OE Supply-Chain in Nuclear Dr. Boris Gehring March 2017

Transcription

1 OE Supply-Chain in Nuclear Dr. Boris Gehring March

2 It should not finally look like this!

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4 Owners Engineers and Supply-Chain services In NPP New build, OE and SCS will help to keep: -Time-line -Costs -Quality -Safety in all areas of nuclear plants and facilities focusing on Safety, Reliability and Availability. TÜV SÜD 06/04/2017 Slide 3

5 Owners Engineers and Supply-Chain services By Independent testing Inspection Certification Engineering consulting Training and Assessment Services Examples: TÜV SÜD 06/04/2017 Slide 3

6 Owners Engineer Services as Owner's Engineer starts with Concept phase, Planning and Design, Component Manufacturing, Construction phase to the Commissioning phase Technical support and expertise: Licensing and environmental support Design reviews Support at the implementation of technical specifications and regulatory requirements, Alignment of modifications Monitoring of the construction and installation process Supporting and monitoring the commissioning and testing International experience in reviews for owners / licensees as well as for manufacturers and design companies Training: suppliers, construction companies and operators Knowledge transfer and exchange of experience by staff training Slide 6

7 Design review of Systems, Structures and Components Federal State Authorities in Germany Assessment of Design of safety systems based on plant design Plant-specific safety features Classification of systems, structures and components Quality management based on classification Scope of our work: Evaluation of necessary safety functions Assessment of system design to ensure these safety functions Redundancy (n + 2), diverse components, separation of trains Emergency power supply, I&C Review of QM specifications Slide 7

8 Assessment of Plant Concept of German NPP Federal State (Länder) Authorities in Germany Assessment of plant concept: Design of safety system: redundancy, emergency power supply, separation of trains, Provisions for impact of internal and external events (transients, loss of coolant, earthquake) Thermo-hydraulic analysis of postulated events Radiological impact on environment Scope of our work: Concept and design assessment, based on German regulations Deterministic approach (n + 2) Accident analyses with validated codes and models Calculation of radiological impact with atmospheric dispersion model Measures for airplane crash or severe accidents (accident management) Slide 8

9 Evaluation of Plant Concept and Systems of German BWR Federal State (Länder) Authorities in Germany Assessment of plant concept: Design of safety system: redundancy, power supply, separation of trains, Provisions for impact of internal and external events (transients, loss of coolant, earthquake) Thermo-hydraulic analysis of all postulated events Radiological impact on environment Scope of our work: Design assessment, based on German requirements Deterministic approach (n + 2) Accident analyses using evaluated codes and models Calculation of radiological impact with atmospheric dispersion model Evaluation of necessary safety functions and systems design Slide 9

10 Owners Engineer Part I Management and process focused support services: Assessment of project scope, execution and management procedures, overall technical project control, responsibilities and levels of authorisation Time schedule analysis and optimisation Support in the establishment of a change management process Preparing HS&E procedures covering all aspects and stages of the project Reviewing the EPC contractors procurement procedures Qualification of Suppliers Supporting preparation of manuals Training Slide 10

11 Engineering Support Turbine Island Oskarshamn Siemens Industrial Turbomachinery AB Swedish NPP Oskarshamn 2 (OKG 2) to be uprated to 135% output TÜV SÜD is contracted to provide Engineering Support Activities: Risk and Event Analysis Turbine Island Scope of our work: Develop a concept for a risk analysis with respect to: Personnel protection Operability Standards covered: IAEA-TECDOC-1209 ISO 31000, ISO Slide 11

12 Comparison of Gen III+ Reactor Designs against the HSE, UK, NRC, IAEA and STUK Safety Requirements Siemens Description of requested reactor designs (EPR, AP-1000, WWER 1000, WWER 1200, SWR-1000) Evaluation of a catalogue for safety assessment of reactor designs Safety assessment of the 5 designs Scope of our work: HSE, NRC, IAEA - STUK Safety Requirement Data base on reactor designs Data base on safety criteria Plant data and safety features of different reactor types The concept of barriers Safety criteria for design of NPP Plant answers to authorities safety criterias Experiences and comparison of plant concepts Slide 12

13 Owners Engineer: Part II Vendor Qualification Application and implementation of required codes, standards and regulations request for compliance with country specific, licensee specific and project specific requirements Equipment Qualification Supply Chain Qualification Third Party Services (DIN IEC / ISO 17020, Notified Body) CE-Marking and European conventional Directives as PED for further Export also to OTHER countries with NPP projects TÜV SÜD AG 06/04/2017 Slide 13

