“legal and “basis of decommissioning” pablo andrade grossi ... · and “basis of...

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“Legal / Regulatory Framework”and “Basis of

Decommissioning”BRAZILPablo Andrade Grossi

Clédola Cassia O. de Tello

National Report

Contents� Introduction� Brazilian situation and international recommendations� The main lacks (what is needed)� What was done or has been done (decom. efforts)� Brazilian ongoing activities� Legal and Regulatory Framework� Basis of Decommissioning� IPR-R1 Research Reactor decommissioning plan and decommissioning strategy � Assessment of Radionuclide Inventory� Co-operation Policy

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INTRODUCTION� Four research reactors are operated by the federal

research institutes.

Oper.TRIGA-Mark I250IPR-R1Oper.ZPR TANK0.10IPEN-MB 01

Oper.POOL5,000.00IEA-R1Oper.ARGONAUTA0.20ARGONAUTA

STATUSTYPEPOWER (kW)FACILITY

INTRODUCTION� The life time life time for the main Brazilian RR was estimated (using MCSMCS) considering the burnburn--up rateup rate and the reactivityreactivity required for level of powerpower

� Life time = f(power, released energy, operation schedule)

~3 - 5%8 years at least250IPR-R1--0.10IPEN-MB 01

~30%10 years5,000.00IEA-R1--0.20ARGONAUTA

Burn-up(actual)

Life time (estimation)POWER (kW)FACILITY

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Brazilian Nuclear Situation- Although the national efforts to establish a

legal/regulatory framework concerning to all nuclear activities, the Brazilian situation is is not completely in compliancenot completely in compliance with the international recommendationsinternational recommendations.

Brazilian Nuclear Structure

Research Reactors

R&D Institutes

DPDResearch & Development DRS

Regutor and Lisencing

NATIONALCOMMISSION

FOR NUCLEAR ENERGY(CNEN)

MINISTRYOF

SCIENCE ANDTECHNOLOGY

INSTITUTE FORTHE ENVIRONEMENT

AND RENEWABLERESOURCES (IBAMA)

ENVIRONMENTMINISTRY

ANGRANuclear Power Plant

ELETROBRASTERMONUCLEAR

SA(ELETRONUCLEAR)

BRAZILIAN ELECTRICPOWER PLANTS

COMPANY(ELETROBRAS)

MINES & ENERGYMINISTRY

PRESIDENTOF

BRAZIL

Formalindependence was achieved

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�� Institutional independenceInstitutional independence of regulatory body (out of our competence level) ;� A complete and specificcomplete and specific legal and regulatory

framework to cover the Decommissioning issues (in special related to R Reactors);�� WellWell--structured and complete structured and complete

Decommissioning Plans for all Brazilian Research Reactors.

The main Brazilian lacks . . .

� Internal and National Standards; � Disassembly procedures and equipment;� Radiation safety assessment reports;� Spent fuel safe storage/transport package

(cask in development / wet storage) waste management, etc.

What was done or has been done (decommissioning efforts)

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� ”Developed Devices for Dismantling and Maintenance of IPR-R1 Research Reactor " (NI-AT4-004/95) 39 p. 1995.

� "Shielding and Criticality Safety Analyses of a Latin American Cask for Transportation and Interim Storage of Spent Fuel From Research Reactors ”, 2003.

� "Characterization of Burned Fuel of the TRIGA IPR – R1 Research Reactor Using Monteburns Code ", 2002.

� CDTN 0023 (Radioactive Waste Management)� CDTN (Radiation Protection Plan)


� National Report of Brazil for the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, 2005

� CNEN 3.01 (Basic Instructions for Radiation Protection)� CNEN 6.02 (Licensing of Radioactive Installations)� CNEN 6.05 (Management of Radioactive Wastes)� Safety Assessment Report Guidelines (CNEN-NE-1.08, CNEN-NE-1.09, CNEN-NE-1.11)


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Latin American Cask

Prototype – external view Prototype – internal view2 basket types (78 TRIGA or 21 MTR elements ) USD$ 60,000.00

Fuel Storage Pools(Assessment using MCS)

RadialView

AxialView

6 fuel in each pool

AluminiumSteelSoilWater

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12 pools for fuel storageAluminium + Steel

