DECOMMISSIONING EXPERIENCE IN SPAIN2011.radioactivewastemanagement.org/download/14 - RODRIGUEZ.pdf · cajon de hormigÓn pretensado 2. reactor 3. superficie soporte 4. ... decommissioning

DECOMMISSIONING EXPERIENCE IN

SPAIN

Manuel Rodríguez Silva ISPRA, July 2011

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DECOMMISSIONING EXPERIENCE IN SPAIN

•Enresa •RW Management Plan

• Enresa’s Fund

•El Cabril

Decommissioning responsibility

Financial aspects

Disposal facilities for:

- LLW

- ILW

- VLLW

- HLW

- Graphite

•On selection / construction

• Green field Final site required

Strategy: The Spanish Scenario

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JOSE CABRERA

2010 / 2016

PIMIC

2006 / 2010

VANDELLÓS 1

1998 / 2003

DECOMMISSIONIG PROJECTS IN SPAIN

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DECOMMISSIONIG PROJECTS IN SPAIN

Madrid. PIMIC (CIEMAT) -Project length: 2006-2011 -Reactor type: Research Reactor & reprocessing facilities -Status: Site Restoration

Madrid

Guadalajara

Tarragona

Tarragona. VANDELLOS 1 NPP -Project length: 1998-2003 -Reactor type: GCR -E. Power: 460 Mw -Status: On dormancy

Guadalajara. JOSE CABRERA NPP (ZORITA) -Project length: 2010-2016 -Reactor type: PWR -E. Power: 160 Mw -Status: Preparatory activities / Conventional dismantling

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15

16

79 10

8

1

12

13

2

3

4

6 5

14

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LEYENDA 1. CAJON DE HORMIGÓN PRETENSADO 2. REACTOR 3. SUPERFICIE SOPORTE 4. CAMBIADOR 5. SOPLANTE 6. TUNEL DE VENTILACIÓN EN PARADA 7. TURBINA 8. CONDENSADOR 9. ALTERNADOR 10. TRANSFORMADOR 11. DISPOSITIVO PRINCIPAL DE MANUTENCIÓN ( DPM ) 12. MANUTENCIÓN DE ELEMENTOS COMBUSTIBLES 13. PISCINAS 14. TOMA DE AGUA DE MAR DE REFRIGERACIÓN 15. ESTACIÓN DE BOMBEO 16. EVACUACIÓN DEL AGUA DE MAR DE REFRIGERACIÓN

Vandellòs I

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Vandellós I

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Decommissioning activities in Spain: PIMIC (I)

NUCLEAR REACTOR

REPROCESSING PILOT PLANT

LIQUID WASTE TREATMENT

BUILDING

LIQUID WASTE STORAGE

BUILDING

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PIMIC Project (CIEMAT)

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Type: Westinghouse - 1-Loop PWR

Net Electrical Power: 160 MWe

Net Thermal Power: 510 MWth

Fuel Elements: 69 – 14x14

Fuel Type: UO2 – enrichment 3,6% (U-235)

Mass UO2 (core) 20,76 t

Control Rod (Banks): 17

Reactor Vessel (Diameter): 2,82 m

Reactor Vessel (Height without Head): 5,87 m

NSSS (Diameter): 70 cm

Containment:

Reinforced concrete + Stainless Steel Head

Spent Fuel Pool:

In Containment

Final cooling:

Tajo River

INSTALLATION MAIN DESIGN DATA

José Cabrera NPP (Zorita)

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CONSTRUCTION WORKS

José Cabrera NPP (Zorita)

