IAEA activities on Operational Excellence in Npps

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1 activities on Operational Excellence in Npps International Atomic Energy Agency

Divisions engaged in activities related to engineering issues of

K Park) Activities from technical, performance and economical

Maintenance methodologies, optimisation I&C modernization, etc.

Activities from safety point of view Safe Long Term Operation

2 Divisions engaged in activities related to engineering issues of operating nuclear power plants Division of Nuclear Power (NENP, J.K Park) Activities from technical, performance and economical points of view Plant life management (PLiM) Ageing management Maintenance methodologies, optimisation I&C modernization, etc. Division of Nuclear Installation Safety (NSNI, Lyons James Edward) Activities from safety point of view Safe Long Term Operation Safety Assessment Support Regulatory Authority Ageing management Periodic safety review, etc.

3 Sub-Programme Structure (1.1.1) Operating Npps Engineering Supports Sub- Programme Integrated Support for Operational Excellence of Npps Safety Operation of NPPs (NSNI) Prepare good Guide and Reports (TMs, CRPs) Implement TC Projects Provide Review Services Organize WSs, Conference Cooperation with Int. Organs Present the Agency Activities Engineering Support for Projects Operation Npps including Safety Aspects 5% 10% Advanced Technology Application for Process Control System 3% 7% 40% Improving Plant Performance by 35% Information Exchange Guide TC Service WS & Conf Int. Ograns Admin 3

4 Two type outputs outcomes for operating nuclear plants Development of Safety standards and series of tech. Guidelines & Reports Direct Service through tech. cooperation projects to assist Member States Training course Workshop Expert Mission Equipment procurement Engineering and Safety review service

5 Regular Programme on Operational Excellence in Npps International Atomic Energy Agency

Heavy Component Replacement Organization for Heavy

Steam Generator Pressurizer Reactor Coolant Piping

components Reactor Coolant Piping PHWR Fuel Channel

6 Heavy Component Replacement Organization for Heavy Components Replacement Technical Issues for PWR Steam Generator Pressurizer Reactor Coolant Piping RPV head Vessel Internal BWR Vessel Internal components Reactor Coolant Piping PHWR Fuel Channel and Feeder Piping, SG Safety and Licensing regulatory issues

7 Comparison between NP & CRP Draft NES CSI 1 Agreement or Contract CSI 6 CSI 2 Extended NES Final NES CSI 5 RCM (1~3) CSI 4 CSI 3 NES : Nuclear Energy Series CSI : Chief Scientific Investigator RCM : Research Coordinated Meeting NPES 7

8 NES series Hybrid Main Control Room Strategic Decision Making, Planning and management Factors influencing decision on I&C upgrades MCR modernization planning MCR Modernization options for components and systems Soft Control Overview Display Panels Alarm System Project Execution Consideration of Human Factors ( Function, Task, System failure, Design consideration )

9 Panels in Old/ New system

10 Consoles in Old / New Safety System

11 Final arrangement in the main control room

12 Training simulator temporary installation

13 Which monitors should be focused?

14 Reactor Pressure Vessel Integrity under Irradiation Damage Testing Irradiation damage challenge Model Matrix damage Core weld How we are achieving success NPES 14

15 CRP 8 and CRP 9 Final Results 15

16 Planned Actives Coordinated Research Projects Qualification, Condition Monitoring, and Management of Aging of Low Voltage Cables in Nuclear Power Plants Members Bulgaria (KNPP) Canada (Kinectrics) China Czech Republic (NRI) France(CEA) Hungary(VEKI, University) Japan (JNES, Toshiba, Hitachi) Korea (KINS) Slovakia(VJUE) Sweden(Habia) USA (NRC, NIST, AMS, USC) Mexico (?) Argentina (?)

17 Cable Failure An effective, viable condition monitoring technique for installed cable systems in nuclear reactor is needed to detect and locate defects before they result in failures.

