德國放射性廢棄物管理法規與管制實務 · 2017-04-17 · assessment of core desgn, KTA 3107… Dipl. Ing. Peter Klein: Master degree Mechanical Engineering, Radioac tive

德國放射性廢棄物管理法規與管制實務

TÜV SÜD TÜV SÜD

Waste Management of Nuclear Facilities in Germany

Seminar on regulations and technology of spent fuel interim storage in Germany

April 19th – 20th, 2017 in Taipei

Dr. J. Shang

Slide 1

TÜV SÜD

1

Contents

Introduction

2 Nuclear Waste Management in Germany

Slide 2

5 Conclusion

3 Repositories for Nuclear Waste in Germany

4 New Development after Fukushima Accidents

TÜV SÜD

1

Contents

Introduction


Slide 3

5 Conclusion



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1. Introduction

Slide 4

Dr. Torsten Thumstädter: PhD. Phys, Radioactive waste management, Safety analysis for waste treatment, tranportand storage, Safety assessment of storage design, thermal hydraulic assessment, safetyassessment of core desgn, KTA 3101…

Dr. Oliver Rabe:PhD. Chemistry, Senior Vice President Global Business DevelopmentRadioactive waste management, Safety assessment of radioactive installations, SNF and HAW storage, Disposal of radioactive waste, Planning and management of International projects

Dr. Jianming Shang:PhD, Chemical Engineering, Radioactive waste management, safety analysis for wastetreatment, tranport and storage, decommissioning nuclear facilities, Safety assessment ofstorage design, attending controls of waste disposal, project management, KTA 2101…

TÜV SÜD

1. Introduction Video Conferece

Slide 5

Dr. Olena Yevetska: PhD, Phys, Safety assessment of waste treatment, tranport and storage, calculation of heatremoval, Safety assessment of storage design, attending controls of waste disposal, KOBAF...

Dipl. Phys. Andreas Vest:Master degree Phys. Criticalty assessment, Safety assessment of waste treatment, tranportand storage, Safety assessment of storage design, thermal hydraulic assessment, safetyassessment of core desgn, KTA 3107…

Dipl. Ing. Peter Klein:Master degree Mechanical Engineering, Radioactive waste management, safety analysis forwaste treatment, tranport and storage, Safety assessment of storage design, attendingcontrols of waste disposal, Castor loading coordination, KTA 3902, 3903, 3905…

TÜV SÜD

Our heritage: 150 years of business success

Establishment of a Mannheim-based steam boiler inspection association by 21 operators and owners of steam boilers, with the objective of protecting man, the environment and property against the risk emanating from a new and largely unknown form of technology

1866

First vehicle periodic technical inspection (PTI)1910

1958 Development of a Bavaria-wide network of vehicle inspection centres in the late 1950s

1926 Introduction of the “TÜV mark / stamp” in Germany

1990s Conglomeration of TÜVs from the southern part of Germany to form TÜV SÜD and the expansion of business operations into Asia

TÜV SÜD continues to pursue a strategy of internationalisation and growth

Today

2006 Expansion of services in ASEAN by acquiring Singapore-based PSB Group

2009 Launch of Turkey-wide vehicle inspection by TÜVTURK

14/04/2017 Corporate Presentation Slide 6

TÜV SÜD

TÜV SÜD Group: Global Presence

Slide 7

Global Headquarters: Munich, Germany

INTERNATIONAL

Euro 930 mio11,900 staff

GERMANY

Euro 1,290 mio12,100 staff

Legend: Countries with TÜV SÜD offices

Regional headquarters

TÜV SÜDTÜV SÜD

TÜV SÜD in numbers: Growing from strength to strength

1 One-stop technical solution provider

800 locations worldwide

employees worldwide 24,000

million Euro in sales revenue 20152,220

150 years of experience

Note: Figures have been rounded off.

Slide 82015-02-12 Nuclear Services

TÜV SÜD

TÜV SÜD nuclear presence worldwide

Power & Systems Steam & PressureTechnology

Chemical,Oil and Gas

Risk Management

Business UnitNuclear Energy

TÜV SÜD AG24,000 employees

TÜV SÜD Mobility TÜV SÜD Industry TÜV SÜD Certification

5 Business Units


TÜV SÜDTÜV SÜD

TÜV SÜD nuclear presence worldwide

Business Unit Nuclear EnergyApprox. 1000 Experts

H.-M. KursaweQuality Assurance Business Support

Dounreay

SellafieldWarrington Harwell

Winfrith

Gloucester

Mannheim

Filderstadt Munich

Seoul

Busan

Daejeon

Kori

Nuclear Technologies

90 expertsGLOUCESTER, UK

S. Browning

TÜV SÜD Energietechnik

200 expertsFILDERSTADT, GERMANY

H.-M. Kursawe

TÜV SÜD KOCEN SERVICES

360 expertsSUNGNAM, KOREA

S.-S. Cha

TÜV SÜD Industrie Service

Energy and Technology250 experts

MUNICH, GERMANYS. Kirchner


TÜV SÜD

Our heritage: more than 60 years of nuclear business success

Middle of the fiftiesTÜV-participation in evaluating and examination ofresearch centres and nuclear facilities

1955

SixtiesFoundation of nuclear departments in the TÜVTÜV-participation in evaluating and examinationof construction of several research reactors and pilot power reactors

1960

1970 Middle of the seventiesFoundation of the association of the „Nuclear“ TÜV which is responsible for exchange ofexperience and technical guidelines for the TÜV activitiesParticipation in licensing and supervisionprocedures of the construction, operation and decommissioning &dismantling of NuclearPower Plants, research reactors, conditioninginstallations, waste storage and wastedisposals.Today

14/04/2017 Corporate Presentation Slide 11

TÜV SÜD

2. Design• Examining conformity with regulation• Finite Element Analysis• Supplier specification check• Risk Assessment• Safety Justifications• Development and evaluation of

safeguards (e.g. fire, explosion, lightning, flooding etc.)

BUNE Services During the Life Time Cycle of a NPP

• Technical and environmental Due Diligence• Preparation of technical specifications• Engineering services for design review of

systems and materials• Consulting support• Review of concept design

1. Planning and Preparation

• Pre-selection and auditing of Manufacturers• Manufacturing supervision• QA/QC on behalf of the client• Notified Body Services, Third-Party

inspection, Type approval (e.g Manufacturer certification as per international rules and standards, such as PED, ASME, ISO 9001:2008 acc. ISO/IEC 17020)

3. Component Manufacturing

4. Construction• Site Supervision• Expediting• QA /QC on behalf of the client• Site Management, health and safety coordination• Notified Body Services, Third-Party Inspection

5. Commissioning

• Acceptance and Performance tests• Warranty Demonstration test• Emission measurement• Leak Testing

6. Operation• Failure investigation, analysis and optimisation

concepts / Accident Management• Stress Test / Special Reviews (e.g. QA-Systems)• Life time assessment / Plant Inspections• Rehabilitation and upgrading • Risk oriented inspection and Maintenance

• Feasibility studies for decommissioning concepts of nuclear facilities.