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DISMANTLING OF THE REACTOR VESSEL & INTERNAL ELEMENTS

MAIN CHALLENGE

SPANISH DECOMMISSIONING

APPROACH

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DECOMMISSIONING VISION

Inputs Outputs Transformation process

+ + RESOURCES MATERIALS

1

2 3 4

5 6

DISMANTLING is not only DEMOLITION, but an INDUSTRIAL

PROCESS

1 2 3 4 5 6

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DECOMMISSIONING VISION

Inputs Outputs Transformation process

+ + RESOURCES MATERIALS

1

2 3 4

5 6

DISMANTLING is not only DEMOLITION, but an INDUSTRIAL

PROCESS

1 2 3 4 5 6

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Characterization

Modifications

Disassemblies

Demolitions

Site restoration

Materials Management

DECOMMISSIONING MAIN STEPS

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CHARACTERIZATION

DECOMMISSIONING PHASES: DESCRIPTION AND EXAMPLES

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OBJECTIVES:

Identification of the types of wastes to be generated (both

radioactive and conventional)

Quantification of the volumes of each of the waste categories

Isotopic Vectors corresponding to the existing radioactive waste

streams (Key for the determination of activity by measuring the

gamma emitters involved)

Planning of operational radiological protection

INITIAL CHARACTERIZATION

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linked

To a Data Base: Physical and Radiological Inventory for José

Cabrera NPP Dismantling Project

INITIAL CHARACTERIZATION

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MATERIAL Activity (Bq) Impacted Mass (kg)

Activation Contamination Total Activation Contamination Total

Steel 1,9E+16 1,3E+12 1,9E+16 1,8E+05 2,5E+06 2,7E+06

Concrete 4,8E+13 4,5E+12 5,3E+13 3,3E+05 5,9E+07 5,9E+07

Scraps iron 1,1E+09 1,1E+09 5,2E+04 5,2E+04

Electric Cables 5,4E+09 5,4E+09 9,4E+04 9,4E+04

Isolations 2,6E+09 2,6E+09 8,2E+03 8,2E+03

PVC & others 9,7E+06 9,7E+06 1,4E+06 1,4E+06

TOTAL 1,9E+16 5,8E+12 1,9E+16 5,1E+05 6,3E+07 6,4E+07

CHARACTERIZATION (José Cabrera NPP Radological Inventory)

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CHARACTERIZATION

PIMIC Radiological characterization campaign

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Adaptation of plant systems to the needs of decommissioning. The adaptation may be a simplification, a reinforcement or a change of layout, in order to minimize risk, interference and unavailability

MODIFICATIONS: SYSTEMS & FACILITIES

SYSTEMS

-Fire protection.

-Electrical and instrumentation

systems and control

-Ventilation.

-Water

-Surveillance and control, etc.

Adaptation of buildings and infrastructure of the plant to new uses required by the decommissioning:

AUXILIARY FACILITIES

-Access control offices, walkways to

controlled areas.

-Storage areas and waste conditioning.

-Declassification area.

-Radiation Protection Equipment and

Materials Management

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MAIN STEPS: PLANT ADAPTATION (VANDELLÓS 1 NPP)

Checkpoint

Fuel tank

Portable ventilation unit

Modular Laundry Controlled area access

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MAIN STEPS: PLANT ADAPTATION (JOSÉ CABRERA NPP)

Electrical System Adaptation

Fire Fight System Conditioning Ventilation System Adaptation

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MAIN STEPS: PLANT ADAPTATION (PIMIC)

Building 11. Initial State Building 11. Final State

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Temporary RadW Store CE-2a/b

CE-2a/b Concrete Filling Area

New Areas for Cutting & Decon

CMT Conditioning Area

Temporary RadW Store

TURBINE BUILDING MODIFICATION & ADAPTATION

PHASE 1.- PREPARATORY ACTIVITIES

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After completion of the preparatory activities, the dismantling of different parts can be started

The removal of radiological systems and components is the core activity of decommissioning projects.

The materials generated should be segregated, characterized and seeded in situ to establish the appropriate management pathway by type.

