romania’s national nuclear and waste management program · support for the nuclear energy...

Romania’s National Nuclear and

Waste Management Program

IFNEC Infrastructure Development Working Group May 8, 2014 , Bucharest

Stela DIACONU Senior Expert ANDR, Romania

CONTENT Main institutions in Romanian nuclear field IFIN-HH INR-Pitesti S.N. Nuclearelectrica S.A. CITON CNCAN Radioactive Waste Management Overview Institutional and legal framework National Strategy for RWM Sources and types of RW Storage and Disposal Facilities Public Involvement ANDR short-time objectives New Challenges

1949 - The Institute of Physics of the Romanian Academy was established

1956 - The Physics Institute of the Academy split into an

Institute of Atomic Physics (IFA), located at Magurele, outside Bucharest, under Hulubei's direction, and the Bucharest Institute of Physics (IFB), based at the Faculty of Physics of the Bucharest University

1957 - VVRS fission reactor and a U120 cyclotron, both of

Soviet make, were put into service on the IFA site, at Magurele

1957 - Romania - founding member of the International Atomic Energy Agency

1997 - the reactor was shut down, waiting for decommissioning 2001 - the Board of Administration of IFIN-HH decided the permanent shutdown and starting of the decommissioning preparation actions. 2002 - the Romanian Government decide the final shutdown for the decommissioning of the Nuclear Reactor VVR-S IFIN-HH develops Basic and Applied Physics Research activities.

„HORIA HULUBEI” NATIONAL INSTITUTE OF PHYSICS AND NUCLEAR ENGINEERING” (IFIN-HH)

IFIN-HH ELI-NP Extreme Light Infrastructure-Nuclear Physics

A very high intensity laser, where beams from two 10 PW lasers are coherently added to get intensities of the order of 1023 - 1024 W/cm2 and electrical fields of 1015 V/m

European laboratory to consistently investigate a very broad range of science domains

• Theoretical Physics • Atomic, Nuclear & Particle Physics • Life & Environmental Physics • Radioisotopes & Radiopharmaceuticals • Technological Irradiations • Radioactive Waste Treatment & Storage • Decommissioning of Nuclear Facilities • Nuclear engineering • Training in nuclear activities

R&D activities:

Institute for Nuclear Research - founded in 1971 – Mioveni site

Support for National Nuclear Power Program: technical support institute for the safe operation of the NPP; fuel technology and testing; equipment production and testing; development of new technologies, methods, computer codes directed

towards end-products or services with applications in NPP; operation and development of experimental infrastructure; basic and applied research; education and training.

INR - Institute for Nuclear Research

Research Reactors Post-irradiation Examination Laboratory Material Testing and Nuclear Fuel Fabrication Radioactive Waste Treatment Laboratories Out-of-Pile Testing Laboratories

INR - Research Infrastructure

INR - ALFRED Project

Main objective: to demonstrate the viability of LFR technology - to perform all preparatory activities (technical design, licensing, siting,…) - to build a demonstration installation of 125 MWe

SNN S.A. BUCHAREST

CERNAVODA NUCLEAR POWER PLANT

PITESTI NUCLEAR FUEL FACILITY

• SAFE & EFFICIENT OPERATION OF UNITS 1 & 2 – CANDU 6

• MANAGEMENT OF ALL SNN ASSETS IN CERNAVODA, INCLUDING PRESERVATION

OF UNITS 3 – 5 & HEATING SUPPLIER

• NUCLEAR FUEL FABRICATION

SOCIETATEA NATIONALA NUCLEARELECTRICA S.A. (SNN)

THE OPERATOR OF NPP

8 by courtesy of S.N. Nuclearelectrica S.A.

Power MW(e)

Type Operation since

Cernavoda 1 706,5 PHWR 1996

Cernavoda 2 704,8 PHWR 2007

Cernavoda 3 720 PHWR Under construction

Cernavoda 4 720 PHWR Under construction

Cernavoda 5 706,5 PHWR Not any more considered

THE NUCLEAR POWER IN ROMANIA

CERNAVODA NUCLEAR POWER PLANT


ELECTRICAL POWER PRODUCTION IN 2012 – BREAKDOWN BY RESOURCE TYPE

STATUS OF THE ELECTRICITY PRODUCTION IN ROMANIA (2013 – BREAKDOWN BY RESOURCE TYPE)

10

19,83

25,76

15,57

8,01

29,71

0,52

0,61

Nuclear Hydro Hydrocarbons Wind Coal Biomass Photovoltaic

by courtesy of S.N. Nuclearelectrica S.A.

