inpro dialogue forum on cooperative approaches to the back

INPRO Dialogue Forum on Cooperative Approaches to the Back End of

the Nuclear Fuel Cycle: drivers and legal, institutional and financial

impediments

26-29 May 2015 IAEA Headquarters, Vienna, Austria

Vienna International Centre (VIC)

of 58

UO2 Powder

Plant

Nuclear Research Institute

VVRS Reactor Cernavoda NPP

Heavy Water Plant

The Ministry of Economy, Commerce and Trade: management of the back

end of the nuclear fuel cycle, including remediation related activities; The Ministry of Energy: nuclear energy production sector, nuclear research &

engineering, nuclear fuel; The Ministry of the Environment: specific responsibilities in the licensing

and control of nuclear installations; CNCAN: the national authority competent in exercising regulation, licensing

and control in the nuclear field; Nuclear Agency for Radioactive Waste (ANDR):

National authority under the supervision of the Ministry of Economy;

responsible for: promotion, development and monitoring the nuclear activities exclusively for peaceful

purposes;

disposal of SNF and RW in Romania;

The waste producers:

Responsible for predisposal activities;

shall bear the expenses related to the collection, handling, transport,

treatment, conditioning, storage and disposal of the waste they have

produced

Main organisations

Romanian Nuclear Fuel Cycle Facilities

Mining

Uranium

Ore

Extraction

Feldioara

Conversion

Factory

Conversion

Pitesti Nuclear

Fuel Factory

Fuel

Fabrication

Drobeta Turnu-Severin

Heavy Water Factory

Heavy Water Production

Cernavoda NPP Units

1 and 2

Electricity Production

Spent Fuel Disposal

The solution is not yet

decided

Cernavoda

Dry Storage Facility

Spent Fuel Storage

The CANDU 6 power reactor was designed specifically for electricity production, unlike other major reactor types that evolved from other uses.

This focused development is one of the reasons that CANDU has such high fuel efficiency.

CANDU 6 is AECL's 700 MWe class nuclear power reactor. The first CANDU 6 plants went into service in the early 1980’s as leading-edge technology, and the design has continuously evolved since to maintain superior technology and performance.

The CANDU 6 power reactor uses nuclear fission process to produce the necessary energy.

The CANDU 6 power reactor

Nuclear Spent Fuel Storage

Cernavoda NPP Spent fuel bundle inventories on December 31, 2012:

Wet Storage:

- about 34,000 Irradiated Fuel Bundles in the Bays of Unit #1, and

- about 26,000 Irradiated Fuel Bundles in the Bays if Unit #2.

Dry Storage - IDSFS : 50,000 Irradiated Fuel Bundles.

Main Storage Bay filling rate (discharge tare): about 5,200 bundles/year/unit

1. Nuclear Power Plant (NPP)

SNN/CNE Cernavoda – U1, CANDU type, 720MWe, in operation from 1996;

SNN/CNE Cernavoda – U2, CANDU type, 720MWe , in operation from 2007;

SNN/CNE Cernavoda –U3&4, CANDU type: to be constructed by 2020;

2. Research reactors (RR)

RAAN/SCN Pitesti, TRIGA type, 14 MW, in operation from 1979

IFIN-HH Magurele, VVR-S type, shutdown in 1997, under decommissioning

3. Mining and milling (M&M)

CNU, various sites/uranium ores extraction mines

CNU/Feldioara, uranium ores processing plant

4. Nuclear Fuel Plant (NFP)

FCN Pitesti, CANDU type fuel fabrication plant

5. Institutional field

Medicine, Industry, Universities, Agricultural

Sources of RW

SNF from VVRS Research Reactor

An important step through the decommissioning of the VVRS RR from Magurele has been made by the repatriation of entire inventory of SF into the Russian Federation. First shipment of HEU SF has been finalised in 2009 under the GTRI programme, conducted by USDOE , NNSA, followed in 2012 by three shipments of LEU SF, fully implemented and financed by Romania.

ANDR main responsibilities (1/3)

• draws up and reviews, at least every 5 years, the National medium and long term strategy on the safe management of SNF and RW, which it forwards for approval to the Ministry of Economy, and monitors its implementation;

• is directly liable for the set up of the repositories for the disposal of RW; the repositories are in the patrimony and administration of ANDR;

• ensures, directly or by means of third parties, the design, construction, commissioning, operation, closing and post-closing monitoring of the repository of RW;

• ensures the set up and annual update of a national data base regarding the quantities, types of generated RW, including the ones resulting from the decommissioning of the nuclear and radiological facilities;

• approves the documentations and procedures drawn up by the holders of license, related to the stages of the safe management of SNF and of RW, in order to comply with the WAC for disposal;

• draws up the WAC for the disposal of RW and subjects them to the approval of CNCAN;


• ensures, directly or by means of third parties, for the disposal, the

execution of services of safe management of:

• the orphan sources of nuclear radiations;

• historical RW resulting from past practices;

• RW resulting from incidents and nuclear accidents;

• the SNF and RW from the economic operators which are

bankrupt or in official winding up;

• ensure, directly or by means of third parties, the physical protection of

the repositories of RW;