The minimization of the dose received by workers and the amount of radioactive waste are the main objectives of this phase

3. DISASSEMBLIES

MAIN STEPS: DISASSEMBLIES

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MAIN STEPS: DISASSEMBLIES (VANDELLÓS 1 NPP)

Computer Hall

380 V Transformer Hall

5,5 KV Transformer Hall

Relay Hall

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MAIN STEPS: DISASSEMBLIES (VANDELLÓS 1 NPP)

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FUEL REPROCESSING INSTALLATION

Decommissioning activities in Spain: PIMIC (II)

REACTOR POND

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Pool Platform

MAIN STEPS: DISASSEMBLIES (PIMIC)

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M1 Cell

MAIN STEPS: DISASSEMBLIES (PIMIC)

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MAIN STEPS: DISASSEMBLIES (JOSÉ CABRERA NPP)

Turbine Building Disassembly and

Conditioning

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MAIN STEPS: DISASSEMBLIES (JOSÉ CABRERA NPP)

Diesel

Main Transformer

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CORE BARREL LOWER INTERNALS

UPPER INTERNALS

THERMAL SHIELD BAFFLE

REACTOR VESSEL & MAJOR COMPONENTS

FORMERS

REACTOR VESSEL

MAIN STEPS: DISMANTLING of MAJOR RAD COMPONENTS (ZORITA)

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Elevation 621,600

Elevation 604,000

+614,700

Transfer Wire Basket

75 tons Crane

35 tons Crane

32 tons New Crane

CE-2a

Reinforced Bell

TRANSPORT AND WASTE PACKAGING

MAIN STEPS: DISMANTLING of MAJOR RAD COMPONENTS (ZORITA)

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4.1 DECONTAMINATION BUILDING

After removal of radiological components and systems, it´s necessary to

decontaminate walls (walls, floors and ceilings) of the buildings for

subsequent demolition.

4.2 DECLASSIFICATION OF SURFACES

The application of the methodology for the declassification of surfaces

ensures the absence of contamination in the walls of buildings facing

subsequent reuse or demolition.

4.3 DEMOLITION

Once declassified, buildings will be demolished to a depth of 1 meter

below ground level.

The debris are usually crushed for reuse on site as filling material

Declassification measures

Demolition activities

MAIN STEPS: DEMOLITIONS

4. DEMOLITIONS

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Decontamination

Evaporation cell soil characterization

MAIN STEPS: DEMOLITIONS (VANDELLÓS 1 NPP)

Reactor Building Characterization

Decontamination

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MAIN STEPS: DEMOLITIONS (VANDELLÓS 1 NPP)

Effluent building demolition

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MAIN STEPS: DEMOLITIONS (PIMIC)

Reactor Pool

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MAIN STEPS: DEMOLITIONS (JOSÉ CABRERA NPP)

Cooling Towers

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• The purpose of this activity is to demonstrate

that the radiological content of the site in its

final state satisfies the release criteria.

If necessary, remediation work is carried out

before the final characterization

(decontamination of affected areas).

Site Characterization

MAIN STEPS: SITE RESTORATION

5. SITE RESTORATION

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EXAMPLES: SITE RESTORATION (PIMIC – CONTAMINATED AREA)

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MAIN STEPS: SITE RESTORATION

The material obtained in demolitions is crushed and used in

site restoration works

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OBJECTIVES:

To separate conventional materials from radioactive

wastes.

To control conventional materials and ensure that they

are not contaminated.

To dispatch the materials safely.

MATERIALS MANAGEMENT

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HISTORICAL OPERATING

DATA

1

RADIOMETRIC STUDIES

2

ACTIVE ZONES

CONVENTIONAL ZONES

ACTIVE PARTS P.D.

CLEAN

CONVENCIONAL COMPONENT P.D.

