DECOMMISSIONING EXPERIENCE IN SPAIN. Manuel Rodríguez Silva

Transcription

1 DECOMMISSIONING EXPERIENCE IN SPAIN Manuel Rodríguez Silva ISPRA, July 2011

2 Strategy: The Spanish Scenario Decommissioning responsibility Enresa RW Management Plan Financial aspects Enresa s Fund Final site required Disposal facilities for: - LLW - ILW - VLLW - HLW - Graphite Green field El Cabril On selection / construction 2

3 DECOMMISSIONIG PROJECTS IN SPAIN VANDELLÓS / 2003 PIMIC 2006 / 2010 JOSE CABRERA 2010 /

4 DECOMMISSIONIG PROJECTS IN SPAIN Madrid. PIMIC (CIEMAT) -Project length: Reactor type: Research Reactor & reprocessing facilities -Status: Site Restoration Tarragona Madrid Guadalajara Tarragona. VANDELLOS 1 NPP Guadalajara. JOSE CABRERA NPP (ZORITA) -Project length: Reactor type: PWR -E. Power: 160 Mw -Status: Preparatory activities / Conventional dismantling -Project length: Reactor type: GCR -E. Power: 460 Mw -Status: On dormancy 4

5 Vandellòs I LEYENDA 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

6 Vandellós I 6

7 REPROCESSING PILOT PLANT Decommissioning activities in Spain: PIMIC (I) NUCLEAR REACTOR LIQUID WASTE STORAGE BUILDING LIQUID WASTE TREATMENT BUILDING 7

8 PIMIC Project (CIEMAT) 8

9 José Cabrera NPP (Zorita) INSTALLATION MAIN DESIGN DATA Type: Westinghouse - 1-Loop PWR Net Electrical Power: 160 MWe Net Thermal Power: Fuel Elements: Fuel Type: Mass UO 2 (core) 510 MWth 69 14x14 UO 2 enrichment 3,6% (U-235) 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 9

10 José Cabrera NPP (Zorita) CONSTRUCTION WORKS 10

11 MAIN CHALLENGE DISMANTLING OF THE REACTOR VESSEL & INTERNAL ELEMENTS 11

12 SPANISH DECOMMISSIONING APPROACH

13 DECOMMISSIONING VISION Inputs Transformation process Outputs + + RESOURCES MATERIALS DISMANTLING is not only DEMOLITION, but an INDUSTRIAL PROCESS 13

14 DECOMMISSIONING VISION Inputs Transformation process Outputs + + RESOURCES MATERIALS DISMANTLING is not only DEMOLITION, but an INDUSTRIAL PROCESS 14

15 DECOMMISSIONING MAIN STEPS Characterization Modifications Disassemblies Demolitions Site restoration Materials Management 15

16 CHARACTERIZATION 16

17 DECOMMISSIONING PHASES: DESCRIPTION AND EXAMPLES

18 INITIAL CHARACTERIZATION 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 18

19 INITIAL CHARACTERIZATION linked To a Data Base: Physical and Radiological Inventory for José Cabrera NPP Dismantling Project 19

20 CHARACTERIZATION (José Cabrera NPP Radological Inventory) MATERIAL Activity (Bq) Impacted Mass (kg) Activation Contamination Total Activation Contamination Total Steel Concrete Scraps iron Electric Cables Isolations PVC & others TOTAL 1,9E+16 1,3E+12 1,9E+16 1,8E+05 2,5E+06 2,7E+06 4,8E+13 4,5E+12 5,3E+13 3,3E+05 5,9E+07 5,9E+07 1,1E+09 1,1E+09 5,2E+04 5,2E+04 5,4E+09 5,4E+09 9,4E+04 9,4E+04 2,6E+09 2,6E+09 8,2E+03 8,2E+03 9,7E+06 9,7E+06 1,4E+06 1,4E+06 1,9E+16 5,8E+12 1,9E+16 5,1E+05 6,3E+07 6,4E+07 20