3m deep

Floor

Reactor Room

Reactor Pool

Aluminum10 mm

Concrete71.5 mm

Concrete203 mm

Steel6.3mm

Steel

Soil

Buried Reactor Pool

C

PCNC

Ground Level

Assessmentof type andamounts ofRadWaste

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RadionuclideInventory Assessment(Spent fuel)68 fuel elementsburn-up 6000 MWh

�� Interaction with Regulatory BodyInteraction with Regulatory Body in order to develop national regulations, standards and guidelines for RR Decommissioning;�� IntegrateIntegrate of the existent individual effortsindividual efforts

aiming to establish a Decommissioning establish a Decommissioning GroupGroup (matrix structure) to perform the Brazilian Decommissioning activities;� This group will perform decommissioningperform decommissioning

activities in a joint workactivities in a joint work;

Brazilian ongoing activities

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� Use the IPRIPR--R1 as a modelR1 as a model and after extending to all Brazilian Research Reactors, and other facilities; � Some initial steps on these activities were

done and all consulted stakeholders had all consulted stakeholders had interestinterest in such decommissioning tasks;

Brazilian ongoing activities

Legal and Regulatory Framework� The decision on levels for the release of

materials, buildings and site from the nuclear regulatory control is established in national regulations:� CNEN 3.01 (Basic Instructions for Radiation Protection)

� CNEN 6.02 (Licensing of Radioactive Installations);� CNEN 6.05 (Management of Radioactive Wastes);� Internal procedures.

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Legal and Regulatory Framework� The regulation establishes that the facility owner is total responsible for the decommissioning.

� The operator and regulator responsibilities are clearly assigned and established in the regulations.

� In the Brazilian Waste Management Program there are two important targets regarding to decommissioning:� revision of the legal and regulatory framework and development of the missing regulation

� construction of the repository

Basis of Decommissioning

� A preliminary Decommissioning Plan was already done, based in the IAEA`s guidelines.� This Decommissioning Plan is being now

completed with some existing documents and available information from different groups regarding to this subject .

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Basis of Decommissioning� The Decommissioning Strategy will be

decided between the two options:� Immediate total dismantling� Safe enclosure� Since the reactor lifetime is about at least 10

years, the strategy will be selected just before the shutdown considering the legislation, political and economical situation. The most probable option is the immediate dismantling.


� An attempt to assess the radionuclideinventory was made simulating the end of life of fuel elements (spent fuel). � Then the inventory assessment for the

activation of the structures and shielding can be carried out by the same group, using e.g. Monte Carlo Simulation.

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� The preliminary qualitative assessment showed that the radioactive waste could be some concrete, aluminum and stainless steel structural pieces and pumps, contaminatedwith U, fission products and activation products. � The assessment of the waste amount can be

done through simulation program.


� The necessary equipment, tools and instruments to dismantling the reactor are available either in CDTN or to be hiring. � A description of some of these materials and

procedures to use them are presented in the document: "Developed Devices for Dismantling and Maintenance of IPR-R1 Research Reactor" (NI-AT4-004/95) 39 p. 1995.

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Basis of Decommissioning� In CDTN there is a group responsible for the radioactive and hazardous wastes. � There are some established procedures for

sampling, treating, and conditioning the wastes and data recording. � Some facilities to treat the waste are already

available: Bailing, crushing, cementation, chemical precipitation and immobilisation.


Waste Treatment

Installations

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Basis of Decommissioning� CDTN has an Intermediate Storage Facility,

which the area is 30m x 15m, and 7m high. This facility has the requirements to store the radioactive waste.� Other materials will be classified as

recyclable, regular or hazardous material and treated according to the environmentalstandards (10.000 ABNT Norm Series). � There are already some systems to store

safely and temporally all activated materials.

Basis of DecommissioningIntermediate

Storage Facility

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� Some technical alternatives has been made for spent fuel storage and transport (cask / wet storage), and other packages, which were developed and licensed for theGoiania's accident, could be also used in emergency cases.


Package developed to receive the 137Cs source from the Goiania’s radiological accident.

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� For the end point the most suitable optionwould be to use the area for nuclear proposes in view of the fact that this reactor area is in the CDTN's site, and there are often demands for new nuclear facilities.

Basis of Decommissioning� Until now the cost estimation has not been

done. � This will be one of the task to be addressed

by the proposed Decommissioning Group. � The IPR-R1 Reactor belongs to CDTN, one

research institute of CNEN, and then the decommissioning costs will be provided by CNEN (CNEN is a institution of the Science and Technology Ministry).

