Annex to the Accreditation Certificate D IS according to DIN EN ISO/IEC 17020:2012

Transcription

1 Deutsche Akkreditierungsstelle GmbH Annex to the Accreditation Certificate D IS according to DIN EN ISO/IEC 17020:2012 Period of validity: to Date of issue: Holder of certificate: TÜV SÜD Industrie Service GmbH Inspektionsstelle Elektro und Leittechnik Westendstraße 199, München for its inspection body Type A Inspections in the fields: Electrical and I&C Systems Abbreviations used: see last page Inspection Procedures: IS ET AE001 V1.2 January 2015 IS ET AE002 V1.3 December 2013 IS ET AE003 V1.0 IS ET AE004 V1.1 December 2013 Procedure: Type Approval according to YVL Procedure: Type Testing Procedure: Compliance Check of the SW Design Procedure: Compliance Check of the HW Design 1/7

2 IS ET AE005 V1.0 IS ET AE006 V1.0 IS ET AE007 V1.1 February 2014 IS ET AE008 V1.0 IS ET AE009 V1.0 IS ET AE010 V1.0 IS ET AE011 V1.0 IS ET AE012 V1.0 IS ET AE013 V1.0 IS ET AE014 V1.0 IS ET AE015 V1.0 IS ET AE016 V1.2 January 2014 IS ET AE017 V1.0 IS ET AE018 V1.0 Procedure: Compliance Check of the Configuration Control Procedure: Compliance Check of Practical Testing Procedure: Compliance Check of Manufacturing Documents Procedure: Compliance Check of the Quality System for Manufacturing Procedure: Development Process Audit Procedure: Auditing of the Manufacturing Quality Procedure: Assessment of the HW Design Procedure: Assessment of the SW Design Procedure: Assessment of Operating Experience Procedure: Assessment of Test Specifications Procedure: Inspection of Test Setup Procedure: Supervision and Witnessing of Practical Tests Procedure: Witnessing of Functional Tests Procedure: Witnessing of Mechanical Load Tests Period of validity: to Date of issue: /7

3 IS ET AE019 V1.0 IS ET AE020 V1.0 IS ET AE021 V1.0 IS ET AE022 V1.0 IS ET AE023 V1.0 IS ET AE024 V1.0 IS ET AE025 V1.0 IS ET AE026 V1.0 IS ET AE027 V1.0 Procedure: Witnessing of Climatic Tests Procedure: Witnessing of the LOCA Test Procedure: Witnessing of Radiation Tests Procedure: Witnessing of Post Accident Tests Procedure: Witnessing of EMC Tests Procedure: Assessment of a Failure Modes and Effects Analysis Procedure: Critical Load Analysis Procedure: Check of Failure Rates Procedure: Inspection of Manufacturing Processes Inspection is carried out based on: DIN IEC DIN EN DIN EN Nuclear power plants Electrical equipment of the safety system Qualification Analysis techniques for system reliability Procedure for failure mode and effects analysis (FMEA) Nuclear power plants Instrumentation and control systems important to safety Software aspects for computer based systems performing category A functions Period of validity: to Date of issue: /7

4 DIN EN ( Errata) DIN EN (all parts) DIN EN (all parts) DIN EN DIN EN ISO 13849: DIN EN DIN EN IAEA NS G IEC IEEE Programmable controllers Functional safety of electrical/electronic/programmable electronic safety related systems Functional safety of electrical/electronic/programmable electronic safety related systems Nuclear power plants Instrumentation and control important for safety Software aspects for computer based systems performing category B or C functions Safety of machinery Safety related parts of control systems Nuclear power plants Instrumentation and control important to safety Hardware design requirements for computer based systems Nuclear power plants Instrumentation and control important to safety General requirements for systems Software for computer based systems important to safety in nuclear power plants Nuclear power plants Instrumentation and control important to safety Selection and use of industrial digital devices of limited functionality IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations Period of validity: to Date of issue: /7

5 IEEE 334 IEEE IEEE 382 IEEE IEEE IEEE 572 IEEE 650 IEEE KTA KTA KTA KTA KTA KTA IEEE Standard for Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating Stations IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations IEEE Standard for Qualification for Actuators for Power Operated Valve Assemblies with Safety Related Functions for Nuclear Power Plants IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations IEEE Standard Design and Qualification of Class 1E Control boards, Panels, and Racks Used in Nuclear Power Generating Stations IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations IEEE Standard Qualification of Class 1E Battery Chargers and Inverters for Nuclear Power Generating Stations IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations General Requirements Regarding Quality Assurance Cable Penetrations through the Reactor Containment Vessel Reactor Protection System and Monitoring Equipment of the Safety System Accident Measuring Systems Type Testing of Electrical Modules for the Safety Related Instrumentation and Control System Electrical Drive Mechanisms of the Safety System in Nuclear Power Plants Period of validity: to Date of issue: /7

6 KTA KTA KTA KTA KTA KTA KTA KTA RCC E 2005 RSK LL 11/96 SiAnf KKW VDI/VDE YVL Type Testing of Measuring Sensors and Transducers of the Safety Related Instrumentation and Control System Factory Tests, Post repair Tests and Certification of Satisfactory Performance in Service of Modules and Devices for the Instrumentation and Controls of the Safety System General Requirements for the Electrical Power Supply in Nuclear Power Plants Emergency Power Generating Facilities with Diesel Generator Units in Nuclear Power Plants Emergency Power Facilities with Batteries and AC/DC Converters in Nuclear Power Plants Emergency Power Facilities with Static and Rotating AC/DC Converters in Nuclear Power Plants Switchgear Facilities, Transformers and Distribution Networks for the Electrical Power Supply of the Safety System in Nuclear Power Plants Ensuring the Loss of Coolant Accident Resistance of Electrotechnical Components and of Components in the Instrumentation and Controls of Operating Nuclear Power Plants Design and Construction Rules for Electrical Equipment of Nuclear Islands 2005 Edition RSK guidelines for pressurized water reactors (available in German only) Safety Requirements for Nuclear Power Plants Requirements of repetition parts and criteria for their use in the instrumentation and control to safety in nuclear power plants General part Instrumentation Systems And Components at Nuclear Facilities Period of validity: to Date of issue: /7

7 YVL E Electrical and I&C Equipment of a Nuclear Facility Abbreviations used: DIN EN IAEA IEC IEEE IS ET AE0xx KTA RSK VDE VDI YVL x.x German Institute for Standardization European Standard International Atomic Energy Agency International Electrotechnical Commission Institute of Electrical and Electronics Engineers In house method of the TÜV SÜD Industrie Service GmbH the Nuclear Safety Standards Commission Reactor Safety Commission the Association for Electrical, Electronic & Information Technologies the Association of German Engineers Regulatory Guides on nuclear safety Period of validity: to Date of issue: /7