CERNAVODA NUCLEAR POWER PLANT UNITS 1 & 2 PERFORMANCE

GROSS CAPACITY FACTOR U1+U2 (%)

12

0

20

40

60

80

100

GCF U1 97,62 84,8 100,10 91,53 99,67 87,16 99,40 101,02

GCF U2 93,23 96,92 90,6 97,24 91,07 98,47 89,15 100,42

GCF U1+U2 95,37 90,87 95,35 94,38 95,37 92,82 94,28 100,72

2007 2008 2009 2010 2011 2012 2013 2014 Q1

PLANT PERFORMANCE


IMPACT ON PEOPLE & ENVIRONMENT CUMMULATED RELEASES OF RADIOACTIVE EFFLUENTS U1&U2 (μSv)

LEGAL DOSE FOR POPULATION 1000 µSv AUTHORISATION CONSTRAINT 100 µSv THE AVERAGE ANNUAL DOSE 0,57% FROM THE LEGAL DOSE (16 YEAR ROLLING)

13

0

2

4

6

8

10

12

Radioactiv e ef f luents U1 10,45 4,82 7,07 3,98 2,24 4,25 3,53 1,014

Radioactiv e ef f luents U2 0,15 0,88 1,44 1,75 1,37 2,05 1,99 0,567

Total 10,6 5,7 8,51 5,73 3,61 6,30 5,52 1,58

2007 2008 2009 2010 2011 2012 2013 2014 Q1


COLLECTIVE RADIATION EXPOSURE: COMPARISON OF CANDU-6 UNITS MEAN VALUE (man·mSv)/ UNIT

14

0

200

400

600

800

1000

1200

1400

1600

1800

2000

Cernav oda NPP 270,8 344,5 242,5 393,6 196,4 459 254,5 29,08

CANDU-6 mean v alue 1058 1816 1316 1108 747

2007 2008 2009 2010 2011 2012 2013 2014 Q1


Center of Technology for Nuclear Projects (CITON)

CITON is part of the Autonomous Authority for Technologies for Nuclear Activities (RATEN)

Main activity : – Design and Engineering works for the construction –

installation, commissioning and operation and maintenance of nuclear power plants and other nuclear facilities

– Research and Development studies associated with the implementation of National Nuclear Program

CITON as a full-service engineering company can assist the

customers with all phases of projects implementation including development support and EPC interconnection.

National Commission for Nuclear Activities Control (CNCAN)

the regulatory authority in the

nuclear field elaborates the strategy and the

policy for regulation, licensing and control with regard to: – nuclear safety – radiological safety – non-proliferation of nuclear

weapons – physical protection of nuclear

installations and materials – transport of radioactive

materials – safe management of

radioactive waste and spent fuel

Radioactive Waste Management

Institutional responsibilities in RWM

Waste producers – Responsible for predisposal activities of SNF and RW and for decommissioning of

their facilities; – Bear the expenses related to the collection, handling, transport, treatment,

conditioning, storage and disposal of its wastes – Pay the annual contributions to the funds for disposal of SNF and RW and for

decommissioning of nuclear facilities

National Commission For Nuclear Activities Control (CNCAN) – regulatory body in the nuclear field

Nuclear Agency and for Radioactive Waste (ANDR) – Support for the nuclear energy development in Romania (power and non –

power applications), exclusively for peaceful purposes – Responsible for disposal of radioactive waste (RW) and spent nuclear fuel (SNF),

and ensure at national level the coordination of the nuclear installations decommissioning processes

Legal framework

Law no. 111/1996 on the safe development, regulation, authorization and control of nuclear activities, republished, with the subsequent amendments and completions

Order no.844/2004 regarding the approval of “National Strategy on Medium and Long Term Management of Spent Nuclear Fuel and Radioactive Waste, including the Disposal and Decommissioning of Nuclear and Radiological Facilities”

Law no. 105/1999 for ratifying the Joint Convention on the safe management of spent fuel and on the safe management of radioactive waste