• performs audits at the main generators of radioactive waste in order

to ensure the compliance of the activities of safe management of RW

with WAC;

• monitors the radioactivity of the environment in the area of the

repositories in order to protect the population and the environment;


• periodically checks, for reporting purposes, according to the

regulations in force, the stage of accumulation of the financial

resources designated to the management of the SNF and RW and the

decommissioning of the nuclear and/or radiological facilities;

• draws up and updates, periodically, technical-economic studies

regarding the estimation of the costs related to the disposal of the SNF

and RW for the establishment of the amounts of the annual

contributions of the license holders;

• manages the financial resources designated to the management of

the SNF and RW and the decommissioning of the nuclear and/or

radiological facilities;

• informs and prepares the public of the area close to the repositories

for the acceptance of their location.

The National Strategy for Safe Management of the Spent Nuclear Fuel and of the Radioactive

Waste

Basic principle

Basic principle of radioactive waste disposal in Romania:

• VLLW: less complex arrangement than LILW-SL;

• LILW-SL: near surface disposal facility;

• LILW-LL and SNF: geological repository;

• SNF is considered RW;

• Import of RW is forbidden.

LILW-SL

INTERIM

STORAGE

ON NPP SITE

SALIGNY

REPOSITORY

(2020)

NPP

TREATMENT

FACILITY

EXISTING PLANNED

RR

TREATMENT

FACILITIES

BAITA BIHOR

REPOSITORY

RR /

INSTITUTIONA

L

LILW-LL

NPP Mining

INTERIM

STORAGE

ON NPP SITE

NPP

TREATMENT

FACILITY

The National Strategy for Safe Management of Radioactive Waste

- LILW -

Milling

DISPOSAL IN

GEOLOGICAL

REPOSITORY

(2056)

STORAGE IN

TAILING

PONDS

CLOSURE

OF TAILING

PONDS

RR /

INSTITUTIONAL

INTERIM

STORAGE

ON RRs SITE

RR

TREATMENT

FACILITIES

NFP

DISPOSAL IN

SURFACE

TRENCHES

IN SITU

CAPPING /

RELOCATING

IN MINES

NPP

The National Strategy for Safe Management of Radioactive Waste

- SNF, NPP -

Dry storage (50 years)

Wet storage (6-7 years)

- The first dry storage module was commissioned in May 2003; - The site can accommodate 50 years operation spent fuel from two CANDU 6 units. - Possibility to extend the site to accommodate the spent fuel produced by 4 units from Cernavoda NPP.


Wet Storage

• Wet storage in the Main Storage Bay for minimum six years.

• Fuel bundles are placed on special designed trays (24 fuel bundles/tray) that are stacked one to each other up to 19 trays per stack.

• Stacks are inspected and sealed by IAEA inspectors.


Dry Storage

The Intermediate Dry Spent Fuel Storage for Cernavoda is the MACSTOR system.

The MACSTOR (Modular Air Cooled STORage) System is designed for storing fuel, which has been cooled for a period of six years.

MACSTOR - Design and

Safety Features

The MACSTOR module is primarily cooled by a natural convection from the storage cylinders surface.

It is designed:

- to withstand natural and man-made hazards.

- for zero release over the entire storage period.

The MACSTOR design ensures that the containment of fission products is maintained during all phases of the fuel handling operations.

MACSTOR - Design and

Safety Features

Specifically, the MACSTOR modules are qualified for:

– design basis tornado, wind loads and related tornado missiles;

– seismic events;

– floods;

– snow loads;

– heavy rain;

– extreme ambient air temperature and humidity;

– wind loads.

Fuel Storage

At the storage area, the transfer flask is lifted from the transporter by the gantry crane above the storage module.

The loading plug previously positioned over the

storage cylinder to be loaded is removed, the transfer

flask positioned over the cavity, and the fuel basket

lowered into the storage cylinder

Interim Dry Spent Fuel

Storage Facility

Nuclear Fuel Cycle Facilities: Radioactive Waste Storage Facilities

– Operated by Cernavoda

NPP

– Capacity for 2 Units, 40

years of operation, solid

(solidified) waste;

– Consist of 3 Structures:

Concrete warehouse

Concrete cylindrical cells

Concrete cubes.

DIDR - The structure no. 1 – warehouse inside view

Cernavoda NPP RW Storage Facility

Assumptions: - 25 y operating period / unit followed by refurbishment

- 5300 SFB / year / unit;

- DICA: 12.000 SFB / module;

- wet storage period: 6-7 years;

- dry storage period: 50 years / module;

Projected inventory – Cernavoda NPP, scenario 1

2003 2056

Refurbishment (2 y per Unit)

Operation of dry storage module (DICA)

1996 2021 2022 2047

U1 Normal operation Normal operation Decommissioning

2007 2032 2033 2058


2056

Operation of deep geological repository

NOTE: Preliminary decommissioning plan for U1 and 2 is under approval

-525.000 SFB to be disposed of;

- RW / LL under estimation.