• Characterization of radioactive waste with mobile measuring equipment on-site

• Radiological protection.• Assessment of concepts for intermediate and final

waste storage• Assessment and documentation for radioactive

material transportation

F ibilit t di f d i i i tity studies for decommissioning coit t di f d i i i

7. Decommissioning

Slide 122016-04-07

TÜV SÜD

The nuclear power plant life cycle

Licensing for nuclear power plants (NPP)

Design and construction of

NPPsNuclear power plant operation

Nuclear decommissioning

Additional nuclear services provided by TÜV SÜD: • Safety assessment of nuclear installations• Radiation protection• Nuclear fuel supply and waste management


TÜV SÜD

1

Contents

Introduction


Slide 15

5 Conclusion



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Brunsbüttel

GreifswaldBrokdorf

KrümmelStadeUnter-weser

EmslandGorleben

RheinsbergLingen Grohnde Asse

MorslebenKonrad

Ahaus

WürgassenHamm-Uentrop

Duisburg

Jülich

Mülheim-Kärlich

Biblis Kahl

Grafenrheinfeld

MitterteichPhilippsburg

ObrigheimKarlsruhe

NeckarwestheimGundremmingen Isar

Niederaichbach

Nuclear power plant

Authorisation for electricity production expired in 2011according to the last revised German Atomic Act Amendment

Nuclear power plant shut down

Nuclear power plant completely decommissioned

Research facility with wastetreatment facility

Waste treatment facility

Central interim storage facility

Repository

1 Exploration

2 Emplacement completed

3 Construction

Nuclear power plants and their corresponding disposal facilities in Germany

Nuclear Waste Management in Germany

Source: VGB

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Status of German NPP after Fukushima

Slide 17Nuclear Services

Technical Support for Licensing Authority in the federal states of GermanyNuclear Power Plant Type Nominal Output

(Gross) MWIn Operation

GKN-1 Neckar PWR 840 NO

GKN-2 Neckar PWR 1.395 YES (until 2022)KBR Brokdorf PWR 1.440 YES (until 2021)KKB Brunsbüttel BWR 806 NO

KKE Emsland PWR 1.400 YES (until 2022)KKG Grafenrheinfeld PWR 1.345 NoKKI-1 Isar BWR 912 NO

KKI-2 Isar PWR 1.475 YES (until 2022)KKK Krümmel BWR 1.316 NO

KKP-1 Philippsburg BWR 926 NO

KKP-2 Philippsburg PWR 1.458 YES (until 2019)KKU Unterweser PWR 1.410 NO

KRB B Gundremmingen BWR 1.344 YES (until 2017)KRB C Gundremmingen BWR 1.344 YES (until 2021)KWB A Biblis PWR 1.225 NO

KWB B Biblis PWR 1.300 NO

KWG Grohnde PWR 1.430 YES (until 2021)

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Where is waste produced in Germany?

Radioactive residual products and waste are mainly produced:• in connection with power generation by nuclear power plants• during research and development activities• during decommissioning and dismantling of nuclear facilities• in industry and, small quantities, also in the medicine sector

Producer (waste producer/producer liable for disposal) of radioactive waste in Germany are divided into the following groups: • Nuclear power plants• Decommissioned nuclear power plants• Nuclear industry (e. g. manufacturing of fuel elements)• Reprocessing (Reprocessing facility Karlsruhe)• Federal state collecting facilities (including central collecting facilities for

radioactive waste of the Bundeswehr (German Federal Armed Forces))• Research facilities

Slide 18

TÜV SÜD Slide 19

radioactivity / waste declaration

heat generatingwaste

highlyradioactive

examples for waste final storagedistribution

total appearance of waste

intermediatelevel

low-level

waste generatingnegligible heat

Fission products from nuclear fuel repossession Conditioned fuel elements

e.g. final storage Gorleben

5 % of the waste volume with 99 % radioactivity

Core components

Reprocessing waste

Waste from operation of a NPPDecommissioning waste

final storage Konrad

95 % of the waste volume with 1 % radioactivity

Bq / m3

1016

1014

1012

1010

108

© VGB-Folien

Classification of Radioactive Waste

Source: VGB

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Source: GRS

Nuclear Facility Decommissioning Operation DismantledNPP 22 8 3

Research Reactor 8 3 28Fuel Cycle 1 2 5

Nuclear Waste in Germany

Heat Generating Waste Negligible Heat Generating Waste

Waste from Nuclear Power Generation

Waste(NPP, Industry,Research etc.)

Waste(Enrichment)

Waste(Asse II Mine)

28,000 m3 Ca. 300,000 m3 100,000 m3 200,000 m3

Activity > 99% Activity < 1%

Slide 20

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RadioactivityBq / m3

106

1014

1012

1010

108

2 m32 m32 m3

18 m3

1 m3

170 m3

2 m3

2 m3

nodular resinsfilter cartridgesmetal elementsevaporator concentrates

filter concentrates and sludgesolid waste

nodular resins

oils

© VGB

Typical Waste of a NPP with PWR

Slide 21

e.g. raw waste of a 1,300 MW plant per year and scope of radioactivity

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Liquid wasteSolid wasteType of waste

Raw waste

Conditioning

Waste products

Final storagecontainer

Metal parts,debris,i. a.

Metal parts,insulation,i. a.

Paper,plastics,textiles, i.a.

Oil Sludge Evaporatorconcentrate

Filter concentrate

Ion-exchange resin

Combustion Desiccation, drainage, cementation

compression

Solid waste Pellet Salt rock, granulate, powder,cement block

e. g. container, cast-iron packaging e. g. container

© VGB

Waste Management

Slide 22

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Total mass of a control area(PWR reference power plant)

156,500Concrete & reinforcement

Plant components

Radioactive waste(concrete/reinforcement)Material for safe re-use

Waste for conventionaldumpingRadioactive waste(plant components)Radioactive waste(secondary waste, e.g.from decontamination)

for final storage

for safe re-use

for dumpingfor final storagefor final storage

600

9,800

7003,000

13,500500

for free re-use 143,000

© VGB

Waste Management

Slide 23

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Waste Management – Disposal Concept GKN1

Slide 2414/04/17

Note: Removal = In Germany removal refers to a proceeding for the release of non-contaminated and non-activated substances as well as movable goods, buildings, facilities or part of facilities (in this section shortly referred to as “substances”) from nuclear supervision, unless the substances stem from the controlled 42 area.

Total massGKN I

330,900 Mg

Mass outside control area

202,900 Mg

Clearance on non-dismantledbuildings

119,200 Mg

Plant componentsmass to bedismantled

7,500 Mg


16,600 Mg

Massbuildings

186,300 Mg

Massbuildings

120,500 Mg

Radioactiveresiduals from

dismantling

11,125 Mg

Radioactive wastefrom dismantling

975 Mg

Non-radioactiveresiduals from

dismantling

13,300 Mg

Clearance/removalon non-dismantled

buildings

186,300 Mg

Additional masses

500 Mg Nuclearmaterial cycle

300 Mg

Clearance acc. to 29 StrSchV

9,700 Mg

Disposal asradioactive

material

2,800 Mg

Secondarywaste

200 Mg

120,500 7,500

119,200 1,300 6,525 9753,300 13,300

16,600 168,300

Mass controlarea

128,000 Mg

300 9,275 1,55075425

975

200

© EnBW

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Waste Management – Disposal Concept KKP 1

Slide 2514/04/17

Total massKKP 1

397,400 Mg

Mass outside control area

174,900 Mg

Clearance on non-dismantledbuildings

194,700 Mg


22,400 Mg


8,900 Mg

Massbuildings

166,000 Mg

Massbuildings

200,100 Mg

Radioactiveresiduals from

dismantling

27,750 Mg

Radioactive wastefrom

dismantling

1,150 Mg

Non-radioactiveresiduals from

dismantling

7,800 Mg

Clearance/removalon non-dismantled

buildings

166,000 Mg

Additional masses

500 Mg Nuclearmaterial cycle

500 Mg

Clearance acc. to 29 StrSchV

24,950 Mg

Disposal asradioactive

material

4,300 Mg

Secondarywaste

350 Mg

200,100 22,400

194,700 5,400 21,250 11501,100 7,800

8,900 166,000

Mass controlarea

222,500 Mg

500 24,550 2,700

100400

1,150

350

Note: Removal = In Germany removal refers to a proceeding for the release of non-contaminated and non-activated substances as well as movable goods, buildings, facilities or part of facilities (in this section shortly referred to as “substances”) from nuclear supervision, unless the substances stem from the controlled 42 area.

