRA 2
RADIOACTIVE
WASTE STORAGE
CENTER 500kV Switchyard
Ilustrative picture
UAS (ISFSI) – 2020 Waste Monit. Building – New
Civil works – 95%
NN CNEN 9.01
(Nov./2012)
ENERCON Contract
(Mar/2015)
UFABC University
(Feb/2017)
PDP rev0
UFABC University / ETN
(Nov./2014)
PDP rev. 0 REVIEW
Analising strategy / chapters / Data collection
>>> Develop the site specific Decommissioning
Cost Estimate Software (DCE)
PDP reviewed
(June/2018)
UFABC - End
2. Chronology of Brazilian Licencing in Brazil
PDP Improv. / DCE
(Sept/2017)
Enercon - End
Implementation of ENERCON comments /
Biography Research / Review and
release of new PDP >> English and
Portuguese
>>> Qualification of National Partner –
University of ABC
Submit to CNEN
PDP ver 1
(End of 2018)
NN CNEN 9.02
(Oct./2016)
4
3. Decommissioning in Brazil
For sites with more than one facility, a site
strategy for decommissioning
shall be developed to ensure that
interdependences between the facilities
are taken into account in the planning for
individual facilities that will lead to final
decommissioning plans for each facility
An important consideration when selecting
the decommissioning strategy
is the desired end state5 of the facility
following completion of the
decommissioning.
The preferred end state would be to
achieve a situation whereby the
site is released for unrestricted use (with or
without buildings) or a situation
whereby it may be released for restricted
use. Other end states could involve
partial release of a site or release of a site
under restricted conditions to control
its future use. The foreseen end states for
the three different strategies are
shown in Fig. 1.
The end state is defined as a
predetermined criterion defining the point
at which
a specific task or process (i.e.
decommissioning) will be considered
complete
5
GSR part 6 , Decommissioning of Facilities, IAEA, 2014)
INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning of Facilities Using Radioactive
Material, IAEA Safety Standards Series No. WS-R- 5, IAEA, Vienna (2006).
Decommissioning Strategies for Facilities Using Radioactive Material, SRS no 50. IAEA, 2007.
• Decommissioning: ADMINISTRATIVE AND TECHNICAL ACTIONS TO
ALLOW THE REMOVAL OF SOME OR ALL OF THE REGULATORY CONTROLS FROM A FACILITY (CNEN NN 9.01, 2012)
• With no unacceptable risk to the public, the workers or the environment
• Decommissioning Strategies for CNAAA:
Deferred Dismantling: Angra 1 and 2 NPPs
Immediate Dismantling: Angra 3 NPP
• Desired End State – Unrestricted use
• Important Issues
o Integrated National RW and SFAs Policy
o LLW / ILW Repository – under siting selection phase
o HLW and SFA Repository – waiting for political decision
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4. PDP - PRELIMINARY DECOMMISSIONING PLAN
1. Introduction
2. Facility description
3. Decommissioning strategy
4. Project management
5. Decommissioning activities
6. Surveillance and maintenance
7. Waste management
8. Cost estimate and funding mechanisms
9. Safety assessment
10. Environmental assessment
11. Health and safety
12. Quality assurance
13. Emergency planning
14. Physical security and safeguards
15. Final radiation survey
SRS no 45 Standard Format and Content for Safety Related Decommissioning Documents. 2005, IAEA.
I - TABLE OF CONTENTS OF PDP
IMPROVEMENTS
NEW
CHAPTERS SRS45
SITE SPECIFIC
DCE
CNEN NN 9.01 Descomissionamento De Usinas Nucleoelétricas
ISDC International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 2012, NEA/OECD
6
4. PDP – Preliminary Decommissioning Plan -II. Schedule - Life extension assumed
Transition Period Safe Storage ~35years
RV / Internals / Large Comp
Rem. and Decont Systems.
Demol / Site Restor.
7
Planning
2062 (2042 with no LTO)
2082
2093
• Transition Period Cost not included 1st DCE-
operational RW and SF.
>>> to be included – After CNEN requirement
• 40 years of operation + 20 years of life extension
• Angra 1/ 2 / 3 - reactor vessel and internals will
be removed sequentially.