Law 378/2013 for the transposition of Council Directive 2011/70/Euratom establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste

CNCAN norms and regulations

Aarhus and Espoo Conventions

Environmental Protection Law 265/2006

G.D. 1076/2004 on strategical environmental assessment procedure

G.D. 445/2009 on environmental impact procedure

Elements of RWM Policy

Spent fuel produced by NPP’s shall be stored for limited period in dry

storage facilities; after the storage period spent nuclear fuel shall be disposed of in a deep geological repository

Spent fuel produced by research reactors shall be returned back to origin countries

LILW-SL shall be disposed of in a near surface repository

VLLW could be disposed of in less complex arrangement than LILW-SL

LILW-LL shall be disposed in a deep geological repository

LILW-SL

INTERIM STORAGE

ON NPP SITE

LILW N-S REPOSITORY

NPP TREATMENT

FACILITY

NPP

EXISTING PLANNED

RR TREATMENT FACILITIES

BAITA BIHOR REPOSITORY

RR / INSTITUTIONAL

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LILW-LL

NPP Mining

INTERIM STORAGE

ON NPP SITE

NPP TREATMENT

FACILITY

The National Strategy for Safe Management of Radioactive Waste

- Low & Intermediate Level Waste -

Milling

DISPOSAL IN GEOLOGICAL REPOSITORY

STORAGE IN TAILING PONDS

CLOSURE OF TAILING

PONDS

RR / INSTITUTIONAL

INTERIM STORAGE

ON RRs SITE

RR TREATMENT FACILITIES

NUCLEAR FUEL PLANT

DISPOSAL IN SURFACE

TRENCHES

IN SITU CAPPING /

RELOCATING IN MINES

The strategy for the management of spent nuclear fuel resulted from operation both of NPP and of research reactors

22

S.N. NUCLEARELECTRICA S.A. CNE Cernavoda (Unit 1 & 2)

spent nuclear fuel bundles resulting from the operation of 2 CANDU nuclear power reactors radioactive waste (solid, liquid, mixed) resulting from the operation and maintenance

radioactive waste resulting from the decommissioning FCN Piteşti Branch

radioactive waste (solid and liquid) resulting from the production of CANDU type nuclear fuel „HORIA HULUBEI” NATIONAL INSTITUTE OF PHYSICS AND NUCLEAR ENGINEERING” (IFIN-HH) spent nuclear fuel assemblies resulting from the operation of VVR-S nuclear research reactor

radioactive waste (liquid, solid, spent sealed sources) generated by nuclear and radiological facilities from IFIN-HH

radioactive waste resulting from the decommissioning of VVR-S nuclear research reactor

ROMANIAN AUTHORITY FOR TECHNOLOGIES FOR NUCLEAR ENERGY (RATEN) Institute for Nuclear Research Piteşti (INR)

spent nuclear fuel elements resulting from the operation of TRIGA nuclear research reactor radioactive waste (solid, liquid, spent sealed sources) generated by nuclear and radiological facilities from INR

NATIONAL URANIUM COMPANY SA (CNU) Feldioara Branch

radioactive sludge resulting from the uranium ore processing solid radioactive waste generated by nuclear/radiological facilities of the branch

Suceava, Banat and Bihor Branches sterile and radioactive rocks resulting from the uranium ores research and extraction activities

OTHER GENERATORS (MINOR) OF RADIOACTIVE WASTE ACROSS ROMANIA Medicine, industry, agriculture…

radioactive waste (solid, liquid, spent sealed sources) generated by nuclear and radiological facilities from hospitals, factories, laboratories

Sources and Types of Radioactive Waste

Storage Facilities

RADIOACTIVE WASTE STORAGE SOLUTION

IN ORDER TO REDUCE THE STORAGE VOLUME FOR THE LOW AND MEDIUM LEVEL RADIOACTIVE WASTE, THEY ARE COMPACTED AND THEN STORED IN AN RADIOACTIVE WASTE INTERIM STORAGE, ON SITE.