© EnBW

TÜV SÜD

Waste Management – Disposal Concept GKN I / KKP 1

[Mg] Total mass Rad. waste Clearance Clearance/RemovalBuildings

KKP 1 397,400 4,300 [1,1 %] 24,950 [6.3 %] 360,700 [90,8 %]GKN I 330,900 2,800 [0,8 %] 9,700 [2.9 %] 305,500 [92,3 %]

Slide 2614/04/17

© EnBW

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Waste Management – Disposal Concept GKN I / KKP 1

Packaging example of radioactive waste - GKN I

Slide 2714/04/17

Type of repository container QuantityMOSAIK Container 245Konrad-Container Typ III 117Konrad-Container Typ IV 206Konrad-Container Typ V 28Sum 596

2,800 Mg

MOSAIK-Container Konrad-Container© EnBW

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Central Decontamination Department (HDB)

Slide 2814/04/17

Preparation for Repository KONRADAccording to the German waste disposal concept, separate radioactive waste repositories are envisaged for:• Heat-generating wastes (final storage still open)• Wastes with negligible heat production (LAW, MAW)

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Wet storage in the water pool

• Less expensive installation but higher operatingcosts

• Active cooling systems, water purification and airfiltration necessary

• Inclusion of the radioactive inventory only throughfuel element cladding tubes possiblyinsufficient protection against external effects(Fukushima!)

• Accelerated aging effects – corrosion, gas formation (hydrogen) as a result of radiolysis andcasing tube damages

Dry storage in vessels

• More expensive installation but less operatingcosts

• Passive natural convection-air cooling, largelymaintenance-free

• Inclusion of the radioactive inventory through fuelelement cladding tubes and thick-walled vessels

effective protection against external effects• Reduced aging effects• Minimum decay time in the cooling pool

necessary

Options for the long-termed interim storage of spent fuel elements


Slide 29

Dry storage is theprefered alternative fromthe safety-related point

of view

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Dry storage of spent fuel elements

CASTOR-System• Vertical storage of fuel elements in thick-walled metallic vessels• Sealing through double lid system with high sealing requirement• Vessel ensures shielding, heat removal, protection against external

effects, criticality safety• In Germany: site interim storage from type STEAG, GNS/WTI, GKN

tunnel

NUHOMS-System• Horizontal storage of fuel elements in welded, thin-walled vessels• Transportation in a shielding-vessel• Storage in concrete compositions• Overall structure ensures shielding, criticality safety, heat removal,

protection against external effects• In USA, Armenia, Ukraine (Tschernobyl)


Slide 30

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Slide 31

Interim storage concepts abroad:NUHOMS-System

• Components: transportable stainless steel canister in horizontal, modular storage structures of reinforcedconcrete; transfer vessel

• Used amongst others in USA and Armenia, also plannedfor ISF-2 in Tschernobyl/Ukraine

Source: GRS

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Slide 32

Interim storage concepts abroad:NAC Multi-Purpose Canister System

• Components: transportable stainless steel canister; vertical storage vessels ofreinforced concrete; transfer vessel

• Used especially in USA

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Review to the history of dry interim storage

1977 Planings for a nuclear waste management centre in Gorleben and a wet storage in Ahaus

03.10.1979 Request for a TLB-Storage in Ahaus

03.04.1980 Request for a TLB-Storage in Gorleben

05.09.1983 license for Gorleben (First storage 26.04.1995)

10.04.1987 license for Ahaus (First storage 25.06.1992)

06.1992 First vessel-loading for the dry interim storage

1994 Additional to the reprocessing the direct final storage is allowed

2000 At every nuclear power plant site an interim storage has to be built

01.07.2005 Only direct final storage as allowed disposal route

23.07.2013 Act to site selection of repository for radioactive waste with heat generation (> 2 kw/m3 )

31.12.2013 Also reprocessing-wastes have to be stored local


Slide 33

TÜV SÜD

Final storage

Directfinal storage

Storage in the fuel pool of the NPP

Spent fuel elementsNew

fuelelements

Nuclear power plant

Intermediate storage in the central interimstorage facility or in the interim storage facility on-site

ConditioningReprocessingWaste

Fuel element manufacturingUranium &plutonium return

© VGB-Folien

How to Dispose Fuel Elements in Germany

Slide 34

Not allowed in Germany by law since 01.07.2005

TÜV SÜD

11 billion (109) kWh

2 bulk containers-Transport andintermediate storage- e.g. type CASTOR®

Fuel element storage

Final storage e.g. 4 POLLUX® final storage containers

Nuclear power plant40 fuel elements( 21 t nuclear fuel)

Fuel element conditioning

© VGB-Folien

Disposal of Fuel Elements

Slide 35

Direct final storage; figures regarding a pressurized-water reactor per operating year

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Requirements on the design of a transportation and storage vessel

• Inclusion of the radioactive inventory• Removal of decay heat• Warranty of subcriticality• Shielding of ionized radiation• Safe handling and safe transportation


Slide 36

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Requirements on the design of a transportation and storage vessel

• Inclusion of the radioactive inventory• Removal of decay heat• Warranty of subcriticality• Shielding of ionized radiation• Safe handling and safe transportation


Slide 37

Protection LidSecondary LidHe-FillingNeutron Shielding (PE)Primary Lid

Trunnions for Handling and Tie-Down

Nodular Cast Iron Shell

Neutron Shielding

Trunnions for Handling

Cooling Fins

Wall thickness: ca. 420 mmLoaded Weight: max. 130 t © GNS

TÜV SÜD


Slide 38

Secondary Lid

Pressure Switch

Neutron Shielding

He Positive Pressure 6 bar

Primary Lid

He Negative Pressure 0,5 bar

Source: GNS

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Castor for spent fuel and Canister

Folie 3914.04.2017

Source: GNS

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Slide 40

Interim storage concepts in Germany

Concept

ConceptConceptair inletair

inlet

Inlet air

Exhaust air

Source: GRS

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Slide 41

Status of interim storage in Germany

Central interimstorage

Site interimstorage

Interim storage In operation

since

storedvessels

(31.12.2014)

TotalAround 850 casks will still be added until the final exit from the nuclear energy of Germany