Present State-of-the-Art Techniques Mechanical

Induction Time Electrical Dielectric loss measurements Voltage

FDR, JTFDR) Consultancy Meeting to Prepare the Scope and

18 Present State-of-the-Art Techniques Mechanical Elongation-At-Break, Compressive Modulus Chemical Oxidation Induction Time Electrical Dielectric loss measurements Voltage withstand test Partial discharge testing Reflectometry (TDR, FDR, JTFDR) Consultancy Meeting to Prepare the Scope and Benchmark Approach (1-2 Aug 2011) neering/crp/alvc/

19 Planned Actives Coordinated Research Projects Review and Benchmark of Calculation Methods of Piping Wall Thinning due to Erosion-Corrosion in Nuclear Power Plants Objective References and boundary conditions for the use of the available prediction tools Support the development of a solid technical base and serve as a guideline for FAC Programme Members Argentina Belgium Brazil China Canada(Hold) Czech Republic (NRI) France(EDF) Korea Pakistan Russia(Geotherm) Slovakia Germany (Areva) USA(?) Japan Mexico(?)

20 Planned Actives Available software for FAC predictions Checkworks, Comsy, Smart Candu, BRT- Cicero, JSME code, Checcup (Fossil), RAMEK, Facemaker Invited Users and Developer Prepare input data and boundary condition Real FAC data Npps Developing Guidelines

21 On-going programme Update TECDOCs Cable ageing management (Printing) SG ageing management (Printing) EQ procedure (final stage) Updated Containment ageing ( in 2012) SCC guidelines (printing) PLiM Model Foreign material exclusion

22 2. requirements & Guidelines related to Maintenance and Outage management

Hierarchy of Safety Standards Safety Standard Series Fundamentals Requirements underlying

concepts and principles of safety and protection Establish requirements what needs to be done

Supportive Publications (Safety Report Series, Technical Report Series, TECDOCs): Information

23 Hierarchy of Safety Standards Safety Standard Series Fundamentals Requirements underlying principles - aimed at decision makers and regulatory bodies, Present basic objectives, concepts and principles of safety and protection Establish requirements what needs to be done ( shall statements) to meet objectives and principles in Safety Fundamentals Guides Other Supportive Publications (Safety Report Series, Technical Report Series, TECDOCs): Information on good practices in Member States Recommended ways ( should statements ) on how to meet Safety Requirements

24 Safety Standards related to Maintenance Safety of Nuclear Power Plants: Operation (Safety Requirements NS-R-2) Maintenance, Surveillance and Inservice Inspection in Nuclear Power Plants (Safety Guide NS-G-2.6)

25 Related documents Risk-informed In-service Inspection of Piping Systems of Nuclear Power Plants: NES NP-T-3.1 Process, Status, Issues and Development (2010) Implementation Strategies and Tools for Condition Based Maintenance, -TECDOC-1551, May 2007 Guidance for Optimizing NPP Maintenance Programme, -TECDOC-1383, 2003 This TECDOC addresses a broad range of maintenance and maintenance management issues including those related to outage management: asset life management, risk informed maintenance, and techniques and tools for maintenance optimization programme. Configuration Management in Nuclear Power Plants TECDOC-1335, 2003 The processes described in this TECDOC for improving configuration management practices have particular relevance for modifications that are made during planned outages. Thus, this TECDOC should be used as a source of information in this area. Nuclear Power Plant Outage Optimization Strategy, TECDOC-1315, 2002 This document was used as the starting point for the development of the draft technical document to be published later in 2006, Management Strategies for Nuclear Power Plant Outages, It includes a number of examples of outage management practices that are not fully addressed in the soon to be published document. Thus, it should be of particular value. Assuring the Competence of NPP Contractor Personnel -TECDOC-1232, 2001 The objective of this TECDOC is to assist NPPs and other organizations to ensure that NPP contractor personnel are competent to undertake their assigned tasks. Planned outages are the time frames when contractors are used in greatest numbers. Thus, this TECDOC has particular application to outage management. 25

