Greifswald Project Introduction/Experience summary Axel Bäcker

Transcription

1 Decommissioning operation of large decommissioning projects 20 years experience Decommissioning management of five power reactors on the Greifswald site Greifswald Project Introduction/Experience summary Axel Bäcker

2 Parent Company EWN GmbH Shareholder is Federal Ministry of Finance/Berlin NPP Greifswald Headquarter Headquarter at Greifswald Sites: Nuclear Power Plants at Greifswald and Rheinsberg (both under dismantling) NPP Rheinsberg Subsidiaries: 1 Nuclear Experimental Reactor Jülich - (AVR GmbH) (shut down 1988, green field till 2015) Decomm. projects on Karlsruhe site - (WAK GmbH) WAK - Reprocessing Plant Karlsruhe Decommissioning and Waste Management (Vitrification of the HLLW stored at WAK site and decommissioning the WAK area) MZFR FR 2. KNK HDB treatment and disposal centre 1 2

3 NPP Greifswald - Decommissioning Project NPP Greifswald (KGR) Greifswald NPP Project Facts Objective: green field (brown field) Duration: NPP Rheinsberg (KKR) Budget: 3.2 bn NPP Stendal (construction stopped) Overall inventory: 1.8 Mio Mg (565,000 Mg) Spent Fuel: 5,037 FE Expected final waste amount: ~16,000 Mg

4 View on the 70 MW Rheinsberg NPP (KKR) IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012

5 View on the Greifswald NPP (KGR) IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012 Wet spent fuel store units 5-8 units 1-4 Warm workshop ISN

6 Basic data KGR and Rheinsberg (KKR) IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012 unit type power MWel operation shut down produced energy GWh 1 KGR WWER KGR WWER KGR WWER KGR WWER KGR WWER KGR WWER ready for commissioning 7 KGR WWER building erected major components installed 8 KGR WWER building erected major components installed KKR WWER

7 KGR NPP decommissioning Initial key decisions Direct dismantling no Safe Enclosure Introduce project organization Project realisation by own staff instead of contractors Erect major interim store on-site for fuel, waste and treatment Reuse of site for industrial and energetic uses

8 KGR NPP decommissioning Key issues All issues are interrelated Personnel Licensing Dismantling Material / Waste Site reuse

9 KGR NPP decommissioning Key issue personnel Personnel strategy No major contractors - use operation personnel Retirement scheme Privatisation Resolve it as soon as possible Education Dismissal with economic support

10 Personnel development of EWN GmbH IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012 Planning

11 KGR NPP decommissioning Key issues All issues are interrelated Personnel Licensing Dismantling Material / Waste Site reuse

12 KGR NPP decommissioning Key issue licensing Licensing strategy One basic license complemented by specific ones (e.g. possession, post operation, small dismantling projects) Part licences time for planning and authority control Exemption levels included in basic license planning of waste management

13 License application Possession, decommissioning and part dismantling (including controlled area unit 5) 2. Model remote dismantling in unit 5 3. Dismantling controlled area units 1 and 2 4. Dismantling controlled area units 3 and 4 5. Remote dismantling of nuclear reactors units Dismantling of remaining buildings and systems 6.1 Dismantling of the non needed part of the cooling water outlet channel 6.2 Dismantling of the facilities in the waste treatment building of units 5/6 / laboratory building 1 (units 1/2) 6.3 Removal of the closed part of he outlet channel 6.4 Dismantling remaining operation systems units 5/ construction reactor periphery reactor nozzles remote dismantling 6.5 Dismantling remaining operation systems units 1/2 and direct safeguarding facilities 6.6 Dismantling remaining operation systems units 3/4 and environment monitoring facilities 6.7 Dismantling remaining operation systems in the waste treatment building of units 5/6 7. Dismantling of RPV5 and internals and transport in the ISN 8. Removal of the contaminated building structures 8.1 Removal of the building of the emergency core cooling system unit 1 and laboratory building 1 (units 1/2) Licensing mile stones Greifswald

