josÉ cabrera npp dismantling and decommissioning project · josÉ cabrera npp dismantling and...

JOSÉ CABRERA NPP DISMANTLING AND

DECOMMISSIONING PROJECT

Manuel Rodríguez Silva

IDN, November 2011

PROJECT GOALS AND VISION

3

José Cabrera NPP D&D Project

SITUATION

SPAIN

Madrid

Almonacid de Zorita

(Guadalajara)

Guadalajara. José Cabrera NPP Dismantling -Project length: 2010-2016 -Reactor type: PWR Reactor -Status: Preparatory activities / Conventional dismantling

4


OBJECTIVES

Complete dismantling of the nuclear (first time in Spain)

Proper management of the resulting materials

1

2

1

2

Dismantling is the best way for controlling the risk at any NPP after operation

5


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

THE INPUTS

7


CONSTRUCTION WORKS

History

8


ENRESA`s RESPONSIBILITY

OTHER RESPONSIBILITIES

ENGINEERING &

START UP

COMMERCIAL STAGE

D&D EXECUTION

PROJECT FINAL SHUTDOWN

TRANSITION STAGE

1963

STRATEGY BASIC STUDIES

DOCUMENTATION + EIS

LICENSING

D&D PLANNING

“LANDING” 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)

LIFE CYCLE

DECOMMISSION

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

History

9


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

History

10


INSTALLATION MAIN CROSS SECTION

TURBINE HALL – CONTAINMENT BUILDING

History

11


SITE MAP & BUILDINGS

1

2 3

7 6 8

9 13

14

15

16

10

17

18

11

12

5

1.- Reactor 2.- Turbine 3.- Auxiliary Building 4.- Offices 5.- Transformers 6.- Diesel 7.- Evaporator 8.- RadWaste Building 1 9.- Warehouse 10.- General Warehouse 11.- RadWaste Building 2 12.- Release Measurements Zone 13.- Electrical Distribution Area 14.- Discharge Channel 15.- Cooling Towers 16.- Release Material Storage Area 17.- Parking 18.- Radwaste Expedition Area

History

THE OUTPUTS

13


RELEASED SITE

14


MATERIALS MANAGEMENT

15


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

THE RESOURCES

17


WORK SCHEDULE

The scheduled time of dismantling works is 6 years

ACTIVITY 2010 2011 2013 2012 2014 2015 2016

PREPARATORY ACTIVITIES

RADIOLOGICAL DISMANTLING

Major rad components

Other components

DESCONTAMINATION AND DEMOLITION

MATERIAL MANAGEMENT

EMPLACEMENT RESTORATION

System Discharge

System Modifications

Conditioning Facilities

CONVENTIONAL DISMANTLING

18


PROJECT MAIN ACTIVITIES Cost

(M€ 2003)

-Engineering & Basic Project 34

-Previous Activities after Shutdown + NSSS Decon 5

-Transition Activities (2006-2010) 6

-Dismantling & Decom Execution 29

-Material & Rad Waste Management 11

-Site Restoration 23

-Others 4

(Un-Expected (%)) 20%

SPENT FUEL MANAGEMENT NOT INCLUDED ( ~ 35 M€) TOTAL ~ 135

BUDGET

PROJECT DATA & FEATURES

19


HUMAN RESOURCES

0

50

100

150

200

250

300

Nº

EMP

LEA

DO

S

PERIODO

PERSONNEL EVOLUTION DURING THE PROJECT

ACTIVIDADES EJECUCIÓNPDC

VIGILANCIA YMANTENIMIENTOINSTALACIÓN

INGENIERÍA Y DIRECCIÓNDE OBRA

Estimated peak: 250 workers

THE PROCESS

(PROJECT PHASES)

21


Characterization

Modifications

Disassemblies

Demolitions

Site restoration

Materials Management

Transfer of ownership

Decommisioning

Statement

DECOMMISSIONING MAIN STEPS

22


DECOMMISSIONING MAIN STEPS

23


MATERIALS RELEASE METHODOLOGY

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

5

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

24



25



Radiological characterization with Box Counter Transfer of handling units

Loading of clered materials Dispatch of cleared materials

DECLASSIFICATION

PROJECT PROGRESS

(UNTIL OCTOBER 2011)

28


PROJECT PROGRESS (2010-2011)

Towers Electrical Building

Water Intake

Strucuture

Turbine Building

DAB (Dismant. Auxiliay Building)

Reactor Building

Electrical and

Auxiliary Building

Cooling Towers

Diesel Building

Waste Storage

Outdoor Areas

Clearance Area

Preparatory Activities

Electric Systems 100% 100% 90% 100%

Mechanical Syst. / Fire Fight System Conditioning

100% 100%

Ventilation System Adaptation

5% 100% 100%

Support Facilities Adequacy

75% 60% 100%

Support Facilities Equipment

70% (*)