2045 (2025 with no LTO)
Safe Storage ~20 years
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4. PDP - III – Decommissioning Cost Estimate (DCE)
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INPUTS OUTPUTS
1E, 1G 3A DECOM PLANNING S3
OUTPUTS 1E, 1G 3B ACTIVITY PREPARATION S5, S7
1A SCHEDULE S1, 6I
1B PRODUCTIVITY LOSS FACTORS 4A, 4B, 5A, 6E
1C TAX
1D CONSUMABLES 4A, 4B, 5A, 6*, 7E, 7F
1E UTIL STAFF RATES 3A, 3B, 7C INPUTS OUTPUTS
1F CONTRACTOR RATES 7D 1B, 1D, 1H 4A UCF CLEAN 4C
1G SKILLED LABOR RATES 1H, 1J, 7C, 7D 1B, 1D, 1H 4B UCF CONTAMINATED 4C
1H DISMANTLE CREW RATES 4A, 4B, 5A, 6*, 7E, 7F 4A, 4B 4C UCF SUMMARY 4D, 4F
1J COMPONENT CREW RATES 6B, 6C, 6G, 6H 4C, 1K, 2A 4D RAD INVENTORY 4E
1K DISPOSAL RATES 4D, 4F, 5D, 5F, 6F, 6J, 6K 4D 4E RAD SUMMARY S5, S6 INPUTS OUTPUTS
4C, 1K, 2A 4F CLEAN INVENTORY 4G 1A, S2 S1 ANNUAL COST
4F 4G CLEAN SUMMARY S7, S6 S3 - S10 S2 COST SUMMARY S1
3A, 7A, S11 S3 PLANNING S2
S11 S4 SAFSTOR PREP S2
3B, 4E, 5E, 6A, 7A, S11 S5 DISMANTLE S2
INPUTS OUTPUTS 4E, 4G, 5E, 5G, 6A, S11 S6 WASTE S2
OUTPUTS 1B, 1D, 1H 5A UNIT COST FACTORS 5C 3B, 4G, 5G, 6A, 7A, S11 S7 DEMOLITION & SITE RESTORATION S2
2A SYSTEMS 4D, 4F 5A 5C UCF SUMMARY 5D, 5F 7A, S11 S8 S&M S2
2B STRUCTURES 5D, 5F 5C, 1K, 2B 5D RAD INVENTORY 5E 7A, S11 S9 PROJECT MANAGEMENT S2
5D 5E RAD SUMMARY S5, S6 7A, S11 S10 MISCELLANEOUS S2
5C, 1K, 2B 5F CLEAN INVENTORY 5G S11 CONTINGENCY S3 - S10
5F 5G CLEAN SUMMARY S7, S6
COST FORMAT BASED ON WBS
INPUTS OUTPUTS
6B - 6K 6A SUMMARY S5, S7, S6
1D, 1J 6B STEAM GENERATOR 6A
1D, 1J 6C PRESSURIZER 6A
1D, 1H 6D FUEL RACKS 6A
1B, 1D, 1H 6E UCF Miscellaneous 6A
1K, 6B, 6C, 6D, 6F COMPONENT WASTE 6A
1D, 1J 6G Rx INTERNALS LABOR 6A
1D, 1J 6H Rx VESSEL LABOR 6A
1A 6I REFERENCE PWR 6J, 6K
1K, 6I 6J INTERNALS WASTE 6A
1K, 6I 6K VESSEL WASTE 6A
INPUTS OUTPUTS
1A, 7B 7A Total Cost S3, S5, S7, S8, S9, S10
7C - 7I 7B Monthly Cost 7A
1E, 1G 7C Utility Staff 7B
1F, 1G 7D DGC Staff 7B
1D 7E Equipment 7A, 7B
1D 7F RP Supplies 7A, 7B
7G Severence 7A
7H Insurance 7B
7I Permits and Fees 7A, 7B
TABS
TABS
TABS
TABS
TABS
TABS
TABS
TABS
SUMMARY
INPUTS
MATERIAL TAKEOFFS
UNIT COST FACTORS - SYSTEMS
UNIT COST FACTORS - STRUCTURES
UNIT COST FACTORS - LARGE COMPONENTS
PLAN AND PREPARE
PERIOD DEPENDENT
11 spreadsheets
Based on WBS of ISDC International Structure for Decommissioning Costing
(ISDC) of Nuclear Installations - OECD/NEA(2012).