21 CHARACTERIZATION PIMIC Radiological characterization campaign 21

22 MODIFICATIONS: SYSTEMS & FACILITIES 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 Adaptation of buildings and infrastructure of the plant to new uses required by the decommissioning: SYSTEMS AUXILIARY FACILITIES -Fire protection. -Electrical and instrumentation systems and control -Ventilation. -Water -Surveillance and control, etc. -Access control offices, walkways to controlled areas. -Storage areas and waste conditioning. -Declassification area. -Radiation Protection Equipment and Materials Management 22

23 MAIN STEPS: PLANT ADAPTATION (VANDELLÓS 1 NPP) Modular Laundry Checkpoint Controlled area access Portable ventilation unit Fuel tank 23

24 MAIN STEPS: PLANT ADAPTATION (JOSÉ CABRERA NPP) Electrical System Adaptation Fire Fight System Conditioning Ventilation System Adaptation 24

25 MAIN STEPS: PLANT ADAPTATION (PIMIC) Building 11. Initial State Building 11. Final State 25

26 PHASE 1.- PREPARATORY ACTIVITIES TURBINE BUILDING MODIFICATION & ADAPTATION New Areas for Cutting & Decon CMT Conditioning Area CE-2a/b Concrete Filling Area Temporary RadW Store Temporary RadW Store CE-2a/b 26

27 MAIN STEPS: DISASSEMBLIES 3. DISASSEMBLIES 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 27

28 MAIN STEPS: DISASSEMBLIES (VANDELLÓS 1 NPP) Computer Hall 380 V Transformer Hall 5,5 KV Transformer Hall Relay Hall 28

29 MAIN STEPS: DISASSEMBLIES (VANDELLÓS 1 NPP) 29

30 Decommissioning activities in Spain: PIMIC (II) FUEL REPROCESSING INSTALLATION REACTOR POND 30

31 MAIN STEPS: DISASSEMBLIES (PIMIC) Pool Platform 31

32 MAIN STEPS: DISASSEMBLIES (PIMIC) M1 Cell 32

33 MAIN STEPS: DISASSEMBLIES (JOSÉ CABRERA NPP) Turbine Building Disassembly and Conditioning 33

34 MAIN STEPS: DISASSEMBLIES (JOSÉ CABRERA NPP) Diesel Main Transformer 34

35 MAIN STEPS: DISMANTLING of MAJOR RAD COMPONENTS (ZORITA) REACTOR VESSEL & MAJOR COMPONENTS UPPER INTERNALS CORE BARREL LOWER INTERNALS REACTOR VESSEL THERMAL SHIELD FORMERS BAFFLE 35

36 MAIN STEPS: DISMANTLING of MAJOR RAD COMPONENTS (ZORITA) TRANSPORT AND WASTE PACKAGING 75 tons Crane 35 tons Crane Elevation 621, , tons New Crane Reinforced Bell Elevation 604,000 CE-2a Transfer Wire Basket 36

37 MAIN STEPS: DEMOLITIONS 4. DEMOLITIONS 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. Declassification measures 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 Demolition activities 37

38 MAIN STEPS: DEMOLITIONS (VANDELLÓS 1 NPP) Evaporation cell soil characterization Reactor Building Characterization Decontamination Decontamination 38

39 MAIN STEPS: DEMOLITIONS (VANDELLÓS 1 NPP) Effluent building demolition 39

40 MAIN STEPS: DEMOLITIONS (PIMIC) Reactor Pool 40

41 MAIN STEPS: DEMOLITIONS (JOSÉ CABRERA NPP) Cooling Towers 41

42 MAIN STEPS: SITE RESTORATION 5. SITE RESTORATION 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 42

43 EXAMPLES: SITE RESTORATION (PIMIC CONTAMINATED AREA) 43

44 MAIN STEPS: SITE RESTORATION The material obtained in demolitions is crushed and used in site restoration works 44

45 MATERIALS MANAGEMENT OBJECTIVES: To separate conventional materials from radioactive wastes. To control conventional materials and ensure that they are not contaminated. To dispatch the materials safely. 45

