TWG-NPPIC, May 2009, Vienna: UK status1 Current status of NPP I&C in the United Kingdom T P Smyth AMEC, Knutsford, Cheshire, UK 22 nd Meeting of the Technical.

Slides:



Advertisements
Similar presentations
Reporting on I&C status and recommendations to IAEA
Advertisements

INTRODUCTION TO AMEC amec.com U.S. CIVIL NUCLEAR INDUSTRY PROGRAM IN ROMANIA SEPTEMBER 21-22, 2009 BUCHAREST, CERNAVODA.
Electrical, Control and Information Systems in the Enhanced CANDU 6 ® Electrical, Control and Information Systems in the Enhanced CANDU 6 ® Candu – Official.
Presented by: Muhammad Ayub Pakistan Nuclear Regulatory Authority Safety Enhancement at Nuclear Power Plants in Pakistan Prospects of Nuclear Energy in.
Vermont Yankee Presentation to VSNAP 7/17/13 VY/Entergy Fukushima Response Update Bernard Buteau.
Westinghouse Atom Atom- 1 Design of Digital Safety Systems in NPP Improvements regarding: System Requirements, Engineering, Argumentation for a Safety.
The UK Nuclear Market. Paul Lester CEO Lord Mandelson Secretary of State for Business, Innovation and Skills.
ONR Presentation to NuLeAF Tanya MacLeod. Responsibilities Prime responsibility for the assessment and management of Flood and Coastal Risk on site rests.
The Future of the Nuclear Power Industry in the UK and Implications for the South West Peter Higginson Technical & Safety Manager Hinkley Point B Nuclear.
© ABB Group August 13, 2015 | Slide 1 Power Generation Service Life Cycle Management for Power Plants Daniel Looser, Power Gen Europe in Amsterdam, June.
1 BARRY DUNGEY General Manager Engineering & Maintenance June 2008 Loy Yang Power Station Control System Upgrade.
Oconee RPS/ESPS Digital Upgrade Presented by: Michael Bailey June 3,
Christophe Delamare EDMS Accelerator Consolidation Workshop GS/ASE activities.
Motor Control Center MNS iS with Condition Monitoring
IAEA International Atomic Energy Agency International Standards for NPP I&C Presented to TWG-NPPIC 2009 May 21 Vienna, Ausria Gary Johnson
1 © 2013 Westinghouse Electric Company LLC. All Rights Reserved Westinghouse Non-Proprietary Class 3 David Cliff UK Licensing Manager AP1000 Westinghouse.
INTERNATIONAL ATOMIC ENERGY AGENCY Technical Committee Meeting of Technical Working Group on Nuclear Power Plant Control and Instrumentation May.
No: 1 CEMSIS wp6_beg010_v0_1_fisa slides.ppt CEMSIS FIKS-CT Cost-Effective Modernisation of Systems Important to Safety Deryk Pavey, Deryk Pavey,
International Atomic Energy Agency Achieving human performance excellence in the nuclear industry through leadership, education, and training C. R. Clark.
Regulatory Approach to the Lifetime Management of the Nuclear Power Plants in Korea June 30, 2004 Choi, Kyung Woo Korea Institute of Nuclear Safety International.
U.S. DOE Light Water Reactor Sustainability Program: Advanced Instrumentation & Controls and Human System Interfaces Research Pathway Bruce Hallbert, Idaho.
Career Clusters & Energy Careers. Objectives for Today’s Meeting Explore where energy careers fit in the career cluster system Build awareness of energy.
Opting for “Long Term Operations” Technical, economic and regulatory considerations MARC Conference June 8, 2010 Sean Bushart, EPRI Sr. Program Manager.
Prospects for Nuclear New Build Chris Savage Nuclear Industry Association 10 th July
Technical Working Group on Nuclear Power Plant Instrumentation and Control Vienna, May 2009 NATIONAL REPORT ON NUCLEAR POWER PLANT INSTRUMENTATION AND.
08 October 2015 M. Ammar Mehdi Introduction to Human Resource Management & SSG-16 Actions 4 th Steering Committee on Competence of Human.
AREVA: Steps towards a global leadership in the energy industry
1 The U.S. NRC’s Reactor Certification and Licensing Process – Meeting the Challenge? Commissioner Peter B. Lyons U.S. Nuclear Regulatory Commission 15.
Opportunities and Challenges Joseph Naser Electric Power Research Institute IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation.
No: 1 CEMSIS wp6_beg037_v0_2_fisa 2003 slides.ppt CEMSIS FIKS-CT Cost-Effective Modernisation of Systems Important to Safety Deryk Pavey, Deryk.
> AREVA NP GmbH NRPP-G, AREVA NP All rights are reserved, see liability notice.
Electrical Cable Aging and Condition Monitoring Codes and Standards for NPPs Dr. Stephanie Watson Engineering Laboratory NIST 100 Bureau Drive, MS 8615.