• Order of magnitude -30% to +50% - PPD2014 - Is not site specific, and usually based on scaling up or
down other estimate similar plants. Is not based on
specific drawings or site information
• Budgetary -15% to +30% - PPD2018 - Based on system and building drawings, layouts and
equipment drawing for major components.
• Definitive -5% to +15% - Based on detailed building, system and equipment
drawings, characterization survey data, one line electrical
and system drawings and plot plants and elevation
drawings. Detailed review of scope and required activities
and their costs.
Methodology & Flowchart
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Unplanned / Prematurely Shutdown - Decommissioning:
I.Voluntary Decision: ETN must meet the requirements laid down by the Regulator Agency in
order to ensure safe implementation of early decommissioning process of the Nuclear Facility and present the financial guarantee for the accomplishment of this activity.
II.Government action: I The Govern must complement the Decommissioning Trust Fund
(DTF)
III.Accident: US$ 500 million issurance for each plant to promote early decommissioning of the
plants.
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4. PDP - III – Decommissioning Cost Estimate (DCE)
PDP 2014 (10CFR50.75 / NUREG 1307)
DCE
(ISDC)%
Angra 1 $431.600.000 $601.211.984 39%
Angra 2 $529.600.000 $708.292.836 34%
Angra 3 $529.600.000 $665.913.404 26%
Support
Buildings$14.922.904
Total $1.490.800.000 $1.990.341.127 34%
PDP 2014 x DCE 2017
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4. PDP – IV RADIOACTIVE WASTE AND SPENT FUEL SUMMARY FORESEEN (m3):
a) OPERATIONAL
Angra 1 Angra 2 Angra 3 Total
LLW 1920.52 515.82 574.56 3010.9
ILW 4938.48 405.28 451.44 5795.2
Total 6859 921.1 1026 8806.1
Planned SFAs 2095 2873 2845 7813
Ref.: GMO.O-007/17 – DPR.O / ACS.T
b) DECOMMISSIONING
Ref.: Based on the facility, system and equipment drawings; radiological survey data; past incident reports and plant visits - ENERCON
Angra 1 Angra 2 Angra 3 Support Buildings Total
LLW 7.319 12.941 12.839 639 33.737
LLW - HA 121 194 88 0 403
ILW 91 170 170 0 431
ILW – HA 37 7 227 0 271
HLW 13 62 299 0 374
Total 7.581 13.374 13.623 639 35.216
Clean 312.940 428.145 428.145 49.174 1.218.404
Total + Clean 320.520 441.519 441.768 49.813 1.253.620
10
Fill a detail Gap in the PDP of CNAAA and to attend a requirement of CNEN.
Reasons for Delay and Financial Trouble / Loss in the Transition Period (IAEA, 2004):
I. Unavailability of funds;
II. Early, unplanned and permanent shutdown of a plant - political, regulatory or
economic reasons;
III. Lack of a decommissioning strategy; Lack of infrastructure (Intermediate or Final
Repository) or technology;
IV - Lack of regulation for decommissioning;