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Basis of Decommissioning� Traditionally CDTN and CNEN have as

practice to work together with other countriesand institutions. � In a project to manage the small spent sources from medical application in Latin America CDTN’s tools are brought to other countries in order to make the job.

� This experience is common among Latin American countries and it has been shown as a good practice.


� Some companies in Brazil have know-how and resources to develop and implement big infrastructure and engineering projects. � Then they could be hired to help in the

decommissioning activities, if necessary.

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Summary� This project is helping to make us aware about the decommissioning of research reactors and other installations.

� It was verified that some people are already concerned about this issue, and the need to create a Decommissioning Group.

� As the regulatory body takes part of the R2D2P, the decommissioning regulation will be prepared to fill this lack.

Thank you for your attention

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National Report of Brazilfor the

Joint Convention on the safety of spent fuel management and on the

safety of radioactive waste management

Describes the decommissioning of one nuclear facility in Brazil:

USAM - Monazite Sand Treatment Facility

Legal and Regulatory Framework

� Nuclear Facilities Licensing(CNEN-NE-1.04)


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� Safety Assessment Report Guidelines(CNEN-NE-1.08, CNEN-NE-1.09, CNEN-NE-1.11)


� 3.01 (Basic Instructions for Radiation Protection)� 6.02 (Licensing of Radioactive Installations)� 6.05 (Management of Radioactive Wastes)


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� Brazil: A Country Profile on Sustaintable Energy Development

Discussion about Nuclear Power Plants Decommissionig


Legal and Regulatory FrameworkIn Brazil In Brazil when the national regulations

don’t cover a specific nuclear and radioactive issues the consensus is to:consensus is to:

Use the IAEA recommendationsUse the IAEA recommendations.

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DECOMMISSIONING PLAN� Brazil do not have a not have a

decommissioning policy.decommissioning policy.

� Then IPR-R1 did not have a decommissioning plan as part of its original licensing documentation.

DECOMMISSIONING PLAN�� IntroductionIntroduction;

donedone�� Facility descriptionFacility description: Physical description of the

site and facility; operational history; systems and equipment; radioactive and toxic material inventory;donedone

�� Decommissioning strategy:Decommissioning strategy:partly donepartly done

�� Project management:Project management: resources; organization and responsibilities; review and monitoring arrangements; training and qualifications; reporting and records;to be doneto be done

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DECOMMISSIONING PLAN�� Decommissioning activities:Decommissioning activities: description and

schedule of phases and tasks; decontamination activities; dismantling; waste management; surveillance and maintenance programs; to be doneto be done

�� Safety assessment:Safety assessment: dose predictions for tasks; demonstration of ALARA for tasks; radiation monitoring and protection system; physical security and materials control; management of safety; risk analysis; operating rules and instructions; justification of safety for workers, general population, and environment; to be done to be done ((established norm and proceduresestablished norm and procedures by CNEN 3.01 and CDTN, internal competencyinternal competency identified))

DECOMMISSIONING PLAN�� Environmental impact assessment:Environmental impact assessment:

to be done to be done (CDTNCDTN has environmental protection staffstaff)�� Quality assurance program:Quality assurance program:

partly done partly done (application of the existing procedures)�� Radiation protection and safety program:Radiation protection and safety program:partly done partly done (CDTNCDTN has radiological and environmental

protection staffstaff)�� Radiological criteria clearance:Radiological criteria clearance:

partly done partly done (exemption levels establishedexemption levels established and CDTNCDTNhas radiological and environmental protection staffstaff).

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DECOMMISSIONING STRATEGY� There are two possible strategiestwo possible strategies, since

the reactor lifetimelifetime is about at least 10 at least 10 years.years.�� Immediate total dismantling Immediate total dismantling (green field)(green field)�� Safe enclosure Safe enclosure (restricted uses, brown field)(restricted uses, brown field)� Just before the shutdown the strategy will

be selected consideringselected considering the legislation, political and economical situationsituation.

Reactor LocationFederal University Campus

CDTNCDTN(site)(site)

RR Building

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Reactor Location

RR Building

Restricted AreaUnrestricted Area

Reactor Facility

Library OfficesCafeteria

Laboratories

Reactor Building

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CORE

Reactor Room

Reactor Facility

Laboratories

End state ofdecommissioning activities� The final goal of the first strategyfirst strategy is the unrestricted use of the localunrestricted use of the local. � In the second strategysecond strategy initially the local will be classified for restricted use (brown field)restricted use (brown field)

(as a historical piece of a TRIGA technologyas a historical piece of a TRIGA technology)After some decades the final goal will be the unrestricted use unrestricted use of the place, after the full , after the full decontaminationdecontamination.