26 Related Documents Advances in Safety Related Maintenance -TECDOC-1138, 2000 This document describes approaches to maintenance that take into account the NPP as a whole and its global safety performance, rather than individual components and their individual performances. Practices emerging from the development of these concepts are results and risk based, and include the use of PSA in maintenance decisions. Such tools can be used to assist in making decisions regarding online maintenance and the scheduling of maintenance during planned outages. Good Practices with Respect to the Development and Use of NPP Procedures -TECDOC-1058, 1998 This document addresses lessons learned regarding effective methods for the development and use of NPP procedures; administrative as well as operational. It provides examples of proven methods for development and use of plant procedures, including those intended for use during outages. Good Practices for Cost Effective Maintenance of NPPs -TECDOC-928, 1997 This document focuses on five areas for cost effective maintenance: increasing production through improved plant material condition, reduced duration of planned outages, use of online maintenance and reduced frequency of forced outages; reducing workload; improving maintenance processes; improving productivity; and measuring performance of maintenance. Management of Procurement Activities in a Nuclear Installation, -TECDOC- 919, 1996 The objective of this TECDOC is to address NPP operating organization needs, related to the proper control of fulfillment of contractual quality and safety requirements. As many of these procurement activities are conducted in support of outage management, this document has relevance for this topic. Good Practices for Outage Management in Nuclear Power Plants TECDOC-621, 1991 This document provides greater detail regarding outage management practices than are included in either -TECDOC-1315 or this document. Even though the document was published in 1991 many of the examples provided continue to be relevant today. 26

27 TECDOC 1383: Guidance for optimizing nuclear power plant maintenance program (example) Publication: 2003 To provide guidance for optimizing maintenance at NPPs by relating internationally recognized good practices and methods

28 3. Service

SALTO Peer Review Service (1) Projected services review modules DBR CM EQ PSR SALTO Peer Review LTO justif.

FSAR The SALTO peer review addresses the following safety aspects of LTO: (1) Organization and functions;

documents; (4) Identification of structures and components (SC) for LTO review; (5) Existing plant

29 SALTO Peer Review Service (1) Projected services review modules DBR CM EQ PSR SALTO Peer Review LTO justif. verification of preconditions review process documentation AM Scop. + Scr. FSAR The SALTO peer review addresses the following safety aspects of LTO: (1) Organization and functions; (2) Configuration/modification management; (3) Current safety analysis report and other licensing basis documents; (4) Identification of structures and components (SC) for LTO review; (5) Existing plant programmes relevant for LTO; (6) Review of ageing management programmes; and (7) Revalidation of analyses that used time limited ageing assumptions

30 PLiM - SALTO TC Projects Support to establish PLiM Programme under TC project Regioanl Europe, Regional Asia and Reginal Latin America Argentina : PLiM programme for Embalse NPP China : Ageing management of Critical Components Hungary : License Renewal of Paks Nuclear Power Plant Operation Mexico : Life Management programme for Laguna Verde NPPs Ukraine : Action Plans for Nuclear Power Plant Lifetime Management Pakistan : Development of Capabilities in Automatic UT and Material Corrosion testing for Assessment of Structural Integrity Review missions (SALTO peer review services) implemented: South Ukraine NPP (Mar. 2007, Ukraine) Kori 1 NPP LTO Peer review (Republic of Korea July 2007) Dukovany NPP LTO Peer review (Czech republic 3Q 2008) Paks NPP SALTO Peer review (Hungary Sept. 2008) Borssele NPP SALTO Peer review (Netherlands) 30

31 Hungary Paks Case Requested to conduct a peer review of selected parts of the Licence Renewal documentation developed by Paks NPP for submission to the Hungarian Atomic Energy Authority (HAEA), in support of long term operation at Paks NPP. A regulatory program for the License Renewal (LR) of the Paks NPP was established by the Hungarian Atomic Energy Agency (HAEA). The main objective is the extension of the plant operating license of 20 years beyond its design life. In this context, the HAEA developed a set of regulatory documents at different binding levels and modified the existing high-tier legal documents to address the relevant licensing issues, to define the process characteristics, and to clarify the regulatory involvement and review actions.

Hungary Paks Case A National TC project for Hungary was funded by the in the period 2003-2006.