V. Loss / demotivation of key people and adaptation to cultural changes;
VI. Lack of planning for the decommissioning made during the operation of the plant.
5. Transition Period Preliminar Planning – Angra 1
Motivos de Desligamento
dos Reatores
Região /
País EUROPA USA Rússia Japão Canadá Total
Reactors closed
having fulfilled
their purpose or
being no longer
economic to run
Nº
reatores 61 32 7 11 4 115
Reactors closed
prematurely by
political decision or
others
Nº
reatores 33 1 0 2 0 37
Total
Nº
reatores 94 33 7 13 4 151
% 62,3 21,9 4,6 8,6 2,6 100
EPRI / NRC + IAEA + International references ~84,2%
5. Main Referencees Research
Shutdown reactors in world- accidents excluded– (WNA, jan 2018)
5. EPRI + IAEA – Referencees
2016
2004
2004
+ Lessons Learned
+ Other References
4.1. Licencing
4.2. Human Resources and Organizational Struture
4.3. Communication Plan
4.4. Historical Site Assessment(HSA) e RW Characterization
4.5. Chemmical Decontamination of Systems
4.6. Cool and Dim planning
4.7. Removal of Inflamable material and transition to a Incipient Fire Brigade (IFB)
4.8. SPENT FUEL MANAGEMENT
4.9. Removal and Reduction of Hotspots
4.10. Asbestos Removal
4.11. Dismantling of systems and non radioactive buildings
4.12. Removal / retirement of systems and review of technical specifications
4.13. Safety Assessment for the TP
4.14. SUMMARY OF ACTIVITIES FOR THE NPP
4.15. COST ESTIMATE FOR TRANSITION PERTIOD – order of magnitude
4.16 Quality Plan and Administrative controls
5. I - Table of Contents of Angra 1 Transition Period Plan
5. II - Spent Fuel Management
Figura 16 – Transfering route from Angra 1 and Angra 2 for UAS (Eletronuclear, 2016)
ISFSI to be constructed until 2020
– UAS (Unidade de Armazenamento a seco)
Under licencing and project phase
Plants Storage Capacity
(cels) Cels being used
SFA inside the
core
End of capacity
forecast
Angra 1 1.252 978 121 Dez/21
Angra 2 1.084 756 193 Jul/21
5. II - UAS – ISFSI – Dry SF Storage
VERTICAL or Horizontal – BID to choose
Short Schedule
Worldwide implemented (+90 plants)
More than 2300 implemented
CNEN resolution 199 Jul/2016 >> Certified solution
following NRC licencing
- RG 3.62 (Std Format and Content for the SAR for Onsite
Storage of SFS Casks) -
NUREG 1567 (Std Review Plan for SF Dry Storage
Facilities) - 10
CFR 72 – Licensing Req for the ISSF and HLW)
Expandable – 15 >> 72 >> +2 x 90
HOLTEC INTERNATIONAL - BID Winner – Turn Key
33 NPPs >> 706 Canisters, >> 36.336 SFAs
5. II - UAS – ISFSI – 1st phase
~ 5 operation cycles of Units 1 e 2:
Angra 1: 222 SFAs - 6 Overpacks
Angra 2: 288 SFAs - 9 Overpacks
Total: 510 SFAs - 15 Storage Overpacks
Transport cask Canister
Overpack
Storage
Angra 1
Angra 2
Traport Vehicle
5. II - CNAAA - Spent Fuel Inventory
Storage place Angra-1