SOLID RADIOACTIVE WASTE INTERIM STORAGE (INSIDE VIEW)


QUADRICELL A CONCRETE REINFORCED STRUCTURE WITH 8 LOCATIONS FOR STORAGE, EACH OF THEM HAVING A SQUARE BASE WITH THE FOLLOWING DIMENSIONS 2.3 X 2.3 X 2.5 M. EACH CELL HAS A CONTAINER HAVING SQUARE FORM IN WHICH ARE STORED ITEMS THAT ARE VERY CONTAMINATED OR VERY LARGE.

SPENT FILTERS STORAGE IS A CONCRETE REINFORCED BUILDING WITH THE FOLLOWING DIMENSIONS: 15 X 15 X 4.5 M. THE INSIDE OF THE STRUCTURE IS PROVIDED WITH CARBON STEEL PIPES HAVING COVERS. THE STORAGE IS COVERED WITH CONCRETE SLABS. THIS FACILITY IS DESIGNED FOR THE FILTER CARTRIDGES FROM THE PURIFICATION SYSTEM OF THE PLANT.


RADIOACTIVE WASTE STORAGE SOLUTION

ON DECEMBER 31, 2013 IN THE SPENT FUEL INVENTORIES WERE:

34,000 IRRADIATED FUEL BUNDLES IN THE BAYS OF UNIT 1, AND

31,000 IRRADIATED FUEL BUNDLES IN THE BAYS OF UNIT 2. 28 by courtesy of S.N. Nuclearelectrica S.A.

RADIOACTIVE WASTE STORAGE SOLUTION AFTER 7 YEARS OF COOLING IN THE SPENT FUEL BAY, THE NUCLEAR FUEL

REMOVED FROM THE REACTOR IS TRANSFERRED IN AN INTERMEDIATE DRY SPENT FUEL STORAGE, ON SITE.

29

ON DECEMBER 31, 2013, AT THE DRY STORAGE FACILITY THERE WERE 55,000 IRRADIATED FUEL BUNDLES. by courtesy of S.N. Nuclearelectrica S.A.

Existing and Planned Disposal Facilities

DNDR Baita Bihor

intended exclusively for the disposal of low and intermediate level institutional radioactive waste

situated at 840m altitude, in two abandoned mine galleries of Băiţa uranium ore exploration

operational since 1985 and will be able to host about 21.000 standard containers (220 L steel drums) with institutional radioactive waste content

designed for disposal of about 5.000 m3 low and intermediate level institutional radioactive waste, conditioned in standard Portland cement and stored in drums (mostly 220 L steel drums, but also 320 L and 400 L drums)

under the administration of IFIH-HH

Estimated time of closure: 2025

DFDSMA General view of the proposed repository Location: Saligny site inside the exclusion zone of the Cernavoda NPP Land owners: Saligny Local Council and private owners Repository area: about 40 ha Disposal concept: near surface similar with L’Aube (France), or El Cabril (Spain) repositories Disposal capacity: 122,000 m3

Waste inventory: LILW-SL with limited quantities of LILW-LL, generated by operation, refurbishment and decommissioning of 4 units of Cernavoda NPP. Note: In order to assess the capacity of DFDSMA repository to host some institutional waste after closure of Baita Bihor national repository, possible changes in the technical documentation are under analysis.

DFDSMA - Site characterization

Site characteristics on geology, hydrogeology, geochemistry, tectonics, seismicity, surface processes, meteorology, climate and human activities impact lead to the conclusion that Saligny site has the potential to be suitable for a near-surface repository.

DFDSMA conceptual design

maximum 64 disposal cells (rectangular array of 8x8): Inside dimensions of a cell: 27,9 m x 15,2 m x 5,1 m

384 disposal modules per disposal cell (rectangular array of 8x16 on three levels):

A single type of disposal module: a cubical fibre-reinforced concrete container outside dimensions of a module: 1,7m x 1,7m x 1,7m (5 m3 outside volume) loading volume: 3 m3

DFDSMA repository project

Disposal cells: •are designed to withstand earthquakes; •are placed in an unsaturated zone well above the highest level of water table (protection from groundwater infiltration); •have a foundation consisting of an impermeable concrete pad with an integrated drain (allow any infiltrated water to run off by gravity to the water collection system where the presence and activity of water can by monitored); •are covered by temporary mobile shelters during loading period; •are backfilled with sand when all modules are in place; •are covered and coated with waterproof material that will serve as temporary cover until final cap is constructed.