Active Zones Preparation 30% 10%

Conventional Dismantling 100% 100% 100% 100%

Radiological Dismantling

(*) Design / manufacturing activities ongoing

29


PROJECT PHASES

PHASE 0 – REMOVAL of FUEL & PRELIMINARY WORKS

• Post-Shutdown Activities

• Primary System Decontamination

• Update Initial Radiological Characterization

• Update Physical Inventory

• Shutdown-Drain & Isolation of Non Required Systems & Components

• Construction of ITS (Independent Temporary Storage)

• Dry Store Cask Loading (Fuel Pool empty)

30


SPENT FUEL – CASK LOADING

HI-STORM going to the PAD

STORAGE AREA

HI-TRACK – EXIT of CONTAINMENT BUILDING

MPC into the HI-STORM

PHASE 0.- REMOVAL of SPENT FUEL & PRELIMINARY WORKS

31


12 HI-STORM Z CASKS

INDEPENDENT TEMPORARY STORAGE (ITS) FACILITY


32


BUILDINGS & COMPONENTS – INITIAL RADIOLOGICAL IDENTIFICATION

Samples & Laboratory Measurements


33


PROJECT PHASES

PHASE 1 – PREPARATORY ACTIVITIES

• Mobilization & Set-up of Site Offices

• Hazardous Material Removal

• Dismantling of Non Radioactive Systems & Areas & Equipments

• Modification & Reconfiguration of Systems & Equipments

• Turbine Hall: Modification + Adaptation

• Tests & Start up Procedures of the New Systems & Facilities

34


Discharge systems

PHASE 1.- PREPARATORY ACTIVITIES

DISCONNECT SYSTEMS & EQUIPMENTS

35


New Electrical Building Power Cells & Cabins

3 kV & 380 V

Electric Supply System Modification

D&D New Principal Transformer

46 kV Equipment

Modification


36


Electric Supply System Modification


37


Fire Fight System Conditioning


38


New Tubes & Modifications


New Controlled Area Ventilation

New Equipments


39




40


Cooling Towers

Diesel Turbine Building Transformers

Conventional Dismantling of Systems & Buildings


41


COOLING TOWERS DEMOLITION

42


COMPONENTS DISASSEMBLY IN DIESEL BUILDING

43


DISASSEMBLY OF THE MAIN TRANSFORMER

44


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


45


TURBINE BUILDING MODIFICATION AND ADAPTATION

46



47



48



49



50



51



Section of concrete structures with diamond

wire

52



53



54



55



56



57



58



59



60



61



62



63


Electrical rewiring


64


Ventilation System

Adaptation


FOLLOWING ACTIVITIES

66


PROJECT PHASES

PHASE 2 – DISMANTLING of MAJOR RAD COMPONENTS

• Radioactive Equipment & Systems – Decontamination + Dismantling

• Reactor Internals Segmentation

• Dismantling of Large Components + NSSS Removal

• Cleareance Survey of Materials (Equipment & Systems)

• Rad Waste Processing, Storage & Disposal

• Conventional Materials Management

67


CORE BARREL LOWER INTERNALS

UPPER INTERNALS

THERMAL SHIELD BAFFLE

REACTOR VESSEL & MAJOR COMPONENTS

FORMERS

REACTOR VESSEL

PHASE 2.- DISMANTLING of MAJOR RAD COMPONENTS

68


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

PHASE 2.- DISMANTLING of MAJOR RAD COMPONENTS

69


PREPARATORY WORKS

70


PREPARATORY WORKS

71


PREPARATORY WORKS

José Cabrera NPP Reactor

Cavity

72


PREPARATORY WORKS

Section of concrete structures with diamond wire

73


PREPARATORY WORKS

74


PREPARATORY WORKS

75


PREPARATORY WORKS

76


PREPARATORY WORKS

77


PROJECT PHASES

PHASE 3 – REMOVE of AUX. INSTALLATIONS,CLEAN & DEMOLITIONS

• Miscellaneous Systems & Equipment Removal

• Radioactive Structures Decontamination

• Post Radiological Characterization

• Cleareance Survey of Materials (Structures & Buildings)

• Demolition & Removal of Structures & Buildings

78


PROJECT PHASES

PHASE 4 – ENVIRONMENTAL RESTORATION • Final Cleanup

• Final Radiological De-License Survey

• Backfill of Cavities

• Site Restoration

• Landscaping

• Close out Report

• Regulatory Approval of De-License Application

• Site Formally De-Licensed

• Return to the Owner

79


LANDSCAPING

PHASE 4.- ENVIRONMENTAL RESTORATION

JOSÉ CABRERA 2016

80


Thank you

for your attention

josÉ cabrera npp dismantling and decommissioning project · josÉ cabrera npp dismantling and...

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