Capacity Occupied
New Fuel Storage Room 45 0
Region 1 Spent Fuel Pool 252 168
Region 2 Spent Fuel Pool 1,000 810
Reactor Core 121 121
Total of Spent Fuel (Reactor Core + SFP) 1099
Storage place Angra-2
Capacity Occupied
New Fuel Storage Room 75 0
Region 1 Spent Fuel Pool 264 44
Region 2 Spent Fuel Pool 820 712
Reactor Core 193 193
Total of Spent Fuel (Reactor Core + SFP) 949
Updated June/2018
5. CNAAA - Spent Fuel Inventory – FAILED /DAMAGED
ANGRA 1 - FUEL ASSEMBLY RECONSTITUTION EQUIPMENT (FARE)
ANGRA 2 - FUEL ASSEMBLY RECONSTITUTION UNIT (FARU)
NPP FA FAILED / DAMAGED CYCLE ACTUAL STATUS Burnup during failure (MWD/MTU)
ANGRA 1 F27 FAILED 4 REPAIRED 5.909,60 ANGRA 1 M06 FAILED 14 FAILED 17.154,00
ANGRA 1 S05 DAMAGED 10 REPAIRED 14.263,70
ANGRA 1 T13 FAILED 13 FAILED 38.752,70
ANGRA 1 U06 FAILED 14A FAILED 37.526,70 ANGRA 1 U27 FAILED 14 FAILED 34.596,90 ANGRA 1 U37 FAILED 12 REPAIRED 18.242,10 ANGRA 1 V05 FAILED 14 REPAIRED 20.432,80 ANGRA 1 V24 FAILED 14A FAILED 23.377,60
ANGRA 1 W12 FAILED 14 FAILED 5.913,10 ANGRA 1 W16 FAILED 14 FAILED 5.849,10
ANGRA 1 W24 FAILED 14A FAILED 10.267,60 ANGRA 1 X26 FAILED 16 FAILED 31.573,90
ANGRA 1 AC02 DAMAGED 22 DAMAGED 46.462,60 ANGRA 1 AC38 DAMAGED 20 DAMAGED 29.567,70
ANGRA 1 AF40 DAMAGED 22 DAMAGED 20.519,40
ANGRA 2 106 FAILED 1 REPAIRED 19.603,21
ANGRA 2 144 FAILED 2 REPAIRED 31.359,29
ANGRA 2 C033 FAILED 4 REPAIRED 15.435,98
ANGRA 2 H036 FAILED 11 FAILED 42.784,30 ANGRA 2 J027 DAMAGED 11 DAMAGED 35.971,50
SFA - REPAIRED
5. II - UAS Dry Storage Summary Schedule
S O N D J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J
Planejado
Previsto
Realizado
Transferência Angra 1
Nota: Cronograma Executivo Geral - rev. 1
LEGENDA
2020 2021
CONTRATAÇÕES
LICENCIAMENTO
EXECUÇÃO DE PROJETOS
IMPLEMENTAÇÃO
2017 2018 2019
Obras Preparatórias
Implantação
Transferência Angra 2
Status: 31/12/17
A T I V I D A D E S
2015 2016
27/08/2020
14/01/2021
PROCUREMENT
LICENCING
SUMMARY
EXECUTION
Civil Works
Implementation
Angra 2 SF transfer
Angra 1 SF transfer
Executed
Planned updated
Planned
Aug./2020
Jan./2021
~11 months of margin until completion of SFP capacity
5. III - Activities Summary – Transition Period of Angra 1
1. PRE-PLANNING 1.1. Licensing planning
• Certificate of Permanent Termination of Operation and Removal of SFA
• Post shutdown decommissioning activities report (PSDAR)
• Review of the DCE and Transition Period Costs
• Irradiated Fuel Management Plan (IFMP)
• License Termination Plan (LTP)
• Post Defueled Technical Specifications Request (PDTS)
• Permanent Shutdown Emergency Plan (PSEP)
• Physical Protection Plan for Permanent Shutdown and Exception Requests
• Prepare a Quality Management Plan without SFAs
• Requalification Program for Operators / Fuel Handling Training and Certification Program (CFH)