14 Equipment Qualification Methodology Technical Input Check of Design Requirements TÜV SÜD Services System and Component Classification Nuclear or/and conventional requirements? Nuclear Regulations and Requirements Conventional Regulations and Requirements Conventional requirements covered by nuclear! Scope of Equipment Qualification Technical Verification of relevant nuclear requirements Technical Verification of relevant conventional requirements Confirmation by Independant Inspection Body IEC Confirmation by Notified Body; PED, LVD, Slide 14

15 Equipment Qualification Steps 1 and 2 Step 1 Input from Designer/Owner Safety Class Assignment Technical and System Specification Qualification Requirements Applicable/Required Standards, Guidelines Rules, Directives,.. TÜV SÜD Services: Support the Preparation of Specifications, Check of Completeness and Quality Technical Details Compliance Check according to applicable regulations Nuclear and non Nuclear Requirements Local regulation List of Relevant Requirements Step 2 TÜV SÜD Services: Compliance Check and Code Comparison (Japan - UK) - Assessment of Technical Specifications with Respect to Applicable Standards and Requirements, Definition of Required Qualification Activities Slide 15

16 Project YUMOD in NPP Leibstadt (Switzerland) AXPO (Owner) Scope of our work : Verifying of project specification created by the manufacturer Review of design documents Review of written procedures for examination and testing during the manufacturing process Modernisation of primary cooling system Standard: ASME B&PV Code, Section III Slide 16

17 Further projects based on ASME B&PV Code, Sections III and XI Project AUTANOVE in NPP Beznau (Switzerland) Review of design documents and procedures for examination and testing International Special Review of Korean NPP Review of maintenance and in-service inspections of eight units at four sites Review of the compliance of procedures with ASME III and XI requirements SIEMENS / NPP Oskarshamn 2 (Sweden) Exchange of turbine and power amplification documentation for the systems Requalification of components Slide 17

18 Equipment Qualification Steps 3 and 4 Step 3 Technical Documents Detailed layout of equipment / component Drawings, calculations, material, description of manufacturing, welding consumables, coating, inspection plan, Pre-Qualification and Manufacturing Documents TÜV SÜD Services: Assessment of Pre-Qualification and Manufacturing Documents with respect to applicable Standards and Requirements, Confirmation of Qualification Activities Step 4 Conformity Assessment by AIA/NoBo Quality and Acceptance Tests Independent check by Inspection Agency (IEC 17020) Independent check by Notified Body (where necessary) EQUIPMENT QUALIFICATION Calculations/Simulations Theoretical Examination Practical Testing Assessment of QA in Manufacturing Process Test Report Declaration of Conformity Slide 18

19 Qualification of Nuclear Components NPP Olkiluoto 3, Finland (EPR) Scope of our work: Design review (e.g. seismic calculations, FEM analysis, GIPs and FIPs) Construction inspection at the manufacturer (e.g. functional test, compliance with construction plan) Construction of EPR at Olkiluoto: Design Review Qualification for SC3, SC4 and EYT components Commissioning inspection from 2015 ongoing Slide 19

20 DIN EN Services as Inspection Body Type A DIN EN ISO/IEC Failure analysis, condition assessment and/or inspection of components - Inspection of documents. - Design review, on-site inspections during construction and commissioning of nuclear facilities and safety assessments of systems, structures and components; confirmation of compliance with given requirements and with general requirements - Inspection of maintenance procedures. Preventive, risk-based well and failure-based maintenance. Slide 20

21 TÜV SÜD Accreditations Accreditations DIN EN ISO/IEC 17020: 2012 (DAkkS) DIN EN ISO/IEC 17025: 2005 (DAkkS) ISO 9001: 2008 ISO 14001: 2004 KOLAS Our expertise standards Nuclear Codes and Standards: IAEA KTA (Germany) RCC (France) NUREG PNAEG / FNP (Russia) SAPs (UK) YVL (Finland) Design Codes: ASME DIN EN ISO/IEC GOST (Russia) KEPIC (Korea) Slide 21

22 Supporting Services During Transportation and Shipment Preparation and review of shipment and transport documentation TÜV SÜD services comprise support of transportation, packaging and storage of radioactive as well as other hazardous materials. Provision of clearance measurements for radioactive materials Inspections of hazardous materials during transport and shipment Supervision of transportation and shipment of hazardous material Design review of transport packages, containers and storage casks Testing and inspections of transport packages, containers and storage casks Transport supervision: dont forget! Citical transports has to be inspected and supervised all the way through Slide 22