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Cost and Funding�� The IPRThe IPR--R1 Reactor belongs to CDTNR1 Reactor belongs to CDTN, one

research institute of CNEN, then the decommissioning costs will be provided by decommissioning costs will be provided by CNENCNEN. �� CNEN is a public institutionCNEN is a public institution of the Science

and Technology Ministry, so:�� Decommissioning CostsDecommissioning Costs should be

estimated in advance and the budgetthe budget would be defined in accordance of the previewed previewed institutional projectinstitutional project.

� The dismantling will occur only in the dismantling will occur only in the facility rooms (when necessary)facility rooms (when necessary) because the RR building is integrate with laboratories, offices, a library and a cafeteria.� The radioactive wastesradioactive wastes will be classified and

collected following the regulatory body normregulatory body norm:CNEN 6.05 – Radioactive Waste Management.

Management of materials/waste

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� Bailing, crushing, cementation, chemical precipitation and immobilization are the treatment options available in CDTNtreatment options available in CDTN. � Low and intermediate waste will be stored in

the Intermediate Storage Facility in CDTN .Intermediate Storage Facility in CDTN .� Other materials will be classified as recyclable, regular or hazardous materialrecyclable, regular or hazardous materialand treated according to the environmental standards (10.000 ABNT Norm Series10.000 ABNT Norm Series).

Management of materials/waste

Release from nuclear regulatory control�� The radiological protection staff will define The radiological protection staff will define the release criteriathe release criteria for material and facility rooms following the regulatory body normsfollowing the regulatory body norms:� 3.01 (Basic Instructions for Radiation Protection)� 6.02 (Licensing of Radioactive Installations)� 6.05 (Management of Radioactive Wastes), and

internal procedures.

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Decommissioning expertiseand tools�� There was already a decommissioning There was already a decommissioning

experience in Brazilexperience in Brazil, done in USAM Monazite Sand Treatment Facility.� This facility has produced rare earth since

1950’s. The area is now free of regulatory The area is now free of regulatory control for unrestricted usecontrol for unrestricted use. �� CDTN has expertiseCDTN has expertise to perform the

majority of decommissioning works, and for other ones there are enough enterprises in Brazil to carry out them.

CONCLUSION�� Now is time for IPRNow is time for IPR--R1 decommissioning R1 decommissioning planning.planning.� The main taskmain task will be the management of management of internal groupsinternal groups (matrix structure) to develop the decommissioning planningdevelop the decommissioning planningand in the future perform the decommissioning activitiesdecommissioning activities in a joint joint workwork.

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CONCLUSION� There was a International Congress in

Santos, Brazil, in October and we presented the paper “IPR-R1 TRIGA Research Reactor Decommissioning: Preliminary Plan“. The objective is to join dispersed expertise in Brazil and know about isolated experiences in decommissioning.

Figura 3.4.3 - Vareta Combustível do Reator TRIGA

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IPR-R1 Reactor

IPR-R1Core

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Spent Fuel Elements - RR� IEA-R1 - Part of its spent fuel was returned to USA, in 1999. � Storage facilities at IEA-R1 consist on racks in the reactor

pool (capacity of 156 assemblies). � 21 storage positions are occupied (7-10 years can be full). � The option to send SFA (Spent Fuel Assembly) to USA will

cease, and a national solution will have to be adopted.

Spent Fuel Elements - RRIAEA REGIONAL PROJECT – OBJECTIVES

� Provide the basic conditions to define a regional strategy for managing spent fuel;

� Provide solutions taking into consideration the economic and technological reality of the countries involved,

� Determine the basic conditions for managing RR spent fuel during operational and interim storage as well as final disposal,

� Establish forms of regional cooperation for spent fuel characterization, safety, regulation and public communication.

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Spent Fuel Elements - RR� Argonauta and IPR-1 � at the moment due to the low nominal power, except for

aging concerns, spent fuel is not a problem.

� IPR-1 - the first fuel assembly replacement of the reactor is expected to occur only in 2010.

IPR R1 CORE

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