© GRS

Interim Storage Vessels In Operation since

TBL Ahaus 329 June 1992

TBL Gorleben 113 April 1995

Lubmin 78 Nov. 1999

AVR Jülich 152 August 1993

Biblis KWB 74 18.05.2006

Brokdorf KBR 29 05.03.2007

Brunsbüttel KKB 11 02.05.2006*

Emsland KKE 38 05.04.2007

Grafenrheinfeld KKG 21 27.02.2006

Grohnde KWG 30 27.04.2006

Gundremmingen KGG 48 25.08.2006

Isar KKI 35 12.03.2007

Krümmel 29 14.11.2006

Neckarwestheim GKN 53 10.12.2002

Philippsburg KKP 58 06.12.2006

Unterweser KKU 27 19.03.2007

Lingen KWL 32 18.06.2007

Total 1157

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Waste Management

Interim storage

TÜV SÜD Slide 4214/04/17

Interim storage for spent fuel (examples)

Castors in interim storage © www.zeit.de

TÜV SÜD

1

Contents

Introduction


Slide 43

5 Conclusion



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Repositories for Nuclear Waste in Germany

Source: VGB


Former exploration mine for nuclear waste GORLEBENRock SaltHAWRepository for nuclear waste MORSLEBEN (Rock Salt)Former repository for

Repository for nuclear waste KONRAD (Iron Ore/Clay))Repository for

Former test repository for nuclear waste ASSE II (Rock Salt)Former test repository for

retrieval (ca. 200.000 m3)Slide 44

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Source: VGB

Gorleben for Radwaste with heat generation > 2 kW/m3

1977 : Site selection

1979 - 1985: exploration (surface)

1986 – 2000: exploration (underground)

01.10. 2000: Moratorium (10 a)

2010: Safety Assessment by GRS

2013: Act to site selection of repository

Volume: - m3

Activity: Bq

Exploration Gorleben

Slide 45

TÜV SÜD

Repositories for Nuclear Waste in GermanyFormer Repository Morsleben for Radwaste with heat generation < 2 kW/m3

1970: Site selection GDR

1986: Commissioning

1990: FRG

1998: Stop of the storage

2001: BfS decision: Decommissioning

2009: Plan-approval procedure

(13000 objections)

2013: ESK Safety review

Volume: 36.754 m3

Activity: β/γ: x 1013 Bq α:1,8 x 1014 Bq

Repository Morsleben

Slide 46

TÜV SÜD


Source: VGB

Repository Konrad for Radwaste with heat generation < 2 kW/m3

1965 - 1976 : Iron mine

1976 - 1982: exploration

1982 - 2002: Plan-approval procedure (20 a)

2007: Ende of the legal process for

objections

Status: Construction

2022: Commissioning

Volume: 303.000 m3

Activity: : 2 x 1018 Bq; : 1,5 x1017

Repository Konrad

Slide 47

TÜV SÜD

Repositories for Nuclear Waste in GermanyFormer Repository ASSE II for Radwaste with heat generation < 2 kW/m3

1909 - 1964 : Rock salt mine

1965 - 1967: exploration for

1967 - 1978: operation

1995 – 2008: Closedown

2009: Stop operation

2010: decision for „retrieval“

2013: act for acceleration of retrieval

2033: Begin of retrival

Former Repository ASSE II

Slide 48

TÜV SÜD


National action plan:

Nuclear waste disposal: National responsibility (domestic)

Spent fuel from research reactor: Return to country of origin.

Two repositories in Germany: Repository KONRAD and repository according to StandAG

Waste from ASSE II and uranium enrichment have to be considered by construction of repository

Repository KONRAD for nuclear waste with heat Generation < 2 kW/m3: Commssioning 2022

Repository for nuclear waste with heat Generation > 2 kW/m3 : Site 2031, Commissioning 2050

Waste from reprocessing in interim storage for nuclear waste with heat Generation > 2 kW/m3 on site

Decommissioning MORSLEBEN

Slide 49

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1

Contents

Introduction


Slide 50

5 Conclusion



TÜV SÜD Slide 51

New Development after Fukushima Accidents

08.2011: Acceleration of phase out of nuclear energy

07.2013: Act to site selection for repository

01.2014: The Federal Office for the Safety of Nuclear WasteManagement (BfE)

06.2015: National action plan for nuclear waste management

12.2016: German court decision: Compensation for ESC

01.2017 Agreement between government and ESC01.2017 Reorganization of responsibilities in nuclaer disposal

1 Establishment of a fund to finance the nuclear disposal2 Disposal transitional law

…

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03.2017Slide

Modification of Act to site selection for repository

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1

Contents

Introduction


Slide 52

5 Conclusion



TÜV SÜD Slide 53

Conclusion

Status of nuclear facilities in GermanyQuantity of nuclear waste in GermanyStrategy for waste treatment in Germany Histroy of site selection of repositoryNational action plan acc. guideline of 2011/70/ EuratomSteps of nuclear waste disposal in Germany

TÜV SÜD

Thank you for your attention

Slide 54

TÜV SÜD TÜV SÜD

Laws and Regulations Waste Management in Germany

Seminar on regulations and technology of spent fuel interim storage in Germany

April 19th – 20th, 2017 in Taipei

Dr. J. Shang

Slide 1

TÜV SÜD

1

Contents

Nuclear Regulation in the Federal System

2 The German Safety Law, Acts & Ordinances, Guidelines & Technical...

Slide 2

5 Example: Dry Cask Storage of Spent Fuel & Waste (>2 kW/m3)

3 German Licensing and Supervision Procedures

4 Requirements of Application Documents and Assessment Issues

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1

Contents



Slide 3




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Slide 4

Germany is a federal state with:

• federal government

• 16 state governments

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States

Nuclear Regulation in the Federal System: Who is doing what?

Slide 5

Berlin

LegislationAdministration(Execution of laws)

Federation

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Slide 6

Operators of NPP

The Regulatory Body

instruction

Federal Ministry of Environment, Nature Conservation, Building and Nuclear Safety (BMUB)

Ministry of Environment e.g. Baden-Württemberg (UM BW)responsibility for supervision & licensing

Supersion licensing

reports

Level

Federation

State

responsibility for regulations, guides & advisory groups

TSO, Offices Consulting BodiesBfS/BfEESK, RSK,GRS…

TSOTÜVGRS, MPA

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1

Contents



Slide 7




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Licensing - Requirements according to 7 AtG

Slide 8

What does “necessary damage prevention” mean? Or - how do we know: “How safe is safe enough?”