“IN SITU” RADIOLOGICAL

CONTROL

3

+

RADIOACTIVE WASTE

DESTINATION (Administrative control)

EXIT GATE MONITORS

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CLEARANCE

4

Disassembly & Preparation of MDC handling

Units

YES

Disassembly & preparation

MTC handling unit

EL CABRIL DISPOSAL FACILITY

TRANSPORT

NO CONDITIONING AND PREPARATION FOR

TRANSPORT

6. MATERIALS MANAGEMENT

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43 t

218 t

4.000 t

4.700 t 95.300 t

175 t

MATERIALS MANAGEMENT: EXPECTED QUANTITIES

104.000 tons to manage Only 4% is radiactive All materials have a destination

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MATERIALS MANAGEMENT

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Gestión de materiales convencionales

GESTION DE

MATERIALES

CONVENCIONALES

PROCEDENTES DE

PARTES ACTIVAS

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6. MATERIALS MANAGEMENT

Radiological characterization with Box Counter Transfer of handling units

Loading of clered materials Dispatch of cleared materials

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ZORITA DECOMMISSIONING

SPECIFIC ISSUES RELATED TO THE TRANSFER OF RESPONSIBILITY

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ENRESA`s RESPONSIBILITY

OTHER RESPONSIBILITIES

ENGINEERING

& START UP

OPERATION D&D EXECUTION

PROJECT TRANSITION TO

DECOMMISSIONING

1963

STRATEGY BASIC STUDIES

DOCUMENTATION + EIS

LICENSING

D&D PLANNING

“SETTLE” PLAN

2006 1969

SITE RETURN to the OWNER

ELECTRICAL NET DISCONNECTION

NSSS DECONTAMINATION

SPENT FUEL MANAGEMENT

SPENT FUEL CASKS at the ISFI

TRANSFER of RESPONSIBILITY

(Feb, 11, 2010)

2016 2010

Build up Starting – Jul-65

1st Criticallity – Jun-68

1st Electrical Net Connection – Jul-68

Commercial Status– Oct-69

FIRST NPP IN SPAIN DEVELOPING the SPANISH NUCLEAR INDUSTRY

BASE for TRAINING

TRANSFER OF RESPONSIBILITY TO THE DECOMMISSIONING OPERATOR

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Feb, 11 – 2010 – 12:05h

Feb, 11 – 2010 – 13:03h


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The hand over of responsibility to operate the plant is a complex situation, specific of the spanish framework, that requires plenty of planning and negotiation between the owner and the decommissioning operator (Enresa).


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HAND OVER PREPARATORY ACTIVITIES

1. AGREEMENTS WITH THE OWNER

2. ORGANIZATIONAL DESIGN

3. PROCUREMENT OF SERVICES


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STAKEHOLDERS &

POLICIES

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POLICIES

enresa

Regulatory body

General public

Former operator

•Change of role !

Local institutions

• Safety ! • Radioactive waste !

•No mistakes !

•Local employment ! •Safety !

FACTS, FEARS & EXPECTATIONS

• Sbd.else’s site

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POLICIES

Engineering Project

Decommissioning Viability

Waste Mangt. organization

Policies

• Internal training • Local employment • Communication &

transparency • Safety

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Communication Goal:

To Inform

To neutralize negative opinions and attitudes

Remove false expectations

To Form

COMMUNICATION AS A KEY FACTOR

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CT Mestral Visit

SITE VISIT IN DISMANTLING

PIMIC Visit

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PROFESSIONAL TRAINING

CT Mestral

OIEA Course (PIMIC)

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JOSE CABRERA

2010 / 2016

PIMIC

2006 / 2010

VANDELLÓS 1

1998 / 2003

CONCLUSIONS

Lessons learned

Lessons learned

Lessons learned

Decommissioning is a complex industrial activity, plenty of technical and not technical matters, as we have seen in the previus slides. Our commitment is to constantly review and improve the model we have shown, so that can undertake with solvency our current

and future demands.

. . .

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Thanks for your attention

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Documents

DECOMMISSIONING EXPERIENCE IN SPAIN2011.radioactivewastemanagement.org/download/14 - RODRIGUEZ.pdf · cajon de hormigÓn pretensado 2. reactor 3. superficie soporte 4. ... decommissioning