46 6. MATERIALS MANAGEMENT HISTORICAL OPERATING DATA 1 + RADIOMETRIC STUDIES 2 CONVENTIONAL ZONES CONVENCIONAL COMPONENT P.D. ACTIVE ZONES ACTIVE PARTS P.D. Disassembly & preparation MTC handling unit RADIOACTIVE WASTE IN SITU RADIOLOGICAL CONTROL 3 CLEAN Disassembly & Preparation of MDC handling Units CONDITIONING AND PREPARATION FOR TRANSPORT TRANSPORT NO CLEARANCE 4 YES EXIT GATE MONITORS 5 EL CABRIL DISPOSAL FACILITY DESTINATION (Administrative control) 46

47 MATERIALS MANAGEMENT: EXPECTED QUANTITIES 218 t 43 t 175 t tons to manage t t Only 4% is radiactive All materials have a destination t 47

48 MATERIALS MANAGEMENT 48

49 Gestión de materiales convencionales GESTION DE MATERIALES CONVENCIONALES PROCEDENTES DE PARTES ACTIVAS 49

50 6. MATERIALS MANAGEMENT Transfer of handling units Radiological characterization with Box Counter Loading of clered materials Dispatch of cleared materials 50

51 ZORITA DECOMMISSIONING SPECIFIC ISSUES RELATED TO THE TRANSFER OF RESPONSIBILITY 51

52 TRANSFER OF RESPONSIBILITY TO THE DECOMMISSIONING OPERATOR FIRST NPP IN SPAIN DEVELOPING the SPANISH NUCLEAR INDUSTRY BASE for TRAINING TRANSFER of RESPONSIBILITY (Feb, 11, 2010) SITE RETURN to the OWNER ENGINEERING & START UP OPERATION TRANSITION TO DECOMMISSIONING D&D EXECUTION PROJECT Build up Starting Jul-65 1 st Criticallity Jun-68 1 st Electrical Net Connection Jul-68 Commercial Status Oct-69 ELECTRICAL NET DISCONNECTION NSSS DECONTAMINATION SPENT FUEL MANAGEMENT SPENT FUEL CASKS at the ISFI ENRESA`s RESPONSIBILITY OTHER RESPONSIBILITIES STRATEGY BASIC STUDIES DOCUMENTATION + EIS LICENSING D&D PLANNING SETTLE PLAN 52

53 TRANSFER OF RESPONSIBILITY TO THE DECOMMISSIONING OPERATOR Feb, :05h Feb, :03h 53

54 TRANSFER OF RESPONSIBILITY TO THE DECOMMISSIONING OPERATOR 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). 54

55 TRANSFER OF RESPONSIBILITY TO THE DECOMMISSIONING OPERATOR HAND OVER PREPARATORY ACTIVITIES 1. AGREEMENTS WITH THE OWNER 2. ORGANIZATIONAL DESIGN 3. PROCUREMENT OF SERVICES 55

56 STAKEHOLDERS & POLICIES 56

57 POLICIES FACTS, FEARS & EXPECTATIONS Former operator Change of role! enresa Local institutions Local employment! Safety! Sbd.else s site Regulatory body No mistakes! General public Safety! Radioactive waste! 57

58 POLICIES Decommissioning Viability Engineering Project Waste Mangt. organization Policies Internal training Local employment Communication & transparency Safety 58

59 COMMUNICATION AS A KEY FACTOR Communication Goal: To Inform To neutralize negative opinions and attitudes Remove false expectations To Form 59

60 SITE VISIT IN DISMANTLING PIMIC Visit CT Mestral Visit 60

61 PROFESSIONAL TRAINING CT Mestral OIEA Course (PIMIC) 61

62 CONCLUSIONS 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. Lessons learned Lessons learned Lessons learned VANDELLÓS / 2003 PIMIC 2006 / 2010 JOSE CABRERA 2010 /

63 Thanks for your attention 63

64 64