The German safety regulations put this prerequisite into concrete terms and help the state authorities and the TSOs to decide whether proposed measures are sufficient and acceptable.

guidelinesrecommendations

laws ordinances

national and international rules e.g. KTA rules, DIN ISO rules

Legislation (Federation)

Federation and the States

experts from industry,expert organizationsand authorities

TÜV SÜD

Atomic Energy Act (27, January 2017)

Slide 9

Act on the Peaceful Utilization of Atomic Energy and the Protection against its Hazards (Atomic Energy Act, AtG)Purpose of the AtG:

• to phase out the use of nuclear energy for the commercial generation of electricity … ensure orderly operation up until the date of termination

• to protect life, health and real assets against the hazards of nuclear energy and the harmful effects of ionizing radiation …

• to prevent danger to the internal or external security of the Federal Republic of Germany from the application or release of nuclear energy or ionizing radiation

• to enable the Federal Republic of Germany to meet its international obligations in the field of nuclear energy and radiation protection

TÜV SÜD

Atomic Energy Act

Slide 10

Includes an important paragraph for decommissioning & dismantling:

7 Licensing of installations:

(3) The decommissioning of an installation as defined in … as well as the safe enclosure of an installation definitively decommissioned, or the dismantling of an installation or of parts thereof shall require a licence. …

TÜV SÜD

Atomic Energy Act

Slide 11

Includes an important paragraph for Storage of Spent Fuel:

6 Licensing of installations for Storage of Spent Fuel:

- Every storage besides the state storage requires a license

- The license shall be given, if- Reliability and qualification of responsible persons,- Required preventions against damage in line with the state of the art in science

and technology - Required prevention for the fulfillment of legal liability for damages and- Required protection against disruptive action or other third-party influencesare guaranteed

23: Responsibility of the Federal Office for Radiation Protection and the FerderalOffice for Nuclear Waste Management (BfS/BfE)

TÜV SÜD

Atomic Energy Act

Slide 12

Includes an important paragraph in context withsupervision

20 Authorized experts“In the licensing and supervisory procedures hereunder or under the statutory ordinances issued hereunder, the authorities in charge may consult authorized experts. …”

privatly organized Technical Support Organisations (TSOs), in the state Baden-Württemberg mainly the TÜV SÜD ET.

TÜV SÜD

Ordinances: StrlSchV

Slide 13

Ordinance on the Protection against Damage and Injuries Caused by Ionizing Radiation(Radiation Protection Ordinance, StrlSchV)

Purpose of the StrlSchV:

Regulates principles and requirements of preventive and protectivemeasures which apply to the use and effects of man-made and naturallyoccurring radioactive substances and ionizing radiation in order to protect man and the environment from the harmful effects of ionizing radiation.

TÜV SÜD

Requirements that Have to Be Met by the Applicant

Slide 14

Requirements for decommissioning or construction of interim storageaccording to the Ordinance on the Nuclear Licensing Procedure (AtVfV)

2. Form and contents of the application

(1) The application shall be submitted in writing to the licensing authority. (2) The application shall specify

1. the name and address or head office of the applicant; 2. whether the application refers to a license or an advance notice; 3. the site, type and size of the installation

3. Kind and scope of the documents (1) The application shall be accompanied by the documents needed to examine

the licensing prerequisites, in particular

1. a safety analysis report 2. supplementary plans, drawings and descriptions of the

installation and its components; …..

TÜV SÜD

Ordinances: VwVfG

Slide 15

Administrative Procedure Act (VwVfG)

Purpose of the VwVfG:defines the procedures and the decision principles of the administrative processes (if not governed by the AtG)

TÜV SÜD

Environmental Impact Assessment Act (UVPG)

Slide 16

Environmental Impact Assessment:integrated into procedures for the authorization of specific projects, especially industrial installations and infrastructure projects

• impacts on the environment (including human beings) have to be investigated and described early on

• the public and authorities with environmental responsibilities may give their opinion on the project or plan/programme and the likely environmental impacts

• the authority responsible for authorizing the project takes into account all informations/opinions when deciding on the project

TÜV SÜD

ESK, RSK and SSK Guidelines

Slide 17

ESK: Nuclear Waste Management CommissionRSK: Reactor Safety CommissionSSK: Commission on Radiological Protection

ESK: advises the BMUB in matters of nuclear waste management (conditioning, interim storage and transport, decommissioning and dismantling of nuclear facilities, disposal in deep geological formations)RSK: advises the BMUB in safety-related matters and thus matters concerning the physical protection of nuclear installations and radioactive waste managementSSK: advises the BMUB on issues concerning the protection from the risks of ionising and non-ionising radiation

Binding by specification in the license!

TÜV SÜD

Interim Storage of Spent Fuel Elements

Slide 18

German regulations for the dry interim storage of spent fuel elements and heat-generating radioactive wastes

6 AtG in connection with 9a AtG

ESK-guidelinesFor the dry interim storage of irradiated fuel

elements in casks and heat-generatingradioactive wastes

ESK-guidelinesFor the realisation of periodical safety

reviews and the technical agingmanagement for the interim storage for

irradiated fuel elements and heat-generating radioactive wastes

Fundamental safety targets:• Confinment of radioactive inventory• Removal of decay heat• Warranty of subcriticality• Shielding of ionized radiation• Avoid unnecessary radiation exposure

Retention license(currently limited on 40 years)

Operation of interimstorage

Transportation of casks to theconditioning and final storage

Source: GRS

TÜV SÜD

ESK Recommendations

Slide 19

Guidellines for dry cask storage of spent fuel andheat generating waste, 10.June.2013

1. Confinement of radioactive material2. Criticality safety3. Heat removal4. Shielding of ionising radiation5. Radiation protection6. Structure provisions7. Technical Installations8. Accident analysis9. Self-sufficient operation of the interim storage facility10. Quality assurance11. Operation of the interim storage facility12. Emergency preparedness13. Periodic safety review14. Termination of storage

TÜV SÜD

ESK Recommendations

Slide 20

Guidellines for execution of periodic safety review and technical aiging management of dry cast storage of spent fuel and heat generating waste, 13.03.2014

1. Responsibility and period2. Scope of periodic safety review3. Results of PSR4. Technical aiging management

TÜV SÜD

Harmonization with international regulations

Slide 21

Periodical Safety Review: Euratom: European Atomic CommunityWERA: Western European Nuclear Regulators' Association

Section 6:

Member States shall ensure that the national framework in place requires licence holders, under the supervision of the competent regulatory authority, to regularly assess and verify, and continuously improve, as far as reasonably achievable, the nuclear safety of their nuclear installations in a systematic and verifiable manner.

Safety Reference Level 59:

The licensee shall carry out at regular intervals a review of the safety of the facility (PSR). The review shall be made periodically, at a frequency which shall be established by the national regulatory framework (e.g. every ten years).

Source: GRS

TÜV SÜD

Implementation of PSR in interim storage for irradiated fuel elements and heat-generating wastes in vessels

• First version of PSR-guidelines set up in Nov. 2010 from ESK

• Legal basis: 19a Sec. 3 AtG (launched in Dec. 2010)

• Decision BMUB and ESK: Test of realization of the guidelines in two chosen interim storages (Gorleben, Lingen) before the final implementation

• Pilot project for the implementation of the PSR-guidelines: TBL Gorleben– Start in Oct. 2011– PSR-Report submitted at NMU in May 2013– Report of the technical aging management, expected in 2016– Findings from the pilot project have been entered in the update of the guidelines

• Updated version of the PSR-guidelines published in March 2014Basis for the realization of the PSR in further interim storages

Interim Storage of Spent Fuel Elements

Slide 22

TÜV SÜD

1

Contents



Slide 23




TÜV SÜD

LSP acc. to 7 of ATG or StrlSchV


Slide 24

Expert organizations,e.g. TÜV SÜD ET, GRS, MPA…

Applicante.g. KKP

Application for a license with description and supporting documents

Reports withrecommendations

Order for review onselected subjects Order for review on

selected subjects

Report (withrecommendations)

licencePublic

hearing

Nuclear LicensingProcedure OrdinanceEnvironmental Impact

Assessment Act

Advisory organizations, e.g. RSK, SSK ; other federal state authorities

StateRegulatory Body

e.g. Baden-Württemberg

comments

Federation

TÜV SÜD


Slide 25

LSP acc. to 6 of German Atomic Energy Act

Publicity Applicant

TSO

State Building Authority

State Authorities

supervisory authorityof the state 24 AtG

regulatory authority:BfS/BfE

23 AtG

© BfS

TÜV SÜD

1

Contents



Slide 26

5 Supervision of Dry Cask Storage of Spent Fuel & Waste (>2 kW/m3)



TÜV SÜD

Requirements of Application Documents

Slide 27

© BfS

Requirements of application documents for interim storage according to theOrdinance on the Nuclear Licensing Procedure (AtVfV)