NEXT STEPS IN THE DEVELOPMENT OF THE NEAR-SURFACE REPOSITORY PROGRAM

• Getting different agreements / authorisations from different authorities; (PUZ, environmental impact assessment , etc.)

• Implementation of an improved, up-dated communication strategy in order to increase the public acceptance

• Prepare a business model

• Governmental Decision to define the project and to establish the project company

Geological Disposal

According to the current RWM Strategy, a geological repository is the disposal solution for the SNF generated by Cernavoda NPP , for the HLW and for LL-LILW;

The facility should start to operate in 2055

The Geological Disposal Program is in early stage of development

6 geological formations were identified, potentially favourable to host the geological repository, namely: the green schists from Dobrogea, granite, basalt, clay, salt and

volcanic stuff.

Between 2007-2008 a technical project of cooperation with IAEA was carried out, entitled “Developing a geological disposal concept for spent nuclear fuel in Romania” (TC ROM 3/005). Among its main results we can mention:

– The analysis of the geological information existing in Romania from the point of view of the possibilities to select the potential host-rocks for the geological repository;

– The properties analysis of green schists from Central Dobrogea, a possible site of the future geological repository, carried out in the NAGRA laboratories (Switzerland);

– Laying down a “roadmap” including the activities to be developed in the future for selecting the site for the geological repository and for its construction;

Road map should be improved and R&D needs to be defined, and, in this respect a “National Workshop on Geological Disposal Planning” was organized in the frame of IAEA TC Project ROM9031, in December last year

In order to up-date the RWM National Strategy, other options are analyzed, such as recycling the spent nuclear fuel generated by the CANDU Units of Cernavoda NPP

Geological Disposal (cont)

radioactive waste repositories : ways to protect human and

natural environment fears and worries

exacerbated perception of the risk two main components: a rational one and an emotional one

both should be addressed in an efficient communication process

with the stakeholders stakeholder: any actor – institution, group or individual, with an

interest or with a role to play in the process

COMMUNICATION PROCESS RELATED TO RW MANAGEMENT

Stakeholders Involvement Approaches

-implementation of the repositories showed delays or even failed -FSC, GMF, COWAM, CIP, RISCOM, TRUSTNET, RISKGOV, IPPA -Decide-Announce-Defend - Engage-Interact-Cooperate Recommendations - To create a framework for public involvement and to perform an inclusive governance;

-To involve the public as early as possible in the process;

-To provide added value to the host community.

ANDR Communication Strategy

Specific Objectives related to RWM A correct information of the general and local public regarding the

radioactive waste issue in Romania and how this issue is solved abroad; Diminishing of public fears concerning radioactive waste by providing

exact and clear information, timely and in appropriate language; Gaining and maintaining the public’s confidence in ANDR Highlighting the clear allocation of the activities and the attributions of

ANDR and of the other institutions from the field (CNCAN, waste producers);

Promotion of the fact that ANDR is not a radioactive waste producer but it makes a public service in identifying and implementing the optimal solutions for safe management of radioactive waste, ensuring protection conditions for workers, public and environment;

Establishment and maintaining good cooperation relationships with the institutions involved in this field, from the country and from abroad;

Getting public acceptance regarding the siting, construction, operation and closure of the radioactive waste repositories.

Implemented steps

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• Continuing the Saligny repository project Getting the siting license for siting a near surface radioactive waste disposal facility in Saligny Set-up the project company

• Development of a strategy for safe management of SNF Possibility to recycle the CANDU used fuel

• Coordination of decommissioning at Magurele VVR reactor

Approving documentation and coordinate second stage of decommission

• Strengthening the efforts to increase the Public Acceptance for Radioactive Waste Repositories Set–up and implement a more efficient communication strategy Possibility to start local social programmes

ANDR short-term objectives

44

• Updating the national radioactive waste inventory;

• Performing auditing and verifications to the main waste producers;

• Review the fee for safe management of SNF and RW and decommissioning of nuclear and radiological installations;

• Updating the national strategy / programme for safe management of SNF and RW

ANDR short-term objectives

NEW CHALLENGES

ELI-NP Extreme Light Infrastructure-Nuclear Physics

ALFRED The European Lead Fast Reactor Demonstrator

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