32 Hungary Paks Case A National TC project for Hungary was funded by the in the period The mission reviewed the following sections of the presented License Renewal documentation: Scope (section 3) Integrated Plant Assessment (section 4) Time Limited Ageing Analysis (section 5) Maintenance Rule (section 9). Identified 5 recommendations and 4 suggestions including: Scoping and screening process of systems and subsystems to DGs, Process and requirements related to ASME Code application, Administrative barriers for IT-based cyber security solutions, Implementations of system and component specific monitoring, surveillance, diagnostic and prognostic techniques

Requirements Chapter 5: Specific Design Guidelines Requirements Chapter 7: Design Process for I&C

33 Independent Engineering Review of I&C Service More specifically, sections in the following chapters were used as reference guides in the review: Chapter 4: General Design Guidelines Requirements Chapter 5: Specific Design Guidelines Requirements Chapter 7: Design Process for I&C Systems Important to Safety Doosan, Republic of Korea in 2009 Radiy, Ukraine in 2010 AES-2006, Russia in 2012

34 Independent Engineering Review of I&C Service

35 Maintenance and Outage Management Assessment Service Benefits of MOMA : The NPP can obtain support and assistance in assessment and optimization of its maintenance programme and/or outage management. It aims to help the NPP improve its performance of maintenance and outage in a competitive nuclear power business environment. The specific benefits of the assessment are as follows: Disseminate nuclear industrial best practices on maintenance programme and outage management in the world; Benchmark, evaluate and optimize the approach to maintenance programme and outage management; Identify solutions to known problems at nuclear power plants, if any. Need to develop the guidelines to prepare and conduct review missions of MOMA How about your idea? Do we need to develop MOMA?

36 TC Projects International Atomic Energy Agency

Technical Cooperation Activities in 2009~2011 Enhancing Research Reactor Utilization and Safety Sustainable Energy Development and Preparation for Nuclear Power Introduction of Nuclear Power for

37 Technical Cooperation Activities in 2009~2011 Enhancing Research Reactor Utilization and Safety Sustainable Energy Development and Preparation for Nuclear Power Introduction of Nuclear Power for Electricity Generation Developing and Implementing PLiM and PLeX Programmes in NPPs Establishing a Structural Integrity Assessment Procedure for NPP Components RER 4030 BUL 4013 HUN 4017 UKR 4014 RAS 4031 CPR 4029 CPR 4030 CPR 4032 ROK 9047 National TC projects Regional TC projects Interregional TC projects RLA 0038 RLA 4021 ARG 4093 MEX 4057 MEX 4058 BRA 4058 RAF 4022 ALG 0013 EGY 4053 GHA 0010 LIB 4010 MOR 4017 NIR 4008 NIR 4009 SUD 0011 RAS 0053 INS 4037 JOR 4005 JOR 4006 MAL 400 THA 4015 VIE 4015 TUN

38 Workshop and Equipment supply 38

39 Technical Cooperation Projects RER4027 RER9082 RAS4028 RLA4021 HUN4017 ARG4091 RUS9004 PAK4046 MEX4057 UKR4013 HUN0007 CPR4027 ARG4090 CPR4028 MEX4058 Strengthening Capabilities for NP Performance and Service Life including Engineering Aspects Improvement of Design Basis and Configuration Management Documentation Integrated Management Systems for an Expanding Nuclear Power Programmes Cracking and Structural Integrity of Components in LWR License Renewal of Paks NPP Operation Plant Life Management Program for Critical Systems, Structures & Components of Embalse NPP Enhancement of NPP Operational Safety Development of Capabilities in Automatic UT and Material Corrosion Testing for Assessment of Structural Integrity Developing Capabilities for Nuclear Safety Operational Analysis for the New Power Uprate for Laguna Verde NPP Action Plans for NPP Lifetime Management Knowledge Management in nuclear institutions Improvement of Self-Reliance Management Capability of NPP Projects Completing the Atucha II NPP Validation of In-Service-Inspection NDT Technology of NPP Improving the Reliability of Equipment at the Laguna Verde Nuclear Power Plant CPR PAK ARM BUL ROM RER RER RER RER ARG

40 Thank You!

IAEA Activities in LTO Area

IAEA Activities in LTO Area Activities in LTO Area Robert Krivanek R.Krivanek@iaea.org Project manager for LTO Division of Nuclear Installation Safety International Atomic Energy Agency Contents 1. SALTO (Safety Aspects of LTO) Peer