14 KGR NPP decommissioning Key issues All issues are interrelated Personnel Licensing Dismantling Material / Waste Site reuse

15 KGR NPP decommissioning Key issue dismantling Dismantling strategy Accelerated plant inventory removal out of the units decoupling of dismantling from further treatment/fragmentation As large parts as possible to Interim Storage Decay storage (Dismantling with fuel in plant)

16 KGR NPP decommissioning Key issue dismantling Dismantling principles dismantling planning on system basis, execution on room basis start in unit 5; low contamination / radiation dose from low to high contamination / radiation dose use market equipment in situ decontamination only for dose reduction whole components / parts as possible for decay or treatment in interim storage 5 reactors (ca. 214 t) 18 (30) steam generators (ca. 160 t) 5 pressurizers (ca. 107 t) main cooling pumps etc.

17 KGR NPP decommissioning Key issue dismantling Dismantling large components - Reasons Dose rate reduction due to self-shielding and decay Time reduction of dismantling per unit Further treatment (for free release) in the warm workshop or the ISN independent from the dismantling of the units

18 KGR NPP decommissioning Key issue dismantling Dismantling large components Pressurizer

19 KGR NPP decommissioning Key issue dismantling Dismantling large components - steam generator and RPV unit 1

20 KGR NPP decommissioning Key issue dismantling Dismantling of large components - Uncut components in the ISN RPV from KGR RPV from KKR Steam generators

21 KGR NPP decommissioning Key issue dismantling Dismantling strategy - summary Dismantling planning on system basis, execution on room basis Low ambient dose rate by removing hot spots Dismantling from lower to higher contamination (start in unit 5) Separating the dismantling from the conditioning activities Use of market equipment already tested in nuclear industry Remote dismantling of highly activated components Experienced personnel with good knowledge of the plant Dismantling of components as large as possible Inactive trials of difficult procedures Flexibility of strategy (dismantling strategy for reactors) in 1993 and 2004

22 KGR NPP decommissioning Key issue dismantling Dismantling strategy for activated components in 1993 Installation of cutting places in the former steam generator box, in succession in units 5, 2, 4 Trial dismantling in unit 5 with inactive parts of reactors 6 8 Cutting the reactors in this order: unit 5, units 1 and 2, units 3 and 4 Interim storage in special containers for final disposal

23 KGR NPP decommissioning Key issue dismantling Dismantling strategy for activated components in 1993

24 KGR NPP decommissioning Key issue dismantling Band-saw (horizontal) Dry cutting area

25 KGR NPP decommissioning Key issue dismantling Band-saw (vertically) - Dry cutting area

26 KGR NPP decommissioning Key issue dismantling View in the wet cutting area

27 KGR NPP decommissioning Key issue dismantling Dismantling strategy for activated components in 2004 Dismantling the reactor pressure vessels 1-5 without cutting transport to the ISN for decay storage using special designed STD (Shielding and Transport Device) Cutting only the internals of reactor pressure vessels 1 and 2 Dismantling the internals 3-5 without cutting transport into the ISN for decay storage using special designed STD Main goals: Reduction of time and costs Optimization of radiation protection

28 KGR NPP decommissioning Key issue dismantling Main data RPV Mass: 214 Mg High: 11,8 m Diameter out side: in side: 4,3 m 3,3 m Wall thickness: mm Dismantling RPV unit 5 - Dismantled RPV

29 KGR NPP decommissioning Key issue dismantling Dismantling RPV unit 5 Transport to the ISN

30 KGR NPP decommissioning Key issue dismantling Unit 1/2: Reloading of the RPV from the gliding system on the trailer

31 KGR NPP decommissioning Key issues All issues are interrelated Personnel Licensing Dismantling Material / Waste Site reuse

32 KGR NPP decommissioning Key issue Material Strategy Construct interim storage on-site for fuel, material (waste) and treatment Early and complete use of free release / exemption Early planning and implementation of treatment facilities and logistic