• Request exclusions from the nuclear insurance policy
• Specific Safety Analysis for the Transition Activities
• FSAR review considering permanent shutdown
1.2. Review of programs and procedures
1.3. Review and Analysis of HSA / Updated Radiometric Survey
1.4. Hazardous material survey and analysis
1.5. Preparation of contract with support consulting company
1.6. Planning for Cool and Dim Condition
1.7. Communication Plan
1.8. Human Resources Plan with organizational restructuring of the company during the TPA1.
2. PERMANENT SHUTDOWN ACTIVITIES 2.1. Plant Shutdown and Inspection
2.2. Removal of SF and materials
2.3. Draining and drying all systems that are unnecessary
2.4. Sampling for characterization of radiological inventory
2.5. Removal of fluids from systems (water, oils, etc.)
2.6. Chemical decontamination of systems for dose reduction (if applicable)
2.7. Removal of decontamination waste
2.8. Removal of combustible material
2.9. Removal of used resin
2.10. Removal of other radioactive waste from operations
2.11. Electrical isolation of equipment
2.12. Asset recovery: resale / transfer of plant equipment and components such as surplus stock to other licensed facilities (contaminated material) and
unlicensed (uncontaminated material)
3. EQUIPMENT CONTRACTS AND GENERAL MATERIALS 3.1. General equipment for dismantling
3.2. General equipment for decontamination of personnel and tools
3.3. General equipment for radiological protection
3.4. General Physical Security Equipment and Maintenance for Long Term Storage Safe Storage
3.5. Acquisition of casks for SFAs
3.6. Acquisition of transfer casks for LLW / ILW / HLW to the final repository (to be built)
4. SAFE STORAGE PREPARATION ACTIVITIES 4.1. Decontamination of areas and equipment to facilitate dismantling (if decided for specific cases)
4.2. Drainage of the SFP and decontamination (if applicable)
4.3. Dismantling and transfer of contaminated equipment and material for long-term storage / Final repository of radioactive waste
4.4. Sampling for the characterization of the radiological inventory in the facilities for the safestorage
4.5. Site reconfiguration, isolation and protective structures
4.6. Characterization of the radiological inventory for decommissioning and decontamination
4.7. Preparation of the temporary RW storage area (if necessary)
4.8. Removal of fuel handling equipment (if necessary)
4.9. Personal training
4.10. Asset recovery: Sale / transfer of the metal or materials and equipment saved or components for recycling or reuse (partial)
4.11. Cool and Dim Condition Implantation
4.12. Evaluation and removal of hotspots (where applicable)
4.13 SITE PHYSICAL SAFETY PLANNING, MONITORING AND MAINTENANCE DURING SAFE STORAGE
4.13.1. Operation of physical security and site surveillance
4.13.2. Inspection and maintenance of buildings and systems in operation
4.13.3. Site conservation
4.13.4. Energy and water supply
4.13.5. Radiological and environmental periodic survey
5. III - Activities Summary – Transition Period of Angra 1
5. PROCESSING RADIACTIVE WASTE, STORAGE AND DISPOSAL 5.1. Radioactive Waste processing, storage and safety analysis for disposal
5.2. Feasibility studies on waste transport
5.3. Special permissions, packaging and transportation
5.4. System fluids (water, oils, etc.) processing
5.5. Decontamination waste processing
5.6. Operation Fuel Material processing
5.7. Spent Resins processing
5.8. Other nuclear and hazardous materials from facility operations
5.9. Storage of waste from operation
5.10. Disposal
6. PROJECT MANAGEMENT, ENGINEERING AND SUPPORT 6.1. Mobilization and preparatory work
6.2. Project and engineering management services
6.3. Public relations
6.4. Support Services
6.5. Radiotiological Protection
6.6. Restructuring Human Resources
7. RESEARCH AND DEVELOPMENT 7.1. Research and development of the decontamination process, measurement of radioactivity and dismantling processes, tools and not usual equipment
7.2. Simulation and modeling of more complicated tasks
7.3. Search for international experiences and updated lessons learned
8. SPENT NUNCLEAR FUEL MANAGEMENT 8.1. SNF transportation to UAS
8.2. Transportation for final Disposal (when ready)
5. III - Activities Summary – Transition Period of Angra 1
Assumptions: • Experiences with the Transition from Operation to Decommissioning at NPPs on the U.S. (Kim &
McGrath, 2016)
>> 43,5% Human Resources - of the cost of the Decommissioning
• Actual Staff of Angra 1 operation and maintenance
• Medium Brazilian salary estimate + taxes and other tributes (still to be updated with
ETN real salaries)
• 3 to 5 years of Transition Period Duration
• Convervative estimative
5. IV - COST ESTIMATE FOR TPA1 – order of magnitude
Duração (meses) Total Cost TPA1 (order of magnitude) * 36 R$ 343.423.256 $ 105.668.694
48 R$ 457.897.674 $ 140.891.592
60 R$ 572.372.093 $ 176.114.490
>> Approximate staffing costs during transition period in U.S. - $25 Million/year
(Kim & McGrath, 2016)
* Transition Period Initial Planning for Angra 1 (Pinho, Bruno Estanqueira, 2018)
Link: http://www.con.ufrj.br/wp-content/uploads/2018/05/Disserta%C3%A7%C3%A3o-Bruno-Estanqueira-Pinho.pdf
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Confinamento
Thank you!
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Bruno Estanqueira Pinho Fuel Assembly and Safety Analysis Advisory Technical Directorate
+55 21 2588-7938