I. Superial Documents

1. Application for construction of an interim storage (ZL)2. Report of Security for ZL3. Safety Analysis Report for ZL4. Description of ZL5. Environmental Impact Assessment6. Authentication of Compulsory Cover (Financial Security)

II. Responsible Person

1. Requisite Qualification of Responsible Person for ZL2. Reliability of Responsible Person for ZL

TÜV SÜD


Slide 28

© BfS

III. Storage Concept

1. Framework Report to Storage of Spent Fuel Assemblies2. Technical Acceptance Condition3. Implementation Regulation4. Safety Guideline for Dry Storage of Spent Fuel Elements Assembies

IV. Site

1. Vegetational Field Mapping 2. Environmental Impact Study3. Analysis of Spread Statistics4. Potential Radiation Exposure by Operation of ZL5. Building Assessment6. Seismic Analysis7. Calculation of Temperatur Circulation8. Design Calculation for Heat Removal from ZL9. Heat Removal from cask

TÜV SÜD


Slide 29

© BfS

IV. Site

10. Underground Water Warming11. Temperatur Change around ZL12. Heat Exchange by Radiation between casks13. Flow Behavior of the Air in ZL

1. Safety Classification of System and Components2. Accidents Analysis3. Monitoring of Ageing Issues4. Plausibility Check of Drops of Casks5. Measures to Impact Force Reduction at Down Position

TÜV SÜD


Slide 30

© BfS

VI. Structural Engineering

1. Description of Building2. Operation Description3. Fire Precautions4. Storage Plan5. Views of Building6. Requirements of Building Design7. Fire Load List8. decontaminable coatings9. Damper Concrete: Plan Manufacture and Installation10. Measurement Program11. Installation Plan

VII. Maschine Technology

1. Description of Crane2. Description of Monitoring System for casks

TÜV SÜD


Slide 31

© BfS

VII. Maschine Technology

3. Description of Cask Handling4. Description of Doors5. Description of Louvre Flap6. Description of Vehicles7. Description of Drinking Water Supply and Waste Water Disposal8. Description of Heating and Ventilation Systems9. Description of Waste Water Treatment in Control Area10. Description of Design and Construction for an extra

Cask Head Schieldung

VIII. Electrical and Control Technology

1. Description of Electrical and Instrumentation and Control Equipment2. Description of Radiation Protection Instrumentation3. Description of Cask Monitoring System4. Consumer Recording

TÜV SÜD


Slide 32

© BfS

VIII. Electrical and Control Technology

5. Grounding and Lightning Protection6. Description of System and Components for Grounding and Lightning

Protection7. Description of Fire Alarm System 8. Description of Uninterruptible Power Supply9. Technical Drawings of Uninterruptible Power Supply10. Backup Power Supply

IX. Radiation Protection

1. Radiation Exposure in the Area of ZL2. Dose Assessment due to Operation of the Interim Storage3. Description of Components for Radiation Monitoring in ZL4. Environmental Monitoring due to Operation of the Interim Storage5. Plan for Arising and Whereabouts of Radioactive Waste ( 72 StrlSchV)

TÜV SÜD


Slide 33

© BfS

X. CASTOR

1. Storage of empty casks inside contaminated 2. Requirement for cladding tubes of fuel assemblies for dry storage3. Investigation of the extensibility of the cladding tube samples from a

fuel rod with 54 MWd / kgU burnup4. Determination of activity inventories of used empty cask via local5. dose rate measurements6. Welding plan7. Manufacturing and inspection sequence plan8. Investigation of corrosion of sealing components by Cs9. Assessment of the long-term corrosion behavior of metal seal 10. Assessment of the long-term behavior of the silver-coated metal seal11. Specification for pressure switch12. Evidence for the exclusion of a systematic failure of envelope tube

inside of CASTOR V/19 or V/52 during the storage

TÜV SÜD


Slide 34

© BfS

XI. CASTOR V/19

1. Description of CASTOR V/19 2. Description of repair concept CASTOR V/19, types lids welded3. Radioactive inventory4. Loading procedure5. Shielding design6. Containment system and internal pressure7. Proof of subcriticality8. Thermal design9. Thermal expansion of the moderator material10. Mechanical design11. Long-term behavior of container components12. Mechanical accident analysis13. Thermal accident analysis14. Parts list15. Relaxation of bolted joints

TÜV SÜD


Slide 35

© BfS

XI. CASTOR V/19

16. Design of the load attaching points17. Mechanical design of the cover and cover bolts18. Long-term function of the pressure switch for monitoring19. Welding plan20. Manufacturing and inspection sequence plan21. Parts list

XII. CASTOR V/52

1. Description of CASTOR V/52 2. Radioactive Inventory3. Loading procedure4. Shielding design5. Containment system and internal pressure

TÜV SÜD


Slide 36

© BfS

XII. CASTOR V/52

7. Proof of subcriticality8. Thermal design9. Thermal expansion of the moderator material10. Mechanical design11. Long-term behavior of cask components12. Mechanical accident analysis13. Thermal accident analysis1. Relaxation of bolted joints16. Design of the load attaching points17. Mechanical design of the cover and cover bolts18. Long-term function of the pressure switch for monitoring19. Welding plan20. Manufacturing and inspection sequence plan21. Parts list

TÜV SÜD


Slide 37

© BfS

XIII. Regulations and Instructions

1. Instruction of handling, operation and maintenance for CASTOR2. Process quality control plans3. Instruction of CASTOR handling

XIV. Operating Documents

1. Operating manual- Personnel operating rules- Storage operating rules- Maintenance rules- Radiation protection rules- Guard and access rules- Alarm rules- Fire protection rules- First aid rules- Documentation rules

TÜV SÜD


Slide 38

© BfS

XIV. Operating Documents- Prerequisites and conditions for operation- Safety-related limits- Reporting criteria- Normal operation- Abnormal operation- Accidents- Operation of the systems and fault and alarm signals- Inspection and maintenance manual- CASTOR installation plan

XV. Quality Control - Quality management manual- Quality assurance for building- Quality assurance for CASTOR

TÜV SÜD


Slide 39

© BfS

XVI. Interaction with other systems- Interaction with reactor I and reactor II - Interface description between 6 und 7 AtG- Self-sufficiency of ZL- License from responsible authority acc. 7 StrlSchV

XVII. Others

- Description acc. Art 37 Euratom- Accidents analysis for European Commission

TÜV SÜD

Assessment Issues

Slide 40

© BfS

Licence was granted by BfS (2003-12-19)

Expertise of ZL was carried out by TÜV NORD & TÜV SÜD (2003-12)(TÜV SÜD: Site-specific aspects)

Expertise of CASTOR V/19: was executed by TÜV SÜD (2003-12)

Expertise of CASTOR V/52: was conducted by TÜV SÜD (2003-12)

Expertise of seismic issues: was performed by BAG (2003-10)