33 KGR NPP decommissioning Key issue Material Spent fuel in CASTOR casks ISN - hall 8 - dry storage of fuel

34 KGR NPP decommissioning Key issue Material Types of operational waste in EWN low and intermediate level active resins from the controlled area resin-sludge mixtures from the controlled area liquid evaporator concentrate low active resins from the turbine hall (SG leakages) low active sludge from the monitored area mixed solid radioactive waste waste oil from the controlled area filter material (filter pads)

35 KGR NPP decommissioning Key issue Material Dismantling - Material categories Result of characterisation (Inventory) (Category 0) - unrestricted material Category I - unrestricted material Category II - suspected material Category III - contaminated material

36 KGR NPP decommissioning Key issue Material Production of packages Dismantling area in the turbine hall

37 KGR NPP decommissioning Key issue Material Treatment of dismantled material - Warm Workshop on Greifswald Site Band saws Decontamination box for high-pressure water blasting procedure Thermal cutting box

38 KGR NPP decommissioning Key issue Material On site Interim Storage - Independence from Final Storage Facility No final storage available (until 1998 ERAM) ISN storage for spent fuel, waste and material incl. treatment capacities Separation dismantling from material treatment decay, avoidance of bottle necks Optimization of the whole decommissioning process

39 KGR NPP decommissioning Key issue Material storage of spent fuel interim and decay storage of radioactive material storage area m² dimension l. 240m x w. 140m x h. 18m Cross section Interim Storage North halls 1-7 radioactive material: containers - cast iron containers - concrete containers - steel containers - casks (cast iron) - large components hall 8 spent fuel in CASTOR casks masses halls 1-7 approx Mg hall 8 585Mg (heavy metal)

40 KGR NPP decommissioning Key issue Material Treatment of dismantled material - Interim Storage North High pressure compactor Drying facility Scrap shear Band saw

41 KGR NPP decommissioning Key issue Material Storage halls - Interim Storage North

42 KGR NPP decommissioning Key issue Material Release measurement facilities

43 KGR NPP decommissioning Key issue Material Technical project progress (October 2012) KGR: ca. 270,000 Mg material have been dismantled controlled area unit 1-5: appr. 92 % supervised area unit 1-5: appr. 100 % ISN: 25,100 Mg material/waste have been stored in ISN, including: 5 reactor pressure vessel (~214 Mg) + 1 RPV from KKR 18 steam generators (~160 Mg) 4 pressurizer (107 Mg)

44 KGR NPP decommissioning Key issues All issues are interrelated Personnel Licensing Dismantling Material / Waste Site reuse

45 KGR NPP decommissioning Key issue Site reuse Strategy Start planning as soon as possible new working places positive influence on project

46 KGR NPP decommissioning Key issue Site reuse IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012 Outlet channel during operation of the NPP Industrial Harbour Industrial harbour

47 KGR NPP decommissioning Key issue Site reuse Preconditions: IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012

48 Site Development - Transport of fundament tubes for wind power plants IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012

49 Site Development - Turbine hall units 1 to 4 IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012 Company: Liebherr-MCCtec Product: large maritime cranes

50 KGR NPP decommissioning Key issue Site reuse Company Ecanol / Premicon - biodiesel plant (since 2006 in operation)

51 Other EWN projects SWEDEN FINLAND Participation of EWN GmbH External international projects LITHUANIA Ignalina in international decommissioning projects Rubenow Site in Eastern Europe GERMANY SLOVAKIAI Bohunice HUNGARY Paks Chernobyl UKRAINE Kozloduy BULGARIA

52 Other EWN projects Decommissioning Submarines of the Russian Northern Fleet Main goal: Safe and long term storage of 120 reactor compartments at Saida Bay

53 Other EWN projects Decommissioning Submarines of the Russian Northern Fleet Nov Entsorgungszentrum Saida Long Term- Interim Storage Sept. 2011

54 Thank you for your attention! IAEA Workshop on Decommissioning Planning and Licensing, Karlsruhe/Germany November 2012