Nuclear Decommissioning in the UK Presented by Chris Jones.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
TACIS Project: R8.01/98 – TRANSLATION, EDITING AND DIFFUSION OF DOCUMENTS (Result Dissemination) Probabilistic Safety Analysis Technology (PSA) TACIS R3.1/91.
Life cycle services for automation products
IAEA I&C Activities Presented by Björn Wahlström, Chairman TWG-NPP CI.
C O N T R A C T O R I N F O R M A T I O N E X C H A N G E Reister CE Presentation 1/98 1 Program Elements and Related Activities Rich Reister U.S. Department.
ROMANIAN EXPERIENCE IN TRAINING AND QUALIFICATION OF THE NPP OWNER/OPERATOR FOR UNIT 1 OF CERNAVODA NPP Dr. Ioan Rotaru TM/WS on Topical Issues on Infrastructure.
British Energy Public Meeting, Nether Stowey, Monday 20 th October 2008 Richard Mayson, Nuclear Counsel © Copyright EDF Energy plc. All rights reserved.
1 Review of Specifications for Digital Upgrades NHUG Summer Meeting July 17, 2008 Tim Mitchell Component Engineering Palo Verde Nuclear Generating Station.
International Atomic Energy Agency 1 Grid, Industrial involvement and procurement Akira OMOTO DIR, NENP.
API Recommended Practice 17X Recommended Practice for Design, Installation, and Maintenance of Subsea Booster Pump Systems Status Report October 3,
IAEA International Atomic Energy Agency Methodology and Responsibilities for Periodic Safety Review for Research Reactors William Kennedy Research Reactor.
IAEA International Atomic Energy Agency IAEA Safety Standards for Research Reactors W. Kennedy Research Reactor Safety Section Division of Nuclear Installation.
Regional Meeting on Applications of the Code of Conduct on Safety of Research Reactors Lisbon, Portugal, 2-6 November 2015 Diakov Oleksii, Institute for.
Westinghouse Non-Proprietary Class 3© 2015 Westinghouse Electric Company LLC. All Rights Reserved. 1 Graham Cable Vice President, New Plant Development.
International Atomic Energy Agency M. El-Shanawany IAEA Technical Support & Capacity Building Programme M. El-Shanawany Department of Nuclear Safety &
IAEA International Atomic Energy Agency INTRODUCTION Module 2.
IAEA International Atomic Energy Agency AGEING MANAGEMENT ASSESSMENT Module 9 Session 9 Resource document: AMAT Guidelines, Reference document for Ageing.
I & C.
IAEA International Atomic Energy Agency New IAEA Safety Guide (information) Human Factor Engineering for NPP (DS492) Alexander Duchac SAS,NSNI.
Safety Assessment of General Design Aspects of NPPs (Part 2) IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information.
IAEA International Atomic Energy Agency Technical Meeting on Regulatory Oversight of Human and Organizational Factors Vienna, Austria | December.
Next Generation Nuclear Plant Licensing Strategy William D. Reckley NRC/NRO/ARP March 12, 2009.
Electrical Engineering for NSS - Status and Planning- Thomas Gahl Electrical Engineering Group Leader February 26, 2014.
An overview of I&C Systems in APR 1400 Parvaiz Ahmed Khand December 28, 2007.
Workshop on Risk informed decision making on nuclear power plant safety January 2011 SNRC, Kyiv, Ukraine Benefits and limitations of RIDM by Géza.
Operations WBS Dictionary Integrated Control Systems Henrik Carling ESS/ICS Date:
EC/IAEA/ISOE Workshop Portoroz Slovenia April 2002 Electronic Personal Dosimetry Presented by Andy Weeks.
IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Workshop Information IAEA Workshop Licensing Renewal of Operating License Periodic.
1 Multinational Design Evaluation Program (MDEP) and the Working Group on Digital I&C (DICWG) NPEC January 26, NPEC.
PREEV PROJECT: REGULATORY PRACTICES ON AGEING AND LIFE EXTENSION
Autonomous Robotics in the Nuclear Industry
Offerings for design safety from harmonization
Communication and Consultation with Interested Parties by the RB
IAEA General Conference Regulatory Cooperation Forum Regulatory Approach Prescriptive vs Performance Based David Senior Executive Director -
IAEA – Safety Demonstration of Advanced Water Cooled Nuclear Power Plants Session: Digital I&C Systems Topic: Defence in Depth & Diversity – Challenges.
Mikael Olsson Control Engineer
Nuclear Safety Standards Committee 35th Meeting 24 – 28 June 2013
Presentation transcript:

TWG-NPPIC, May 2009, Vienna: UK status1 Current status of NPP I&C in the United Kingdom T P Smyth AMEC, Knutsford, Cheshire, UK 22 nd Meeting of the Technical Working Group on Nuclear Power Plant Instrumentation and Control, May 2009, Vienna

TWG-NPPIC, May 2009, Vienna: UK status 2 Current status of NPP I&C in the United Kingdom Nuclear Power Plants in the UK Status of I&C at nuclear plants  Reactor Protection Systems  Data Processing Systems  Refuelling machines Status of regulatory environment affecting I&C Recommendations

TWG-NPPIC, May 2009, Vienna: UK status 3 Nuclear Power Plants in the UK (1) x 610 MWeAGR Hinkley Point B x 605 MWeAGR Hunterston B Expected shutdown Start operation Unit capacityTypeReactors MWeTotal (19)‏ x 1196 MWePWR Sizewell B x 625 MWeAGR Torness x 615 MWeAGR Heysham x 615 MWeAGR Heysham x 595 MWeAGR Hartlepool x 545 MWeAGR Dungeness B x 490 MWeMagnox Wylfa x 217 MWeMagnox Oldbury

TWG-NPPIC, May 2009, Vienna: UK status 4 Nuclear Power Plants in the UK (2) ‏  Electricity sources 19% nuclear 36% gas 38% coal  Need to plan for energy replacement 7 plants will close in next 9 years 14 reactors 7359 MWe 13% of electricity sources North Sea oil and gas will be limited in future  New build Generic Design Assessment (AP1000, EPR) Target completion of GDAs June 2011 Sites identified

TWG-NPPIC, May 2009, Vienna: UK status 5 AGR : Reactor Protection Systems (1) ‏ Neoprene insulation degradation  Magnox Oldbury power station  Degradation with age Perishing Sweating Hygroscopic Becomes conductive - resistance < 1 MΏ  Stray currents in sensitive circuits Thermocouple amplifiers

TWG-NPPIC, May 2009, Vienna: UK status 6 AGR : Reactor Protection Systems (2) ‏ Neoprene insulation degradation ‏

TWG-NPPIC, May 2009, Vienna: UK status 7 AGR : Reactor Protection Systems (3) ‏ Neoprene insulation degradation

TWG-NPPIC, May 2009, Vienna: UK status 8 AGR : Reactor Protection Systems (4) ‏ Neoprene insulation degradation  Survey of all safety equipment Presence of neoprene State of neoprene Circuit function  Replacement equipment at older stations Obsolescent anyway  Repairs at newer stations Heysham 2 / Torness  6 years work, 1 more year to finalise all equipment  Prioritised by susceptibility

TWG-NPPIC, May 2009, Vienna: UK status 9 AGR : Reactor Protection Systems (5) ‏ Neutron Flux measurement systems  AGR detectors located in core at 8 locations High temperatures  Detector spares Wide range detector – integral cable Manufacturing spares – re-establishing production processes Currently a batch of 10 in progress  Electronic units Neoprene Repairs at Heysham 2 / Torness Replacement at other stations

TWG-NPPIC, May 2009, Vienna: UK status 10 AGR : Data Processing Systems  Safety claims on equipment Some reactor control functions Some alarms  Hinkley Point B New DPS installed (1999)‏  Dungeness B New DPS being installed Control / equipment protection functions segregated Ready for works testing  Other AGR's Stabilization of equipment  Adequate spares provision / hardware support.  Improved air conditioning Heysham 2: specification phase

TWG-NPPIC, May 2009, Vienna: UK status 11 AGR : Refuelling Machines  Online refuelling Stringent safety requirements  Equipment obsolescence Key focus at present  Heysham 2 / Torness Replacement of Reypac controllers with Siemens S7  I/O replaced, emulates original equipment  Reypac controller replacement  Software reverse engineered and ported  Safety functions partitioned  Successful implementation, scope of replacement expanded.  Safety standards Modern standards considered when replacing equipment

TWG-NPPIC, May 2009, Vienna: UK status 12 Regulatory Environment (1) ‏  Standards hierarchy NII SAPs and TAGs ( IAEA standards IEC standards  IEC Modern standards reviews  Design, Operation and Maintenance  Part of Periodic Safety Reviews  PSA based assessment Target / year  Limit of reliability claims for software based systems Assume 1 demand / year /demand Require diverse protection to make up /demand

TWG-NPPIC, May 2009, Vienna: UK status 13 Regulatory Environment (2) ‏  Application to Sizewell B Primary Protection System  Four channels, 2 out of 4 tripping  Software based  Production excellence  IEC  Independent confidence building  Extensive testing  Independent code safety assessment Secondary Protection System  Four channels, 2 out of 4 tripping  Protection for frequent faults  Laddic – magnetic amplifiers  Diverse technology

TWG-NPPIC, May 2009, Vienna: UK status 14 Regulatory Environment (3) ‏ New build  In general, same regulatory requirements as Sizewell B Diversity requirements in reactor protection systems Possibly less onerous protection system targets  Passively safe systems will make fewer demands  Smart Instruments Regulator considering application to nuclear facilities Assessment of evidence Plant owner collaboration  Shared qualification and licensing assessments  SIL1  No fieldbus

TWG-NPPIC, May 2009, Vienna: UK status 15 Recommendations IAEA topics  Estimating and extending life of I&C equipment to address ageing and obsolescence  Supporting the evaluation, acceptance and licensing of digital I&C system  Lessons learned from I&C project implementation and guidance for modernisation and new plant project