Expertise of UVP (EIA) was realized by Öko-Institute (2003-12)

Expertise of storage of CASTOR V/19: was performed by TÜV NORD(2003-12)

Expertise of storage of CASTOR V/52: was executed by TÜV NORD(2003-12)

TÜV SÜD

KOBAF

Slide 41

© BfS

KOBAF: Coordination Office for Information on Cask Handling

BMUB: Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety

ESK: Nuclear Waste Management Commission

State authorities

BAM: Federal Institute for Materials Research

TÜV SÜD:

TÜV NORD:

GNS: Gesellschaft für Nuklear-Service mbH

Operators:

TÜV SÜD

Assessment Issues

Slide 42

© BfS

Following aspects have to be considered by the assessment

1 SiteGeographical location, population distribution, soil and water use, commercial and industrial issues, military installations, traffic routes, meteorological, geological, hydrological and seismological conditions, radiological preload on site…

2 Interim StorageProtection objectives and requirements derived therefrom; rules and standards; construction, arrangement and development, dimensions, allocation and use; construct, structuaral design, service loads during normal operation, special charges of impacts from inside and outside, load combinations and design; accompanying control of construction and documentation; service life; changes and deviations during construction; technical equipments, lifting and handling equipment, storage hall crane, shielding doors, entrance gates; CASTOR service station, electrotechnical equipment, earthing and lightning protection

TÜV SÜD

Assessment Issues

Slide 43

© BfS


2 Interim Storageinstrumentation and control equipment, CASTOR monitoring system, communication systems, process wastewater collection system, ventilation systems; fire protection plan and equipment; container and container inventories; quality control, quality assurance during construction and operation, quality assurance and production of CASTOR, documentation; long-term and ageing effects, long-term monitoring, concept against ageing, progression of the state of science and technology, structural engineering ageing, equipment ageing, electrical and I & C ageing, peronnel ageing, ageing of documentation…

3 Removal of the decay heat from the storage building Temperatur of storage building, exhaust temperatures, componenttemperatures and –temperature differences, temperatures of the building walls and the building ceiling, temperature of the storage building floor, temperature differences in the concrete components,

TÜV SÜD

Assessment Issues

Slide 44

© BfS


3 Removal of the decay heat from the storage building Temperatur of storage building, exhaust temperatures, componenttemperatures and –temperatuere differences, temperatures of the building walls and the building ceiling, temperature of the storage building floor, Temperature differences in the concrete components, heat removal from the loading area to the maintenance station, CASTOR temperature…

4 Radiation protection

Rules and standards, shielding measures and dose rates, shieldingconcept, methods for calculation of shielding, dose rate in the control area, dose rate in the monitoring area, dose rate on the premises outside of the monitoring area and at the boundary of the premises, maximum potential radiation exposure on the border of premises including radiological preload; operational radiation protection, spatial distribution and radiation protection areas, radiation protection measures in theworkplace, radiation exposure of personnel,

TÜV SÜD

Assessment Issues

Slide 45

© BfS

Following aspects have to be considered by the assessment4 Radiation protectionScope of other radioactive substances, treatment of residues and waste, kindand operating conditions of the test source, empty CASTOR and insidecontaminated CASTOR, bringing out of goods or materials from the controlled area, organizational radiation protection measures; radiation monitoring, monitoring concept, place dose rate monitoring, contamination monitoring, radiological monitoring of ambient air in storage, personal monitoring, environmental monitoring, discharge of radioactive materials and radiation exposure in the environment…

5 Operation of the interim storageOperations, commissioning, operational manual, testing manual, technical acceptance criteria and rules, handling of CASTOR, amendment procedure

6 Interactions with existing nuclear power plantsEquipment and systems engineering connections with existing nuclear power plant, impact of events of existing nuclear power plant…

TÜV SÜD

Assessment Issues

Slide 46

© BfS


7 Accident analysisImpacts from inside, mechanical effects, thermal effects, operatingsewage leaks, operator error, failure of utilities, failure of instrumentation and control equipment; external impacts, incidents and accidents in the nuclear power plant, radiation exposure in the area, radiological consequences of design basis accidents, radiological impact of residual risk events…

8 Proof of subcriticalityRules and standards, analyzes and information provided by the applicant, own calculations

9 Decommissioning…13 Recommendations

TÜV SÜD

1

Contents



Slide 47

5 Supervision of Dry Cask Storage of Spent Fuel & Waste (>2 kW/m3)



TÜV SÜD

Supervision of Dry Cask Storage of Spent Fuel & Waste

Slide 48

© BfS

Accompanying control during the construction and operation:

Realization of more than 50 recommendations

Commissioning

CASTOR loading

Periodical inspections

Instruction of inspection

Acceptance of periodical inspections

TÜV SÜD

Realization of more than 50 recommendations

Slide 49

© BfS

Retrofit of security-issues for ZL

New findings from licensing & supervesion procedures:Impact from outsidePublic participation…

New modification in construction

Acceptance test by inspector

TÜV SÜD


Slide 50

TÜV SÜD


Slide 51

TÜV SÜD


Slide 52

TÜV SÜD


Slide 53

TÜV SÜD Energietechnik GmbH Baden-Württemberg Slide 117-04-11

Introduction ofManagement of NuclearFacilities in GermanyGovernment Organization and Resposibilities, Monitoring Mechanism andNotification Provisions

Seminar on regulations and technology of spent fuel interimstorage in Germany

April 19th – 20th , 2017 in Taipei

Dr. T. Thumstädter

Introduction of Management of Nuclear Facilities in Germany


Government Organization for SpentFuel Management

The Role and Resposibility of BUMB, ESK, BfS and BfE

Spent Fuel Intermediate Storage Licensing Process

Current Status of Spent Fuel Storage in Germany

Introduction of Mangement of Nuclear Facilities in Germany


Brief History of Spent Nuclear Fuel (SNF) policy in Germany:

• Until 1994 requirement of reprocessing of SNF in the atomic energy act (AtG = Atomgesetz)• Since 1994 the possibility to choose between reprocessing and direct disposal• Since 2005 prohibition of SNF reprocessing only direct disposal is permitted

But so far no final repository is available, instead

• In 2013 the site selection act (Stand AG = Standortauswahlgesetz) for the search and selection ofa site for final repository for heat generating radioactive waste (esp. SNF) → latest in 2031 a siteshall be selected

Challenge: Handel SNF of 17 nuclear power plants (NPP) and several research reactors with therequirement of direct disposal with no exsiting repository

→ SNF interim storage on site unitl a final repository is available

1. Government Organization for Spent Fuel Storage Management




Structure of the Nuclear Supervision in Germany

Ferderal Structure in Germany

Bund (Federal Government)

Länder (sing. Land) (States, local Governments with competence in certain fields e. g. education)

Nuclear Supervision and Licencing

Bund Laws, ordiances and anouncements

Länder Execution of the regulations

But the authorities of the Bund can give directives to the Länder authorities in certain cases.



1. Government Organization for Spent Fuel Storage ManagementResposibilities

In Germany: Poluter –pays priciple

Repository is refinanced by poluters

StrlSchV = Radiation Protection Ordinance (Strahlenschutzverordnung)

©BMUB

Introduktion of Mangement of Nuclear Facilities in Germany



• Planning, construction and operation ofrepositories

• Repository supervision

• Licensing of storage facilities for nuclear fuel andtransports

• Plan approval and licensing for repositories• Granting of approvals under mining law• Mining supervision• Granting of permits under water law

Independent technical expert organisationse.g. GRS, TUV,..