Transfer of SFB

Assumptions: - 25 y operating period / unit followed by refurbishment

- 5300 SFB / year / unit;

- DICA: 12.000 SFB / module;

- wet storage period: 6-7 years;

- dry storage period: 50 years / module;

Projected inventory – Cernavoda NPP, scenario 2

2003 2056

Refurbishment (2 y per Unit)

Operation of dry storage module (DICA)

1996 2021 2022 2047


2007 2032 2033 2058


2019 2044 2045 2070


2020 2045 2046 2071


2056

Operation of deep geological repository

NOTE: Preliminary decommissioning plan for U1 and 2 is under approval

-1.060.000 SFB to be disposed of;

- RW / LL under estimation.

Transfer of SFB

Cernavoda Units 1& 2 Preliminary

Decommissioning Plan, May 2013

HLW in the form of used fuel will be stored onsite until a geological repository or a suitable alternative storage or disposal facility is available.

WET STORAGE FOR

AT LEAST 6 YEARS

DRY STORAGE FOR

ABOUT 50 YEARS

GEOLOGICAL

REPOSITORY USED

FUEL

Existing facility

Planned facility

Geological map

The DGR concept

• generic (for costing purposes)

and has not been based on

conditions at any particular site.

There is no host rock established

and no proposed site. It is

assumed a Generic Site;

• assumes the similarity of

Canadian Concept for a Deep

Geological Repository for CANDU

spent fuel;

• DGR facility will dispose both

spent fuel and long lived wastes

from 4 Cernavoda Units in

operation their decommissioning;

• DGR will be located for both

waste types at a depth between

500-1000 m.

Basic Principle 1 – Waste minimisation

IAEA-TECDOC-1575 Rev. 1 (INPRO Manual - WM)

Generation of RW associated with SF management is minimized through:

- the quality of fuel;

- online fuelling (this allows through the systems for detecting the failed fuel and immediate replacement);

- canning of the failed fuel;

- control of water parameters for wet storages;

- control of confinement and of the isolation air parameters for dry storage.

Basic Principle 2 – Protection of Human Health and the Environment


In the licensing process, the RB pays due attention to the effective protection of workers, public and environment. The dose estimate and monitoring are based on the analysis of the external effective doses and of the (internal) committed effective doses for members of critical groups for all radiation pathways.

These analysis are performed according to methods and procedures recommended in IAEA and in other western regulations.

The results of the analyses leads to derived emissions limits for the effluents, and the monitoring program of the environment shall demonstrate that the derived emissions limits are observed both in normal operation and during events with relative high probability of occurrence.

Basic Principle 3 – Burden on future generations


Romania authorities fully accept and promote this principle.

Based on the GO no.11/2003 were created the Funds earmarked for the management of radioactive waste and for decommissioning of nuclear installations.

Basic Principle 4 – Waste optimization


The classifications of the radioactive waste as well as the requirements for classification are established by RB in the Order 156/2005 approving the Regulation on the classification of radioactive waste. According to art. 6 in Order 156/2005 the general classification of radioactive waste refers strictly to the requirements regarding the isolation from the biosphere at final disposal radioactive waste.

According to the general classification the radioactive waste are: a) exempt waste; b) transition waste; c) very low level waste; d) short lived low and intermediate level waste; e) long lived low and intermediate level waste; f) high level waste.

Basic Principle 4 – Waste optimization


According to art. 9 of CNCAN Order 156/2005 the operational classification of radioactive waste shall be performed by the licensee. For establishing the operational classification the licensee shall take into account:

a) origin of managed waste such as: site, facility, the arising system, b) types of managed waste such as: used filters, worn-out components,

demolished structures, miscellaneous trash, spent sealed sources, radioisotopes handling residues;

c) nuclear and radiological properties such as: fissile content, heat generation, ambient dose rate, surface contamination, activity concentration, radionuclide composition and half-lives of dominant nuclides, radiolysis potential;

d) other properties such as: physico-chemical and biological properties/hazards corrosivity, content of free liquids, flammability, volatility, solubility, miscibility, dispersibility, organic content, complexing/chelating agents, reactivity, sorption of radionuclides, swelling potential, chemically or biologically hazardous substances, etc.;

e) management options such as: compressibility, combustibility, immobilization, segmentation, decontamination or melting.

• reviewing the National Strategy for safe management of Spent Nuclear

Fuel and Radioactive Waste according to the requirements of Council

Directive 2011/70/EURATOM of 19 July 2011 establishing a Community

framework for the responsible and safe management of spent fuel and

radioactive waste;

• to elaborate and implement a strategic programme for the initial stages

of repository development, including site selection, surface-based site

characterisation, development of a URL, development of the safety

case, etc.;

• reviewing the costs for geological disposal.

Next steps

• The SNF is safe managed according to best international practices;

• Geological disposal of SNF is considered the end-point to ensure

sustainable, safe and secure long-term management;

• Knowledge of the complex geological context of Romania exists

through mapping;

• A concept for DRG was elaborated;

• The DGR will be designed to receive the SNF and LILW/LL coming from

operation, dismantling and refurbishment of Romanian nuclear facilities;

• The programme for implementing geological disposal of SNF and

LILW/LL is in the initial stages (no host rock established and no

proposed site).

Conclusions

Thank you for your attention!

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