©BMUB



1. Government Organization for Spent Fuel Storage ManagementSummary of the licensing and supervising structure

Interim Storage (SNF):

Licensing authority: BfELicensee: generater of SNFSupervising authority: Länder ministries (mostly enviroment)

Final Repository:

Licensing authority: BfELicensee: BfSSupervising auhority: BfSOperator: Deutsche Gesellschaft zum Bau und Betrieb von Endlagern und Abfallstoffen

mbH (German Service Company for the Construction and Operation of WasteRepositories, DBE)









2. The Role and Resposibilities of BUMB, ESK, BfS and BfEFerderal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety – BMUB

(Bundesministerium für Umwelt, Naturschutz, Bau und Reaktorsicherheit)

• Resposibily for the effective protection of the people and the environment against the hazards of nuclearenergy and harmful effects of ionizing radiation

• Promotes the government‘s policy

• Three directorates (Safety of Nuclear Facilities, Radiation Protection, Nuclear Fuel Cycle)

• Supervises the ministeries of the Länder

• Has the possibility for directives in individual cases

• http://www.bmub.bund.de/en/



2. The Role and Resposibilities of BUMB, ESK, BfS and BfEAdvisory Commissions• The BMUB can get advice from commissions of independant experts• The members of the commission represent a broad view of positions according to the state of the

art in science and technology with reference to the concerning issue• Comissions can set up working groups with additional experts for in-depth considerations• General appoinment of a commission member is 3 years. Reappoinments in succession should

not be more than 6 yearsNuclear Waste Management Commission – ESK

(Entsorgungskommission)• Founded in 2008• Successor of the Reactor Safety Commission in the matters of fuel supply and waste

management• 13 members (Germany, France, Switzerland)• Advises the BUMB in the fields: conditioning, storage and transport of rad. waste,

decommissioning and dismanteling, disposal in deep geological formations• http://www.entorgungskommission.de/EN



2. The Role and Resposibilities of BUMB, ESK, BfS and BfECommission on Radiological Protection – SSK

(Strahlenschutzkommission)• Founded in 1974• 18 members• Gives recommendations on all issues related to the protection of the public and empoyees of

medical facilities, research, industry and nuclear nuclear facilities against ionizing and non-ionizingradiation

• Sets up the SSK Crisis Management Group in case of radiological or nuclear incidents orcorresponding execises

• http://www.ssk.de/ENReactor Safety Commission – RSK(Reaktorsiocherheitskommission)

• Founded in 1958• 17 members• Recommendations on issues related to nuclear safety and physical protection of NPP• http://www.rskonline.de/EN



2. The Role and Resposibilities of BUMB, ESK, BfS and BfE

Federal Office of Radiation Protection – BfS(Bundesamt für Strahlenschutz)

• The construction and operation of federal facilities for the safekeeping and the disposal ofradioactive waste, the Asse II mine, the transfer of tasks to third parties and the supervision of theparties

• Decisions concerning exeptions from the duty to construct a storage facility on site of a NPP after decommissioning is filed

• Various issues concerning the protection against ionizing and non-ionizing radiation

• http://www.bfs.de/EN/



2. The Role and Resposibilities of BUMB, ESK, BfS and BfEFedral Office for Nuclear Waste Management – BfE

(Bundesamt für kerntedchnische Entsorgungsicherheit)

• Plan approval and licensing for a final repsoitories according to § 9b AtG

• Approvals under the relevant mining laws

• Mining supervison of ferral facilities for safekeeping and disposal.

• Approvals under the relevant water protection laws

• Licensing of interim storage facilities and transport casks

• https://www.bfe.bund.de/en/








TÜV SÜD Energietechnik GmbH Baden-Württemberg Slide 15

TSO = Technical Support Organization

17-04-11

3. Spent Fuel Interim Storage Licensing Process

• Licensing of interim storage facilities is regulated in §6 AtG (License is necessary)

Licensing authorityBfE

TSO(§20 AtG)

Licensee




A license due to §6 AtG is bounded,

that means

it has to be granted,

if the licensee fulfils the requirements of §6 AtG




Requirements for a license according to §6 AtG

1. Reliability of the licensee and the appropiate knowledge of the resposible staff

2. Protection against the dangers of the stored fuel at the state of the art with respect to science andtechnology

3. Provision of suffcient finacial rescourses for compensations in the case of a hazard

4. Protection against the attacks of third parties (security)




State of the Art with Respect to Science and Technology for Protection

It means that methods and technics that are recognized as the most suitable in the technical andscientific community have to be applied even there is only one vendor.

It does not mean that the whole facility has to be desigened according to the state of the art withrespect to science and technology

But the safety means resp. provisions.




Duration of the License

• A license due to §6 AtG is granted for 40 years from the entering of the first cask for storage

• An enhancement needs a new approval, the parliament has to consulted









4. Current Status of Spent Fuel Storage in GermanyTreartment of spent fuel in Germany:

Long Term Strategy• Dry interim storage in casks• Subsequently conditioning and possibly direct disposal in deep geological formations• For SNF of research reactors transport to the country of origin or disposal

Current Pratice/Facitities• 4 central dry storage facilities• 12 dry storage facilities at NPP sites• 1 wet storage facility at NPP site (KWO, shall be emptied in 2017)

Planned Facilities

• Final Respository for heat generating radiactive waste is planned; at the moment the site isselected according to the site selection act. Site shall be determined in 2031.



4. Current Status of Spent Fuel Storage in Germany

Conditioning Plants• Pilot Conditioning Plant – PKA (Pilotkonditionierungsanlage)• Located in Gorleben• Completed in 2000• Licensed for a throuput of 35 MgHM/a• Since 2001 PKA is licensed only for repair of defect casks for light water reactor (LWR) fuel and

vitrified high activated waste (HAW) and handling for other radioactive mateials• Conditioning due to the POLLUX-concept has been demostrated (fuel assemblies (FA) are

dissassambeled, rods put into canisters and then in casks and the casks shall be put into saltdomes which are to be fulfiled)

©GNS



4. Current Status of Spent Fuel Storage in GermanyStorage Facilities (interim)

• 4 centralized storage facilities (Gorleben, Ahaus, Rübenow and Jülich)• 12 on-site storage facilities

All dry cask storages with passive air-cooling in reinforced concrete structures

• 1 on-site storage facility, dry cask in tunnels of an old stone pit (GKN)• 1 wet-storage facility at KWO (shall be emptied in 2017 and the SNF shall be shipped to GKN-

site)• About 3,249 MgHM in dry cask storage facilities

©GNS



4. Current Status of Spent Fuel Storage in GermanyFinal Repository

• In 1986 starting to sink shafts into salt at the Gorleben site• Exploration until 2000• Moratorium until 2013• In 2013 final ending of exploration• In 2013 site selection act, Gorleben is considered but not exclusivly• Commission to develope the searching procedure and the involvement of all stake holders has

finished ist work in 2016.• New draft of the site selection act was developed in 2017• Site decision expected in 2031

©GNS



4. Current Status of Spent Fuel Storage in Germany

Overview of total quatities of SNF for German LWR (P > 50 MW) (December 2013)

©BMUB


Slide 26